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1

Mobile Facility  

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

Facility Facility AMF Information Science Architecture Baseline Instruments AMF1 AMF2 AMF3 Data Operations AMF Fact Sheet Images Contacts AMF Deployments Hyytiälä, Finland, 2014 Manacapuru, Brazil, 2014 Oliktok Point, Alaska, 2013 Los Angeles, California, to Honolulu, Hawaii, 2012 Cape Cod, Massachusetts, 2012 Gan Island, Maldives, 2011 Ganges Valley, India, 2011 Steamboat Springs, Colorado, 2010 Graciosa Island, Azores, 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 is configured in a standard layout. Pictured here in Gan, the second mobile facility is configured in a standard layout. To explore science questions beyond those addressed by ARM's fixed sites at

2

TA-55: LANL Plutonium-Processing Facilities  

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

TA-55: LANL Plutonium-Processing Facilities TA-55: LANL Plutonium-Processing Facilities TA-55: LANL Plutonium-Processing Facilities TA-55 supports a wide range of national security programs that involve stockpile stewardship, plutonium processing, nuclear materials stabilization, materials disposition, nuclear forensics, nuclear counter-terrorism, and nuclear energy. ...the only fully operational, full capability plutonium facility in the nation. National Security At the Los Alamos National Laboratory (LANL), virtually all plutonium operations occur within the Plutonium Facility at Technical Area 55 (TA-55). TA-55 is the nation's most modern plutonium science and manufacturing facility, and it is the only fully operational, full capability plutonium facility in the nation. Thus, TA-55 supports a wide

3

Waste minimization at a plutonium processing facility  

SciTech Connect

As part of Los Alamos National Laboratory`s (LANL) mission to reduce the nuclear danger throughout the world, the plutonium processing facility at LANL maintains expertise and skills in nuclear weapons technologies as well as leadership in all peaceful applications of plutonium technologies, including fuel fabrication for terrestrial and space reactors and heat sources and thermoelectric generators for space missions. Another near-term challenge resulted from two safety assessments performed by the Defense Nuclear Facilities Safety Board and the U.S. Department of Energy during the past two years. These assessments have necessitated the processing and stabilization of plutonium contained in tons of residues so that they can be stored safely for an indefinite period. This report describes waste streams and approaches to waste reduction of plutonium management.

Pillay, K.K.S. [Los Alamos National Laboratory, NM (United States)

1995-12-31T23:59:59.000Z

4

ARM Mobile Facilities  

ScienceCinema (OSTI)

This video provides an overview of the ARM Mobile Facilities, two portable climate laboratories that can deploy anywhere in the world for campaigns of at least six months.

Orr, Brad; Coulter, Rich

2014-09-15T23:59:59.000Z

5

AMF ARM Mobile FAcility  

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

AMF ARM Mobile FAcility Details on the AMF proposal process can be found at http:www.arm.govacrfsubmitproposals.stm. For more information, contact: Mark Miller Mary Jane...

6

ARM Mobile Facilities  

SciTech Connect

This video provides an overview of the ARM Mobile Facilities, two portable climate laboratories that can deploy anywhere in the world for campaigns of at least six months.

Orr, Brad; Coulter, Rich

2010-12-13T23:59:59.000Z

7

Interim Storage of Plutonium in Existing Facilities  

SciTech Connect

'In this era of nuclear weapons disarmament and nonproliferation treaties, among many problems being faced by the Department of Energy is the safe disposal of plutonium. There is a large stockpile of plutonium at the Rocky Flats Environmental Technology Center and it remains politically and environmentally strategic to relocate the inventory closer to a processing facility. Savannah River Site has been chosen as the final storage location, and the Actinide Packaging and Storage Facility (APSF) is currently under construction for this purpose. With the ability of APSF to receive Rocky Flats material an estimated ten years away, DOE has decided to use the existing reactor building in K-Area of SRS as temporary storage to accelerate the removal of plutonium from Rocky Flats. There are enormous cost savings to the government that serve as incentive to start this removal as soon as possible, and the KAMS project is scheduled to receive the first shipment of plutonium in January 2000. The reactor building in K-Area was chosen for its hardened structure and upgraded seismic qualification, both resulting from an effort to restart the reactor in 1991. The KAMS project has faced unique challenges from Authorization Basis and Safety Analysis perspectives. Although modifying a reactor building from a production facility to a storage shelter is not technically difficult, the nature of plutonium has caused design and safety analysis engineers to make certain that the design of systems, structures and components included will protect the public, SRS workers, and the environment. A basic overview of the KAMS project follows. Plutonium will be measured and loaded into DOT Type-B shipping packages at Rocky Flats. The packages are 35-gallon stainless steel drums with multiple internal containment boundaries. DOE transportation vehicles will be used to ship the drums to the KAMS facility at SRS. They will then be unloaded, stacked and stored in specific locations throughout the reactor building. The storage life is projected to be ten years to allow the preparation of APSF. DOE has stipulated that there be no credible release during storage, since there are no design features in place to mitigate a release of plutonium (i.e. HEPA filters, facility containment boundaries, etc.). This mandate has presented most of the significant challenges to the safety analysis team. The shipping packages are designed to withstand certain accidents and conditions, but in order to take credit for these the storage environment must be strictly controlled. Damages to the packages from exposure to fire, dropping, crushing and other impact accidents have been analyzed, and appropriate preventative design features have been incorporated. Other efforts include the extension of the shipping life (roughly two years) to a suitable storage life of ten years. These issues include the effects of internal pressure increases, seal degradation and the presence of impurities. A process known as the Container Qualification Program has been conducted to address these issues. The KAMS project will be ready to receive the first shipment from Rocky Flats in January 2000. No credible design basis scenarios resulting in the release of plutonium exist. This work has been useful in the effort to provide a safer disposition of plutonium, but also the lessons learned and techniques established by the team will help with the analysis of future facility modifications.'

Woodsmall, T.D.

1999-05-10T23:59:59.000Z

8

Radiological Safety Training for Plutonium Facilities  

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

145-2008 145-2008 April 2008 DOE HANDBOOK Radiological Safety Training for Plutonium Facilities U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Radiological Safety Training for Plutonium Facilities DOE-HDBK-1145-2008 Program Management Guide

9

Radiological Safety Training for Plutonium Facilities  

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

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE-HDBK-1145-2013 March 2013 DOE HANDBOOK Radiological Safety Training for Plutonium Facilities U.S. Department of Energy TRNG-0061 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. ii Radiological Safety Training for Plutonium Facilities DOE-HDBK-1145-2013 Program Management Foreword

10

TA-55: LANL Plutonium-Processing Facilities  

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

materials stabilization, materials disposition, nuclear forensics, nuclear counter-terrorism, and nuclear energy. ...the only fully operational, full capability plutonium...

11

Hanford, WA Selected as Plutonium Production Facility | National Nuclear  

National Nuclear Security Administration (NNSA)

Hanford, WA Selected as Plutonium Production Facility | National Nuclear Hanford, WA Selected as Plutonium Production Facility | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Hanford, WA Selected as Plutonium Production Facility Hanford, WA Selected as Plutonium Production Facility January 16, 1943 Hanford, WA

12

ARM Mobile Facility (AMF2)  

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

ARM Mobile Facility (AMF2) ARM Mobile Facility (AMF2) The ARM Mobile Facility (AMF2) is a durable, oceangoing mobile climate observatory. In 2008, the second ARM Mobile Facility (AMF2) was developed to extend the capabilities of the original AMF (AMF1) deployed in 2005. The AMF2 is portable, modular, and suited for operations on oceangoing ships and in harsh environments. The AMF2 has improved data flow and communications (primarily wireless) and optimized operating procedures. AMF2 instrument capabilities include standard meteorological instrumentation, a broadband and spectral radiometer suite, and remote sensing instruments. This instrumentation provides researchers with data from climate regimes not previously explored. The AMF2 also has available space, power, and data processing capabilities for additional instruments

13

LANL Plutonium-Processing Facilities National Security  

E-Print Network (OSTI)

of technical capabilities. These capabilities form a center of excellence for actinide science and technology, dismantlement, and materi- als management. Among other things, these efforts support requests for power sources acceptability. Plutonium experiments at TA-55 support the nation's stockpile assessment, without the need

14

MICROBIAL TRANSFORMATIONS OF PLUTONIUM AND IMPLICATIONS FOR ITS MOBILITY.  

SciTech Connect

The current state of knowledge of the effect of plutonium on microorganisms and microbial activity is reviewed, and also the microbial processes affecting its mobilization and immobilization. The dissolution of plutonium is predominantly due to their production of extracellular metabolic products, organic acids, such as citric acid, and sequestering agents, such as siderophores. Plutonium may be immobilized by the indirect actions of microorganisms resulting in changes in Eh and its reduction from a higher to lower oxidation state, with the precipitation of Pu, its bioaccumulation by biomass, and bioprecipitation reactions. In addition, the abundance of microorganisms in Pu-contaminated soils, wastes, natural analog sites, and backfill materials that will be used for isolating the waste and role of microbes as biocolloids in the transport of Pu is discussed.

FRANCIS, A.J.

2000-09-30T23:59:59.000Z

15

ARM - ARM Mobile Facility 1 Article  

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

CenterARM Mobile Facility 1ARM Mobile Facility 1 Article CenterARM Mobile Facility 1ARM Mobile Facility 1 Article Media Contact Lynne Roeder lynne-dot-roeder-at-pnnl-dot-gov @armnewsteam Field Notes Blog Topics Field Notes89 AGU 3 AMIE 10 ARM Aerial Facility 2 ARM Mobile Facility 1 6 ARM Mobile Facility 2 47 BAECC 1 BBOP 4 MAGIC 12 MC3E 17 SGP 2 STORMVEX 29 TCAP 3 Search News Search Blog News Center All Categories What's this? Social Media Guidance News Center All Categories Features and Releases Facility News Field Notes Blog feed Events feed Employment Research Highlights Data Announcements Education News Archive What's this? Social Media Guidance January 13, 2011 [ARM Mobile Facility 1, Blog, Field Notes] AMF1 Azores Pack-up: Rust, Corrosion, and Wet Instruments Bookmark and Share PSP shows the harsh beating it took from the Atlantic mists.

16

Security and Safeguards Aspects of Plutonium Facilities in BNFL, UK  

Science Journals Connector (OSTI)

The processing and storage of plutonium at BNFLs Sellafield site started in the early 1950s and included civil plutonium from 1964 onwards. BNFLs proactive policy on plutonium management demands that plutonium...

Dr R. Howsley

1995-01-01T23:59:59.000Z

17

Good Practices for Ocupational Radiological Protection in Plutonium Facilities  

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

Not Measurement Not Measurement Sensitive DOE- STD-1128-2013 April 2013 DOE STANDARD GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1128-2013 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii DOE-STD-1128-2013 Foreword This Technical Standard does not contain any new requirements. Its purpose is to provide information on good practices, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. U.S. Department of Energy (DOE) health

18

CONTAMINATED PROCESS EQUIPMENT REMOVAL FOR THE D&D OF THE 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINISHING PLANT (PFP)  

SciTech Connect

This paper describes the unique challenges encountered and subsequent resolutions to accomplish the deactivation and decontamination of a plutonium ash contaminated building. The 232-Z Contaminated Waste Recovery Process Facility at the Plutonium Finishing Plant was used to recover plutonium from process wastes such as rags, gloves, containers and other items by incinerating the items and dissolving the resulting ash. The incineration process resulted in a light-weight plutonium ash residue that was highly mobile in air. This light-weight ash coated the incinerator's process equipment, which included gloveboxes, blowers, filters, furnaces, ducts, and filter boxes. Significant airborne contamination (over 1 million derived air concentration hours [DAC]) was found in the scrubber cell of the facility. Over 1300 grams of plutonium held up in the process equipment and attached to the walls had to be removed, packaged and disposed. This ash had to be removed before demolition of the building could take place.

HOPKINS, A.M.; MINETTE, M.J.; KLOS, D.B.

2007-01-25T23:59:59.000Z

19

Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility  

SciTech Connect

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.

Greager, E.M.

1997-12-11T23:59:59.000Z

20

OPEN AIR DEMOLITION OF FACILITIES HIGHLY CONTAMINATED WITH PLUTONIUM  

SciTech Connect

The demolition of highly contaminated plutonium buildings usually is a long and expensive process that involves decontaminating the building to near free- release standards and then using conventional methods to remove the structure. It doesn't, however, have to be that way. Fluor has torn down buildings highly contaminated with plutonium without excessive decontamination. By removing the select source term and fixing the remaining contamination on the walls, ceilings, floors, and equipment surfaces; open-air demolition is not only feasible, but it can be done cheaper, better (safer), and faster. Open-air demolition techniques were used to demolish two highly contaminated buildings to slab-on-grade. These facilities on the Department of Energy's Hanford Site were located in, or very near, compounds of operating nuclear facilities that housed hundreds of people working on a daily basis. To keep the facilities operating and the personnel safe, the projects had to be creative in demolishing the structures. Several key techniques were used to control contamination and keep it within the confines of the demolition area: spraying fixatives before demolition; applying fixative and misting with a fine spray of water as the buildings were being taken down; and demolishing the buildings in a controlled and methodical manner. In addition, detailed air-dispersion modeling was done to establish necessary building and meteorological conditions and to confirm the adequacy of the proposed methods. Both demolition projects were accomplished without any spread of contamination outside the modest buffer areas established for contamination control. Furthermore, personnel exposure to radiological and physical hazards was significantly reduced by using heavy equipment rather than ''hands on'' techniques.

LLOYD, E.R.

2007-05-31T23:59:59.000Z

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


21

Decommissioning of the TA-42 plutonium contaminated incinerator facility  

SciTech Connect

During 1978, a plutonium (/sup 239/Pu) contaminated incinerator facility at the Los Alamos National Laboratory, Los Alamos, New Mexico, was decommissioned. The project involved dismantling the facility and burying the debris at an on-site radioactive solid waste disposal/storage area. Contaminated soil from the 5000 m/sup 2/ area was also buried. The facility was constructed in 1951 to incinerate /sup 239/Pu contaminated wastes. It was later used as a decontamination facility. The major features included a 185-m/sup 2/ floor area control building, incinerator, cyclone dust collector, spray cooler, venturi scrubber, air filter bank, ash separator, and two 140 000-liter ash storage tanks. Six-hundred cubic meters of debris and 1200 m/sup 3/ of soil contaminated with less than 10 nCi /sup 239/Pu per gram of soil were buried at the Laboratory disposal area. Five cubic meters of /sup 239/Pu contaminated ash residues containing more than 10 nCi /sup 239/Pu per gram of waste were packaged and stored to meet the Department of Energy's 20-year retrievable storage criteria. The operation consumed 80 work days and 5800 manhours at a cost of $150 000. This report presents the details concerning decommissioning procedures, the health physics, the waste management, the environmental surveillance results, and a cost breakdown for the operation.

Harper, J.R.; Garde, R.

1981-11-01T23:59:59.000Z

22

Type A Accident Investigation of the March 16, 2000, Plutonium-238 Multiple Intake Event at the Plutonium Facility, Los Alamos National Laboratory, New Mexico  

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

On March 16, 2000, at approximately 2 p.m., a radiological release of plutonium-238 occurred near a glovebox in the Plutonium Processing and Handling Facility (TA-55) of the Los Alamos National Laboratory. At least seven of the eight workers who were in the room at the time received confirmed intakes of plutonium-238.

23

Transuranic (Tru) waste volume reduction operations at a plutonium facility  

SciTech Connect

Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos National Laboratory Continuous Improvement Program by improving the efficiency, cost-effectiveness, and formality of glovebox operations. In this report, the technical issues, associated with implementing this process improvement are addressed, the results discussed, effectiveness of Lessons Learned evaluated, and waste savings presented.

Cournoyer, Michael E [Los Alamos National Laboratory; Nixon, Archie E [Los Alamos National Laboratory; Dodge, Robert L [Los Alamos National Laboratory; Fife, Keith W [Los Alamos National Laboratory; Sandoval, Arnold M [Los Alamos National Laboratory; Garcia, Vincent E [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

24

Decontamination of Battelle-Columbus' Plutonium Facility. Final report  

SciTech Connect

The Plutonium Laboratory, owned and operated by Battelle Memorial Institute's Columbus Division, was located in Battelle's Nuclear Sciences area near West Jefferson, Ohio, approximately 17 miles west of Columbus, Ohio. Originally built in 1960 for plutonium research and processing, the Plutonium Laboratory was enlarged in 1964 and again in 1967. With the termination of the Advanced Fuel Program in March, 1977, the decision was made to decommission the Plutonium Laboratory and to decontaminate the building for unrestricted use. Decontamination procedures began in January, 1978. All items which had come into contact with radioactivity from the plutonium operations were cleaned or disposed of through prescribed channels, maintaining procedures to ensure that D and D operations would pose no risk to the public, the environment, or the workers. The entire program was conducted under the cognizance of DOE's Chicago Operations Office. The building which housed the Plutonium Laboratory has now been decontaminated to levels allowing it to house ordinary laboratory and office operations. A ''Finding of No Significant Impact'' (FNSI) was issued in May, 1980.

Rudolph, A.; Kirsch, G.; Toy, H.L. (comps.)

1984-11-12T23:59:59.000Z

25

RADIOLOGICAL CONTROLS FOR PLUTONIUM CONTAMINATED PROCESS EQUIPMENT REMOVAL FROM 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINSHING PLANT (PFP)  

SciTech Connect

The 232-Z facility at Hanford's Plutonium Finishing Plant operated as a plutonium scrap incinerator for 11 years. Its mission was to recover residual plutonium through incinerating and/or leaching contaminated wastes and scrap material. Equipment failures, as well as spills, resulted in the release of radionuclides and other contamination to the building, along with small amounts to external soil. Based on the potential threat posed by the residual plutonium, the U.S. Department of Energy (DOE) issued an Action Memorandum to demolish Building 232-2, Comprehensive Environmental Response Compensation, and Liability Act (CERC1.A) Non-Time Critical Removal Action Memorandum for Removal of the 232-2 Waste Recovery Process Facility at the Plutonium Finishing Plant (04-AMCP-0486).

MINETTE, M.J.

2007-05-30T23:59:59.000Z

26

Evaluation of existing United States` facilities for use as a mixed-oxide (MOX) fuel fabrication facility for plutonium disposition  

SciTech Connect

A number of existing US facilities were evaluated for use as a mixed-oxide fuel fabrication facility for plutonium disposition. These facilities include the Fuels Material Examination Facility (FMEF) at Hanford, the Washington Power Supply Unit 1 (WNP-1) facility at Hanford, the Barnwell Nuclear Fuel Plant (BNFP) at Barnwell, SC, the Fuel Processing Facility (FPF) at Idaho National Engineering Laboratory (INEL), the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), and the P-reactor at the Savannah River Site (SRS). The study consisted of evaluating each facility in terms of available process space, available building support systems (i.e., HVAC, security systems, existing process equipment, etc.), available regional infrastructure (i.e., emergency response teams, protective force teams, available transportation routes, etc.), and ability to integrate the MOX fabrication process into the facility in an operationally-sound manner that requires a minimum amount of structural modifications.

Beard, C.A.; Buksa, J.J.; Chidester, K.; Eaton, S.L.; Motley, F.E.; Siebe, D.A.

1995-12-31T23:59:59.000Z

27

Guide of good practices for occupational radiological protection in plutonium facilities  

SciTech Connect

This Technical Standard (TS) does not contain any new requirements. Its purpose is to provide guides to good practice, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. the technical rationale is given to allow US Department of Energy (DOE) health physicists to adapt the recommendations to similar situations throughout the DOE complex. Generally, DOE contractor health physicists will be responsible to implement radiation protection activities at DOE facilities and DOE health physicists will be responsible for oversight of those activities. This guidance is meant to be useful for both efforts. This TS replaces PNL-6534, Health Physics Manual of Good Practices for Plutonium Facilities, by providing more complete and current information and by emphasizing the situations that are typical of DOE`s current plutonium operations; safe storage, decontamination, and decommissioning (environmental restoration); and weapons disassembly.

NONE

1998-06-01T23:59:59.000Z

28

Documentation of acceptable knowledge for Los Alamos National Laboratory Plutonium Facility TRU waste stream  

SciTech Connect

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the TRU waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility`s mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC.

Montoya, A.J.; Gruetzmacher, K.M.; Foxx, C.L.; Rogers, P.Z.

1998-03-01T23:59:59.000Z

29

Documentation of acceptable knowledge for LANL Plutonium Facility transuranic waste streams  

SciTech Connect

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site-specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the transuranic waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility`s mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC.

Montoya, A.J.; Gruetzmacher, K.; Foxx, C.; Rogers, P.S.Z.

1998-07-01T23:59:59.000Z

30

Plutonium-Uranium Extraction (PUREX) facility preclosure work plan  

SciTech Connect

The dangerous waste permit identification number (WA7890008967)was issued by the U.S. Environmental Protection Agency and the Washington State Department of Ecology. This identification number encompasses a number of treatment, storage, and/or disposal units within the Hanford Facility. One of these treatment, storage, and/or disposal units is the PUREX Facility,currently undergoing a phased closure. The PUREX Facility Preclosure Work Plan submittal differs from closure plans previously submitted by the U.S. Department of Energy, Richland Operations Office to the Washington State Department of Ecology,in that the closure process occurs in three distinct phases as part of the decommissioning process (i.e., transition,surveillance and maintenance, and disposition). Final closure will occur during the disposition phase. This phased decommissioning process is implemented because development of a complete closure plan during the transition phase is impractical and future land use determinations have not been identified. The objective of the transition phase is to place the PUREX Facility in a safe configuration with respect to human health and the environment. Following the transition phase activities, the PUREX Facility will begin the surveillance and maintenance phase of 10 or more years until disposition phase activities commence. The closure plan for the PUREX facility will be prepared during the disposition phase. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels. The PUREX Storage Tunnels are an operating storage unit(DOE/RL-94-24).

Bhatia, R.K., Westinghouse Hanford

1996-07-09T23:59:59.000Z

31

Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities  

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

2 2 December 2006 DOE STANDARD GUIDE OF GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. ii This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-1128-98 iii Change Notice 1: DOE-STD-1128-98, Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities

32

DOE-HDBK-1145-2001; Radiological Safety Training for Plutonium Facilities  

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

SENSITIVE SENSITIVE DOE-HDBK-1145-2001 August 2001 DOE STANDARD Radiological Safety Training for Plutonium Facilities U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Radiological Safety Training for Plutonium Facilities DOE-HDBK-1145-2001 Program Management Guide Foreword This Handbook describes an implementation process for training as recommended in

33

Lawrence Livermore National Laboratory Operational Drill at the B332 Plutonium Facility  

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

HSS Independent Activity Report - Rev. 0 Report Number: HIAR LLNL-2013-02-27 Site: Lawrence Livermore National Laboratory (LLNL) Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Lawrence Livermore National Laboratory Operational Drill at the B332 Plutonium Facility Date of Activity: 02/27/2013 Report Preparer: Thomas Rogers Activity Description/Purpose: The Livermore Site Office (LSO) and Lawrence Livermore National Security, LLC (LLNS) requested personnel from the U.S. Department of Energy (DOE) Office of Safety and Emergency Management Evaluations (HS-45) to observe an operational drill at the Plutonium Facility in Building 332 (B332). LSO and LLNS desired HS-45's participation to help

34

Measurements at Los Alamos National Laboratory Plutonium Facility in Support of Global Security Mission Space  

SciTech Connect

The Los Alamos National Laboratory Plutonium Facility at Technical Area (TA) 55 is one of a few nuclear facilities in the United States where Research & Development measurements can be performed on Safeguards Category-I (CAT-I) quantities of nuclear material. This capability allows us to incorporate measurements of CAT-IV through CAT-I materials as a component of detector characterization campaigns and training courses conducted at Los Alamos. A wider range of measurements can be supported. We will present an overview of recent measurements conducted in support of nuclear emergency response, nuclear counterterrorism, and international and domestic safeguards. This work was supported by the NNSA Office of Counterterrorism.

Stange, Sy [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Herrera, Gary D. [Los Alamos National Laboratory; McLaughlin, Anastasia D. [Los Alamos National Laboratory; Montoya, Charles M. [Los Alamos National Laboratory; Quihuis, Becky A. [Los Alamos National Laboratory; Trujillo, Julio B. [Los Alamos National Laboratory; Van Pelt, Craig E. [Los Alamos National Laboratory; Wenz, Tracy R. [Los Alamos National Laboratory

2012-07-13T23:59:59.000Z

35

Plutonium Mobility Studies: 216-Z-9 Trench Sample Analysis Results  

SciTech Connect

A variety of analyses were conducted on selected sediment samples collected from two wells (299 W15-46 and 299-W15-48) drilled near the 216-Z-9 Trench to elucidate the form and potential for Pu and Am to be mobilized under present conditions and those that could be expected in future remediation scenarios. Analyses included moisture content, determination of the less than sand size fraction (silt plus clay), carbon analysis, SEM/EDS analysis, microwave-assisted acid digestions for total element analysis, and extraction tests using Hanford groundwater as the leachate. Results of the extraction tests were used as input to conduct equilibrium geochemical modeling of the solutions with Geochemists Workbench. Geochemical modeling results for Pu were evaluated in terms of recent conclusions regarding the solubility and redox reactions of Pu by Neck et al. (2007a, 2007b). It was found that the highest concentrations of Pu and Am were associated with sediments of low silt/clay content and occur above silt/clay rich layers within the sediment profile. It was also found that the Pu and Am were relatively enriched in the silt/clay portion of these samples. The fact that the highest concentrations of Pu and Am occurred in sediments with low silt/clay contents suggests that waste solutions had perched on top of the low permeability silt/clay rich layers and interactions with the high silt/clay layers was minimal. SEM/EDS analysis indicated that the Pu and Am in these sediments does not occur as discrete micron size particles, and therefore must occur as mononuclear or polynuclear/ nanoclusters size particles adsorbed throughout the sediment samples. Leaching of these samples with Hanford groundwater indicates that release of Pu and Am from the sediments is correlated most significantly with the acidity of the water and not the initial concentrations of Pu and Am in the sediments. Only extracts that were acidic after contact with the sediments (pH 4.3 to 5.4) contained detectable concentrations of extractable Pu and Am. Water extracts from samples containing high concentrations of TBP suggest that if the TBP degradation products DBP and MBP are available in these sediments, they do not significantly increase the extractability of Pu or Am. Geochemical modeling results suggest that the concentrations of Am in water in contact with these sediments is not controlled by the solubility of Am(OH)3(c), but rather by desorption of Am that has been previously adsorbed to the sediments during the period of active wastewater disposal. Sediment extracts that had measureable concentrations of Am only occurred in samples that were fairly acidic (pH 4.3 to 4.6), indicating that Am will remain effectively sequestered to sediments when pH conditions approach those of normal Hanford groundwater (mildly alkaline, ~ pH 8). The geochemical modeling results indicate that Pu in acidic extracts is significantly undersaturated with respect to PuO2(am). However, recent reviews of Pu solubility and redox reactions suggest that the data used for these calculations is incomplete (Neck et al. 2007a, 2007b). The results of Neck et al. (2007a, 2007b) suggest that Pu concentrations in solutions in contact with the 216-Z-9 Trench sediment samples might be controlled by a mixed valent solid phase [(PuV)2x(PuIV)1-2xO2+x(am)] with various dissolved Pu(V) complexes and Pu(IV)O2(am) colloids or nanoclusters being the dominant species in solution for typical Hanford groundwater conditions. Adsorption is likely to have a major impact on the mobility of these species (Neck et al. 2007a, 2007b; Clark et al. 2006; Kaplan et al. 2006; Powell et al. 2005). Further research is planned to verify these hypotheses.

Cantrell, Kirk J.; Geiszler, Keith N.; Arey, Bruce W.

2008-09-05T23:59:59.000Z

36

Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities  

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

28-2008 28-2008 December 2008 DOE STANDARD GUIDE OF GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-STD-1128-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1128-2008 iii Foreword This Technical Standard does not contain any new requirements. Its purpose is to provide a guide to good practice, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. U.S. Department of Energy (DOE) health physicists may adapt

37

Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities  

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

STD-1128-2008 STD-1128-2008 December 2008 DOE STANDARD GUIDE OF GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-STD-1128-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1128-2008 iii Foreword This Technical Standard does not contain any new requirements. Its purpose is to provide a guide to good practice, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. U.S. Department of Energy (DOE) health physicists may adapt

38

Rough order of magnitude cost estimate for immobilization of 50 MT of plutonium sharing existing facilities at Hanford with pit disassembly {ampersand} conversion facility: alternative 11  

SciTech Connect

The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 50 metric tons (nominal) of plutonium as a ceramic in an existing facility at Hanford, the Fuels and Materials Examination Facility (FMEF). The Pit Disassembly and Conversion Facility (PDCF), which is being costed in a separate report by LANL, will also be located in the FMEF in this co-location option.

DiSabatino, A., LLNL

1998-06-01T23:59:59.000Z

39

Treatment of Uranium and Plutonium Solutions Generated in the Atalante Facility, France - 12004  

SciTech Connect

The Atalante complex operated by the French Alternative Energies and Atomic Energy Commission (CEA) at the Rhone Valley Research Center consolidates research programs on actinide chemistry, especially separation chemistry, processing for recycling spent fuel, and fabrication of actinide targets for innovative concepts in future nuclear systems. The design of future systems (Generation IV reactors, material recycling) will increase the uranium and plutonium flows in the facility, making it important to anticipate the stepped-up activity and provide Atalante with equipment dedicated to processing these solutions to obtain a mixed uranium-plutonium oxide that will be stored pending reuse. Ongoing studies for integral recycling of the actinides have highlighted the need for reserving equipment to produce actinides mixed oxide powder and also minor actinides bearing oxide for R and D purpose. To meet this double objective a new shielded line should be built in the facility and should be operational 6 years after go decision. The main functions of the new unit would be to receive, concentrate and store solutions, purify them, ensure group conversion of actinides and conversion of excess uranium. This new unit will be constructed in a completely refurbished building devoted to subcritical and safe geometry of the process equipments. (author)

Lagrave, Herve [French Alternative Energies and Atomic Energy Commission - CEA, Rhone Valley Research Center, BP 17171, 30207 Bagnols-sur-Ceze Cedex (France)

2012-07-01T23:59:59.000Z

40

Rough order of magnitude cost estimate for immobilization of 18.2 MT of plutonium sharing existing facilities at Hanford with pit disassembly {ampersand} conversion facility: alternative 2  

SciTech Connect

The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 18.2 metric tons (nominal) of plutonium as a ceramic in an existing facility at Hanford, the Fuels and Materials Examination Facility (FMEF). The Pit Disassembly and Conversion Facility (PDCF), which is being costed in a separate report will also be located in the FMEF in this co- location option. The technical engineering data used as the basis for this study is presented in the EIS Data Call Input Report, `Plutonium Immobilization Plant Using Ceramic in Existing Facilities at Hanford.` The FMEF will require minimal facility modifications to accommodate the Plutonium Immobilization Plant (PIP). Adequate space is available within the FMEF for installation of the immobilization process equipment. Facility HVAC, utility, and support systems exist to support the immobilization operations. Building modifications are primarily the removal of the SAF line (gloveboxes and support equipment) on the 70` level and building interior changes. The plutonium immobilization equipment will primarily occupy the 42` and 70` levels of the FMEF, with the same equipment layout as in the sole occupancy case. The Pit Disassembly and Conversion Facility would occupy the 21` and O` (Entry) levels. Elements of the FMEF and adjacent Fuel Assembly Area (FAA) that will be shared by PIP and PDCF include shipping and receiving, laboratory, waste handling, security, offices, maintenance shops, SNM storage vault, and utilities. It was assumed that the existing utilities and support systems are adequate or only need minor upgrades to support both the PIP and PDCF. The PIP cost estimate was reconciled with the PDCF cost estimate to confirm the use and costs of shared systems and personnel. The facility design for a 50 metric ton plutonium throughput plant will be used for the 18.2 metric ton facility. Plutonium conversion operations will operate at the same design rate as the 50 metric ton facility over the 10 year operating period. Some of the process equipment will operate for a shorter period of time and fewer operators will be required. The assumptions, missions, design bases, facility and process descriptions, and accident analyses are the same. Therefore it is assumed that the capital cost for the 18.2 metric ton facility is identical to that of the 50 metric ton facility. However, the following operating costs will be less: consumable materials, equipment replacement and maintenance labor, employment requirements, and waste generation.

DiSabatino, A., LLNL

1998-06-01T23:59:59.000Z

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


41

Plutonium immobilization plant using glass in existing facilities at the Savannah River Site  

SciTech Connect

The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a glass immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors.

DiSabatino, A., LLNL

1998-06-01T23:59:59.000Z

42

Retrofit of an Engineered Glove-port to a Los Alamos National Laboratory's Plutonium Facility Glovebox  

SciTech Connect

At the Los Alamos National Laboratory's Plutonium Facility (TA-55), various isotopes of plutonium along with other actinides are routinely handled such that the spread of radiological contamination and excursions of contaminants into the operator's breathing zone are prevented through the use of a variety of gloveboxes (the glovebox coupled with adequate negativity providing primary confinement). The current technique for changing glovebox gloves are the weakest part of this engineering control. 1300 pairs of gloves are replaced each year at TA-55, generating approximately 500 m{sup 3}/yr of transuranic (TRU) waste and Low Level Waste (LLW) waste that represents an annual disposal cost of about 4 million dollars. By retrofitting the LANL 8'' glove-port ring, a modern 'Push-Through' technology is utilized. This 'Push-Through' technology allows relatively fast glove changes to be done by operators with much less training and experience and without breaching containment. A dramatic reduction in waste is realized; exposure of the worker to residual contamination reduced, and the number of breaches due to installation issues is eliminated. In the following presentation, the evolution of the 'Push- Through' technology, the features of the glove-port retrofit, and waste savings are discussed. (author)

Rael, P.E.D.; Cournoyer, M.E.Ph.D.; Chunglo, S.D.; Vigil, T.J.; Schreiber, P.E.S. [Los Alamos National Laboratory, Los Alamos, NM (United States)

2008-07-01T23:59:59.000Z

43

Mobile Climate Monitoring Facility to Sample Skies in Africa | Department  

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

Mobile Climate Monitoring Facility to Sample Skies in Africa Mobile Climate Monitoring Facility to Sample Skies in Africa Mobile Climate Monitoring Facility to Sample Skies in Africa January 18, 2006 - 10:47am Addthis WASHINGTON, D.C. -- The U.S. Department of Energy's Atmospheric Radiation Measurement (ARM) Program is placing a new, portable atmospheric laboratory with sophisticated instruments and data systems in Niger, Africa, to gain a better understanding of the potential impacts of Saharan dust on global climate. Dust from Africa's Sahara desert-the largest source of dust on the planet-reaches halfway around the globe. Carried by winds and clouds, the dust travels through West African, Mediterranean, and European skies, and across the Atlantic into North America. Unfortunately, Africa is one of the most under-sampled climate regimes in the world, leaving scientists to

44

ARM Mobile Facility - Design and Schedule for Integration  

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

Mobile Facility - Design and Schedule for Integration Mobile Facility - Design and Schedule for Integration K. B. Widener Pacific Northwest National Laboratory Richland, Washington Abstract The Atmospheric Radiation Measurement (ARM) Program has a need for an ARM Mobile Facility (AMF) that can be deployed anywhere in the world for up to 12 months at a time. This system shall be modular so that it can meet the needs of ARM science objectives of each individual deployment. The design phase for developing the AMF has begun. A design review was held for the AMF in December 2002. The design of the shelters, instrumentation, and data system along with the schedule for integration will be presented. Introduction Early in the development of the ARM Program, the need to be able to make atmospheric measurements

45

Plutonium immobilization plant using glass in new facilities at the Savannah River Site  

SciTech Connect

The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a glass immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors.

DiSabatino, A.

1998-06-01T23:59:59.000Z

46

Plutonium immobilization plant using ceramic in existing facilities at the Savannah River site  

SciTech Connect

The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources, and through a ceramic immobilization process converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors. The ceramic immobilization alternative presented in this report consists of first converting the surplus material to an oxide, followed by incorporating the plutonium oxide into a titanate-based ceramic material that is placed in metal cans.

DiSabatino, A., LLNL

1998-06-01T23:59:59.000Z

47

Investigation of the November 8, 2011, Plutonium Contamination in the Zero Power Physics Reactor Facility, at the Idaho National Laboratory  

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

On November 8, 2011, workers at the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Zero Power Physics Reactor (ZPPR) Facility were packaging plutonium (Pu) reactor fuel plates. Two of the fuel storage containers had atypical labels indicating potential abnormalities with the fuel plates located inside. Upon opening one of the storage containers, the workers discovered a Pu fuel plate wrapped in plastic and tape. When the workers attempted to remove the wrapping material, an uncontrolled release of radioactive contaminants occurred, resulting in the contamination of 16 workers and the facility

48

MoWiTT:Mobile Window Thermal Test Facility  

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

0 0 MoWiTT: Mobile Window Thermal Test Facility The window has come a long way since the days when it was a single pane of glass in a wood frame. Low-emissivity windows were designed to help buildings retain some of the energy that would have leaked out of less efficient windows. Designing efficient window-and-frame systems requires accurate measurement of the flow of energy through windows in realistic conditions, a capability provided by the Mobile Window Thermal Test facility. Consisting of a pair of outdoor, room-sized calorimeters, MoWiTT measures the net energy flow through two window samples in side-by-side tests using ambient weather conditions. MoWiTT characterizes the net energy flow as a function of time and measures the temperatures, solar fluxes, and

49

Plutonium aging  

SciTech Connect

The author describes the plutonium aging program at the Los Alamos National Laboratory. The aging of plutonium components in the US nuclear weapons stockpile has become a concern due to several events: the end of the cold war, the cessation of full scale underground nuclear testing as a result of the Comprehensive Test Ban Treaty (CTBT) and the closure of the Rocky Flats Plant--the site where the plutonium components were manufactured. As a result, service lifetimes for nuclear weapons have been lengthened. Dr. Olivas will present a brief primer on the metallurgy of plutonium, and will then describe the technical approach to ascertaining the long-term changes that may be attributable to self-radiation damage. Facilities and experimental techniques which are in use to study aging will be described. Some preliminary results will also be presented.

Olivas, J.D.

1999-03-01T23:59:59.000Z

50

PLUTONIUM-URANIUM EXTRACTION (PUREX) FACILITY ALARACT DEMONSTRATION FOR FILTER HOUSING  

SciTech Connect

This document presents an As Low As Reasonably Achievable Control Technology (ALARACT) demonstration for evaluating corrosion on the I-beam supporting filter housing No.9 for the 291-A-l emission unit of the Plutonium-Uranium Extraction (PUREX) Facility, located in the 200 East Area of the Hanford Site. The PUREX facility is currently in surveillance and maintenance mode. During a State of Washington, Department of Health (WDOH) 291-A-l emission unit inspection, a small amount of corrosion was observed at the base of a high-efficiency particulate air (HEPA) filter housing. A series of internal and external inspections identified the source of the corrosion material as oxidation of a small section of one of the carbon steel I-beams that provides support to the stainless steel filter housing. The inspections confirmed the corrosion is isolated to one I-beam support location and does not represent any compromise of the structural support or filter housing integrity. Further testing and inspections of the support beam corrosion and its cause were conducted but did not determine the cause. No definitive evidence was found to support any degradation of the housing. Although no degradation of the housing was found, a conservative approach will be implemented. The following actions will be taken: (1) The current operating filter housing No.9 will be removed from service. (2) The only remaining available filter housings (No.1, No.2, and No.3) will be placed in service. These filter housings have new HEPA filters fitted with stainless steel frames and faceguards which were installed in the spring of 2007. (3) Filter housings No.5 and No.10 will be put on standby as backups. To document the assessment of the unit, a draft ALARACT filter housing demonstration for the PUREX filter housing was prepared, and informally provided to WDOH on August 7, 2008. A follow up WDOH response to the draft ALARACT filter housing demonstration for the PUREX filter housing questioned whether deteriorated galvanized filter faceguards discovered during an internal filter housing inspection met American Society of Mechanical Engineers (ASME) AG-l or Military Specification (MIL) 51068 standards. The filter system was designed and installed prior to the issuance of AG-l, February 1986; however, MIL 51068 did require galvanized faceguards. The faceguards are not necessary for filtration or structural purposes; it is concluded that the system is in compliance with the intent of the applicable standard. Appendix B provides supporting information to address this issue.

LEBARON GJ

2008-11-25T23:59:59.000Z

51

Assessment of plutonium storage safety issues at Department of Energy facilities  

SciTech Connect

The Department of Energy (DOE) mission for utilization and storage of nuclear materials has recently changed as a result of the end of the ``Cold War`` era. Past and current plutonium storage practices largely reflect a temporary, in-process, or in-use storage condition which must now be changed to accommodate longer-term storage. This report summarizes information concerning current plutonium metal and oxide storage practices which was presented at the Office of Defense programs (DP) workshop in Albuquerque, New Mexico on May 26-27, 1993 and contained in responses to questions by DP-62 from the field organizations.

Not Available

1994-01-01T23:59:59.000Z

52

Plutonium Consumption Program, CANDU Reactor Project: Feasibility of BNFP Site as MOX Fuel Supply Facility. Final report  

SciTech Connect

An evaluation was made of the technical feasibility, cost, and schedule for converting the existing unused Barnwell Nuclear Fuel Facility (BNFP) into a Mixed Oxide (MOX) CANDU fuel fabrication plant for disposition of excess weapons plutonium. This MOX fuel would be transported to Ontario where it would generate electricity in the Bruce CANDU reactors. Because CANDU MOX fuel operates at lower thermal load than natural uranium fuel, the MOX program can be licensed by AECB within 4.5 years, and actual Pu disposition in the Bruce reactors can begin in 2001. Ontario Hydro will have to be involved in the entire program. Cost is compared between BNFP and FMEF at Hanford for converting to a CANDU MOX facility.

NONE

1995-06-30T23:59:59.000Z

53

Rough order of magnitude cost estimate for immobilization of 18.2 MT of plutonium using existing facilities at the Savannah River site: alternatives 3A/5A/6A/6B/7A/9A  

SciTech Connect

The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 18.2 metric tons (nominal) of plutonium using ceramic in a new facility at Savannah River Site (SRS).

DiSabatino, A., LLNL

1998-06-01T23:59:59.000Z

54

The impact of two Department of Energy orders on the design and cost of select plutonium facilities at Los Alamos National Laboratory  

SciTech Connect

The Los Alamos National Laboratory (LANL) is a research and development facility in northern New Mexico, owned by the federal government and operated for the US Department of Energy (DOE) by the University of California (UC). LANL conducts research and experiments in many arenas including plutonium. Its plutonium facilities are required to meet the facility design and safety criteria of applicable DOE orders as specified in the UC contract. Although DOE 420.1, Facility Safety, superseded DOE 6430.1A, General Design Criteria, the UC contract requires LANL to adhere to DOE 6430.1A, Division 13 in its special nuclear facilities. A comparison of costs and savings relative to installation of double-wall piping at two LANL plutonium facilities is demonstrated. DOE 6430.1A is prescriptive in its design criteria whereas DOE 420.1 is a performance-based directive. The differences in these orders impact time and design costs in nuclear construction projects. LANL`s approach to integrated quality and conduct of operations for design, needs to be re-evaluated. In conclusion, there is a need for highly-technical, knowledgeable people and an integrated, quality/conduct of operations-based approach to assure that nuclear facilities are designed and constructed in a safe and cost-effective manner.

Rey, V.C.

1999-02-01T23:59:59.000Z

55

Environmental consequences of postulate plutonium releases from Atomics International's Nuclear Materials Development Facility (NMDF), Santa Susana, California, as a result of severe natural phenomena  

SciTech Connect

Potential environmental consequences in terms of radiation dose to people are presented for postulated plutonium releases caused by severe natural phenomena at the Atomics International's Nuclear Materials Development Facility (NMDF), in the Santa Susana site, California. The severe natural phenomena considered are earthquakes, tornadoes, and high straight-line winds. Plutonium deposition values are given for significant locations around the site. All important potential exposure pathways are examined. The most likely 50-year committed dose equivalents are given for the maximum-exposed individual and the population within a 50-mile radius of the plant. The maximum plutonium deposition values likely to occur offsite are also given. The most likely calculated 50-year collective committed dose equivalents are all much lower than the collective dose equivalent expected from 50 years of exposure to natural background radiation and medical x-rays. The most likely maximum residual plutonium contamination estimated to be deposited offsite following the earthquake, and the 150-mph and 170-mph tornadoes are above the Environmental Protection Agency's (EPA) proposed guideline for plutonium in the general environment of 0.2 ..mu..Ci/m/sup 2/. The deposition values following the 110-mph and the 130-mph tornadoes are below the EPA proposed guideline.

Jamison, J.D.; Watson, E.C.

1982-02-01T23:59:59.000Z

56

President Truman Increases Production of Uranium and Plutonium...  

National Nuclear Security Administration (NNSA)

Uranium and Plutonium Washington, DC President Truman approves a 1.4 billion expansion of Atomic Energy Commission facilities to produce uranium and plutonium for nuclear weapons...

57

EIS Data Call Report: Plutonium immobilization plant using ceramic in new facilities at the Savannah River Site  

SciTech Connect

The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a ceramic immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors. The ceramic immobilization alternative presented in this report consists of first converting the surplus material to an oxide, followed by incorporating the plutonium oxide into a titanate-based ceramic material that is placed in metal cans.

DiSabatino, A.

1998-06-01T23:59:59.000Z

58

Using mobile distributed pyrolysis facilities to deliver a forest residue resource for bio-fuel production.  

E-Print Network (OSTI)

??Distributed mobile conversion facilities using either fast pyrolysis or torrefaction processes can be used to convert forest residues to more energy dense substances (bio-oil, bio-slurry (more)

Brown, Duncan

2013-01-01T23:59:59.000Z

59

SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities  

E-Print Network (OSTI)

SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities Ron Fulbright Inspector (SWAMI) is a prototype mobile robot designed to perform autonomous inspection of nuclear waste user interface building tool called UIM/X. Introduction Safe disposal of nuclear waste is a difficult

Stephens, Larry M.

60

Ion exchange separation of plutonium and gallium (1) resource and inventory requirements, (2) waste, emissions, and effluent, and (3) facility size  

SciTech Connect

The following report summarizes an effort intended to estimate within an order-of-magnitude the (1) resource and inventory requirements, (2) waste, emissions, and effluent amounts, and (3) facility size, for ion exchange (IX) separation of plutonium and gallium. This analysis is based upon processing 3.5 MT-Pu/yr. The technical basis for this summary is detailed in a separate document, {open_quotes}Preconceptual Design for Separation of Plutonium and Gallium by Ion Exchange{close_quotes}. The material balances of this separate document are based strictly on stoichiometric amounts rather than details of actual operating experience, in order to avoid classification as Unclassified Controlled Nuclear Information. This approximation neglets the thermodynamics and kinetics which can significantly impact the amount of reagents required. Consequently, the material resource requirements and waste amounts presented here would normally be considered minimums for processing 3.5 MT-Pu/yr; however, the author has compared the inventory estimates presented with that of an actual operating facility and found them similar. Additionally, the facility floor space presented here is based upon actual plutonium processing systems and can be considered a nominal estimate.

DeMuth, S.

1997-09-30T23:59:59.000Z

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


61

DOE-STD-1128-98; Changes to DOE-STD-1128-98, "Guide for Occupational Radiological Protection in Plutonium Facilities"  

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

Changes to DOE-STD-1128-98, "Guide for Occupational Radiological Protection in Plutonium Changes to DOE-STD-1128-98, "Guide for Occupational Radiological Protection in Plutonium Facilities Section/Page Change Cover Change "Metric" to "Not Measurement Sensitive". Throughout the document Change "the DOE Radiological Control Manual (RCM)" to "the DOE standard DOE- STD-1098-99, Radiological Control (RCS)". Change "RCM" to "RCS". Replace (DOE, 1993c) with (DOE, 1998a). Replace (DOE, 19941) with (DOE, 1999b). Delete reference to DOE Order 5700C, Quality Assurance. Replace ANSI N13.6-1989 (ANSI, 1996) with ANSI/HPS N13.6 (ANSI, 1999a). Change "ANSI N323-1993 (ANSI, 1993)" to "ANSI N323a (ANSI, 1997b)". Change "DOE Order 420.1 (DOE, 1995c)" to "Order 420.1A (DOE, 2002a)".

62

Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0  

SciTech Connect

The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15T23:59:59.000Z

63

ARM - Field Campaign - Application of the ARM Mobile Facility (AMF) to  

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

govCampaignsApplication of the ARM Mobile Facility (AMF) to Study the govCampaignsApplication of the ARM Mobile Facility (AMF) to Study the Aerosol Indirect Effects in China Campaign Links China Website Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign : Application of the ARM Mobile Facility (AMF) to Study the Aerosol Indirect Effects in China 2008.05.15 - 2008.12.29 Website : http://www.arm.gov/sites/amf/hfe/ Lead Scientist : Zhanqing Li For data sets, see below. Description Aerosols in China have exceptionally high loading and diverse properties whose influence has been detected across the Pacific Rim. The rapid pace of changes in the atmospheric environment over China provides a natural testbed for identifying and quantifying the climatic effects of aerosols. Preliminary analyses of multiple satellite datasets (MODIS, TMI, TRMM)

64

Plutonium Vulnerability Management Plan  

SciTech Connect

This Plutonium Vulnerability Management Plan describes the Department of Energy`s response to the vulnerabilities identified in the Plutonium Working Group Report which are a result of the cessation of nuclear weapons production. The responses contained in this document are only part of an overall, coordinated approach designed to enable the Department to accelerate conversion of all nuclear materials, including plutonium, to forms suitable for safe, interim storage. The overall actions being taken are discussed in detail in the Department`s Implementation Plan in response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. This is included as Attachment B.

NONE

1995-03-01T23:59:59.000Z

65

Mobile Facility Records Annual Climate Cycle in Niger, Africa  

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

Facility Records Annual Facility Records Annual Climate Cycle in Niger, Africa Because dust can block incoming solar energy, and because solar energy drives weather and climate, scientists around the world are looking for ways to better understand these natural phenomena. In 2006, scientists sponsored by the U.S. Department of Energy's Atmospheric Radiation Measurement (ARM) Climate Research Facility conducted a year-long field campaign in Niamey, Niger, to provide key information for the African Monsoon Multidisciplinary Analyses, or AMMA, project. During the 12-month experiment at the airport in Niamey, researchers used a portable atmospheric laboratory, airplanes, and satellites to collect information about clouds, aerosols, and solar and terrestrial energy in the skies above the site. Measurements obtained

66

Atmospheric deposition, resuspension and root uptake of plutonium in corn and other grain-producing agroecosystems near a nuclear fuel facility  

SciTech Connect

Plutonium released to the environment may contribute to dose to humans through inhalation or ingestion of contaminated foodstuffs. Plutonium contamination of agricultural plants may result from interception and retention of atmospheric deposition, resuspension of Pu-bearing soil particles to plant surfaces, and root uptake and translocation to grain. Plutonium on vegetation surfaces may be transferred to grain surfaces during mechanical harvesting. Data obtained from corn grown near the US Department of Energy`s H-Area nuclear fuel chemical separations facility on the Savannah River Site was used to estimated parameters of a simple model of Pu transport in agroecosystems. The parameter estimates for corn were compared to those previously obtained for wheat and soybeans. Despite some differences in parameter estimates among crops, the relative importances of atmospheric deposition, resuspension and root uptake were similar among crops. For even small deposition rates, the relative importances of processes for Pu contamination of corn grain should be: transfer of atmospheric deposition from vegetation surfaces to grain surfaces during combining > resuspension of soil to grain surfaces > root uptake. Approximately 3.9 {times} 10{sup {minus}5} of a year`s atmospheric deposition is transferred to grain. Approximately 6.2 {times} 10{sup {minus}9} of the Pu inventory in the soil is resuspended to corn grain, and a further 7.3 {times} 10{sup {minus}10} of the soil inventory is absorbed by roots and translocated to grains.

Pinder, J.E. III; McLeod, K.W.; Adriano, D.C. [Savannah River Ecology Lab., Aiken, SC (United States); Corey, J.C.; Boni, A.L. [Savannah River Lab., Aiken, SC (United States)

1989-12-31T23:59:59.000Z

67

Atmospheric deposition, resuspension and root uptake of plutonium in corn and other grain-producing agroecosystems near a nuclear fuel facility  

SciTech Connect

Plutonium released to the environment may contribute to dose to humans through inhalation or ingestion of contaminated foodstuffs. Plutonium contamination of agricultural plants may result from interception and retention of atmospheric deposition, resuspension of Pu-bearing soil particles to plant surfaces, and root uptake and translocation to grain. Plutonium on vegetation surfaces may be transferred to grain surfaces during mechanical harvesting. Data obtained from corn grown near the US Department of Energy's H-Area nuclear fuel chemical separations facility on the Savannah River Site was used to estimated parameters of a simple model of Pu transport in agroecosystems. The parameter estimates for corn were compared to those previously obtained for wheat and soybeans. Despite some differences in parameter estimates among crops, the relative importances of atmospheric deposition, resuspension and root uptake were similar among crops. For even small deposition rates, the relative importances of processes for Pu contamination of corn grain should be: transfer of atmospheric deposition from vegetation surfaces to grain surfaces during combining > resuspension of soil to grain surfaces > root uptake. Approximately 3.9 {times} 10{sup {minus}5} of a year's atmospheric deposition is transferred to grain. Approximately 6.2 {times} 10{sup {minus}9} of the Pu inventory in the soil is resuspended to corn grain, and a further 7.3 {times} 10{sup {minus}10} of the soil inventory is absorbed by roots and translocated to grains.

Pinder, J.E. III; McLeod, K.W.; Adriano, D.C. (Savannah River Ecology Lab., Aiken, SC (United States)); Corey, J.C.; Boni, A.L. (Savannah River Lab., Aiken, SC (United States))

1989-01-01T23:59:59.000Z

68

Research Program to Determine Redox Reactions and Their Effects on Speciation and Mobility of Plutonium in DOE Wastes  

SciTech Connect

Plutonium in geologic matrices undergoes a variety of complex reactions which complicate its environmental behavior. These complexities in plutonium chemistry whereby a large variety of precipitation, dissolution, adsorption/desorption, and redox reactions control plutonium speciation and concentrations, result in the need for a rather large amount of reliable, fundamental data to predict Pu behavior in geologic media. These data are also needed for evaluation of remediation strategies that involve removing most of the contaminants by selective methods, followed by in situ immobilization of residual contaminants. Two areas were studied during this project: (1) thermodynamic data for Th(IV) and Pu(IV) complexes of EDTA and for Pu(V) interactions with chloride; (2) kinetic data for redox reactions of Pu in the presence of common redox agents (e.g., H{sub 2}O{sub 2}, MnO{sub 2}, and NaOCl) encountered under waste disposal conditions. These studies are relevant to understanding Pu behavior in wastes disposed of in diverse geologic conditions (e.g., at the WIPP and YUCCA Mountain repositories and in contaminated sediments at many different DOE sites) and also for developing effective remediation strategies (e.g., processing of high level waste tanks). These studies have yielded data to address redox reactions of plutonium in the presence of environmentally important agents (e.g. organic and inorganic oxidants/reductants).

Choppin, G.R.; Rai, D.

2000-10-01T23:59:59.000Z

69

Plutonium Disposition Program | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plutonium Disposition Program Plutonium Disposition Program Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition > Plutonium Disposition Program Plutonium Disposition Program The U.S.-Russia Plutonium Management and Disposition Agreement (PMDA), which entered into force on July 13, 2011, commits each country to dispose of at least 34 metric tons (MT) of weapon-grade plutonium withdrawn from their respective nuclear weapon programs. The U.S. remains firmly committed to its PMDA obligation to dispose of excess weapons plutonium. U.S. Plutonium Disposition The current U.S. plan to dispose of 34 MT of weapon-grade plutonium is to fabricate it into Mixed Oxide (MOX) fuel and irradiate it in existing light water reactors. This approach requires construction of new facilities

70

Cost-benefits of a mobile, trailer-contained, vibratory finishing decontamination facility  

SciTech Connect

The objective of this study was to determine the cost-benefits of a vibratory finishing process, developed at Pacific Northwest Laboratory (PNL), which has been used successfully to remove a variety of transuranic (TRU) contaminants from surfaces of metallic and nonmetallic wastes. Once TRU contaminants are removed, the metallic and nonmetallic materials can be disposed of as low-level waste (LLW). Otherwise, these materials would be disposed of in geologic repositories. This study provides an economic evaluation of the vibratory finishing process as a possible method for use in decontaminating and decommissioning retired facilities at Hanford and oher sites. Specifically, the economic evaluation focuses on a scoping design for a mobile, trailer-contained facility, which could be used in the field in conjunction with decontamination and decommissioning operations. The capital cost of the mobile facility is estimated to be about $1.09 million including contingency and working capital. Annual operating costs, including disposal costs, are estimated to be $440,000 for processing about 6340 ft/sup 3//yr of pre-sectioned, TRU-contaminated material. Combining the operating cost and the capital cost, annualized at a discount rate of 10%, the total annual cost estimate is $602,000. The unit cost for vibratory finishing is estimated to be about $11/ft/sup 3/ of original reference glove box volume (Abrams et at. 1980). All costs are in first quarter 1981 dollars. Although not directly comparable, the unit cost for the vibratory finishing process is very favorable when considered beside typical, substantially higher, unit costs for processing and geologically disposing of TUR-contaminated materials. The probable accuracy of this study cost estimate is about +- 30%. It is therefore recommended that a detailed cost estimate be prepared if a mobile facility is designed.

Hazelton, R.F.; McCoy, M.W.

1982-07-01T23:59:59.000Z

71

Colloidal Cutin-like Siderophoric Molecules Mobilize Plutonium from Contaminated Soils of the Rocky Flats Environmental Technology Site (RFETS), USA  

SciTech Connect

Relatively recently, inorganic colloids have been invoked to reconcile the apparent contradictions between expectations based on classical dissolved-phase Pu transport and field observations of 'enhanced' Pu mobility (Kersting et al. Nature 1999, 397, 56-59). A new paradigm for Pu transport is mobilization and transport via biologically produced ligands. This study for the first time reports a new finding of Pu being transported, at sub-pM concentrations, by a cutin-like natural substance containing siderophore-like moieties and virtually all mobile Pu. Most likely, Pu is complexed by chelating groups derived from siderophores that are covalently bound to a backbone of cutin-derived soil degradation products, thus revealing the history of initial exposure to Pu. Features such as amphiphilicity and small size make this macromolecule an ideal collector for actinides and other metals and a vector for their dispersal. Cross-linking to the hydrophobic domains (e.g., by polysaccharides) gives this macromolecule high mobility and a means of enhancing Pu transport. This finding provides a new mechanism for Pu transport through environmental systems that would not have been predicted by Pu transport models.

Xu, C.; Santschi, P; Roberts, K; Zhong, J; Hatcher, P; Hung, C; Francis, A; Dodge, C; Honeyman, B

2008-01-01T23:59:59.000Z

72

Methods for developing seismic and extreme wind-hazard models for evaluating critical structures and equipment at US Department of Energy facilities and commercial plutonium facilities in the United States  

SciTech Connect

Lawrence Livermore National Laboratory (LLNL) is developing seismic and wind hazard models for the US Department of Energy (DOE). The work is part of a three-phase effort to establish building design criteria developed with a uniform methodology for seismic and wind hazards at the various DOE sites throughout the United States. In Phase 1, LLNL gathered information on the sites and their critical facilities, including nuclear reactors, fuel-reprocessing plants, high-level waste storage and treatment facilities, and special nuclear material facilities. Phase 2 - development of seismic and wind hazard models - is discussed in this paper, which summarizes the methodologies used by seismic and extreme-wind experts and gives sample hazard curves for the first sites to be modeled. These hazard models express the annual probability that the site will experience an earthquake (or windspeed) greater than some specified magnitude. In the final phase, the DOE will use the hazards models and LLNL-recommended uniform design criteria to evaluate critical facilities. The methodology presented in this paper also was used for a related LLNL study - involving the seismic assessment of six commercial plutonium fabrication plants licensed by the US Nuclear Regulatory Commission (NRC). Details and results of this reassessment are documented in reference.

Coats, D.W.; Murray, R.C.; Bernreuter, D.L.

1981-02-04T23:59:59.000Z

73

THE PLUTONIUM STORY  

E-Print Network (OSTI)

THE PLUTONIUM STORY Glenn T. Seaborg Lawrence Berkeley48. THE PLUTONIUM STORY Glenn T. Seaborg Lawrence Berkeley

Seaborg, G.T.

2010-01-01T23:59:59.000Z

74

Plutonium Equivalent Inventory for Belowground Radioactive Waste at the Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

SciTech Connect

The Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Many aspects of the management of this waste are conducted at Technical Area 54 (TA-54); Area G plays a key role in these management activities as the Laboratory's only disposal facility for low-level radioactive waste (LLW). Furthermore, Area G serves as a staging area for transuranic (TRU) waste that will be shipped to the Waste Isolation Pilot Plant for disposal. A portion of this TRU waste is retrievably stored in pits, trenches, and shafts. The radioactive waste disposed of or stored at Area G poses potential short- and long-term risks to workers at the disposal facility and to members of the public. These risks are directly proportional to the radionuclide inventories in the waste. The Area G performance assessment and composite analysis (LANL, 2008a) project long-term risks to members of the public; short-term risks to workers and members of the public, such as those posed by accidents, are addressed by the Area G Documented Safety Analysis (LANL, 2011a). The Documented Safety Analysis uses an inventory expressed in terms of plutonium-equivalent curies, referred to as the PE-Ci inventory, to estimate these risks. The Technical Safety Requirements for Technical Area 54, Area G (LANL, 2011b) establishes a belowground radioactive material limit that ensures the cumulative projected inventory authorized for the Area G site is not exceeded. The total belowground radioactive waste inventory limit established for Area G is 110,000 PE-Ci. The PE-Ci inventory is updated annually; this report presents the inventory prepared for 2011. The approach used to estimate the inventory is described in Section 2. The results of the analysis are presented in Section 3.

French, Sean B. [Los Alamos National Laboratory; Shuman, Rob [WPS: WASTE PROJECTS AND SERVICES

2012-04-18T23:59:59.000Z

75

EIS-0244: Plutonium Finishing Plant Stabilization, Hanford Site, Richland, WA  

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

This EIS evaluates the impacts on the human environment of: Stabilization of residual, plutonium-bearing materials at the PFP Facility to a form suitable for interim storage at the PFP Facility. Immobilization of residual plutonium-bearing materials at the PFP Facility. Removal of readily retrievable, plutonium-bearing materials left behind in process equipment, process areas, and air and liquid waste management systems as a result of historic uses.

76

Plutonium finishing plant dangerous waste training plan  

SciTech Connect

This training plan describes general requirements, worker categories, and provides course descriptions for operation of the Plutonium Finish Plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas.

ENTROP, G.E.

1999-05-24T23:59:59.000Z

77

EIS-0219: F-Canyon Plutonium Solutions  

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

This EIS evaluates the potential environmental impacts of processingthe plutonium solutions to metal form using the F-Canyon and FB-Line facilities at the Savannah River Site.

78

Cost Estimating for Decommissioning of a Plutonium Facility--Lessons Learned From The Rocky Flats Building 771 Project  

SciTech Connect

The Rocky Flats Closure Site is implementing an aggressive approach in an attempt to complete Site closure by 2006. The replanning effort to meet this goal required that the life-cycle decommissioning effort for the Site and for the major individual facilities be reexamined in detail. As part of the overall effort, the cost estimate for the Building 771 decommissioning project was revised to incorporate both actual cost data from a recently-completed similar project and detailed planning for all activities. This paper provides a brief overview of the replanning process and the original estimate, and then discusses the modifications to that estimate to reflect new data, methods, and planning rigor. It provides the new work breakdown structure and discusses the reasons for the final arrangement chosen. It follows with the process used to assign scope, cost, and schedule elements within the new structure, and development of the new code of accounts. Finally, it describes the project control methodology used to track the project, and provides lessons learned on cost tracking in the decommissioning environment.

Stevens, J. L.; Titus, R.; Sanford, P. C.

2002-02-26T23:59:59.000Z

79

ARM - Facility News Article  

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

From Coastal Clouds to Desert Dust: ARM Mobile Facility Headed to Africa Bookmark and Share ARM operations staff prepare the ARM Mobile Facility in Point Reyes, California, for...

80

Plutonium Finishing Plant safety evaluation report  

SciTech Connect

The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE`s independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91.

Not Available

1995-01-01T23:59:59.000Z

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


81

Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium  

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

Nuclear Materials & Waste » Nuclear Materials & Waste » Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium and Uranium-233 Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium and Uranium-233 105-K building houses the K-Area Material Storage (KAMS) facility, designated for the consolidated storage of surplus plutonium at Savannah River Site pending disposition. The plutonium shipped to KAMS is sealed inside a welded 3013 containers that are nested in 9975 shipping containers. 105-K building houses the K-Area Material Storage (KAMS) facility, designated for the consolidated storage of surplus plutonium at Savannah River Site pending disposition. The plutonium shipped to KAMS is sealed inside a welded 3013 containers that are nested in 9975 shipping

82

THE PLUTONIUM STORY  

E-Print Network (OSTI)

bulk of the uranium, as uranyl nitrate hexahydrate, from thelarge- amounts of uranyl nitrate from plutonium. Methods hadPlutonium. A sample of uranyl nitrate weighing 1.2 kilograms

Seaborg, G.T.

2010-01-01T23:59:59.000Z

83

Plutonium Processing Plant Deactivated | National Nuclear Security  

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

Processing Plant Deactivated | National Nuclear Security Processing Plant Deactivated | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated June 20, 1997 Hanford, WA Plutonium Processing Plant Deactivated The Plutonium Uranium Extraction Facility (PUREX), the largest of the

84

Plutonium Processing Plant Deactivated | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Processing Plant Deactivated | National Nuclear Security Processing Plant Deactivated | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated June 20, 1997 Hanford, WA Plutonium Processing Plant Deactivated The Plutonium Uranium Extraction Facility (PUREX), the largest of the

85

ARM - Facility News Article  

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

January 11, 2011 Facility News ARM Mobile Facility Completes Extended Campaign in the Azores; Next Stop-India Bookmark and Share The ARM Mobile Facility obtained data on Graciosa...

86

The sorption of thorium, protacintium and plutonium onto silica particles in the presence of a colloidal third phase  

E-Print Network (OSTI)

, such as former nuclear weapons production facilities, remain as repositories for no longer needed actinide stockpiles or waste by-products such as plutonium. All three of these actinides: thorium, protactinium, and plutonium are known to be particle...

Roberts, Kimberly Ann

2009-05-15T23:59:59.000Z

87

Facilities  

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

Facilities 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 accelerator DARHT's electron accelerators use large, circular aluminum structures to create magnetic fields that focus and steer a stream of electrons down the length of the accelerator. Tremendous electrical energy is added along the way. When the stream of high-speed electrons exits the accelerator it is

88

Final Environmental Impact Statement - Plutonium Finishing Plant Stabilization, May 1996  

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

- Plutonium Finishing Plant Stabilization, May 1996 - Plutonium Finishing Plant Stabilization, May 1996 file:///I|/Data%20Migration%20Task/EIS-0244-FEIS-1996/eis0244f_1.html[6/27/2011 2:33:34 PM] 1.0 INTRODUCTION This Introduction contains the following information: Background of the Plutonium Finishing Plant Facility Scope of this Environmental Impact Statement Contents of this Environmental Impact Statement The presence of significant quantities of plutonium-bearing materials in the Plutonium Finishing Plant (PFP) Facility, Hanford Site, Washington, poses unacceptable risks to workers, the public, and the environment. On October 24, 1994, the United States Department of Energy (DOE) announced, in an initial mailing to 1,500 interested parties, its intent to prepare an Environmental Impact Statement (EIS) pursuant to the National

89

Geomorphology of plutonium in the Northern Rio Grande  

SciTech Connect

Nearly all of the plutonium in the natural environment of the Northern Rio Grande is associated with soils and sediment, and river processes account for most of the mobility of these materials. A composite regional budget for plutonium based on multi-decadal averages for sediment and plutonium movement shows that 90 percent of the plutonium moving into the system is from atmospheric fallout. The remaining 10 percent is from releases at Los Alamos. Annual variation in plutonium flux and storage exceeds 100 percent. The contribution to the plutonium budget from Los Alamos is associated with relatively coarse sediment which often behaves as bedload in the Rio Grande. Infusion of these materials into the main stream were largest in 1951, 1952, 1957, and 1968. Because of the schedule of delivery of plutonium to Los Alamos for experimentation and weapons manufacturing, the latter two years are probably the most important. Although the Los Alamos contribution to the entire plutonium budget was relatively small, in these four critical years it constituted 71--86 percent of the plutonium in bedload immediately downstream from Otowi.

Graf, W.L. [Arizona Univ., Tempe, AZ (United States). Dept., of Geography

1993-03-01T23:59:59.000Z

90

THE PLUTONIUM STORY  

E-Print Network (OSTI)

vast processing plants at Hanford, Washington, in Decemberconsideration for use at Hanford. The various parts of thewere tested c u the Hanford concentration:, of plutonium in

Seaborg, G.T.

2010-01-01T23:59:59.000Z

91

Workers Remove Glove Boxes from Ventilation at Hanfords Plutonium Finishing Plant  

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

An employee at Hanfords Plutonium Finishing Plant uses a portable band saw to cut the last ventilation duct attached to glove boxes inside the facilitys former processing area.

92

Estimated airborne release of plutonium from Atomics International's Nuclear Materials Development Facility in the Santa Susana site, California, as a result of postulated damage from severe wind and earthquake hazard  

SciTech Connect

The potential mass of airborne releases of plutonium (source term) that could result from wind and seismic damage is estimated for the Atomics International Company's Nuclear Materials Development Facility (NMDF) at the Santa Susana site in California. The postulated source terms will be useful as the basis for estimating the potential dose to the maximum exposed individual by inhalation and to the total population living within a prescribed radius of the site. The respirable fraction of airborne particles is thus the principal concern. The estimated source terms are based on the damage ratio, and the potential airborne releases if all enclosures suffer particular levels of damage. In an attempt to provide a realistic range of potential source terms that include most of the normal processing conditions, a best estimate bounded by upper and lower limits is provided. The range of source terms is calculated by combining a high best estimate and a low damage ratio, based on a fraction of enclosures suffering crush or perforation, with the airborne release from enclosures based upon an upper limit, average, and lower limit inventory of dispersible materials at risk. Two throughput levels are considered. The factors used to evaluate the fractional airborne release of materials and the exchange rates between enclosed and exterior atmospheres are discussed. The postulated damage and source terms are discussed for wind and earthquake hazard scenarios in order of their increasing severity.

Mishima, J.; Ayer, J.E.

1981-09-01T23:59:59.000Z

93

Plutonium's Future Brightens  

Science Journals Connector (OSTI)

NUCLEAR POWER reactors fueled with plutonium may be on the way. The big step: a just-completed fuel fabrication plant at the Atomic Energy Commission's Argonne National Laboratory. Aim of the $4 million plant is to find out how plutonium-239 fuel elements ...

1959-05-25T23:59:59.000Z

94

EIS-0299: Proposed Production of Plutonium-238 (Pu-238) for Use in Advanced Radioisotope Power Systems (RPS) for Space Missions  

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

This EIS is for the proposed production of plutonium-238 (Pu-238) using one or more DOE research reactors and facilities.

95

ARM - Facility News Article  

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

96

Process modeling of plutonium conversion and MOX fabrication for plutonium disposition  

SciTech Connect

Two processes are currently under consideration for the disposition of 35 MT of surplus plutonium through its conversion into fuel for power production. These processes are the ARIES process, by which plutonium metal is converted into a powdered oxide form, and MOX fuel fabrication, where the oxide powder is combined with uranium oxide powder to form ceramic fuel. This study was undertaken to determine the optimal size for both facilities, whereby the 35 MT of plutonium metal will be converted into fuel and burned for power. The bounding conditions used were a plutonium concentration of 3--7%, a burnup of 20,000--40,000 MWd/MTHM, a core fraction of 0.1 to 0.4, and the number of reactors ranging from 2--6. Using these boundary conditions, the optimal cost was found with a plutonium concentration of 7%. This resulted in an optimal throughput ranging from 2,000 to 5,000 kg Pu/year. The data showed minimal costs, resulting from throughputs in this range, at 3,840, 2,779, and 3,497 kg Pu/year, which results in a facility lifetime of 9.1, 12.6, and 10.0 years, respectively.

Schwartz, K.L. [Univ. of Texas, Austin, TX (United States). Dept. of Nuclear Engineering

1998-10-01T23:59:59.000Z

97

Summary - Plutonium Preparation Project at the Savannah River Site  

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

Site Site EM Project: PuPP ETR Report Date: October 2008 ETR-17 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Plutonium Preparation Project at the Savannah River Site Why DOE-EM Did This Review The purpose of the Plutonium Preparation Project (PuPP) is to prepare for disposition of plutonium materials; for examination, re-stabilization, and disassembly of the Fast Flux Test Facility (FFTF) unirradiated fuel; and for repackaging of Pu stored in 3013 containers. Of ~12.8 MT of plutonium, ~4.1 MT will be directly transferred to the MOX Fuel Fabrication Facility (MFFF); ~3.7 MT will require processing prior to transfer to the MFFF; and ~5 MT was proposed to be processed in H-Canyon with the

98

Workers Complete Demolition of Hanford's Historic Plutonium Vaults |  

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

Workers Complete Demolition of Hanford's Historic Plutonium Workers Complete Demolition of Hanford's Historic Plutonium Vaults Workers Complete Demolition of Hanford's Historic Plutonium Vaults April 1, 2012 - 12:00pm Addthis RICHLAND, Wash. - The Richland Operations Office and contractor CH2M HILL Plateau Remediation Company this month completed demolition of a large plutonium vault complex, formerly one of the highest security facilities at the Hanford site. "This project was a joint safety success between our workers who spent months cleaning out the facilities, the demolition crews who tore the buildings down and the crews who helped remove the waste for disposal. It took teamwork and cooperation to remove the complex safely and efficiently," said Ty Blackford, CH2M HILL Vice President of Decommissioning, Waste, Fuels and Remediation Services.

99

Plutonium Disposition Program | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

accumulating newly separated weapon-grade plutonium. RUSSIAN PLUTONIUM DISPOSITION Russia plans to dispose of its 34 metric tons of weapon-grade plutonium by fabricating it...

100

Plutonium radiation surrogate  

DOE Patents (OSTI)

A self-contained source of gamma-ray and neutron radiation suitable for use as a radiation surrogate for weapons-grade plutonium is described. The source generates a radiation spectrum similar to that of weapons-grade plutonium at 5% energy resolution between 59 and 2614 keV, but contains no special nuclear material and emits little .alpha.-particle radiation. The weapons-grade plutonium radiation surrogate also emits neutrons having fluxes commensurate with the gamma-radiation intensities employed.

Frank, Michael I. (Dublin, CA)

2010-02-02T23:59:59.000Z

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


101

Plutonium: Requiem or reprieve  

SciTech Connect

Many scientific discoveries have had profound effects on humanity and its future. However, the discovery of fissionable characteristics of a man-made element, plutonium, discovered in 1941 by Glenn Seaborg and associates, has probably had the greatest impact on world affairs. Although about 20 new elements have been synthesized since 1940, element 94 unarguably had the most dramatic impact when it was introduced to the world as the core of the nuclear bomb dropped on Nagasaki. Ever since, large quantities of this element have been produced, and it has had a major role in maintaining peace during the past 50 years. in addition, the rapid spread of nuclear power technology worldwide contributed to major growth in the production of plutonium as a by-product. This article discusses the following issues related to plutonium: plutonium from Nuclear Power Generation; environmental safety and health issues; health effects; safeguards issues; extended storage; disposal options.

Pillay, K.K.S. [Los Alamos National Laboratory, Berkeley, CA (United States)

1996-01-01T23:59:59.000Z

102

U.S. Department of Energy Categorical Exclusion ...  

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

Testing, Calibration, and Training of Mobile Plutonium Facility (MPF) Equipment Savannah River Site AikenAikenSouth Carolina The Mobile Plutonium Facility (MPF) will use several...

103

U.S. Department of Energy Categorical Exclusion ...  

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

Infrastructure Modification for the Mobile Plutonium Facility (MPF) at the 645-N Complex Savannah River Site AikenAikenSouth Carolina Relocate Mobile Plutonium Facility (MPF) to...

104

Supplement Analysis Plutonium Consolidation  

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

9-SA-4 9-SA-4 SUPPLEMENT ANALYSIS STORAGE OF SURPLUS PLUTONIUM MATERIALS AT THE SAVANNAH RIVER SITE INTRODUCTION AND PURPOSE In April 2002, DOE decided to immediately consolidate long-term storage at the Savannah River Site (SRS) of surplus, non-pit weapons-usable plutonium then stored at the Rocky Flats Environmental Technology Site (RFETS) (DOE, 2002a). That 2002 decision did not affect an earlier DOE decision made in the January 21, 1997, Record of Decision (ROD, DOE, 1997) for the Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement (Storage and Disposition PEIS, DOE, 1996) to continue storage of non-pit surplus plutonium at Hanford, the Idaho National Laboratory (INL), and the Los Alamos

105

Plutonium in Lake Ontario  

Science Journals Connector (OSTI)

The presence of West Valley-delivered radionuclides in the western basin of Lake Ontario is demonstrated through an analysis of plutoniums and associated radionuclides in a 210Pb-dated sediment core. It is observed that the radionuclide profiles are consistent with the 1970 West Valley peak discharge and not the 1963 fallout peak activity. The drainage basin soils are estimated to annually release only about 0.006% of their fallout 239,240Pu inventory to the receiving waters. Taken together, on a lakewide basis, both releases have made very little contribution to the overall levels of plutoniums in the open waters though surges in West Valley emissions were obviously a significant contributor to western Lake Ontario waters. It appears nuclear reactor operations contribute very little plutonium to the open waters. Their influence on the nearshore zone must await the availability of relevant release and monitoring data.

S.R. Joshi

1995-01-01T23:59:59.000Z

106

Lithium metal reduction of plutonium oxide to produce plutonium metal  

DOE Patents (OSTI)

A method is described for the chemical reduction of plutonium oxides to plutonium metal by the use of pure lithium metal. Lithium metal is used to reduce plutonium oxide to alpha plutonium metal (alpha-Pu). The lithium oxide by-product is reclaimed by sublimation and converted to the chloride salt, and after electrolysis, is removed as lithium metal. Zinc may be used as a solvent metal to improve thermodynamics of the reduction reaction at lower temperatures. Lithium metal reduction enables plutonium oxide reduction without the production of huge quantities of CaO--CaCl.sub.2 residues normally produced in conventional direct oxide reduction processes.

Coops, Melvin S. (Livermore, CA)

1992-01-01T23:59:59.000Z

107

In-line measurement of plutonium and americium in mixed solutions  

SciTech Connect

A solution assay instrument (SAI) has been developed at the Los Alamos National Laboratory and installed in the plutonium purification and americium recovery process area in the Los Alamos Plutonium Processing Facility. The instrument is designed for accurate, timely, and simultaneous nondestructive analysis of plutonium and americium in process solutions that have a wide range of concentrations and Am/Pu ratios. For a 25-mL sample, the assay precision is < 1%, both for plutonium and for americium having concentrations >5 g/L within a 2000-s count time.

Li, T.K.

1981-01-01T23:59:59.000Z

108

Plutonium 239 Equivalency Calculations  

SciTech Connect

This document provides the basis for converting actual weapons grade plutonium mass to a plutonium equivalency (PuE) mass of Plutonium 239. The conversion can be accomplished by performing calculations utilizing either: (1) Isotopic conversions factors (CF{sub isotope}), or (2) 30-year-old weapons grade conversion factor (CF{sub 30 yr}) Both of these methods are provided in this document. Material mass and isotopic data are needed to calculate PuE using the isotopic conversion factors, which will provide the actual PuE value at the time of calculation. PuE is the summation of the isotopic masses times their associated isotopic conversion factors for plutonium 239. Isotopic conversion factors are calculated by a normalized equation, relative to Plutonium 239, of specific activity (SA) and cumulated dose inhalation affects based on 50-yr committed effective dose equivalent (CEDE). The isotopic conversion factors for converting weapons grade plutonium to PuE are provided in Table-1. The unit for specific activity (SA) is curies per gram (Ci/g) and the isotopic SA values come from reference [1]. The cumulated dose inhalation effect values in units of rem/Ci are based on 50-yr committed effective dose equivalent (CEDE). A person irradiated by gamma radiation outside the body will receive a dose only during the period of irradiation. However, following an intake by inhalation, some radionuclides persist in the body and irradiate the various tissues for many years. There are three groups CEDE data representing lengths of time of 0.5 (D), 50 (W) and 500 (Y) days, which are in reference [2]. The CEDE values in the (W) group demonstrates the highest dose equivalent value; therefore they are used for the calculation.

Wen, J

2011-05-31T23:59:59.000Z

109

Characterizing Surplus US Plutonium for Disposition - 13199  

SciTech Connect

The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems. (authors)

Allender, Jeffrey S. [Savannah River National Laboratory, Aiken SC 29808 (United States)] [Savannah River National Laboratory, Aiken SC 29808 (United States); Moore, Edwin N. [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)] [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)

2013-07-01T23:59:59.000Z

110

Characterizing surplus US plutonium for disposition  

SciTech Connect

The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems.

Allender, Jeffrey S.; Moore, Edwin N.

2013-02-26T23:59:59.000Z

111

Demolition Begins on Hanford's Historic Plutonium Vaults - Plutonium  

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

Demolition Begins on Hanford's Historic Plutonium Vaults - Demolition Begins on Hanford's Historic Plutonium Vaults - Plutonium Finishing Plant on track to meet regulatory milestone Demolition Begins on Hanford's Historic Plutonium Vaults - Plutonium Finishing Plant on track to meet regulatory milestone November 18, 2011 - 12:00pm Addthis Media Contacts Geoff Tyree Department of Energy Geoffrey.Tyree@rl.doe.gov 509-376-4171 Dee Millikin CH2M HILL Plateau Remediation Company Dee_Millikin@rl.gov 509-376-1297 RICHLAND, WASH. - The U.S. Department of Energy (DOE) and contractor CH2M HILL Plateau Remediation Company (CH2M HILL) began demolishing a vault complex that once held stores of plutonium for the U.S. nuclear weapons program at the Hanford Site in southeast Washington State. The vault complex is part of Hanford's Plutonium Finishing Plant, which

112

Safeguards on Plutonium  

Science Journals Connector (OSTI)

... reactors throughout the world. They promise cheap power and such other important benefits as the desalination of seawater. Although the economic forecasts have generally been over-optimistic, commercial organizations are ... kind of plutonium; or any number of other technical factors may have changed the basic economics of power production.

LEONARD BEATON

1966-12-31T23:59:59.000Z

113

XANES Identification of Plutonium Speciation in RFETS Samples  

SciTech Connect

Using primarily X-ray absorption near edge spectroscopy (XANES) with standards run in tandem with samples, probable plutonium speciation was determined for 13 samples from contaminated soil, acid-splash or fire-deposition building interior surfaces, or asphalt pads from the Rocky Flats Environmental Technology Site (RFETS). Save for extreme oxidizing situations, all other samples were found to be of Pu(IV) speciation, supporting the supposition that such contamination is less likely to show mobility off site. EXAFS analysis conducted on two of the 13 samples supported the validity of the XANES features employed as determinants of the plutonium valence.

LoPresti, V.; Conradson, S.D.; Clark, D.L.

2009-06-03T23:59:59.000Z

114

Rebaselining seismic risks for resumption of Building 707 plutonium operations at the Rocky Flats Plant  

SciTech Connect

Natural phenomena risks have been assessed for plutonium handling facilities at the Rocky Flats Plant, based on numerous studies performed for the Department of Energy Natural Phenomena Hazards Project. The risk assessment was originally utilized in the facilities Final Safety Analysis Reports and in subsequent risk management decisions. Plutonium production operations were curtailed in 1989 in order for a new operating contractor to implement safety improvements. Since natural phenomena events dominated risks to the public, a re-assessment of these events were undertaken for resumption of plutonium operations.

Elia, F. Jr. [Stone and Webster Engineering Corp., Boston, MA (United States); Foppe, T.; Stahlnecker, E. [EG and G Rocky Flats, Inc., Golden, CO (United States)

1993-08-01T23:59:59.000Z

115

ARM - Facility News Article  

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

February 16, 2005 [Facility News] 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 Image - The ARM Mobile Facility in Point Reyes, California Safe and sound at Point Reyes, the ARM Mobile Facility instrumentation is set up on the roof of a shelter until a fence is installed to keep out the curious local cattle. On February 9, the ARM Mobile Facility (AMF) withstood an accident on the way to its deployment location at Point Reyes, California. About an hour from its destination, the truck carrying the two AMF shelters packed with instrumentation and associated equipment swerved to avoid another vehicle and slid off the road and down a steep embankment. Emergency personnel soon

116

Plutonium Consolidation Amended ROD  

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

6450-01-P] 6450-01-P] DEPARTMENT OF ENERGY Amended Record of Decision: Storage of Surplus Plutonium Materials at the Savannah River Site AGENCY: Department of Energy ACTION: Amended Record of Decision SUMMARY: The U.S. Department of Energy (DOE) is amending the Record of Decision (ROD) for the Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement (DOE/EIS-0229, 1996; Storage and Disposition PEIS). Specifically, DOE has decided to take the actions necessary to transfer approximately 2,511 additional 3013-compliant packages 1 containing surplus non-pit weapons-usable plutonium metals and oxides to the Savannah River Site (SRS), near Aiken, South Carolina. Approximately 2,300 containers will be transferred from the Hanford Site (Hanford) near

117

Manufacturing of Plutonium Tensile Specimens  

SciTech Connect

Details workflow conducted to manufacture high density alpha Plutonium tensile specimens to support Los Alamos National Laboratory's science campaigns. Introduces topics including the metallurgical challenge of Plutonium and the use of high performance super-computing to drive design. Addresses the utilization of Abaqus finite element analysis, programmable computer numerical controlled (CNC) machining, as well as glove box ergonomics and safety in order to design a process that will yield high quality Plutonium tensile specimens.

Knapp, Cameron M [Los Alamos National Laboratory

2012-08-01T23:59:59.000Z

118

PLUTONIUM-238 PRODUCTION TARGET DESIGN STUDIES  

SciTech Connect

A new supply chain is planned for plutonium-238 using existing reactors at the Oak Ridge National Laboratory (ORNL) and Idaho National Laboratory (INL) and existing chemical recovery facilities at ORNL. Validation and testing activities for new irradiation target designs have been conducted in three phases over a 2 year period to provide data for scale-up to production. Target design, qualification, target fabrication, and irradiation of fully-loaded targets have been accomplished. Data from post-irradiation examination (PIE) supports safety analysis and irradiation of future target designs.

Hurt, Christopher J [ORNL; Wham, Robert M [ORNL; Hobbs, Randall W [ORNL; Owens, R Steven [ORNL; Chandler, David [ORNL; Freels, James D [ORNL; Maldonado, G Ivan [ORNL

2014-01-01T23:59:59.000Z

119

Independent Activity Report, Hanford Plutonium Finishing Plant...  

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

Plutonium Finishing Plant - May 2012 Independent Activity Report, Hanford Plutonium Finishing Plant - May 2012 May 2012 Criticality Safety Information Meeting for the Hanford...

120

TECHNIQUES FOR MONITORING PLUTONIUM IN THE ENVIRONMENT  

E-Print Network (OSTI)

Detection for Plutonium and Americium Wound Counting," Rockyin vivo Measurement of Americium and Plutonium," Rocky Flatsof its decay daughter, americium 241, are also given since

Nero Jr., A.V.

2011-01-01T23:59:59.000Z

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


121

Rough order of magnitude cost estimate for immobilization of 50MT of plutonium using new faciliites at the Savannah River site: alternative 12A  

SciTech Connect

The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 50 metric tons of plutonium using ceramic in a new facility at Savannah River Site (SRS).

DiSabatino, A., LLNL

1998-06-01T23:59:59.000Z

122

Plutonium and americium behavior in coral atoll environments  

SciTech Connect

Inventories of /sup 239 +240/Pu and /sup 241/Am greatly in excess of global fallout levels persist in the benthic environments of Bikini and Enewetak Atolls. Quantities of /sup 239 +240/Pu and lesser amounts of /sup 241/Am are continuously mobilizing from these sedimentary reservoirs. The amount of /sup 239 +240/Pu mobilized to solution at any time represents 0.08 to 0.09% of the sediment inventories to a depth of 16 cm. The mobilized /sup 239 +240/Pu has solute-like characteristics and different valence states coexist in solution - the largest fraction of the soluble plutonium is in an oxidized form (+V,VI). The adsorption of plutonium to sediments is not completely reversible because of changes that occur in the relative amounts of the mixed oxidation states in solution with time. Further, any characteristics of /sup 239 +240/Pu described at one location may not necessarily be relevant in describing its behavior elsewhere following mobilization and migration. The relative amounts of /sup 241/Am to /sup 239 +240/Pu in the sedimentary deposits at Enewetak and Bikini may be altered in future years because of mobilization and radiological decay. Mobilization of /sup 239 +240/Pu is not a process unique to these atolls, and quantities in solution derived from sedimentary deposits can be found at other global sites. These studies in the equatorial Pacific have significance in assessing the long-term behavior of the transuranics in any marine environment. 22 references, 1 figure, 13 tables.

Noshkin, V.E.; Wong, K.M.; Jokela, T.A.; Brunk, J.L.; Eagle, R.J.

1984-02-01T23:59:59.000Z

123

Airborne release fractions/rates and respirable fractions for nonreactor nuclear facilities. Volume 2, Appendices  

SciTech Connect

This document contains compiled data from the DOE Handbook on Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear facilities. Source data and example facilities utilized, such as the Plutonium Recovery Facility, are included.

Not Available

1994-12-01T23:59:59.000Z

124

LANL | Physics | Dynamic Plutonium Experiments  

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

Dynamic plutonium experiments Dynamic plutonium experiments Since the end of nuclear testing the nation has had to rely on sophisticated computer models to ensure the safety and reliability of the nuclear weapons stockpile. This program is known as science-based stockpile stewardship. Despite possessing the world's fastest computers and most advanced modeling capability, the behavior of materials under dynamic loads that occur in a nuclear weapon are difficult to accurately model. The Dynamic Plutonium experimental program carries out experiments at the Nevada National Security Site on plutonium driven by high explosives. These experiments are needed to measure and understand the behavior of plutonium under extreme conditions. Physics Division has unique capabilities in high-speed x-ray imaging and velocimetry (measuring the

125

Integrated development and testing plan for the plutonium immobilization project  

SciTech Connect

This integrated plan for the DOE Office of Fissile Materials Disposition (MD) describes the technology development and major project activities necessary to support the deployment of the immobilization approach for disposition of surplus weapons-usable plutonium. The plan describes details of the development and testing (D&T) tasks needed to provide technical data for design and operation of a plutonium immobilization plant based on the ceramic can-in-canister technology (''Immobilization Fissile Material Disposition Program Final Immobilization Form Assessment and Recommendation'', UCRL-ID-128705, October 3, 1997). The plan also presents tasks for characterization and performance testing of the immobilization form to support a repository licensing application and to develop the basis for repository acceptance of the plutonium form. Essential elements of the plant project (design, construction, facility activation, etc.) are described, but not developed in detail, to indicate how the D&T results tie into the overall plant project. Given the importance of repository acceptance, specific activities to be conducted by the Office of Civilian Radioactive Waste Management (RW) to incorporate the plutonium form in the repository licensing application are provided in this document, together with a summary of how immobilization D&T activities provide input to the license activity. The ultimate goal of the Immobilization Project is to develop, construct, and operate facilities that will immobilize from about 18 to 50 tonnes (MT) of U.S. surplus weapons usable plutonium materials in a manner that meets the ''spent fuel'' standard (Fissile Materials Storage and Disposition Programmatic Environmental Impact Statement Record of Decision, ''Storage and Disposition Final PEIS'', issued January 14, 1997, 62 Federal Register 3014) and is acceptable for disposal in a geologic repository. In the can-in-canister technology, this is accomplished by encapsulating the plutonium-containing ceramic forms within large canisters of high level waste (HLW) glass. Deployment of the immobilization capability should occur by 2006 and be completed within 10 years.

Kan, T.

1998-07-01T23:59:59.000Z

126

ARM - Facility News Article  

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

March 22, 2007 [Facility News] March 22, 2007 [Facility News] GEWEX News Features Dust Data from ARM Mobile Facility Deployment Bookmark and Share Data from the recent deployment of the ARM Mobile Facility are featured in the February issue of GEWEX News. Data from the recent deployment of the ARM Mobile Facility are featured in the February issue of GEWEX News. The February 2007 issue (Vol. 17, No. 1) of GEWEX News features early results from special observing periods of the African Monsoon Mutidisciplinary Analysis, including data obtained by the ARM Mobile Facility (AMF). The AMF was stationed in the central Sahel from January through December 2006, with the primary facility at the Niamey airport, and an ancillary site in Banizoumbou. The AMF recorded a major dust storm that passed through the area in March, and combined with simultaneous satellite

127

Identification of a physical metallurgy surrogate for the plutonium1 wt.?% gallium alloy  

Science Journals Connector (OSTI)

Future plutonium research is expected to be limited due to the downsizing of the nuclear weapons complex and an industry focus on environmental remediation and decommissioning of former manufacturing and research facilities. However the need to further the understanding of the behavior of plutonium has not diminished. Disposition of high level residues long-term storage of wastes and certification of the nuclear stockpile through the Stockpile Stewardship Program are examples of the complex issues that must be addressed. Limited experimental facilities and the increasing cost of conducting plutonium research provide a strong argument for the development of surrogate materials. The purpose of this work was to identify a plutonium surrogate based on fundamental principles such as electronic structure and then to experimentally demonstrate its viability.

Frank E. Gibbs; David L. Olson; William Hutchinson

2000-01-01T23:59:59.000Z

128

Fissile Material Disposition Program: Deep borehole disposal Facility PEIS date input report for immobilized disposal. Immobilized disposal of plutonium in coated ceramic pellets in grout with canisters. Version 3.0  

SciTech Connect

Following President Clinton`s Non-Proliferation Initiative, launched in September, 1993, an Interagency Working Group (IWG) was established to conduct a comprehensive review of the options for the disposition of weapons-usable fissile materials from nuclear weapons dismantlement activities in the United States and the former Soviet Union. The IWG review process will consider technical, nonproliferation, environmental budgetary, and economic considerations in the disposal of plutonium. The IWG is co-chaired by the White House Office of Science and Technology Policy and the National Security Council. The Department of Energy (DOE) is directly responsible for the management, storage, and disposition of all weapons-usable fissile material. The Department of Energy has been directed to prepare a comprehensive review of long-term options for Surplus Fissile Material (SFM) disposition, taking into account technical, nonproliferation, environmental, budgetary, and economic considerations.

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15T23:59:59.000Z

129

ARM - Facility News Article  

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

July 31, 2009 [Facility News] July 31, 2009 [Facility News] President of the Regional Government Speaks at Opening Ceremony for Mobile Facility in the Azores Bookmark and Share Highlighting the opening ceremony for the ARM Mobile Facility on Graciosa Island, Carlos César, President of the Regional Government of the Azores, signs a weather balloon while local media record the event. Photo by Mike Alsop. Highlighting the opening ceremony for the ARM Mobile Facility on Graciosa Island, Carlos César, President of the Regional Government of the Azores, signs a weather balloon while local media record the event. Photo by Mike Alsop. On June 30, officials from the Regional Government of the Azores recognized the deployment of the ARM Mobile Facility on Graciosa Island during an official opening ceremony held at the site. Notable among the participants

130

ARM - Facility News Article  

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

8, 2011 [Facility News, Publications] 8, 2011 [Facility News, Publications] Journal Special Issue Includes Mobile Facility Data from Germany Bookmark and Share The ARM Mobile Facility operated in Heselbach, Germany, as part of the COPS surface network. The ARM Mobile Facility operated in Heselbach, Germany, as part of the COPS surface network. In 2007, the ARM Mobile Facility participated in one of the most ambitious field studies ever conducted in Europe-the Convective and Orographically Induced Precipitation Study (COPS). Now, 21 papers published in a special issue of the Quarterly Journal of the Royal Meteorological Society demonstrate that the data collected during COPS are providing new insight into: the key chemical and physical processes leading to convection initiation and to the modification of precipitation by orography;

131

ARM - Facility News Article  

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

8, 2010 [Facility News] 8, 2010 [Facility News] Europeans Keen to Hear About Effects of Dust Using Data from Africa Bookmark and Share In 2006, the ARM Mobile Facility joined the AMMA project to obtain data for scientists to study the impact that airborne Saharan dust has on incoming solar radiation. This photo shows the sun setting through a dusty atmosphere near Niamey, Niger, where the mobile facility was deployed for one year. In 2006, the ARM Mobile Facility joined the AMMA project to obtain data for scientists to study the impact that airborne Saharan dust has on incoming solar radiation. This photo shows the sun setting through a dusty atmosphere near Niamey, Niger, where the mobile facility was deployed for one year. Researcher Xiaohong Liu from Pacific Northwest National Laboratory was

132

ARM - Facility News Article  

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

April 30, 2008 [Facility News] April 30, 2008 [Facility News] Team Scouts Graciosa Island for 2009 Mobile Facility Deployment Site Bookmark and Share A location near the airport on the northern end of Graciosa Island was identified as an excellent location for operating the ARM Mobile Facility. Image source: Luis Miguens A location near the airport on the northern end of Graciosa Island was identified as an excellent location for operating the ARM Mobile Facility. Image source: Luis Miguens Indications from a scouting trip by the ARM Mobile Facility (AMF) science and operations management team are that an excellent site for the 2009 deployment may have been found. From April 8 through April 16, the team traveled to Graciosa Island in the Azores to scout sites for the Clouds, Aerosol, and Precipitation in the Marine Boundary Layer (CAP-MBL) field

133

LITERATURE REVIEW FOR OXALATE OXIDATION PROCESSES AND PLUTONIUM OXALATE SOLUBILITY  

SciTech Connect

A literature review of oxalate oxidation processes finds that manganese(II)-catalyzed nitric acid oxidation of oxalate in precipitate filtrate is a viable and well-documented process. The process has been operated on the large scale at Savannah River in the past, including oxidation of 20 tons of oxalic acid in F-Canyon. Research data under a variety of conditions show the process to be robust. This process is recommended for oxalate destruction in H-Canyon in the upcoming program to produce feed for the MOX facility. Prevention of plutonium oxalate precipitation in filtrate can be achieved by concentrated nitric acid/ferric nitrate sequestration of oxalate. Organic complexants do not appear practical to sequester plutonium. Testing is proposed to confirm the literature and calculation findings of this review at projected operating conditions for the upcoming campaign. H Canyon plans to commence conversion of plutonium metal to low-fired plutonium oxide in 2012 for eventual use in the Mixed Oxide Fuel (MOX) Facility. The flowsheet includes sequential operations of metal dissolution, ion exchange, elution, oxalate precipitation, filtration, and calcination. All processes beyond dissolution will occur in HB-Line. The filtration step produces an aqueous filtrate that may have as much as 4 M nitric acid and 0.15 M oxalate. The oxalate needs to be removed from the stream to prevent possible downstream precipitation of residual plutonium when the solution is processed in H Canyon. In addition, sending the oxalate to the waste tank farm is undesirable. This report addresses the processing options for destroying the oxalate in existing H Canyon equipment.

Nash, C.

2012-02-03T23:59:59.000Z

134

Assessment of plutonium in the Savannah River Site environment. Revision 1  

SciTech Connect

Plutonium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fifth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. These are living documents, each to be revised and updated on a two-year schedule. This document describes the sources of plutonium in the environment, its release from SRS, environmental transport and ecological concentration of plutonium, and the radiological impact of SRS releases to the environment. Plutonium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite SNAP 9-A, plane crashes involving nuclear weapons, and small releases from reactors and reprocessing plants. Plutonium has been produced at SRS during the operation of five production reactors and released in small quantities during the processing of fuel and targets in chemical separations facilities. Approximately 0.6 Ci of plutonium was released into streams and about 12 Ci was released to seepage basins, where it was tightly bound by clay in the soil. A smaller quantity, about 3.8 Ci, was released to the atmosphere. Virtually all releases have occurred in F- and H-Area separation facilities. Plutonium concentration and transport mechanisms for the atmosphere, surface water, and ground water releases have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases to the offsite maximum individual can be characterized by a total dose of 15 mrem (atmospheric) and 0.18 mrem (liquid), compared with the dose of 12,960 mrem from non-SRS sources during the same period of time (1954--1989). Plutonium releases from SRS facilities have resulted in a negligible impact to the environment and the population it supports.

Carlton, W.H.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

1992-12-31T23:59:59.000Z

135

Certification of Plutonium Standards for KAMS Neutron Multiplicity Counter  

SciTech Connect

As part of the implementation of the PEIS record of decision in January of 1997, DOE will pursue two technologies to disposition fifty metric tons of its stockpile of plutonium. As a result of this and in order to expedite the closure of Rocky Flats Environmental Technology Site in Colorado, DOE decided to use existing facilities at the Savannah River Site (SRS) for storing all material containing plutonium at KAMS. A neutron multiplicity counter was designed and built to carry out receipt verification measurement at the facility. Since the material covers a wide range and different levels of impurities, it is essential that we obtain a set of working standards. An agreement was drafted to select the first drums to be these standards. A plan was developed for the certification of these standards using Rocky Flat's existing nondestructive assay equipment. This paper will discuss the types of materials to be shipped to SRS, number of standards to certify for each type of material, and the certification plan. It will also discuss the activities necessary to determine the nuclear content of these working standards to be used at SRS facilities in support of shipment and receipt of the Pu containing materials. Definition of instrument qualifications, measurement control processes, measurement methodologies, and calculations necessary to report the gram quantities and their uncertainties for plutonium, americium-241, uranium-235 (if present) and neptunium-237 (if present) will also be presented.

Salaymeh, S.R.

2002-05-31T23:59:59.000Z

136

Establishing interim authorization bases for resumption of plutonium operations  

SciTech Connect

DOE Order 5480.23, Nuclear Safety Analysis Reports, requires that DOE facilities have an approved SAR (Safety Analysis Report). Rocky Flats Plant has a number of facilities for which no SAR exists. DOE Order 5480.21, Unreviewed Safety Questions, makes allowance for the operation of facilities without adequate SARs, through the establishment of an interim Authorization Basis (AB). In order to establish an AB, the nuclear facility must define the population of documents comprising the various elements of the AB and must use this defined population of documents as the basis for performing safety evaluations under DOE requirements. This short note explains the steps Rocky Flats Plant is taking to catalog the large body of documents available in order to establish an AB for those facilities needed to resume plutonium operations.

Ealy, K.; Satterwhite, D.

1993-06-01T23:59:59.000Z

137

PASSIVE NMIS MEASUREMENTS TO ESTIMATE SHAPE OF PLUTONIUM ASSEMBLIES (SLIDE PRESENTATION)  

SciTech Connect

The purpose of this work is to estimate shape of plutonium assemblies using new signatures acquired by passive NMIS measurements (no external source). Applications include identification of containerized regular shapes of plutonium, identification by shape without template, verification of shape for template initialization, and potential utility for estimating shape of holdup in plutonium processing facilities. To illustrate the technique and test its feasibility, laboratory measurements have been performed with californium spontaneous fission sources as a surrogate for plutonium. Advantages of the technique include the following: passive (requires no external source for plutonium measurements), stationary (no scanning of the assembly is required), penetrative (shape is estimated from neutron emissions), obscurable (spatial resolution can be deliberately degraded by changing detector size and/or timing resolution), inexpensive (majority of NMIS components are commercial products), portable (detection system is transported to the item, not vice versa). It is concluded that passive NMIS measurements can infer the mass of plutonium assemblies: NMIS correlations scale directly with spontaneous fission rate (Pu-240); NMIS correlations scale with fissile mass (Pu-239) and multiplication. New third-order correlations can estimate the shape of fission sources (Pu-240 & Pu-239) from passive measurements. Surrogate measurements of californium spontaneous fission sources have demonstrated the feasibility of this concept. Measurements of various shapes of plutonium are necessary to continue the development of this technique.

MARCH-LEUBA, J.A.; MATTINGLY, J.K.; MIHALCZO, J.T.; PEREZ, R.B.; VALENTINE, T.E.

1998-11-25T23:59:59.000Z

138

Plutonium distribution: Summary of public and governmental support issues  

SciTech Connect

Obtaining strong public and governmental support for the plutonium disposition program and for the projects comprising the selected disposition options will be essential to the success of the program in meeting non-proliferation goals established as national policy. This paper summarizes issues related to public and governmental support for plutonium disposition. Recommendations are offered which rest on two fundamental assumptions: (1) public and political support derive from public trust and confidence, and (2) despite widespread support for U.S. non-proliferation goals, establishing and operating facilities to carry out the program will entail controversy. Documentation for the Administration`s policy on non-proliferation as it relates to plutonium disposition is cited and summarized as background for ongoing planning efforts by the Department of Energy (DOE). Consensus is a reasonable goal for efforts to secure public and governmental support for the plutonium disposition program and its elements; unanimity is very unlikely. The program will be aided by the popular recognition of the importance of the nation`s non-proliferation goals, the potential for an energy dividend if an energy production option is selected ({open_quotes}Swords to Plowshares{close_quotes} metaphor), the possibility of influencing disposition decisions in other countries, and the clear need to do something with the excess material ({open_quotes}the no action alternative{close_quotes} will not suffice).

Pasternak, A.

1995-03-31T23:59:59.000Z

139

Interaction of Plutonium with Bacteria in the Repository Environment  

SciTech Connect

Microorganisms in the nuclear waste repository environment may interact with plutonium through (1) sorption, (2) intracellular accumulation, and (3) transformation speciation. These interactions may retard or enhance the mobility of Pu by precipitation reactions, biocolloid formation, or production of more soluble species. Current and planned radioactive waste repository environments, such as deep subsurface halite and granite formations, are considered extreme relative to life processes in the near-surface terrestrial environment. There is a paucity of information on the biotransformation of radionuclides by microorganisms present in such extreme environments. In order to gain a better understanding of the interaction of plutonium with microorganisms present in the waste repository sites we investigated a pure culture (Halomonas sp.) and a mixed culture of bacteria (Haloarcula sinaiiensis, Marinobacter hydrocarbonoclasticus, Altermonas sp., and a {gamma}-proteobacterium) isolated from the Waste Isolation Pilot Plant (WIPP) site and an Acetobacterium sp. from alkaline groundwater at the Grimsel Test Site in Switzerland.

Gillow, J. B.; Francis, A. J.; Lucero, D. A.; Papenguth, H. W.

2000-07-01T23:59:59.000Z

140

Plutonium focus area  

SciTech Connect

To ensure research and development programs focus on the most pressing environmental restoration and waste management problems at the U.S. Department of Energy (DOE), the Assistant Secretary for the Office of Environmental Management (EM) established a working group in August 1993 to implement a new approach to research and technology development. As part of this new approach, EM developed a management structure and principles that led to the creation of specific Focus Areas. These organizations were designed to focus the scientific and technical talent throughout DOE and the national scientific community on the major environmental restoration and waste management problems facing DOE. The Focus Area approach provides the framework for intersite cooperation and leveraging of resources on common problems. After the original establishment of five major Focus Areas within the Office of Technology Development (EM-50, now called the Office of Science and Technology), the Nuclear Materials Stabilization Task Group (EM-66) followed the structure already in place in EM-50 and chartered the Plutonium Focus Area (PFA). The following information outlines the scope and mission of the EM, EM-60, and EM-66 organizations as related to the PFA organizational structure.

NONE

1996-08-01T23:59:59.000Z

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


141

Solution Speciation of Plutonium and Americium at an Australian Legacy Radioactive Waste Disposal Site  

Science Journals Connector (OSTI)

During the 1960s, radioactive waste containing small amounts of plutonium (Pu) and americium (Am) was disposed in shallow trenches at the Little Forest Burial Ground (LFBG), located near the southern suburbs of Sydney, Australia. ... It should also be taken into account that, at some sites, such as the Maxey Flats disposal site,(19) codisposed organic contaminants have been implicated in actinide mobilization. ...

Atsushi Ikeda-Ohno; Jennifer J. Harrison; Sangeeth Thiruvoth; Kerry Wilsher; Henri K. Y. Wong; Mathew P. Johansen; T. David Waite; Timothy E. Payne

2014-08-15T23:59:59.000Z

142

NASA pulls plug on plutonium power source  

Science Journals Connector (OSTI)

... Generators (MMRTGs) but use four times less plutonium-238, a scarce resource. An MMRTG containing 4.8 kilograms of plutonium is currently powering the Curiosity rover on Mars. ...

Eugenie Samuel Reich

2013-11-18T23:59:59.000Z

143

Vitrification of excess plutonium  

SciTech Connect

As a result of nuclear disarmament activities, many thousands of nuclear weapons are being retired in the US and Russia, producing a surplus of about 50 MT of weapons grade plutonium (Pu) in each country. In addition, the Department of Energy (DOE) has more than 20 MT of Pu scrap, residue, etc., and Russia is also believed to have at least as much of this type of material. The entire surplus Pu inventories in the US and Russia present a clear and immediate danger to national and international security. It is important that a solution be found to secure and manage this material effectively and that such an effort be implemented as quickly as possible. One option under consideration is vitrification of Pu into a relatively safe, durable, accountable, proliferation-resistant form. As a result of decades of experience within the DOE community involving vitrification of a variety of hazardous and radioactive wastes, this existing technology can now be expanded to include immobilization of large amounts of Pu. This technology can then be implemented rapidly using the many existing resources currently available. A strategy to vitrify many different types of Pu will be discussed. In this strategy, the arsenal of vitrification tools, procedures and techniques already developed throughout the waste management community can be used in a staged Pu vitrification effort. This approach uses the flexible vitrification technology already available and can even be made portable so that it may be brought to the source and ultimately, used to produce a common, borosilicate glass form for the vitrified Pu. The final composition of this product can be made similar to nationally and internationally accepted HLW glasses.

Wicks, G.G.; Mckibben, J.M.; Plodinec, M.J.

1994-12-31T23:59:59.000Z

144

NNSA B-Roll: MOX Facility  

SciTech Connect

In 1999, the National Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus weapon-grade plutonium, remove impurities, and mix it with uranium oxide to form MOX fuel pellets for reactor fuel assemblies. These assemblies will be irradiated in commercial nuclear power reactors.

2010-05-21T23:59:59.000Z

145

Comparative behavior of plutonium and americium in the equatorial Pacific  

SciTech Connect

Inventories of /sup 239 +240/Pu and /sup 241/Am greatly in excess of global fallout levels persist in the benthic environments of Bikini and Enewetak Atolls. The amount of /sup 239 +240/Pu mobilized to solution at the atolls can be predicted from a distribution coefficient K/sub d/ of 2.3 x 10/sup 5/ and the mean sediment concentrations. The mobilized /sup 239 +240/Pu has solute-like characteristics and different valence states coexist in solution - the largest fraction of the soluble plutonium is in an oxidized form (+V,VI). The adsorption of plutonium to sediments is not completely reversible because of changes that occur in the relative amounts of the mixed oxidation states in solution with time. Characteristics of /sup 239 +240/Pu described at one location may not necessarily describe its behavior elsewhere. The relative amounts of /sup 241/Am to /sup 239 +240/Pu may be altered in future years because of mobilization and radiological decay.

Noshkin, V.E.; Wong, K.M.; Jokela, T.A.; Brunk, J.L.; Eagle, R.J.

1983-01-01T23:59:59.000Z

146

Temporary (mobile) storage testing facilities  

E-Print Network (OSTI)

.8 kV 115 kV CGI bus NWTC wind turbines Alstom 3 MW Siemens 2.3 MW GE 1.5 MW Gamesa 2 MW NREL- standing of how wind turbines react to grid disturbances. To understand the behavior of wind turbines and international levels by wind turbine manufacturers, certification authorities, and utilities. Utility operators

147

John C. Barnes of Savannah River Operations named 2012 Facility...  

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

the Savannah River Site, including the F and H-Canyons and the HB-Line. These facilities conduct hazardous nuclear chemistry, packaging, and processing operations on plutonium and...

148

ARM - Facility News Article  

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

field campaign are now open. GOAMAZON is a deployment of the ARM Mobile Facility to Brazil beginning in 2014. The three calls are being issued in coordination by the U.S....

149

ARM - Facility News Article  

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

Preparations Underway for 2007 ARM Mobile Facility Deployment in Germany Bookmark and Share In the Black Forest region of Germany, the COPS field campaign will cover an area of...

150

Cost-benefit analysis of unfired PuO/sub 2/ pellets as an alternative plutonium shipping form  

SciTech Connect

A limited cost-benefit evaluation was performed concerning use of unfired plutonium dioxide pellets as a shipping form. Two specific processing operations are required for this use, one to form the pellet (pelletizing) and a second to reconstitute an acceptable powder upon receipt (reconstitution). The direct costs for the pelletizing operation are approximately $208,000 for equipment and its installation and $122 per kg of plutonium processed (based upon a 20-kg plutonium/day facility). The direct costs for reconstitution are approximately $90,000 for equipment and its installation and $81 per kg of plutonium processed. The indirect cost considered was personnel exposure from these operations. Whole body exposures ranged from 0.04 man-rem per 100 kg of low-exposure plutonium reconstituted to 0.9 man-rem per 100 kg of average-exposure plutonium pelletized. Hand exposures were much higher - 17 man-rem power 100 kg of low-exposure plutonium reconstituted to 67 man-rem per 100 kg of average plutonium pelletized. The principal benefit is a potential twentyfold reduction of airborne release in the event of an accident. An experimental plan is outlined to fill the data gaps uncovered during this study in the areas of pelletizing and reconstitution process parameters and pellet response behavior to accident-generated stresses. A study to enhance the containment potential of the inner packaging used during shipment is also outlined.

Mishima, J.; Brackenbush, L.W.; Libby, R.A.; Soldat, K.L.; White, G.D.

1983-10-01T23:59:59.000Z

151

Type B Accident Investigation on the August 5, 2003, Pu-238 Multiple Uptake Event at the Pu Facility, Los Alamos National Laboratory  

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

On August 5, 2003, a release of plutonium-238 occurred in a storage room at the Plutonium Facility, Los Alamos National Laboratory, resulting in radiation doses to two workers in the room. The Accident Investigation Board concluded that the direct cause of the accident was the release of airborne contamination from a degraded package that contained cellulose material and plutonium-238 residues.

152

Establishing an authorization basis for the Plutonium Finishing Plant  

SciTech Connect

In the summer of 1998, Hanford's Plutonium Finishing Plant (PFP) project prepared to restart its thermal stabilization process after 1(1/2)-yr suspension in operations. The facility had overcome a number of operational and safety problems, yet it had been unable to achieve appropriate update, approval, and implementation of an appropriate, current authorization basis. This problem threatened to prevent a timely restart, which, in turn, could have caused a loss in momentum and dampened enthusiasm within the facility. The authors describe the approach taken by B and W Hanford Company (BWHC) in conjunction with its partners, the US Department of Energy (DOE) Richland Operations Office and Fluor Daniel Hanford Company (FDH), to establish a defensible authorization basis, which allowed the facility to resume its mission of stabilizing reactive plutonium materials. The approach incorporates methods used within the DOE complex for short-term activities and those undergoing deactivation and implements principles of integrated safety management (ISM), as described in ``Defense Nuclear Facility Safety Board [(DNFSB)] Recommendation 95-2'' and related documents.

Roege, P.E.; Ramble, A.L.

1999-07-01T23:59:59.000Z

153

MOBILE SENSING 1 MOBILE SENSING  

E-Print Network (OSTI)

MOBILE SENSING 1 MOBILE SENSING ! ! Parham Aarabi #12;MOBILE SENSING 2 20 years of sensing research #12;MOBILE SENSING 3 Low Likelihood High Likelihood #12;MOBILE SENSING 4 Image Courtesy of Apple Inc. #12;MOBILE SENSING 5 What can we do with all the sensors on our mobile devices? #12;MOBILE SENSING 6

Prodiæ, Aleksandar

154

PLUTONIUM LOADING CAPACITY OF REILLEX HPQ ANION EXCHANGE COLUMN - AFS-2 PLUTONIUM FLOWSHEET FOR MOX  

SciTech Connect

Radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the dependence of column loading performance on the feed composition in the H-Canyon dissolution process for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). These loading experiments show that a representative feed solution containing {approx}5 g Pu/L can be loaded onto Reillex{trademark} HPQ resin from solutions containing 8 M total nitrate and 0.1 M KF provided that the F is complexed with Al to an [Al]/[F] molar ratio range of 1.5-2.0. Lower concentrations of total nitrate and [Al]/[F] molar ratios may still have acceptable performance but were not tested in this study. Loading and washing Pu losses should be relatively low (<1%) for resin loading of up to 60 g Pu/L. Loading above 60 g Pu/L resin is possible, but Pu wash losses will increase such that 10-20% of the additional Pu fed may not be retained by the resin as the resin loading approaches 80 g Pu/L resin.

Kyser, E.; King, W.; O'Rourke, P.

2012-07-26T23:59:59.000Z

155

ARM - Facility News Article  

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

, 2009 [Facility News] , 2009 [Facility News] Mobile Facility Begins Marine Cloud Study in the Azores Bookmark and Share Located next to the airport on Graciosa Island, the ARM Mobile Facility's comprehensive and sophisticated instrument suite will obtain atmospheric measurements from the marine boundary layer. Located next to the airport on Graciosa Island, the ARM Mobile Facility's comprehensive and sophisticated instrument suite will obtain atmospheric measurements from the marine boundary layer. Extended deployment will obtain seasonal statistics to improve climate models Today marks the beginning of a 20-month field campaign on Graciosa Island in the Azores to study the seasonal life cycle of marine clouds and how they modulate the global climate system. Sponsored by the U.S. Department

156

ARM - Facility News Article  

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

30, 2005 [Facility News] 30, 2005 [Facility News] Coastal Clouds Field Campaign Takes Off in July Bookmark and Share The 2-channel NFOV gets careful attention as it joins the suite of instruments collecting data for the ARM Mobile Facility field campaign at Point Reyes National Seashore. The 2-channel NFOV gets careful attention as it joins the suite 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 Reyes National Seashore in northern California for the Marine Stratus Radiation, Aerosol, and Drizzle Intensive Operational Period. The goals of this 6-month field campaign are to collect data from cloud/aerosol interactions and to improve understanding of cloud organization that is often associated

157

Plutonium assay for safeguards purposes: material heterogeneity and the application of calorimetry  

SciTech Connect

A variety of nuclear materials measurement techniques have been employed by the facility operator (WHC) and the IAEA during the two physical inventory verifications (PIVs) and at other items to determine and verify the quantities of plutonium present in the safeguarded inventory. Results of these analyses were statistically evaluated and are presented in this report.

Welsh, T.I., Westinghouse Hanford

1996-07-01T23:59:59.000Z

158

Production and Characterization of Plutonium Dioxide Particles as a Quality Control Material for Safeguards Purposes  

Science Journals Connector (OSTI)

Production and Characterization of Plutonium Dioxide Particles as a Quality Control Material for Safeguards Purposes ... Although U particles are of major interest in swipe samples from enrichment facilities, Pu particles are of high interest for safeguarding reactors with hot cells, reprocessing, and research and development facilities. ... The environmental sampling for safeguard (ESS) system is presented, that was useful to monitor trace radioactive pollution in the environment and to detect nuclear activities. ...

Taeko Shinonaga; David Donohue; Helmut Aigner; Stefan Brger; Dilani Klose; Teemu Krkel; Riitta Zilliacus; Ari Auvinen; Olivier Marie; Fabien Pointurier

2012-02-28T23:59:59.000Z

159

What is Plutonium? - Fact Sheet  

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

a critical step toward solving the nation's nuclear waste disposal problem a critical step toward solving the nation's nuclear waste disposal problem What Is Plutonium? Plu-to-ni-um n. Symbol Pu (plÇÇ-tÇ'n‘-bm) A radioactive, silvery, metallic transuranic element, produced artificially by neutron bombardment of uranium, having 15 isotopes with masses ranging from 232 to 246 and half- lives from 20 minutes to 76 million years. It is a radiological poison, specifically absorbed by bone marrow, and is used, especially the highly fissionable isotope Pu239, as a reactor fuel and in nuclear weapons. The American Heritage Dictionary, Second College Edition The U.S. Department of Energy's Carlsbad Field Office is responsible for the management, transportation, and permanent disposal of large amounts of the transuranic wastes left over from both World War II and the

160

ARM - Facility News Article  

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

4, 2013 [Facility News] 4, 2013 [Facility News] Work Cut Out for ARM Science Board Bookmark and Share With a new fixed site on the horizon in the Azores, a third ARM Mobile Facility gearing up for action in the Arctic, and more aircraft probes and sensors than scientists can shake a stick at, the ARM Facility continues to expand its considerable suite of assets for conducting climate research. Along with this impressive inventory comes the responsibility to ensure the Facility is supporting the highest-value science possible. Enter the ARM Science Board. This eleven-member group annually reviews complex proposals for use of the ARM mobile and aerial facilities. To maintain excellence and integrity in the review process, each member serves a renewable term of two years, with membership updated annually.

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


161

New Gas Gun Helping Scientists Better Understand Plutonium Behavior  

SciTech Connect

One of the most daunting scientific and engineering challenges today is ensuring the safety and reliability of the nation's nuclear arsenal. To effectively meet that challenge, scientists need better data showing how plutonium, a key component of nuclear warheads, behaves under extreme pressures and temperatures. On July 8, 2003, Lawrence Livermore researchers performed the inaugural experiment of a 30-meter-long, two-stage gas gun designed to obtain those data. The results from a continuing stream of successful experiments on the gas gun are strengthening scientists' ability to ensure that the nation's nuclear stockpile is safe and reliable. The JASPER (Joint Actinide Shock Physics Experimental Research) Facility at the Department of Energy's (DOE's) Nevada Test Site (NTS) is home to the two-stage gas gun. In the gun's first test, an unqualified success, Livermore scientists fired a projectile weighing 28.6 grams and traveling about 5.21 kilometers per second when it impacted an extremely small (about 30-gram) plutonium target. This experiment marked the culmination of years of effort in facility construction, gun installation, system integration, design reviews, and federal authorizations required to bring the experimental facility online. Ongoing experiments have drawn enthusiastic praise from throughout DOE, the National Nuclear Security Administration (NNSA), and the scientific community. NNSA Administrator Linton Brooks said, ''Our national laboratories now have at their disposal a valuable asset that enhances our due diligence to certify the nuclear weapons stockpile in the absence of underground nuclear weapons testing.''

Hazi, A

2005-09-20T23:59:59.000Z

162

EA-0841: Import of Russian Plutonium-238  

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

This EA evaluates the environmental impacts of a proposal to purchase plutonium-238 from the Russian Federation (Russia) for use in the Nation's space program.

163

ARM - Facility News Article  

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

Mobile Facility Beta Testing Complete; System Headed to California Seashore Mobile Facility Beta Testing Complete; System Headed to California Seashore Bookmark and Share A key addition to the ARM Climate Research Facility scientific infrastructure is ready to roll...literally. In February, the ARM Mobile Facility (AMF) is being packed up and shipped from Richland, Washington, to the Point Reyes National Seashore north of San Francisco, California. There, it will be reassembled in preparation for its first deployment as part of a 6-month experiment to study the microphysical characteristics of marine stratus clouds, and in particular, marine stratus drizzle processes. Throughout the deployment, the AMF will accommodate aerosol observing equipment for National Oceanic and Atmospheric Administration (NOAA) researchers co-sponsored by ARM and the DOE Aerosol Science Program.

164

Workers Create Demolition Zone at Hanford Site's Plutonium Finishing...  

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

Create Demolition Zone at Hanford Site's Plutonium Finishing Plant Workers Create Demolition Zone at Hanford Site's Plutonium Finishing Plant August 28, 2014 - 12:00pm Addthis The...

165

Hanford Site Workers Meet Challenging Performance Goal at Plutonium...  

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

Hanford site's Plutonium Finishing Plant are surpassing goals for removing hazardous tanks once used in the plutonium production process. EM's Richland Operations Office and...

166

Coordination and Hydrolysis of Plutonium Ions in Aqueous Solution...  

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

Hydrolysis of Plutonium Ions in Aqueous Solution using Car-Parrinello Molecular Dynamics Free Energy Coordination and Hydrolysis of Plutonium Ions in Aqueous Solution using...

167

Massive Hanford Test Reactor Removed - Plutonium Recycle Test...  

Office of Environmental Management (EM)

Massive Hanford Test Reactor Removed - Plutonium Recycle Test Reactor removed from Hanford's 300 Area Massive Hanford Test Reactor Removed - Plutonium Recycle Test Reactor removed...

168

Molecular Interactions of Plutonium(VI) with SyntheticManganese...  

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

Plutonium(VI) with Synthetic Manganese-Substituted Goethite. Abstract: Plutonium(VI) sorption on the surface of well-characterized synthetic manganese-substituted goethite...

169

EIS-0283-S1: Supplement to the Surplus Plutonium Disposition Environmental  

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

3-S1: Supplement to the Surplus Plutonium Disposition 3-S1: Supplement to the Surplus Plutonium Disposition Environmental Impact Statement EIS-0283-S1: Supplement to the Surplus Plutonium Disposition Environmental Impact Statement SUMMARY The Supplement evaluates the potential environmental impacts of using MOX fuel in these six specific reactors named in the DCS proposal as well as other program changes made since the SPD Draft EIS was published. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD November 5, 1999 EIS-0236-S1: DOE Notice of Availability of the Draft Environmental Impact Statement National Ignition Facility Draft Environmental Impact Statement to the Stockpile Stewardship and Management November 5, 1999 EIS-0236-S1: Notice of Availability for the Draft Supplemental Programmatic

170

Characterization of past and present solid waste streams from the plutonium finishing plant  

SciTech Connect

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE).

Duncan, D R; Mayancsik, B A [Westinghouse Hanford Co., Richland, WA (United States)] [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J A; Vejvoda, E J; Reddick, J A; Sheldon, K M; Weyns, M I [Los Alamos Technical Associates, Kennewick, WA (United States)] [Los Alamos Technical Associates, Kennewick, WA (United States)

1993-02-01T23:59:59.000Z

171

ARM - Facility News Article  

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

25, 2013 [Education, Facility News] 25, 2013 [Education, Facility News] Junior Rangers Enjoy Science Education at ARM Facility on Cape Cod Bookmark and Share Children and adults join in the balloon launch countdown at the ARM Mobile Facility site at Cape Cod National Seashore. Weather balloons are launched at regular intervals four times per day throughout the one-year campaign. Children and adults join in the balloon launch countdown at the ARM Mobile Facility site at Cape Cod National Seashore. Weather balloons are launched at regular intervals four times per day throughout the one-year campaign. School break means vacation, and around Cape Cod, that often means a trip to the seashore. On April 17, families looking for fun and educational outdoor activities spent several hours at Cape Cod National Seashore's

172

Plutonium Disposition Program | National Nuclear Security Administration  

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

Home > Media Room > Fact Sheets > Plutonium Disposition Program Home > Media Room > Fact Sheets > Plutonium Disposition Program Fact Sheet Plutonium Disposition Program Jun 26, 2013 SUPPORTING NUCLEAR NONPROLIFERATION Weapon-grade plutonium and highly enriched uranium (HEU) are the critical ingredients for making a nuclear weapon. With the end of the Cold War, hundreds of tons of these materials were determined to be surplus to U.S. and Russian defense needs. Denying access to plutonium and HEU is the best way to prevent nuclear proliferation to rogue states and terrorist organizations. The most certain method to prevent these materials from falling into the wrong hands is to dispose of them. During the April 2010 Nuclear Security Summit, Secretary of State Hillary Rodham Clinton and Russian Foreign Minister Sergey Lavrov signed a protocol

173

Manhattan Project: F Reactor Plutonium Production Complex  

Office of Scientific and Technical Information (OSTI)

F REACTOR PLUTONIUM PRODUCTION COMPLEX F REACTOR PLUTONIUM PRODUCTION COMPLEX Hanford Engineer Works, 1945 Resources > Photo Gallery Plutonium production area, Hanford, ca. 1945 The F Reactor plutonium production complex at Hanford. The "boxy" building between the two water towers on the right is the plutonium production reactor; the long building in the center of the photograph is the water treatment plant. The photograph was reproduced from Henry DeWolf Smyth, Atomic Energy for Military Purposes: The Official Report on the Development of the Atomic Bomb under the Auspices of the United States Government, 1940-1945 (Princeton, NJ: Princeton University Press, 1945). The Smyth Report was commissioned by Leslie Groves and originally issued by the Manhattan Engineer District. Princeton University Press reprinted it in book form as a "public service" with "reproduction in whole or in part authorized and permitted."

174

Siegfried S. Hecker, Plutonium, and Nonproliferation  

Office of Scientific and Technical Information (OSTI)

Siegfried S. Hecker, Plutonium Siegfried S. Hecker, Plutonium and Nuclear Nonproliferation Resources with Additional Information · Awards Siegfried S. Hecker Photo Credit: Courtesy of Los Alamos National Laboratory LeRoy Sanchez On September 17, 2009, U.S. Energy Secretary Steven Chu named Siegfried S. Hecker as a winner of the Enrico Fermi Award 'in recognition for his contributions to plutonium metallurgy, his broad scientific leadership and for his energetic and continuing efforts to reduce the danger of nuclear weapons around the globe. Dr. Hecker is credited with resolving a long-standing controversy involving the stability of certain structures (or phases) in plutonium alloys near equilibrium that arose from significant discrepancies between U.S. and former USSR research on plutonium metallurgy.'1

175

Benchmark Evaluation of Plutonium Nitrate Solution Arrays  

SciTech Connect

In October and November of 1981 thirteen approach-to-critical experiments were performed on a remote split table machine (RSTM) in the Critical Mass Laboratory of Pacific Northwest Laboratory (PNL) in Richland, Washington, using planar arrays of polyethylene bottles filled with plutonium (Pu) nitrate solution. Arrays of up to sixteen bottles were used to measure the critical number of bottles and critical array spacing with a tight fitting Plexiglas{reg_sign} reflector on all sides of the arrays except the top. Some experiments used Plexiglas shells fitted around each bottles to determine the effect of moderation on criticality. Each bottle contained approximately 2.4 L of Pu(NO3)4 solution with a Pu content of 105 g Pu/L and a free acid molarity H+ of 5.1. The plutonium was of low 240Pu (2.9 wt.%) content. These experiments were performed to fill a gap in experimental data regarding criticality limits for storing and handling arrays of Pu solution in reprocessing facilities. Of the thirteen approach-to-critical experiments eleven resulted in extrapolations to critical configurations. Four of the approaches were extrapolated to the critical number of bottles; these were not evaluated further due to the large uncertainty associated with the modeling of a fraction of a bottle. The remaining seven approaches were extrapolated to critical array spacing of 3-4 and 4-4 arrays; these seven critical configurations were evaluation for inclusion as acceptable benchmark experiments in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook. Detailed and simple models of these configurations were created and the associated bias of these simplifications was determined to range from 0.00116 and 0.00162 {+-} 0.00006 ?keff. Monte Carlo analysis of all models was completed using MCNP5 with ENDF/BVII.0 neutron cross section libraries. A thorough uncertainty analysis of all critical, geometric, and material parameters was performed using parameter perturbation methods. It was found that uncertainty in the impurities in the polyethylene bottles, reflector position, bottle outer diameter, and critical array spacing had the largest effect. The total uncertainty ranged from 0.00651 to 0.00920 ?keff. Evaluation methods and results will be presented and discussed in greater detail in the full paper.

M. A. Marshall; J. D. Bess

2011-09-01T23:59:59.000Z

176

REMOVAL OF LEGACY PLUTONIUM MATERIALS FROM SWEDEN  

SciTech Connect

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

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

2013-08-18T23:59:59.000Z

177

Characterization of plutonium-bearing wastes by chemical analysis and analytical electron microscopy  

SciTech Connect

This report summarizes the results of characterization studies of plutonium-bearing wastes produced at the US Department of Energy weapons production facilities. Several different solid wastes were characterized, including incinerator ash and ash heels from Rocky Flats Plant and Los Alamos National Laboratory; sand, stag, and crucible waste from Hanford; and LECO crucibles from the Savannah River Site. These materials were characterized by chemical analysis and analytical electron microscopy. The results showed the presence of discrete PuO{sub 2}PuO{sub 2{minus}x}, and Pu{sub 4}O{sub 7} phases, of about 1{mu}m or less in size, in all of the samples examined. In addition, a number of amorphous phases were present that contained plutonium. In all the ash and ash heel samples examined, plutonium phases were found that were completely surrounded by silicate matrices. Consequently, to achieve optimum plutonium recovery in any chemical extraction process, extraction would have to be coupled with ultrafine grinding to average particle sizes of less than 1 {mu}m to liberate the plutonium from the surrounding inert matrix.

Behrens, R.G. [Los Alamos National Lab., NM (United States); Buck, E.C.; Dietz, N.L.; Bates, J.K.; Van Deventer, E.; Chaiko, D.J. [Argonne National Lab., IL (United States)

1995-09-01T23:59:59.000Z

178

Survey of Worldwide Light Water Reactor Experience with Mixed Uranium-Plutonium Oxide Fuel  

SciTech Connect

The US and the Former Soviet Union (FSU) have recently declared quantities of weapons materials, including weapons-grade (WG) plutonium, excess to strategic requirements. One of the leading candidates for the disposition of excess WG plutonium is irradiation in light water reactors (LWRs) as mixed uranium-plutonium oxide (MOX) fuel. A description of the MOX fuel fabrication techniques in worldwide use is presented. A comprehensive examination of the domestic MOX experience in US reactors obtained during the 1960s, 1970s, and early 1980s is also presented. This experience is described by manufacturer and is also categorized by the reactor facility that irradiated the MOX fuel. A limited summary of the international experience with MOX fuels is also presented. A review of MOX fuel and its performance is conducted in view of the special considerations associated with the disposition of WG plutonium. Based on the available information, it appears that adoption of foreign commercial MOX technology from one of the successful MOX fuel vendors will minimize the technical risks to the overall mission. The conclusion is made that the existing MOX fuel experience base suggests that disposition of excess weapons plutonium through irradiation in LWRs is a technically attractive option.

Cowell, B.S.; Fisher, S.E.

1999-02-01T23:59:59.000Z

179

EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement  

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

This EIS analyzes the potential environmental impacts associated with alternatives for the disposition of surplus plutonium.

180

ARM - Facility News Article  

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

22, 2011 [Facility News] 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 2013 Fixed sites available FY2013 Priority will be given to proposals that make comprehensive use of the ARM facilities and focus on long-term goals of the DOE Office of Biological and Environmental Research. Successful proposals will be supplied all operational and logistical resources (provided at no cost to the principal

Note: This page contains sample records for the topic "mobile plutonium facility" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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181

ARM Climate Research Facility  

NLE Websites -- All DOE Office Websites

banner banner Home | People | Site Index Atmospheric Radiation Measurement Climate Research Facility US Department of Energy About Science Campaigns Sites Instruments Measurements Data News Publications Education Become a User Recovery Act Mission FAQ Outreach Displays History Organization Participants Facility Statistics Forms Contacts Research Themes Research Highlights Journal Articles Collaborations Atmospheric System Research (ASR) ARM Science Team Meetings Propose a Campaign Submitting Proposals: Guidelines Featured Campaigns Campaign Data List of Campaigns Aerial Facility Eastern North Atlantic Mobile Facilities North Slope of Alaska Southern Great Plains Tropical Western Pacific Location Table Contacts Instrument Datastreams Value-Added Products PI Data Products Field Campaign Data Related Data

182

ARM - Facility News Article  

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

Guest Instruments to Collect Aerosol Data During Coastal Field Campaign Guest Instruments to Collect Aerosol Data During Coastal Field Campaign Bookmark and Share The counter-flow virtual impactor (inset), which can characterize aerosol particles in cloud droplets, joins a number of other guest instruments at the ARM Mobile Facility deployment site at Point Reyes National Seashore in California. The counter-flow virtual impactor (inset), which can characterize aerosol particles in cloud droplets, joins 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 campaign, the Marine Stratus Radiation Aerosol and Drizzle (MASRAD) Intensive Operational Period, is well underway at Point Reyes National Seashore on the northern

183

ARM - Facility News Article  

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

W-Band Cloud Radar Added to ARM Mobile Facility in Africa W-Band Cloud Radar Added to ARM Mobile Facility in Africa Bookmark and Share Most of the WACR is mounted on top of one of the AMF shelters. The WACR computer and chiller (used to keep the WACR cool in temperatures up to 47 degrees C) are located in the shelter below the radar. Most of the WACR is mounted on top of one of the AMF shelters. The WACR computer and chiller (used to keep the WACR cool in temperatures up to 47 degrees C) are located in the shelter below the radar. A W-band ARM Cloud Radar (WACR) recently joined the suite of baseline capabilities offered by the ARM Mobile Facility (AMF). The term "W-band" refers to the specific radio frequency range of this radar, which is a 95 gigahertz pulse Doppler zenith pointing radar, providing profiles of cloud

184

Excess Plutonium: Weapons Legacy or National Asset?  

SciTech Connect

The Nuclear Materials Stewardship Initiative was established in January, 2000, to accelerate the work of achieving integration and cutting long-term costs associated with the management of nuclear materials. As part of that initiative, the Department of Energy (DOE), Office of Environmental Management (EM), has established Nuclear Material Management Groups for the management of excess nuclear materials. As one of these groups, the Plutonium Material Management Group (PMMG) has been chartered to serve as DOE's complex wide resource and point of contact for technical coordination and program planning support in the safe and efficient disposition of the nations excess Plutonium 239. This paper will explain the mission, goals, and objectives of the PMMG. In addition, the paper will provide a broad overview of the status of the plutonium inventories throughout the DOE complex. The DOE currently manages approximately 99.5 MT of plutonium isotopes. Details of the various categories of plutonium, from material designated for national security needs through material that has been declared excess, will be explained. For the plutonium that has been declared excess, the various pathways to disposition (including reuse, recycling, sale, transfer, treatment, consumption, and disposal) will be discussed. At this time 52.5 MT of plutonium has been declared excess and the method of disposition for that material is the subject of study and evaluation within DOE. The role of the PMMG in those evaluations will be outlined.

Klipa, G.; Boeke, S.; Hottel, R.

2002-02-27T23:59:59.000Z

185

Mobile Computing/Mobile Computing/Mobile Computing/Mobile Computing/ Mobile NetworksMobile NetworksMobile NetworksMobile Networks  

E-Print Network (OSTI)

Mobile Computing/Mobile Computing/Mobile Computing/Mobile Computing/ Mobile NetworksMobile NetworksMobile NetworksMobile Networks Mobile IP Prof. Chansu Yu 2 Contents IP for Wired Network Mobile IP Overview Basic Mobile IP Agent Discovery Registration Tunneling Route Optimization Current Topics #12;3 Simplified

Yu, Chansu

186

Plutonium Recycle Test Reactor 309 B-Roll | Department of Energy  

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

Plutonium Recycle Test Reactor 309 B-Roll Plutonium Recycle Test Reactor 309 B-Roll Addthis Description Plutonium Recycle Test Reactor 309 B-Roll...

187

Microwave calcination for plutonium immobilization and residue stabilization  

SciTech Connect

In the late 1980`s development was begun on a process using microwave energy to vitrify low level mixed waste sludge and transuranic mixed waste sludge generated in Building 374 at Rocky Flats. This process was shown to produce a dense, highly durable waste form. With the cessation of weapons production at Rocky Flats, the emphasis has changed from treatment of low level and TRU wastes to stabilizaiton of plutonium oxide and residues. This equipment is versatile and can be used as a heat source to calcine, react or vitrify many types of residues and oxides. It has natural economies in that it heats only the material to be treated, significantly reducing cycle times over conventional furnaces. It is inexpensive to operate in that most of the working components remain outside of any necessary contamination enclosure and therefore can easily be maintained. Limited testing has been successfully performed on cerium oxide (as a surrogate for plutonium oxide), surrogate electrorefining salts, surrogate residue sludge and residue ash. Future plans also include tests on ion exchange resins. In an attempt to further the usefullness of this technology, a mobile, self-contained microwave melting system is currently under development and expected to be operational at Rocky Flats Enviromental Technology Site by the 4th quarter of FY96.

Harris, M.J.; Rising, T.L.; Roushey, W.J.; Sprenger, G.S. [Kaiser-Hill Co., Golden, CO (United States)

1995-12-01T23:59:59.000Z

188

Alternative technical summary report for direct disposition in deep boreholes: Direct disposal of plutonium metal/plutonium dioxide in compound canisters, Version 4.0. Fissile Materials Disposition Program  

SciTech Connect

This report summarizes and compares the Immobilized and Direct Beep Borehole Disposition Alternatives. The important design concepts, facility features and operational procedures are briefly described, and a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

189

ARM - Facility News Article  

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

April 30, 2008 [Facility News] April 30, 2008 [Facility News] ARM Outreach Materials Chosen for Earth Day Display in Washington DC Bookmark and Share Posters for the ARM Mobile Facility and ARM Education and Outreach were selected for the 2008 Earth Day display at DOE Headquarters. Posters for the ARM Mobile Facility and ARM Education and Outreach were selected for the 2008 Earth Day display at DOE Headquarters. Earth Day is officially honored each year on April 22, however, many groups sponsor activities throughout the entire month of April. At DOE Headquarters in Washington DC, two ARM posters were selected to join a poster display representing programs from numerous DOE offices. The display was featured in the Forrestal Building's ground-level and first floor lobby areas throughout the week of April 21. The posters were then displayed at

190

ARM - Facility News Article  

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

15, 2007 [Facility News] 15, 2007 [Facility News] Microwave Radiometers Put to the Test in Germany Bookmark and Share A 2-channel microwave radiometer (left) and a 12-channel microwave radiometer profiler (right) are part of a larger collection of instruments deployed at the ARM Mobile Facility site in Heselbach, Germany, in 2007. A 2-channel microwave radiometer (left) and a 12-channel microwave radiometer profiler (right) are part of a larger collection of instruments deployed at the ARM Mobile Facility site in Heselbach, Germany, in 2007. Microwave radiometers (MWRs) are instruments used to measure emissions of water vapor and liquid water molecules in the atmosphere at specific microwave frequencies. Different MWRs are used to measure various frequencies, but the accuracy of all their retrievals is somewhat suspect,

191

ARM - Facility News Article  

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

1, 2011 [Facility News] 1, 2011 [Facility News] Data from Field Campaign in Black Forest, Germany, are Red Hot Bookmark and Share During COPS, the ARM Mobile Facility operated in Heselbach, Germany, obtaining measurements encompassing the entire life cycle of precipitation. The AMF site also hosted a number of guest instruments for supplemental field campaigns throughout the deployment. During COPS, the ARM Mobile Facility operated in Heselbach, Germany, obtaining measurements encompassing the entire life cycle of precipitation. The AMF site also hosted a number of guest instruments for supplemental field campaigns throughout the deployment. A paper published in a special issue of the Quarterly Journal of the Royal Meteorological Society describing the scientific strategy, field phase, and

192

ARM - Facility News Article  

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

15, 2006 [Facility News] 15, 2006 [Facility News] Radar Wind Profiler Joins ARM Mobile Facility Instrument Suite Bookmark and Share This spring, a 915 MHz radar wind profiler (RWP) was successfully installed at the ARM Mobile Facility (AMF) site in Niamey, Niger, West Africa, for the remainder of the 1-year RADAGAST field campaign which started in January. The RWP will provide information about wind speed, wind direction, and wind shear, and also enable measurements of the turbulence in the lower part of the troposphere. This may be a key variable in determining the vertical distribution of dust in the experimental domain. Gradients in the radar's reflectivity spectrum may also help to provide continuous identification of the depth of the boundary layer in the summer months, when refractive gradients are likely to be maximized by low-level moisture.

193

ARM - Facility News Article  

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

December 3, 2004 [Facility News] December 3, 2004 [Facility News] First Deployment of ARM Mobile Facility to Occur on California Coast Bookmark and Share Image - Point Reyes Beach Image - Point Reyes Beach Point Reyes National Seashore, on the California coast north of San Francisco, has been identified as the official location for the first deployment of the DOE's Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF). As part of a 6-month field campaign beginning in March 2005 to study the microphysical characteristics of marine stratus and, in particular, marine stratus drizzle processes, the AMF will provide a mature instrument system to help fill information gaps in the existing limited surveys of marine stratus microphysical structure. Marine stratus clouds are known to be susceptible to the byproducts of fossil fuel consumption, a

194

ARM - Facility News Article  

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

May 20, 2011 [Facility News] May 20, 2011 [Facility News] From Snow to Sand; Mobile Facility Headed to the Maldives Bookmark and Share AMF2 operations team members pack up the 3-channel microwave radiometer at the STORMVEX valley floor site in Steamboat Springs, Colorado. AMF2 operations team members pack up the 3-channel microwave radiometer at the STORMVEX valley floor site in Steamboat Springs, Colorado. After spending six very snowy months at Steamboat Springs, Colorado, the second ARM Mobile Facility (AMF2) is switching gears and heading to the tropical climes of the Maldives in the Indian Ocean. In mid-April, the Storm Peak Lab Cloud Property Validation Experiment (STORMVEX) came to a close, ending the final chapter of the AMF2's maiden deployment. After packing up the instruments and data systems, the AMF2 team is now preparing

195

ARM - Facility News Article  

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

January 15, 2006 [Facility News] January 15, 2006 [Facility News] ARM Mobile Facility Begins Year-Long Deployment in Africa Bookmark and Share Beginning on January 9, the ARM Mobile Facility began officially collecting atmospheric data from a location at the airport in Niamey, Niger, Africa. As part of the RADAGAST field campaign, the AMF will measure the effects of absorbing aerosols from desert dust in the dry season, and the effects of deep convective clouds and associated moisture loadings on the transmission of atmospheric radiation during the summer monsoon. These measurements will be combined with associated satellite data to provide the first well-sampled direct estimates of the energy balance across the atmosphere. This dataset will provide valuable information to an ongoing effort called

196

Facility Operations 1993 fiscal year work plan: WBS 1.3.1  

SciTech Connect

The Facility Operations program is responsible for the safe, secure, and environmentally sound management of several former defense nuclear production facilities, and for the nuclear materials in those facilities. As the mission for Facility Operations plants has shifted from production to support of environmental restoration, each plant is making a transition to support the new mission. The facilities include: K Basins (N Reactor fuel storage); N Reactor; Plutonium-Uranium Reduction Extraction (PUREX) Plant; Uranium Oxide (UO{sub 3}) Plant; 300 Area Fuels Supply (N Reactor fuel supply); Plutonium Finishing Plant (PFP).

Not Available

1992-11-01T23:59:59.000Z

197

Influence of Iron Redox Transformations on Plutonium Sorption to Sediments  

SciTech Connect

Plutonium subsurface mobility is primarily controlled by its oxidation state, which in turn is loosely coupled to the oxidation state of iron in the system. Experiments were conducted to examine the effect of sediment iron mineral composition and oxidation state on plutonium sorption and oxidation state. A pH 6.3 vadose zone sediment containing iron oxides and iron-containing phyllosilicates was treated with various complexants (ammonium oxalate) and reductants (dithionite-citrate-bicarbonate) to selectively leach and/or reduce iron oxide and phyllosilicate phases. Mssbauer spectroscopy was used to identify initial iron mineral composition of the sediment and monitor dissolution and reduction of iron oxides. Sorption of Pu(V) was monitored over one week for each of six treated sediment fractions. Plutonium oxidation state speciation in the aqueous and solid phases was monitored using solvent extraction, coprecipitation, and XANES. Mssbauer spectroscopy showed that the sediment contained 25-30% hematite, 60-65% Al-goethite, and <10%Fe(III) in phyllosilicate; there was no detectable Fe(II). Upon reduction with a strong chemical reductant (dithionite-citrate buffer, DCB), much of the hematite and goethite disappeared and the Fe in the phyllosilicate reduced to Fe(II). The rate of sorption was found to correlate with the 1 fraction of Fe(II) remaining within each treated sediment phase. Pu(V) was the only oxidation state measured in the aqueous phase, irrespective of treatment, whereas Pu(IV) and much smaller amounts of Pu(V) and Pu(VI) were measured in the solid phase. Surface-mediated reduction of Pu(V) to Pu(IV) occurred in treated and untreated sediment samples; Pu(V) remained on untreated sediment surface for two days before reducing to Pu(IV). Similar to the sorption kinetics, the reduction rate was correlated with sediment Fe(II) concentration. The correlation between Fe(II) concentrations and Pu(V) reduction demonstrates the potential impact of changing iron mineralogy on plutonium subsurface transport through redox transition areas. These findings should influence the conceptual models of long-term stewardship of Pu contaminated sites that have fluctuating redox conditions, such as vadose zones or riparian zones.

Hixon, Amy E.; Hu, Yung-Jin; Kaplan, Daniel I.; Kukkadapu, Ravi K.; Nitsche, Heino; Qafoku, Odeta; Powell, Brian A.

2010-10-01T23:59:59.000Z

198

Plutonium less mysterious with nuclear magnetic resonance  

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

Plutonium less mysterious with nuclear magnetic resonance Plutonium less mysterious with nuclear magnetic resonance Plutonium less mysterious with nuclear magnetic resonance For more than 50 years, chemists and physicists have been searching for the plutonium-239 magnetic resonance signal. May 21, 2012 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials.

199

Sweden Plutonium Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Sweden Plutonium Removal | National Nuclear Security Administration Sweden Plutonium Removal | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > content > Four-Year Plan > Sweden Plutonium Removal Sweden Plutonium Removal Location Sweden United States 62° 24' 4.4136" N, 15° 22' 51.096" E See map: Google Maps Printer-friendly version Printer-friendly version

200

TECHNIQUES FOR MONITORING PLUTONIUM IN THE ENVIRONMENT  

E-Print Network (OSTI)

150 day decay time, except for LMFBR, which assumes 30 days.> N") Plutonium from an LMFBR C'J II I I N") CD C".J c:'-l

Nero Jr., A.V.

2011-01-01T23:59:59.000Z

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


201

Draft Surplus Plutonium Disposition Supplemental Environmental...  

National Nuclear Security Administration (NNSA)

In addition, concerns about criticality would limit the loading in the waste storage tanks and would not support vitrification of 13.1 metric tons (14.4) tons of plutonium....

202

Draft Surplus Plutonium Disposition Supplemental Environmental...  

National Nuclear Security Administration (NNSA)

In addition, concerns about criticality would limit the loading in the waste storage tanks and would not support vitrification of 13.1 metric tons (14.4 tons) of plutonium....

203

Advanced Candu Systems For Plutonium Destruction  

Science Journals Connector (OSTI)

High neutron economy, on-line refuelling, and a simple fuel-bundle design result in a high degree of versatility in the use of the CANDU reactor for the disposition of weapons-derived plutonium. CANDU mixed-oxid...

P.G. Boczar; M.J.N. Gagnon; P.S.W. Chan

1997-01-01T23:59:59.000Z

204

Development of plutonium aerosol fractionation system  

E-Print Network (OSTI)

DEVELOPMENT OF A PLUTONIUM AEROSOL FRACTIONATION SYSTEM A Thesis by MALLA R. MEKALA Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August... 1993 Major Subject: Mechanical Engineering DEVELOPMENT OP A PLUTONIUM AEROSOL FRACTIONATION SYSTEM A Thesis by MALLA R. MEKALA Approved as to style and content by: A. R. McFarland (Chair of Committee) N. K. Anand (Mer toer) (', & C. B...

Mekala, Malla R.

1993-01-01T23:59:59.000Z

205

Mobile Testing  

Science Journals Connector (OSTI)

Mobile apps are everywhere. Some apps entertain and others enable business transactions. Apps increasingly interact with complex IT landscapes. For example, a banking app on a mobile device acts as a front end that invokes services on a back-end server ... Keywords: mobile apps, mobile devices, software quality management, software testing, test automation, test strategy

Klaus Haller

2013-11-01T23:59:59.000Z

206

Mobile Resources  

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

Mobile Resources Mobile Resources Mobile Resources Have a mobile device? Find tips and information here. Questions? 505-667-5809 Email For information call the Service Desk at (505) 667-5809 or email mobilelibrary@lanl.gov The following resources are optimized for mobile devices or have mobile apps available for download. Resource Available App Mobile Website Available off Yellow Network with Pairing or Login Additional Information AACR Journals Apple Yes, the Journals are optimized for mobile viewing. Not the whole AACR site. Instructional pdf on pairing with voucher ACS Apple Android No American Institute of Physics Apple No American Mathematical Society No Yes Instructions for pairing mobile devices, tablets, laptops, etc. American Physical Society No Annual Reviews No Yes Instructions for pairing with mobile device available on website.

207

Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA  

SciTech Connect

Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D&D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project.

Dean, L.N. [Advanced Sciences, Inc., (United States)

1994-02-01T23:59:59.000Z

208

Benchmark Evaluation of Plutonium Hemispheres Reflected by Steel and Oil  

SciTech Connect

During the period from June 1967 through September 1969 a series of critical experiments was performed at the Rocky Flats Critical Mass Laboratory with spherical and hemispherical plutonium assemblies as nested hemishells as part of a Nuclear Safety Facility Experimental Program to evaluate operational safety margins for the Rocky Flats Plant. These assemblies were both bare and fully or partially oil-reflected. Many of these experiments were subcritical with an extrapolation to critical configurations or critical at a particular oil height. Existing records reveal that 167 experiments were performed over the course of 28 months. Unfortunately, much of the data was not recorded. A reevaluation of the experiments had been summarized in a report for future experimental and computational analyses. This report examines only fifteen partially oil-reflected hemispherical assemblies. Fourteen of these assemblies also had close-fitting stainless-steel hemishell reflectors, used to determine the effective critical reflector height of oil with varying steel-reflector thickness. The experiments and their uncertainty in keff values were evaluated to determine their potential as valid criticality benchmark experiments of plutonium.

John Darrell Bess

2008-06-01T23:59:59.000Z

209

Life cycle costs for the domestic reactor-based plutonium disposition option  

SciTech Connect

Projected constant dollar life cycle cost (LCC) estimates are presented for the domestic reactor-based plutonium disposition program being managed by the US Department of Energy Office of Fissile Materials Disposition (DOE/MD). The scope of the LCC estimate includes: design, construction, licensing, operation, and deactivation of a mixed-oxide (MOX) fuel fabrication facility (FFF) that will be used to purify and convert weapons-derived plutonium oxides to MOX fuel pellets and fabricate MOX fuel bundles for use in commercial pressurized-water reactors (PWRs); fuel qualification activities and modification of facilities required for manufacture of lead assemblies that will be used to qualify and license this MOX fuel; and modification, licensing, and operation of commercial PWRs to allow irradiation of a partial core of MOX fuel in combination with low-enriched uranium fuel. The baseline cost elements used for this document are the same as those used for examination of the preferred sites described in the site-specific final environmental impact statement and in the DOE Record of Decision that will follow in late 1999. Cost data are separated by facilities, government accounting categories, contract phases, and expenditures anticipated by the various organizations who will participate in the program over a 20-year period. Total LCCs to DOE/MD are projected at approximately $1.4 billion for a 33-MT plutonium disposition mission.

Williams, K.A.

1999-10-01T23:59:59.000Z

210

Method for Plutonium-Gallium Separation by Anodic Dissolution of a Solid Plutonium-Gallium Alloy  

SciTech Connect

Purified plutonium and gallium are efficiently recovered from a solid plutonium-gallium (Pu-Ga) alloy by using an electrorefining process. The solid Pu-Ga alloy is the cell anode, preferably placed in a moving basket within the electrolyte. As the surface of the Pu-Ga anode is depleted in plutonium by the electrotransport of the plutonium to a cathode, the temperature of the electrolyte is sufficient to liquify the surface, preferably at about 500 C, resulting in a liquid anode layer substantially comprised of gallium. The gallium drips from the liquified surface and is collected below the anode within the electrochemical cell. The transported plutonium is collected on the cathode surface and is recovered.

Miller, William E.; Tomczuk, Zygmunt

1998-12-08T23:59:59.000Z

211

Mobile systems capability plan  

SciTech Connect

This plan was prepared to initiate contracting for and deployment of these mobile system services. 102,000 cubic meters of retrievable, contact-handled TRU waste are stored at many sites around the country. Also, an estimated 38,000 cubic meters of TRU waste will be generated in the course of waste inventory workoff and continuing DOE operations. All the defense TRU waste is destined for disposal in WIPP near Carlsbad NM. To ship TRU waste there, sites must first certify that the waste meets WIPP waste acceptance criteria. The waste must be characterized, and if not acceptable, subjected to additional processing, including repackaging. Most sites plan to use existing fixed facilities or open new ones between FY1997-2006 to perform these functions; small-quantity sites lack this capability. An alternative to fixed facilities is the use of mobile systems mounted in trailers or skids, and transported to sites. Mobile systems will be used for all characterization and certification at small sites; large sites can also use them. The Carlsbad Area Office plans to pursue a strategy of privatization of mobile system services, since this offers a number of advantages. To indicate the possible magnitude of the costs of deploying mobile systems, preliminary estimates of equipment, maintenance, and operating costs over a 10-year period were prepared and options for purchase, lease, and privatization through fixed-price contracts considered.

NONE

1996-09-01T23:59:59.000Z

212

Optimization and implementation study of plutonium disposition using existing CANDU Reactors. Final report  

SciTech Connect

Since early 1994, the Department of Energy has been sponsoring studies aimed at evaluating the merits of disposing of surplus US weapons plutonium as Mixed Oxide (MOX) fuel in existing commercial Canadian Pressurized Heavy Water reactors, known as CANDU`s. The first report, submitted to DOE in July, 1994 (the 1994 Executive Summary is attached), identified practical and safe options for the consumption of 50 to 100 tons of plutonium in 25 years in some of the existing CANDU reactors operating the Bruce A generating station, on Lake Huron, about 300 km north east of Detroit. By designing the fuel and nuclear performance to operate within existing experience and operating/performance envelope, and by utilizing existing fuel fabrication and transportation facilities and methods, a low cost, low risk method for long term plutonium disposition was developed. In December, 1995, in response to evolving Mission Requirements, the DOE requested a further study of the CANDU option with emphasis on more rapid disposition of the plutonium, and retaining the early start and low risk features of the earlier work. This report is the result of that additional work.

NONE

1996-09-01T23:59:59.000Z

213

Stabilization of Plutonium in Subsurface Environments via Microbial Reduction and Biofilm Formation  

SciTech Connect

Plutonium has a long half-life (2.4 x 104 years) and is of concern because of its chemical and radiological toxicity, high-energy alpha radioactive decay. A full understanding of its speciation and interactions with environmental processes is required in order to predict, contain, or remediate contaminated sites. Under aerobic conditions Pu is sparingly soluble, existing primarily in its tetravalent oxidation state. To the extent that pentavalent and hexavalent complexes and small colloidal species form they will increase the solubility and resultant mobility from contamination sources. There is evidence that in both marine environments and brines substantial fractions of the plutonium in solution is present as hexavalent plutonyl, PuO2 2+.

Hakim Boukhalfa; Gary A. Icopini; Sean D. Reilly; Mary P. Neu

2007-04-19T23:59:59.000Z

214

Preserving Plutonium-244 as a National Asset  

SciTech Connect

Plutonium-244 (244 Pu) is an extremely rare and long-lived isotope of plutonium with a half-life of 80 million years. Measureable amounts of 244 Pu are found in neither reactor-grade nor weapons-grade plutonium. Production of this isotope requires a very high thermal flux to permit the two successive neutron captures that convert 242 Pu to 243 Pu to 244 Pu, particularly given the short (about 5 hour) half-life of 243 Pu. Such conditions simply do not exist in plutonium production processes. Therefore, 244 Pu is ideal for precise radiochemical analyses measuring plutonium material properties and isotopic concentrations in items containing plutonium. Isotope dilution mass spectrometry is about ten times more sensitive when using 244 Pu rather than 242 Pu for determining plutonium isotopic content. The isotope can also be irradiated in small quantities to produce superheavy elements. The majority of the existing global inventory of 244 Pu is contained in the outer housing of Mark-18A targets at the Savannah River Site (SRS). The total inventory is about 20 grams of 244 Pu in about 400 grams of plutonium distributed among the 65 targets. Currently, there are no specific plans to preserve these targets. Although the cost of separating and preserving this material would be considerable, it is trivial in comparison to new production costs. For all practical purposes, the material is irreplaceable, because new production would cost billions of dollars and require a series of irradiation and chemical separation cycles spanning up to 50 years. This paper will discuss a set of options for overcoming the significant challenges to preserve the 244 Pu as a National Asset: (1) the need to relocate the material from SRS in a timely manner, (2) the need to reduce the volume of material to the extent possible for storage, and (3) the need to establish an operational capability to enrich the 244 Pu in significant quantities. This paper suggests that if all the Mark-18A plutonium is separated, it would occupy a small volume and would be inexpensive to store while an enrichment capability is developed. Very small quantities could be enriched in existing mass separators to support critical needs.

Patton, Bradley D [ORNL; Alexander, Charles W [ORNL; Benker, Dennis [ORNL; Collins, Emory D [ORNL; Romano, Catherine E [ORNL; Wham, Robert M [ORNL

2011-01-01T23:59:59.000Z

215

A Supplement Analysis on Plutonium Consolidation at Savannah River Site  

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

DOEs April 2002 decision to consolidate surplus, non-pit weapons-usable plutonium at Savannah River Site did not affect a 1997 DOE decision to continue storage of non-pit surplus plutonium at...

216

U.S. and Russia Sign Plutonium Disposition Agreement | National...  

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

Our Jobs Working at NNSA Blog Home About Us Our History NNSA Timeline U.S. and Russia Sign Plutonium Disposition Agreement U.S. and Russia Sign Plutonium Disposition...

217

Consolidation of Surplus Plutonium at Savannah River Site | Department...  

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

plutonium that had been stored at the Rocky Flats Environmental Technology Site in long-term storage at the Savannah River Site. DOE Amends Record of Decision for Plutonium...

218

Fire hazard analysis for Plutonium Finishing Plant complex  

SciTech Connect

A fire hazards analysis (FHA) was performed for the Plutonium Finishing Plant (PFP) Complex at the Department of Energy (DOE) Hanford site. The scope of the FHA focuses on the nuclear facilities/structures in the Complex. The analysis was conducted in accordance with RLID 5480.7, [DOE Directive RLID 5480.7, 1/17/94] and DOE Order 5480.7A, ''Fire Protection'' [DOE Order 5480.7A, 2/17/93] and addresses each of the sixteen principle elements outlined in paragraph 9.a(3) of the Order. The elements are addressed in terms of the fire protection objectives stated in paragraph 4 of DOE 5480.7A. In addition, the FHA also complies with WHC-CM-4-41, Fire Protection Program Manual, Section 3.4 [1994] and WHC-SD-GN-FHA-30001, Rev. 0 [WHC, 1994]. Objectives of the FHA are to determine: (1) the fire hazards that expose the PFP facilities, or that are inherent in the building operations, (2) the adequacy of the fire safety features currently located in the PFP Complex, and (3) the degree of compliance of the facility with specific fire safety provisions in DOE orders, related engineering codes, and standards.

MCKINNIS, D.L.

1999-02-23T23:59:59.000Z

219

Independent Oversight Review, Plutonium Finishing Plant- July 2014  

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

Targeted Review of the Safety Significant Confinement Ventilation System and Review of Federal Assurance Capability at the Plutonium Finishing Plant

220

Independent Activity Report, Hanford Plutonium Finishing Plant- May 2012  

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

Criticality Safety Information Meeting for the Hanford Plutonium Finishing Plant [HIAR-RL-2012-05-14

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


221

Excess plutonium disposition using ALWR technology  

SciTech Connect

The Office of Nuclear Energy of the Department of Energy chartered the Plutonium Disposition Task Force in August 1992. The Task Force was created to assess the range of practicable means of disposition of excess weapons-grade plutonium. Within the Task Force, working groups were formed to consider: (1) storage, (2) disposal,and(3) fission options for this disposition,and a separate group to evaluate nonproliferation concerns of each of the alternatives. As a member of the Fission Working Group, the Savannah River Technology Center acted as a sponsor for light water reactor (LWR) technology. The information contained in this report details the submittal that was made to the Fission Working Group of the technical assessment of LWR technology for plutonium disposition. The following aspects were considered: (1) proliferation issues, (2) technical feasibility, (3) technical availability, (4) economics, (5) regulatory issues, and (6) political acceptance.

Phillips, A. (ed.); Buckner, M.R.; Radder, J.A.; Angelos, J.G.; Inhaber, H.

1993-02-01T23:59:59.000Z

222

ARM - Mobile Aerosol Observing System  

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

FacilitiesMobile Aerosol Observing System FacilitiesMobile Aerosol Observing System AMF Information Science Architecture Baseline Instruments AMF1 AMF2 AMF3 Data Operations AMF Fact Sheet Images Contacts AMF Deployments Hyytiälä, Finland, 2014 Manacapuru, Brazil, 2014 Oliktok Point, Alaska, 2013 Los Angeles, California, to Honolulu, Hawaii, 2012 Cape Cod, Massachusetts, 2012 Gan Island, Maldives, 2011 Ganges Valley, India, 2011 Steamboat Springs, Colorado, 2010 Graciosa Island, Azores, 2009-2010 Shouxian, China, 2008 Black Forest, Germany, 2007 Niamey, Niger, 2006 Point Reyes, California, 2005 Mobile Aerosol Observing System Intensive aerosol observations conducted on the campus of Brookhaven National Laboratory on Long Island, New York, using the ARM Mobile Aerosol Observing System. Intensive aerosol observations conducted on the campus of Brookhaven

223

Production and Characterization of Monodisperse Plutonium, Uranium, and Mixed Uranium?Plutonium Particles for Nuclear Safeguard Applications  

Science Journals Connector (OSTI)

Production and Characterization of Monodisperse Plutonium, Uranium, and Mixed Uranium?Plutonium Particles for Nuclear Safeguard Applications ... In order to prevent nuclear proliferation, the isotopic analysis of uranium and plutonium microparticles has strengthened the means in international safeguards for detecting undeclared nuclear activities. ...

Y. Ranebo; N. Niagolova; N. Erdmann; M. Eriksson; G. Tamborini; M. Betti

2010-04-23T23:59:59.000Z

224

Resource book: Decommissioning of contaminated facilities at Hanford  

SciTech Connect

In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 68 refs., 54 figs., 18 tabs.

Not Available

1991-09-01T23:59:59.000Z

225

First Plutonium Bomb Successfully Tested | National Nuclear Security  

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

Plutonium Bomb Successfully Tested | National Nuclear Security Plutonium Bomb Successfully Tested | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > First Plutonium Bomb Successfully Tested First Plutonium Bomb Successfully Tested July 16, 1945 Los Alamos, NM First Plutonium Bomb Successfully Tested

226

First Plutonium Bomb Successfully Tested | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Plutonium Bomb Successfully Tested | National Nuclear Security Plutonium Bomb Successfully Tested | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > First Plutonium Bomb Successfully Tested First Plutonium Bomb Successfully Tested July 16, 1945 Los Alamos, NM First Plutonium Bomb Successfully Tested

227

Uranium-plutonium-neptunium fuel cycle to produce isotopically denatured plutonium  

SciTech Connect

In view of the considerable amount of /sup 237/ Np produced as a by-product in nuclear power reactors, possible utilization of this nuclide in the nuclear fuel cycle has been studied. In particular, the performance of a gas-cooled fast breeder reactor as a neptunium burner was assessed. A strategy was developed and mass flows were computed for a denatured plutonium LWR strategy using uranium, plutonium and neptunium recycling. 10 refs.

Wydler, P.; Heer, W.; Stiller, P.; Wenger, H.U.

1980-06-01T23:59:59.000Z

228

ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1997-08-01T23:59:59.000Z

229

Manhattan Project: More Piles and Plutonium, 1942  

Office of Scientific and Technical Information (OSTI)

"Met Lab" alumni at the University of Chicago -- Fermi is on the far left of the front row; Zinn is on Fermi's left; Anderson is on the far right of the front row; and Szilard is over Anderson's right shoulder. MORE PILES AND PLUTONIUM "Met Lab" alumni at the University of Chicago -- Fermi is on the far left of the front row; Zinn is on Fermi's left; Anderson is on the far right of the front row; and Szilard is over Anderson's right shoulder. MORE PILES AND PLUTONIUM (1942) Events > Difficult Choices, 1942 More Uranium Research, 1942 More Piles and Plutonium, 1942 Enter the Army, 1942 Groves and the MED, 1942 Picking Horses, November 1942 Final Approval to Build the Bomb, December 1942 At the University of Chicago, meanwhile, Arthur Compton had consolidated most fission research at his new Metallurgical Laboratory(Met Lab). Compton decided to combine all pile research by stages. He continued to fund Enrico Fermi's pile research at Columbia University, while Fermi began preparations to move his work to Chicago. Funding continued as well for the theoretical work of Eugene Wigner at Princeton and of J. Robert Oppenheimer at the University of California, Berkeley. Compton also appointed Leo Szilard head of materials acquisition and arranged for Glenn T. Seaborg to move his plutonium work from Berkeley to Chicago in April 1942.

230

Plutonium and Polonium inside Giant Brown Algae  

Science Journals Connector (OSTI)

... in 1964 (see also refs. 4 and 5) when it emerged that certain marine algae accumulated plutonium so effectively that they might be used to detect small concentration changes in ... to detect small concentration changes in seawater that would be difficult to measure directly. Sessile algae are especially useful as monitoring aids because they can be sampled repeatedly. High concentrations ...

K. M. WONG; V. F. HODGE; T. R. FOLSOM

1972-06-23T23:59:59.000Z

231

Electrochemically Modulated Separation for Plutonium Safeguards  

SciTech Connect

Accurate and timely analysis of plutonium in spent nuclear fuel is critical in nuclear safeguards for detection of both protracted and rapid plutonium diversions. Gamma spectroscopy is a viable method for accurate and timely measurements of plutonium provided that the plutonium is well separated from the interfering fission and activation products present in spent nuclear fuel. Electrochemically modulated separation (EMS) is a method that has been used successfully to isolate picogram amounts of Pu from nitric acid matrices. With EMS, Pu adsorption may be turned "on" and "off" depending on the applied voltage, allowing for collection and stripping of Pu without the addition of chemical reagents. In this work, we have scaled up the EMS process to isolate microgram quantities of Pu from matrices encountered in spent nuclear fuel during reprocessing. Several challenges have been addressed including surface area limitations, radiolysis effects, electrochemical cell performance stability, and chemical interferences. After these challenges were resolved, 6 g Pu was deposited in the electrochemical cell with approximately an 800-fold reduction of fission and activation product levels from a spent nuclear fuel sample. Modeling showed that these levels of Pu collection and interference reduction may not be sufficient for Pu detection by gamma spectroscopy. The main remaining challenges are to achieve a more complete Pu isolation and to deposit larger quantities of Pu for successful gamma analysis of Pu. If gamma analyses of Pu are successful, EMS will allow for accurate and timely on-site analysis for enhanced Pu safeguards.

Pratt, Sandra H.; Breshears, Andrew T.; Arrigo, Leah M.; Schwantes, Jon M.; Duckworth, Douglas C.

2013-12-31T23:59:59.000Z

232

Plutonium in seawater of the Pacific Ocean  

Science Journals Connector (OSTI)

The present plutonium levels in the Pacific Ocean are summarized. The 239,240Pu concentrations in surface seawaters in the early 2000s were in the range of 1.5 to 9.2 mBqm?3 in the North Pacific and 0.8 to 4.1 m...

K. Hirose; M. Aoyama; C. S. Kim

2007-12-01T23:59:59.000Z

233

Hanford Site Near-Facility Environmental Monitoring Data Report for Calendar Year 2008  

SciTech Connect

Near-facility environmental monitoring is defined as monitoring near facilities that have the potential to discharge or have discharged, stored, or disposed of radioactive or hazardous materials. Monitoring locations are associated with nuclear facilities such as the Plutonium Finishing Plant, Canister Storage Building, and the K Basins; inactive nuclear facilities such as N Reactor and the Plutonium-Uranium Extraction (PUREX) Facility; and waste storage or disposal facilities such as burial grounds, cribs, ditches, ponds, tank farms, and trenches. Much of the monitoring consists of collecting and analyzing environmental samples and methodically surveying areas near facilities. The program is also designed to evaluate acquired analytical data, determine the effectiveness of facility effluent monitoring and controls, assess the adequacy of containment at waste disposal units, and detect and monitor unusual conditions.

Perkins, Craig J.; Dorsey, Michael C.; Mckinney, Stephen M.; Wilde, Justin W.; Poston, Ted M.

2009-09-15T23:59:59.000Z

234

PLUTONIUM SOLUBILITY IN HIGH-LEVEL WASTE ALKALI BOROSILICATE GLASS  

SciTech Connect

The solubility of plutonium in a Sludge Batch 6 (SB6) reference glass and the effect of incorporation of Pu in the glass on specific glass properties were evaluated. A Pu loading of 1 wt % in glass was studied. Prior to actual plutonium glass testing, surrogate testing (using Hf as a surrogate for Pu) was conducted to evaluate the homogeneity of significant quantities of Hf (Pu) in the glass, determine the most appropriate methods to evaluate homogeneity for Pu glass testing, and to evaluate the impact of Hf loading in the glass on select glass properties. Surrogate testing was conducted using Hf to represent between 0 and 1 wt % Pu in glass on an equivalent molar basis. A Pu loading of 1 wt % in glass translated to {approx}18 kg Pu per Defense Waste Processing Facility (DWPF) canister, or about 10X the current allowed limit per the Waste Acceptance Product Specifications (2500 g/m{sup 3} of glass or about 1700 g/canister) and about 30X the current allowable concentration based on the fissile material concentration limit referenced in the Yucca Mountain Project License Application (897 g/m{sup 3}3 of glass or about 600 g Pu/canister). Based on historical process throughput data, this level was considered to represent a reasonable upper bound for Pu loading based on the ability to provide Pu containing feed to the DWPF. The task elements included evaluating the distribution of Pu in the glass (e.g. homogeneity), evaluating crystallization within the glass, evaluating select glass properties (with surrogates), and evaluating durability using the Product Consistency Test -- Method A (PCT-A). The behavior of Pu in the melter was evaluated using paper studies and corresponding analyses of DWPF melter pour samples.The results of the testing indicated that at 1 wt % Pu in the glass, the Pu was homogeneously distributed and did not result in any formation of plutonium-containing crystalline phases as long as the glass was prepared under 'well-mixed' conditions. The incorporation of 1 wt % Pu in the glass did not adversely impact glass viscosity (as assessed using Hf surrogate) or glass durability. Finally, evaluation of DWPF glass pour samples that had Pu concentrations below the 897 g/m{sup 3} limit showed that Pu concentrations in the glass pour stream were close to targeted compositions in the melter feed indicating that Pu neither volatilized from the melt nor stratified in the melter when processed in the DWPF melter.

Marra, J.; Crawford, C.; Fox, K.; Bibler, N.

2011-01-04T23:59:59.000Z

235

Mobile Advertising.  

E-Print Network (OSTI)

?? This report has been produced as a result of a Thesis assignment conducted at Ericsson. Itspurpose is to give an overview of the Mobile (more)

Salim, Ali

2009-01-01T23:59:59.000Z

236

ARM - Facility News Article  

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

August 31, 2008 [Facility News] August 31, 2008 [Facility News] Phase 2 of Orbiting Carbon Observatory Field Campaign Begins Bookmark and Share A camera, weather station, and sun tracker with a protective dome are located on the roof of the fully automated FTS mobile laboratory. Inside the shelter, the spectrometer receives the reflected solar beam from the sun tracker, while the main computer system operates all the instruments and acquires the data. A camera, weather station, and sun tracker with a protective dome are located on the roof of the fully automated FTS mobile laboratory. Inside the shelter, the spectrometer receives the reflected solar beam from the sun tracker, while the main computer system operates all the instruments and acquires the data. The Orbiting Carbon Observatory, or OCO, is a National Aeronautics and

237

LANSCE | Facilities  

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

Isotope Production Facility (IPF) Lujan Neutron Scattering Center Materials Test Station (MTS) Proton Radiography (pRad) Ultracold Neutrons (UCN) Weapons Neutron Research Facility...

238

ARM - ARM Facility at EGU 2012  

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

CenterARM Facility at EGU 2012 CenterARM Facility at EGU 2012 Media Contact Lynne Roeder lynne-dot-roeder-at-pnnl-dot-gov @armnewsteam Field Notes Blog Topics Field Notes89 AGU 3 AMIE 10 ARM Aerial Facility 2 ARM Mobile Facility 1 6 ARM Mobile Facility 2 47 BAECC 1 BBOP 4 MAGIC 12 MC3E 17 SGP 2 STORMVEX 29 TCAP 3 Search News Search Blog News Center All Categories What's this? Social Media Guidance News Center All Categories Features and Releases Facility News Field Notes Blog feed Events feed Employment Research Highlights Data Announcements Education News Archive What's this? Social Media Guidance ARM Facility at EGU 2012 At the 2012 European Geophysical Union General Assembly in Vienna, the ARM Climate Research Facility is hosting a booth located near the escalators in the Exhibition Entrance Hall. In their first time attending the assembly,

239

A Note on the Reaction of Hydrogen and Plutonium  

SciTech Connect

Plutonium hydride has many practical and experimental purposes. The reaction of plutonium and hydrogen has interesting characteristics, which will be explored in the following analysis. Plutonium is a radioactive actinide metal that emits alpha particles. When plutonium metal is exposed to air, the plutonium oxides and hydrides, and the volume increases. PuH{sub 2} and Pu{sub 2}O{sub 3} are the products. Hydrogen is a catalyst for plutonium's corrosion in air. The reaction can take place at room temperature because it is fairly insensitive to temperature. Plutonium hydride, or PuH{sub 2}, is black and metallic. After PuH{sub 2} is formed, it quickly flakes off and burns. The reaction of hydrogen and plutonium is described as pyrophoric because the product will spontaneously ignite when oxygen is present. This tendency must be considered in the storage of metal plutonium. The reaction is characterized as reversible and nonstoichiometric. The reaction goes as such: Pu + H{sub 2} {yields} PuH{sub 2}. When PuH{sub 2} is formed, the hydrogen/plutonium ratio is between 2 and 2.75 (approximately). As more hydrogen is added to the system, the ratio increases. When the ratio exceeds 2.75, PuH{sub 3} begins to form along with PuH{sub 2}. Once the ratio surpasses 2.9, only PuH{sub 3} remains. The volume of the plutonium sample increases because of the added hydrogen and the change in crystal structure which the sample undergoes. As more hydrogen is added to a system of metal plutonium, the crystal structure evolves. Plutonium has a crystal structure classified as monoclinic. A monoclinic crystal structure appears to be a rectangular prism. When plutonium reacts with hydrogen, the product PuH{sub 2}, becomes a fluorite structure. It can also be described as a face centered cubic structure. PuH{sub 3} forms a hexagonal crystal structure. As plutonium evolves from metal plutonium to plutonium hydride to plutonium trihydride, the crystal structure evolves from monoclinic to fluorite to hexagonal. This change in crystal structure as a result of adding hydrogen is a shared characteristic with other actinide elements. Americium is isostructural with plutonium because they both form cubic dihyrides and hexagonal trihydrides. Reacting hydrogen with plutonium has the practical application of separating plutonium from other materials that don't react as well with hydrogen. When plutonium is placed in a chamber where there is very little oxygen, it can react with hydrogen without igniting. The hydrogen plutonium reaction can then be reversed, thus regaining the separated plutonium. Another application of this reaction is that it can be used to predict how plutonium reacts with other substances. Deuterium and tritium are two isotopes of hydrogen that are of interest. They are known to react likewise to hydrogen because they have similar properties. The reaction of plutonium and isotopes of hydrogen can prove to be very informative.

Noone, Bailey C [Los Alamos National Laboratory

2012-08-15T23:59:59.000Z

240

Radiological hazard classification of DOE facilities by DOE STD-1027-92: LANL nuclear facility list  

SciTech Connect

Los Alamos facilities containing significant radiological hazards have been reclassified according to DOE-SID 1027-92, a recently issued guide for hazard classification. DOE-STD 1027-92 was provided in support of DOE Order 5480.23 to identify which facilities would be governed under DOE 5480.23 requirements; these would presumably be called nuclear facilities. This new classification has affected the original list of 18 LANL nuclear facilities by increasing it to 39. It has also lowered the classification of TA-55-4, the plutonium processing facility containing highest intrinsic hazard at LANL, from the highest classification to an intermediate classification. This presentation addresses the impact of these changes in the nuclear facility list in the areas of radiological health, safety analysis documentation, and risk management.

Elder, J.C.

1993-05-01T23:59:59.000Z

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


241

Radiological hazard classification of DOE facilities by DOE STD-1027-92: LANL nuclear facility list  

SciTech Connect

Los Alamos facilities containing significant radiological hazards have been reclassified according to DOE-SID 1027-92, a recently issued guide for hazard classification. DOE-STD 1027-92 was provided in support of DOE Order 5480.23 to identify which facilities would be governed under DOE 5480.23 requirements; these would presumably be called nuclear facilities. This new classification has affected the original list of 18 LANL nuclear facilities by increasing it to 39. It has also lowered the classification of TA-55-4, the plutonium processing facility containing highest intrinsic hazard at LANL, from the highest classification to an intermediate classification. This presentation addresses the impact of these changes in the nuclear facility list in the areas of radiological health, safety analysis documentation, and risk management.

Elder, J.C.

1993-01-01T23:59:59.000Z

242

Department of Energy Announces Decision to Consolidate Surplus Plutonium in  

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

Decision to Consolidate Surplus Decision to Consolidate Surplus Plutonium in South Carolina Department of Energy Announces Decision to Consolidate Surplus Plutonium in South Carolina September 5, 2007 - 3:16pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced its decision to consolidate surplus, non-pit plutonium at its Savannah River Site (SRS) in South Carolina, greatly reducing storage costs and significantly enhancing security across the nation's weapons complex. DOE will begin shipping the surplus, non-pit plutonium no sooner than 30 days from today and under the plan this surplus plutonium is expected to be shipped to SRS by 2010. "Consolidation is a key part of the Department's efforts to properly manage surplus plutonium and follows our dedication to non-proliferation,

243

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental  

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

3-S2: Surplus Plutonium Disposition Supplemental 3-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement Summary This EIS analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives. The original EIS is available here. For more information, see: www.nnsa.energy.gov/nepa/spdsupplementaleis Public Comment Opportunities None available at this time. Documents Available for Download April 25, 2013 EIS-0283-S2: Interim Action Determination Surplus Plutonium Disposition Supplemental Environmental Impact Statement (K-Area Materials Storage (KAMS) Area Expansion at the Savannah River Site)

244

Department of Energy Announces Decision to Consolidate Surplus Plutonium in  

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

Department of Energy Announces Decision to Consolidate Surplus Department of Energy Announces Decision to Consolidate Surplus Plutonium in South Carolina Department of Energy Announces Decision to Consolidate Surplus Plutonium in South Carolina September 5, 2007 - 3:16pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced its decision to consolidate surplus, non-pit plutonium at its Savannah River Site (SRS) in South Carolina, greatly reducing storage costs and significantly enhancing security across the nation's weapons complex. DOE will begin shipping the surplus, non-pit plutonium no sooner than 30 days from today and under the plan this surplus plutonium is expected to be shipped to SRS by 2010. "Consolidation is a key part of the Department's efforts to properly manage surplus plutonium and follows our dedication to non-proliferation,

245

LANL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. LANL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within both Category 1 and 2 areas. Technical Area (TA) 55/Plutonium Facility 4 will be used to store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, assemble rods, and store fuel bundles. Bundles will be assembled at a separate facility, several of which have been identified as suitable for that activity. The Chemistry and Metallurgy Research Building (at TA-3) will be used for analytical chemistry support. Waste operations will be conducted in TA-50 and TA-54. Only very minor modifications will be needed to accommodate the LA program. These modifications consist mostly of minor equipment upgrades. A commercial reactor operator has not been identified for the LA irradiation. Postirradiation examination (PIE) of the irradiated fuel will take place at either Oak Ridge National Laboratory or ANL-W. The only modifications required at either PIE site would be to accommodate full-length irradiated fuel rods. Results from this program are critical to the overall plutonium distribution schedule.

Fisher, S.E.; Holdaway, R.; Ludwig, S.B. [and others

1998-08-01T23:59:59.000Z

246

CRITICALITY CURVES FOR PLUTONIUM HYDRAULIC FLUID MIXTURES  

SciTech Connect

This Calculation Note performs and documents MCNP criticality calculations for plutonium (100% {sup 239}Pu) hydraulic fluid mixtures. Spherical geometry was used for these generalized criticality safety calculations and three geometries of neutron reflection are: {sm_bullet}bare, {sm_bullet}1 inch of hydraulic fluid, or {sm_bullet}12 inches of hydraulic fluid. This document shows the critical volume and critical mass for various concentrations of plutonium in hydraulic fluid. Between 1 and 2 gallons of hydraulic fluid were discovered in the bottom of HA-23S. This HA-23S hydraulic fluid was reported by engineering to be Fyrquel 220. The hydraulic fluid in GLovebox HA-23S is Fyrquel 220 which contains phosphorus. Critical spherical geometry in air is calculated with 0 in., 1 in., or 12 inches hydraulic fluid reflection.

WITTEKIND WD

2007-10-03T23:59:59.000Z

247

TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION  

SciTech Connect

Supporting nuclear nonproliferation and global security principles, beginning in 1994 the United States has withdrawn more than 50 metric tons (MT) of government-controlled plutonium from potential use in nuclear weapons. The Department of Energy (DOE), including the National Nuclear Security Administration, established protocols for the tracking of this "excess" and "surplus" plutonium, and for reconciling the current storage and utilization of the plutonium to show that its management is consistent with the withdrawal policies. Programs are underway to ensure the safe and secure disposition of the materials that formed a major part of the weapons stockpile during the Cold War, and growing quantities have been disposed as waste, after which they are not included in traditional nuclear material control and accountability (NMC&A) data systems. A combination of resources is used to perform the reconciliations that form the basis for annual reporting to DOE, to U.S. Department of State, and to international partners including the International Atomic Energy Agency.

Allender, J.; Beams, J.; Sanders, K.; Myers, L.

2013-07-16T23:59:59.000Z

248

PLUTONIUM METALLIC FUELS FOR FAST REACTORS  

SciTech Connect

Early interest in metallic plutonium fuels for fast reactors led to much research on plutonium alloy systems including binary solid solutions with the addition of aluminum, gallium, or zirconium and low-melting eutectic alloys with iron and nickel or cobalt. There was also interest in ternaries of these elements with plutonium and cerium. The solid solution and eutectic alloys have most unusual properties, including negative thermal expansion in some solid-solution alloys and the highest viscosity known for liquid metals in the Pu-Fe system. Although metallic fuels have many potential advantages over ceramic fuels, the early attempts were unsuccessful because these fuels suffered from high swelling rates during burn up and high smearing densities. The liquid metal fuels experienced excessive corrosion. Subsequent work on higher-melting U-PuZr metallic fuels was much more promising. In light of the recent rebirth of interest in fast reactors, we review some of the key properties of the early fuels and discuss the challenges presented by the ternary alloys.

STAN, MARIUS [Los Alamos National Laboratory; HECKER, SIEGFRIED S. [Los Alamos National Laboratory

2007-02-07T23:59:59.000Z

249

Pyrochemical processing of plutonium. Technology review report  

SciTech Connect

Non-aqueous processes are now in routine use for direct conversion of plutonium oxide to metal, molten salt extraction of americium, and purification of impure metals by electrorefining. These processes are carried out at elevated temperatures in either refractory metal crucibles or magnesium-oxide ceramics in batch-mode operation. Direct oxide reduction is performed in units up to 700 gram PuO/sub 2/ batch size with molten calcium metal as the reductant and calcium chloride as the reaction flux. Americium metal is removed from plutonium metal by salt extraction with molten magnesium chloride. Electrorefining is used to isolate impurities from molten plutonium by molten salt ion transport in a controlled potential oxidation-reduction cell. Such cells can purify five or more kilograms of impure metal per 5-day electrorefining cycle. The product metal obtained is typically > 99.9% pure, starting from impure feeds. Metal scrap and crucible skulls are recovered by hydriding of the metallic residues and recovered either as impure metal or oxide feeds.

Coops, M.S.; Knighton, J.B.; Mullins, L.J.

1982-09-08T23:59:59.000Z

250

Mobile IPMobile IP Mobile IPMobile IP  

E-Print Network (OSTI)

Mobile IPMobile IP #12;2 Mobile IPMobile IP · How do we support mobile users whose point of attachment to the network changes dynamically? #12;3 Mobile IPMobile IP · The goal of Mobile IP is to allow connectivity automatically, despite the change. · While Mobile IP can work with wired connections, where you

Yeom, Ikjun

251

ARM - Facility News Article  

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

January 11, 2007 [Facility News] January 11, 2007 [Facility News] ARM Mobile Facility Moves to China in 2008 for Study of Aerosol Impacts on Climate Bookmark and Share Onshore winds and a mountain range to the west of Shanghai form a natural basin which traps particulates in the air above the Yangtze River delta region. (Illustration courtesy of Patricia Ebrey, University of Washington) Onshore winds and a mountain range to the west of Shanghai form a natural basin which traps particulates in the air above the Yangtze River delta region. (Illustration courtesy of Patricia Ebrey, University of Washington) China generates exceptionally high amounts of aerosol particles whose influence on the atmosphere has been detected across the Pacific Rim. In the Yangtze River delta in southeast China, these high aerosol loadings

252

ARM - Facility News Article  

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

31, 2005 [Facility News] 31, 2005 [Facility News] Ancillary Site to Provide Key Data from Africa Bookmark and Share In January 2006, the ARM Mobile Facility (AMF) begins a year-long field campaign in Africa as part of a multi-year international experiment called the African Monsoon Multidisciplinary Analysis (AMMA). The AMF will be placed at the airport in Niamey, Niger, well within view of the Global Earth Radiation Budget (GERB) geostationary satellite. Cloud and radiative property measurements collected by the AMF will be used in conjunction with GERB data for a greater understanding of the atmosphere than could be gained from either dataset alone. While preparing for the campaign, the science team identified the need for instrumentation at an off-site location to compare radiative measurements from the natural environment of

253

ARM - Facility News Article  

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

April 15, 2010 [Facility News] April 15, 2010 [Facility News] Second Phase of African Scientific Exchange Underway Bookmark and Share Left to right: Dr. Zewdu Segele and Hama Hamidou examine reflectivity measurements made by the W-band ARM cloud radar in Niamey during July 2006. Left to right: Dr. Zewdu Segele and Hama Hamidou examine reflectivity measurements made by the W-band ARM cloud radar in Niamey during July 2006. Continuing an international collaboration that began with the ARM Mobile Facility deployment to Niamey, Niger, in 2006, meteorologist Hama Hamidou from the University of Niamey recently arrived at the Cooperative Institute for Mesoscale Meteorological Studies at the University of Oklahoma for a six-month scientific exchange. Under the guidance of Dr. Zewdu Segele, a

254

ARM - Facility News Article  

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

April 30, 2013 [Facility News] April 30, 2013 [Facility News] Gearing Up for Science in Amazon Rainforest Bookmark and Share In March 2013, an initial instrument suite began operating near Manacupuru, in the Brazilian state of Amazonas, as part of the GOAMAZON field campaign. In March 2013, an initial instrument suite began operating near Manacupuru, in the Brazilian state of Amazonas, as part of the GOAMAZON field campaign. Preparing for the biggest and most complex deployment of field resources to date, the ARM Mobile Facility operations team from Los Alamos National Laboratory spent three weeks in Brazil in early March tackling a range of protocol and logistics tasks for next year's GOAMAZON field campaign. Between ARM and Brazilian collaborators, about 80 instruments will obtain

255

President Truman Increases Production of Uranium and Plutonium | National  

National Nuclear Security Administration (NNSA)

Increases Production of Uranium and Plutonium | National Increases Production of Uranium and Plutonium | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > President Truman Increases Production of Uranium and Plutonium President Truman Increases Production of Uranium and Plutonium October 09, 1950

256

LLNL Conducts First Plutonium Shot Using the JASPER Gas Gun ...  

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

of the shocked plutonium. Shock physics experiments complement the ongoing subcritical experiment program at NTS as part of the NNSA's stockpile stewardship program to...

257

Summary - Plutonium Preparation Project at the Savannah River...  

Office of Environmental Management (EM)

3. An alternate waste disposition path that is in compliance with the current Yucca Mountain plutonium license requirements should be developed for the 5MT proposed to...

258

Influence of Iron Redox Transformations on Plutonium Sorption...  

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

state of iron in the system. Experiments were conducted to examine the effect of sediment iron mineral composition and oxidation state on plutonium sorption and oxidation...

259

EIS-0276: Rocky Flats Plutonium Storage, Golden, Colorado  

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

This EIS analyzes DOE's proposed action to provide safe interim storage of approximately 10 metric tons of plutonium at the Rocky Flats Environmental Technology Site (RFETS).

260

LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

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


261

Plutonium metal standards exchange program for actinide measurement quality assurance (20012007)  

Science Journals Connector (OSTI)

Plutonium metal exchange programs operated by the Rocky Flats Plant were conducted from 19561989 to ... of methods and results for plutonium, uranium, neptunium, and americium, measurements.

Lav Tandon; Kevin Kuhn; Diana Decker

2009-11-01T23:59:59.000Z

262

Supplementary data for "Relativistic density functional theory modeling of plutonium and  

E-Print Network (OSTI)

Supplementary data for "Relativistic density functional theory modeling of plutonium and americium equilibrium geometries of plutonium and americium oxide molecules (standard .xyz files separated by empty

Titov, Anatoly

263

Characterization of Representative Materials in Support of Safe, Long Term Storage of Surplus Plutonium in DOE-STD-3013 Containers  

SciTech Connect

The Surveillance and Monitoring Program is a joint Los Alamos National Laboratory/Savannah River Site effort funded by the Department of Energy-Environmental Management to provide the technical basis for the safe, long-term storage (up to 50 years) of over 6 metric tons of plutonium stored in over 5,000 DOE-STD-3013 containers at various facilities around the DOE complex. The majority of this material is plutonium that is surplus to the nuclear weapons program, and much of it is destined for conversion to mixed oxide fuel for use in US nuclear power plants. The form of the plutonium ranges from relatively pure metal and oxide to very impure oxide. The performance of the 3013 containers has been shown to depend on moisture content and on the levels, types and chemical forms of the impurities. The oxide materials that present the greatest challenge to the storage container are those that contain chloride salts. Other common impurities include oxides and other compounds of calcium, magnesium, iron, and nickel. Over the past 15 years the program has collected a large body of experimental data on 54 samples of plutonium, with 53 chosen to represent the broader population of materials in storage. This paper summarizes the characterization data, moisture analysis, particle size, surface area, density, wattage, actinide composition, trace element impurity analysis, and shelf life surveillance data and includes origin and process history information. Limited characterization data on fourteen nonrepresentative samples is also presented.

Narlesky, Joshua E. [Los Alamos National Laboratory; Stroud, Mary Ann [Los Alamos National Laboratory; Smith, Paul Herrick [Los Alamos National Laboratory; Wayne, David M. [Los Alamos National Laboratory; Mason, Richard E. [MET-1: ACTINIDE PROCESSING SUPPORT; Worl, Laura A. [Los Alamos National Laboratory

2013-02-15T23:59:59.000Z

264

Plutonium Oxidation and Subsequent Reduction by Mn (IV) Minerals  

SciTech Connect

Plutonium sorbed to rock tuff was preferentially associated with manganese oxides. On tuff and synthetic pyrolusite (Mn{sup IV}O{sub 2}), Pu(IV) or Pu(V) was initially oxidized, but over time Pu(IV) became the predominant oxidation state of sorbed Pu. Reduction of Pu(V/VI), even on non-oxidizing surfaces, is proposed to result from a lower Gibbs free energy of the hydrolyzed Pu(IV) surface species versus that of the Pu(V) or Pu(VI) surface species. This work suggests that despite initial oxidation of sorbed Pu by oxidizing surfaces to more soluble forms, the less mobile form of Pu, Pu(IV), will dominate Pu solid phase speciation during long term geologic storage. The safe design of a radioactive waste or spent nuclear fuel geologic repository requires a risk assessment of radionuclides that may potentially be released into the surrounding environment. Geochemical knowledge of the radionuclide and the surrounding environment is required for predicting subsurface fate and transport. Although difficult even in simple systems, this task grows increasingly complicated for constituents, like Pu, that exhibit complex environmental chemistries. The environmental behavior of Pu can be influenced by complexation, precipitation, adsorption, colloid formation, and oxidation/reduction (redox) reactions (1-3). To predict the environmental mobility of Pu, the most important of these factors is Pu oxidation state. This is because Pu(IV) is generally 2 to 3 orders of magnitude less mobile than Pu(V) in most environments (4). Further complicating matters, Pu commonly exists simultaneously in several oxidation states (5, 6). Choppin (7) reported Pu may exist as Pu(IV), Pu(V), or Pu(VI) oxic natural groundwaters. It is generally accepted that plutonium associated with suspended particulate matter is predominantly Pu(IV) (8-10), whereas Pu in the aqueous phase is predominantly Pu(V) (2, 11-13). The influence of the character of Mn-containing minerals expected to be found in subsurface repository environments on Pu oxidation state distributions has been the subject of much recent research. Kenney-Kennicutt and Morse (14), Duff et al. (15), and Morgenstern and Choppin (16) observed oxidation of Pu facilitated by Mn(IV)-bearing minerals. Conversely, Shaughnessy et al. (17) used X-ray Absorption near-edge spectroscopy (XANES) to show reduction of Pu(VI) by hausmannite (Mn{sup II}Mn{sub 2}{sup III}O{sub 4}) and manganite ({gamma}-Mn{sup III}OOH) and Kersting et al., (18) observed reduction of Pu(VI) by pyrolusite (Mn{sup IV}O{sub 2}). In this paper, we attempt to reconcile the apparently conflicting datasets by showing that Mn-bearing minerals can indeed oxidize Pu, however, if the oxidized species remains on the solid phase, the oxidation step competes with the formation of Pu(IV) that becomes the predominant solid phase Pu species with time. The experimental approach we took was to conduct longer term (approximately two years later) oxidation state analyses on the Pu sorbed to Yucca Mountain tuff (initial analysis reported by Duff et al., (15)) and measure the time-dependant changes in the oxidation state distribution of Pu in the presence of the Mn mineral pyrolusite.

KAPLAN, DANIEL

2005-09-13T23:59:59.000Z

265

Facility Safety  

Directives, Delegations, and Requirements

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

1996-10-24T23:59:59.000Z

266

Facility Safety  

Directives, Delegations, and Requirements

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

1995-11-16T23:59:59.000Z

267

Certified Facilities  

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

Industrial Leaders: The industrial facilities shown below are among the first to earn certification for Superior Energy Performance (SEP).

268

Recommended plutonium release fractions from postulated fires. Final report  

SciTech Connect

This report was written at the request of EG&G Rocky Flats, Inc. in support of joint emergency planning for the Rocky Flats Plant (RFP) by EG&G and the State of Colorado. The intent of the report is to provide the State of Colorado with an independent assessment of any respirable plutonium releases that might occur in the event of a severe fire at the plant. Fire releases of plutonium are of interest because they have been used by EG&G to determine the RFP emergency planning zones. These zones are based on the maximum credible accident (MCA) described in the RFP Final Environmental Impact Statement (FEIS) of 1980, that MCA is assumed to be a large airplane crashing into a RFP plutonium building.The objective of this report was first, to perform a worldwide literature review of relevant release experiments from 1960 to the present and to summarize those findings, and second, to provide recommendations for application of the experimental data to fire release analyses at Rocky Flats. The latter step requires translation between experimental and expected RFP accident parameters, or ``scaling.`` The parameters of particular concern are: quantities of material, environmental parameters such as the intensity of a fire, and the physico-chemical forms of the plutonium. The latter include plutonium metal, bulk plutonium oxide powder, combustible and noncombustible wastes contaminated with plutonium oxide powder, and residues from plutonium extraction processes.

Kogan, V.; Schumacher, P.M.

1993-12-01T23:59:59.000Z

269

Fuel bundle design for enhanced usage of plutonium fuel  

DOE Patents (OSTI)

A nuclear fuel bundle includes a square array of fuel rods each having a concentration of enriched uranium and plutonium. Each rod of an interior array of the rods also has a concentration of gadolinium. The interior array of rods is surrounded by an exterior array of rods void of gadolinium. By this design, usage of plutonium in the nuclear reactor is enhanced.

Reese, Anthony P. (San Jose, CA); Stachowski, Russell E. (Fremont, CA)

1995-01-01T23:59:59.000Z

270

Processing of Non-PFP Plutonium Oxide in Hanford Plants  

SciTech Connect

Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred routinely at Hanfords Plutonium Finishing Plant (PFP) in glovebox line operations. Plutonium oxide is difficult to dissolve, particularly if it has been high-fired; i.e., calcined to temperatures above about 400C and much of it was. Dissolution of the PuO2 in the scrap typically was performed in PFPs Miscellaneous Treatment line using nitric acid (HNO3) containing some source of fluoride ion, F-, such as hydrofluoric acid (HF), sodium fluoride (NaF), or calcium fluoride (CaF2). The HNO3 concentration generally was 6 M or higher whereas the fluoride concentration was ~0.5 M or lower. At higher fluoride concentrations, plutonium fluoride (PuF4) would precipitate, thus limiting the plutonium dissolution. Some plutonium-bearing scrap also contained PuF4 and thus required no added fluoride. Once the plutonium scrap was dissolved, the excess fluoride was complexed with aluminum ion, Al3+, added as aluminum nitrate, Al(NO3)39H2O, to limit collateral damage to the process equipment by the corrosive fluoride. Aluminum nitrate also was added in low quantities in processing PuF4.

Jones, Susan A.; Delegard, Calvin H.

2011-03-10T23:59:59.000Z

271

Plutonium finishing plant safety systems and equipment list  

SciTech Connect

The Safety Equipment List (SEL) supports Analysis Report (FSAR), WHC-SD-CP-SAR-021 and the Plutonium Finishing Plant Operational Safety Requirements (OSRs), WHC-SD-CP-OSR-010. The SEL is a breakdown and classification of all Safety Class 1, 2, and 3 equipment, components, or system at the Plutonium Finishing Plant complex.

Bergquist, G.G.

1995-01-06T23:59:59.000Z

272

DOE plutonium disposition study: Analysis of existing ABB-CE Light Water Reactors for the disposition of weapons-grade plutonium. Final report  

SciTech Connect

Core reactivity and basic fuel management calculations were conducted on the selected reactors (with emphasis on the System 80 units as being the most desirable choice). Methods used were identical to those reported in the Evolutionary Reactor Report. From these calculations, the basic mission capability was assessed. The selected reactors were studied for modification, such as the addition of control rod nozzles to increase rod worth, and internals and control system modifications that might also be needed. Other system modifications studied included the use of enriched boric acid as soluble poison, and examination of the fuel pool capacities. The basic geometry and mechanical characteristics, materials and fabrication techniques of the fuel assemblies for the selected existing reactors are the same as for System 80+. There will be some differences in plutonium loading, according to the ability of the reactors to load MOX fuel. These differences are not expected to affect licensability or EPA requirements. Therefore, the fuel technology and fuel qualification sections provided in the Evolutionary Reactor Report apply to the existing reactors. An additional factor, in that the existing reactor availability presupposes the use of that reactor for the irradiation of Lead Test Assemblies, is discussed. The reactor operating and facility licenses for the operating plants were reviewed. Licensing strategies for each selected reactor were identified. The spent fuel pool for the selected reactors (Palo Verde) was reviewed for capacity and upgrade requirements. Reactor waste streams were identified and assessed in comparison to uranium fuel operations. Cost assessments and schedules for converting to plutonium disposition were estimated for some of the major modification items. Economic factors (incremental costs associated with using weapons plutonium) were listed and where possible under the scope of work, estimates were made.

Not Available

1994-06-01T23:59:59.000Z

273

Independent Activity Report, Hanford Plutonium Finishing Plant - May 2012 |  

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

Hanford Plutonium Finishing Plant - Hanford Plutonium Finishing Plant - May 2012 Independent Activity Report, Hanford Plutonium Finishing Plant - May 2012 May 2012 Criticality Safety Information Meeting for the Hanford Plutonium Finishing Plant [HIAR-RL-2012-05-14] The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety issues and experiences principally with respect to the Decontamination and Decommissioning (D&D) activities at the Plutonium Finishing Plant (PFP). These discussions also included aspects of Non-Destructive Assay (NDA) in support of criticality safety evaluations.

274

Mobile OFDM communications  

E-Print Network (OSTI)

G. L. Stuber, Principles of Mobile Communications, Kluweranalysis of OFDM in a mobile environment, VehicularA statistical theory of mobile radio reception, Bell Syst.

Wang, Tiejun

2006-01-01T23:59:59.000Z

275

Thermal Stability Studies of Candidate Decontamination Agents for Hanfords Plutonium Finishing Plant Plutonium-Contaminated Gloveboxes  

SciTech Connect

This report provides the results of PNNL's and Fluor's studies of the thermal stabilities of potential wastes arising from decontamination of Hanford's Plutonium Finishing Plant's plutonium contaminated gloveboxes. The candidate wastes arising from the decontamination technologies ceric nitrate/nitric acid, RadPro, Glygel, and Aspigel.

Scheele, Randall D.; Cooper, Thurman D.; Jones, Susan A.; Ewalt, John R.; Compton, James A.; Trent, Donald S.; Edwards, Matthew K.; Kozelisky, Anne E.; Scott, Paul A.; Minette, Michael J.

2005-09-29T23:59:59.000Z

276

Mobile Window Thermal Test  

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

Mobile Window Thermal Test (MoWiTT) Facility Mobile Window Thermal Test (MoWiTT) Facility winter.jpg (469135 bytes) The window has come a long way since the days when it was a single pane of glass in a wood frame. Low-emissivity windows were designed to help buildings retain some of the energy that would have leaked out of less efficient windows. Designing efficient window-and-frame systems is one strategy for reducing the energy use of buildings. But the net energy flowing through a window is a combination of temperature- driven thermal flows and transmission of incident solar energy, both of which vary with time. U-factor and solar heat gain coefficient (SHGC), the window properties that control these flows, depend partly on ambient conditions. Window energy flows can affect how much energy a building uses, depending on when the window flows are available to help meet other energy demands within the building, and when they are adverse, adding to building energy use. This leads to a second strategy for reducing building energy use: using the beneficial solar gain available through a window, either for winter heating or for daylighting, while minimizing adverse flows.

277

E-Print Network 3.0 - aqueous nitrate plutonium Sample Search...  

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

ameri- cium... on suitable practice. Key words Radiochemistry, radioecology, strontium, uranium, plutonium, americium, curium... determination ......

278

First Principles Investigations of Americium, Plutonium and their Mixtures using Dynamical Mean Field Theory  

SciTech Connect

We developed a relativistic dynamical mean field approach to study the properties of Plutonium Americium mixtures.

Gabriel Kotliar and Sergej Savrasov

2007-04-17T23:59:59.000Z

279

Co-Design: Fabrication of Unalloyed Plutonium  

SciTech Connect

The successful induction casting of plutonium is a challenge which requires technical expertise in areas including physical metallurgy, surface and corrosion chemistry, materials science, electromagnetic engineering and a host of other technologies all which must be applied in concert. Here at LANL, we are employing a combined experimental and computational approach to design molds and develop process parameters needed to produce desired temperature profiles and improved castings. Computer simulations are performed using the commercial code FLOW-3D and the LANL ASC computer code TRUCHAS to reproduce the entire casting process starting with electromagnetic or radiative heating of the mold and metal and continuing through pouring with coupled fluid flow, heat transfer and non-isothermal solidification. This approach greatly reduces the time required to develop a new casting designs and also increases our understanding of the casting process, leading to a more homogeneous, consistent product and better process control. We will discuss recent casting development results in support of unalloyed plutonium rods for mechanical testing.

Korzekwa, Deniece R. [Los Alamos National Laboratory; Knapp, Cameron M. [Los Alamos National Laboratory; Korzekwa, David A. [Los Alamos National Laboratory; Gibbs, John W [Northwestern University

2012-07-25T23:59:59.000Z

280

System for imaging plutonium through heavy shielding  

SciTech Connect

A single pinhole can be used to image strong self-luminescent gamma-ray sources such as plutonium on gamma scintillation (Anger) cameras. However, if the source is weak or heavily shielded, a poor signal to noise ratio can prevent acquisition of the image. An imaging system designed and built at Los Alamos National Laboratory uses a coded aperture to image heavily shielded sources. The paper summarizes the mathematical techniques, based on the Fast Delta Hadamard transform, used to decode raw images. Practical design considerations such as the phase of the uniformly redundant aperture and the encoded image sampling are discussed. The imaging system consists of a custom designed m-sequence coded aperture, a Picker International Corporation gamma scintillation camera, a LeCroy 3500 data acquisition system, and custom imaging software. The paper considers two sources - 1.5 mCi /sup 57/Co unshielded at a distance of 27 m and 220 g of bulk plutonium (11.8% /sup 240/Pu) with 0.3 cm lead, 2.5 cm steel, and 10 cm of dense plastic material at a distance of 77.5 cm. Results show that the location and geometry of a source hidden in a large sealed package can be determined without having to open the package. 6 references, 4 figures.

Kuckertz, T.H.; Cannon, T.M.; Fenimore, E.E.; Moss, C.E.; Nixon, K.V.

1984-04-01T23:59:59.000Z

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


281

SHIELDING AND DETECTOR RESPONSE CALCULATIONS PERTAINING TO CATEGORY 1 QUANTITIES OF PLUTONIUM AND HAND-HELD PLASTIC SCINTILLATORS  

SciTech Connect

Nuclear facilities sometimes use hand-held plastic scintillator detectors to detect attempts to divert special nuclear material in situations where portal monitors are impractical. MCNP calculations have been performed to determine the neutron and gamma radiation field arising from a Category I quantity of weapons-grade plutonium in various shielding configurations. The shields considered were composed of combinations of lead and high-density polyethylene such that the mass of the plutonium plus shield was 22.7 kilograms. Monte-Carlo techniques were also used to determine the detector response to each of the shielding configurations. The detector response calculations were verified using field measurements of high-, medium-, and low- energy gamma-ray sources as well as a Cf-252 neutron source.

Couture, A.

2013-06-07T23:59:59.000Z

282

MobileMatch App  

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

MobileMatch VolunteerMatch Mobile App MobileMatch is a mobile extension (app) to LANL's VolunteerMatch site that allows volunteers to search, sign up and track hours. Contact...

283

ARM - Facility News Article  

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

April 15, 2006 [Facility News] April 15, 2006 [Facility News] TWP Site Hosts Preliminary Study for Long Term Measurements of Greenhouse Gases Bookmark and Share To validate the space-based carbon dioxide retrievals by the Orbiting Carbon Observatory (OCO) through comparative carbon dioxide measurements, ARM's Tropical Western Pacific site in Darwin, Australia, is hosting a ground-based solar-viewing Fourier transform spectrometer (FTS) mobile laboratory, sponsored by the OCO Science Team. Between January 15 and February 7, 2006, overflights of the FTS site, as well as "flights of opportunity" by ARM's Proteus aircraft during the Tropical Warm Pool International Cloud Experiment, were completed. Additional flights from the European Union's Geophysica aircraft over the site in November and December

284

Science Facilities  

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

Electron Microscopy Lab Ion Beam Materials Lab Matter-Radiation Interactions in Extremes (MaRIE) Proton Radiography Trident Laser Facility LOOK INTO LANL - highlights...

285

Plutonium recovery from spent reactor fuel by uranium displacement  

DOE Patents (OSTI)

A process is described for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is reestablished.

Ackerman, J.P.

1992-03-17T23:59:59.000Z

286

Occurrence of naturally enriched {sup 235}U: Implications for plutonium behavior in natural environments  

SciTech Connect

It is generally accepted that uranium and most of the fission products, with the exception of the alkalis, alkaline earths and rare gases, remained in the irradiated uranium oxides during the nuclear reactions that took place 2.0 Ga ago in the Oklo uranium deposit (Gabon). New isotope investigations show that clay minerals from argillaceous rocks neighboring the natural fission reactor 10 at Oklo have depleted {sup 235}U with {sup 235}U/{sup 238}U ratios ranging between 0.00560 and the common natural value of 0.00725. One sample, however, is enriched in {sup 235}U with a {sup 235}U/{sup 238}U ratio of 0.007682. Leach experiments of this sample with dilute 1N HCl revealed that the {sup 235}U enrichment is actually restricted to the insoluble residue ({sup 235}U/{sup 238}U = 0.010511), whereas the leachate remains depleted in {sup 235}U. This unique discovery of very enriched uranium, together with samarium, neodymium, rubidium, and strontium isotopic analyses, indicate that a small amount of plutonium could have been more mobile than uranium in the reactor 10, and it is suggested that plutonium was incorporated in the crystallographic structure of clay minerals such as the chlorites. 28 refs., 3 figs., 1 tab.

Bros, R.; Gauthier-Lafaye, F.; Stille, P. [CNRS, Strasbourg (FR)] [CNRS, Strasbourg (FR); Turpin, L. [CNRS, Gif-sur-Yvette (FR)] [CNRS, Gif-sur-Yvette (FR); Holliger, Ph. [Centre d`Etudes Nucleaires, Grenoble (FR)] [Centre d`Etudes Nucleaires, Grenoble (FR)

1993-03-01T23:59:59.000Z

287

Strategies for denaturing the weapons-grade plutonium stockpile  

SciTech Connect

In the next few years, approximately 50 metric tons of weapons-grade plutonium and 150 metric tons of highly-enriched uranium (HEU) may be removed from nuclear weapons in the US and declared excess. These materials represent a significant energy resource that could substantially contribute to our national energy requirements. HEU can be used as fuel in naval reactors, or diluted with depleted uranium for use as fuel in commercial reactors. This paper proposes to use the weapons-grade plutonium as fuel in light water reactors. The first such reactor would demonstrate the dual objectives of producing electrical power and denaturing the plutonium to prevent use in nuclear weapons.

Buckner, M.R.; Parks, P.B.

1992-10-01T23:59:59.000Z

288

Theory of Antineutrino Monitoring of Burning MOX Plutonium Fuels  

E-Print Network (OSTI)

This letter presents the physics and feasibility of reactor antineutrino monitoring to verify the burnup of plutonium loaded in the reactor as a Mixed Oxide (MOX) fuel. It examines the magnitude and temporal variation in the antineutrino signals expected for different MOX fuels, for the purposes of nuclear accountability and safeguards. The antineutrino signals from reactor-grade and weapons-grade MOX are shown to be distinct from those from burning low enriched uranium. Thus, antineutrino monitoring could be used to verify the destruction of plutonium in reactors, though verifying the grade of the plutonium being burned is found to be more challenging.

Hayes, A C; Nieto, Michael Martin; WIlson, W B

2011-01-01T23:59:59.000Z

289

Theory of Antineutrino Monitoring of Burning MOX Plutonium Fuels  

E-Print Network (OSTI)

This letter presents the physics and feasibility of reactor antineutrino monitoring to verify the burnup of plutonium loaded in the reactor as a Mixed Oxide (MOX) fuel. It examines the magnitude and temporal variation in the antineutrino signals expected for different MOX fuels, for the purposes of nuclear accountability and safeguards. The antineutrino signals from reactor-grade and weapons-grade MOX are shown to be distinct from those from burning low enriched uranium. Thus, antineutrino monitoring could be used to verify the destruction of plutonium in reactors, though verifying the grade of the plutonium being burned is found to be more challenging.

A. C. Hayes; H. R. Trellue; Michael Martin Nieto; W. B. WIlson

2011-10-03T23:59:59.000Z

290

Risk assessment of soil-based exposures to plutonium at experimental sites located on the Nevada Test Site and adjoining areas  

SciTech Connect

In the late 1950s and early 1960s, a series of tests was conducted at or near the Nevada Test Site to study issues involving plutonium-bearing devices. These tests resulted in the dispersal of about 5 TBq of {sup 239,240}Pu on the surficial soils at the test locations. Access to the sites is strictly controlled; therefore, it does not constitute a threat to human health at the present time. However, because the residual {sup 239} Pu decays slowly (half-life of 24,110 y), the sites could indeed represent a long-term hazard if they are not remediated and if institutional controls are lost. To investigate the magnitude of the potential health risks for this no-remediation case, we defined three basic exposure scenarios that could bring individuals in contact with {sup 239,240}Pu at the sites: (1) a resident living in a subdivision located at a test site, (2) a resident farmer, and (3) a worker at a commercial facility. Our screening analyses indicated that doses to organs are dominated by the intemal deposition of Pu via the inhalation pathway, and thus our risk assessment focused on those factors that affect inhalation exposures and associated doses, including inhalation rates, activity patterns, tenure at a residence or occupation, indoor/outdoor air relationships, and resuspension outdoors. Cancer risks were calculated as a function of lifetime cumulative doses to the key target organs (i.e., bone surface, liver, and lungs) and risk factors for those organs. Uncertainties in the predicted cancer risks were analyzed using Monte-Carlo simulations of the probability distributions used to represent assessment parameters. The principal sources of uncertainty in the estimated risks were population mobility, the relationship between indoor and outdoor contaminant levels, and the dose and risk factors for bone, liver, and lung.

Layton, D.W.; Anspaugh, L.R.; Bogen, K.T.; Straume, T.

1993-06-01T23:59:59.000Z

291

Relationship of Surplus Plutonium Disposition Alternatives and...  

National Nuclear Security Administration (NNSA)

Building Note: Appendices C and D provide details about the analyses of human health effects at DOE facilities under normal and accident conditions, respectively, while...

292

Facility Safety  

Directives, Delegations, and Requirements

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.

2005-12-22T23:59:59.000Z

293

Measurement and interpretation of plutonium spectra  

SciTech Connect

The atomic spectroscopic data available for plutonium are among the rickest of any in the periodic system. They include high-resolution grating and Fourier-transform spectra as well as extensive Zeeman and isotope-shift studies. We summarize the present status of the term analysis and cite the configurations that have been identified. A least-squares adjustment of a parametric Hamiltonian for configurations of both Pu I and Pu II has shown that almost all of the expected low levels are now known. The use of a model Hamiltonian applicable to both lanthanide and actinide atomic species has been applied to the low configurations of Pu I and Pu II making use of trends predicted by ab initio calculations. This same model has been used to describe the energy levels of Pu/sup 3 +/ in LaCl/sub 3/, and an extension has permitted preliminary calculations of the spectra of other valence states.

Blaise, J.; Fred, M.S.; Carnall, W.T.; Crosswhite, H.M.; Crosswhite, H.

1982-01-01T23:59:59.000Z

294

Thermophysical properties of coexistent phases of plutonium  

SciTech Connect

Plutonium is the element with the greatest number of allotropic phases. Thermally induced transformations between these phases are typically characterized by thermal hysteresis and incomplete phase reversion. With Ga substitutal in the lattice, low symmetry phases are replaced by a higher symmetry phase. However, the low temperature Martensitic phase transformation ({delta} {yields} {alpha}{prime}) in Ga stabilized {delta}-phase Pu is characterized by a region of thermal hysteresis which can reach 200 C in extent. These regions of thermal hysteresis offer a unique opportunity to study thermodynamics in inhomogeneous systems of coexistent phases. The results of thermophysical properties measured for samples of inhomogeneous unalloyed and Ga alloyed Pu will be discussed and compared with similar measurements of their single phase constituents.

Freibert, Franz J [Los Alamos National Laboratory; Mitchell, Jeremy N [Los Alamos National Laboratory; Saleh, Tarik A [Los Alamos National Laboratory; Schwartz, Dan S [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

295

Costing plutonium: economics of reprocessing in India  

Science Journals Connector (OSTI)

The relative merits of reprocessing and direct disposal of spent nuclear fuel have been widely debated in Europe and the USA. An important aspect of the debate has been the economics of reprocessing. So far there have been no studies of the subject in the Indian context. This study assesses the economics of reprocessing in India and the cost of producing plutonium for the fast breeder reactor programme. Our results suggest that the cost of reprocessing each kilogram of spent fuel would cost approximately Rs. 26,000 (approx. $600) with assumptions favourable to reprocessing, and close to Rs. 30,000 (approx. $675) under other assumptions. These costs are lower than the corresponding figures for reprocessing plants in Europe, the USA, and Japan. As in their case, however, it is unlikely to be an economically viable method of waste disposal.

M.V. Ramana; J.Y. Suchitra

2007-01-01T23:59:59.000Z

296

Los Alamos National Laboratory to work on nuclear design, plutonium  

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

Lab to work on nuclear design, plutonium research Lab to work on nuclear design, plutonium research Los Alamos National Laboratory to work on nuclear design, plutonium research and development, and supercomputing LANL selected as preferred alternative site for plutonium research, development, and limited manufacturing, along with nuclear weapons design and engineering, and supercomputing. December 18, 2007 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and

297

Stailization, Packaging, and Storage of Plutonium-Bearing Materials  

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

DOE-STD-3013-2012 MARCH 2012 DOE STANDARD STABILIZATION, PACKAGING, AND STORAGE OF PLUTONIUM-BEARING MATERIALS U.S. Department of Energy AREA PACK Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS Available on the Department of Energy Technical Standards Program Web site at http://www.hss.energy.gov/NuclearSafety/ns/techstds/ DOE-STD-3013-2012 iii ABSTRACT This Standard provides guidance for the stabilization, packaging, and safe storage of plutonium- bearing metals and oxides containing at least 30 wt% plutonium plus uranium. It supersedes DOE-STD-3013-2004, "Stabilization, Packaging, and Storage of Plutonium-Bearing Materials," and is approved for use by all DOE organizations and their contractors. Metals are stabilized by

298

Crystalline ceramics: Waste forms for the disposal of weapons plutonium  

SciTech Connect

At present, there are three seriously considered options for the disposition of excess weapons plutonium: (i) incorporation, partial burn-up and direct disposal of MOX-fuel; (ii) vitrification with defense waste and disposal as glass ``logs``; (iii) deep borehole disposal (National Academy of Sciences Report, 1994). The first two options provide a safeguard due to the high activity of fission products in the irradiated fuel and the defense waste. The latter option has only been examined in a preliminary manner, and the exact form of the plutonium has not been identified. In this paper, we review the potential for the immobilization of plutonium in highly durable crystalline ceramics apatite, pyrochlore, monazite and zircon. Based on available data, we propose zircon as the preferred crystalline ceramic for the permanent disposition of excess weapons plutonium.

Ewing, R.C.; Lutze, W. [New Mexico Univ., Albuquerque, NM (United States); Weber, W.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-05-01T23:59:59.000Z

299

Process for immobilizing plutonium into vitreous ceramic waste forms  

DOE Patents (OSTI)

Disclosed is a method for converting spent nuclear fuel and surplus plutonium into a vitreous ceramic final waste form wherein spent nuclear fuel is bound in a crystalline matrix which is in turn bound within glass.

Feng, X.; Einziger, R.E.

1997-08-12T23:59:59.000Z

300

Process for immobilizing plutonium into vitreous ceramic waste forms  

DOE Patents (OSTI)

Disclosed is a method for converting spent nuclear fuel and surplus plutonium into a vitreous ceramic final waste form wherein spent nuclear fuel is bound in a crystalline matrix which is in turn bound within glass.

Feng, X.; Einziger, R.E.

1997-01-28T23:59:59.000Z

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


301

Worker Involvement Improves Safety at Hanford Site's Plutonium Finishing Plant  

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

Employees at the Hanford site are working together to find new and innovative ways to stay safe at the Plutonium Finishing Plant, one of the sites most complex decommissioning projects.

302

Analytical inverse model for post-event attribution of plutonium  

E-Print Network (OSTI)

specific type of nuclear event: a plutonium improvised nuclear device (IND) explosion. From post-event isotopic ratios, this method determines the devices pre-event isotopic concentrations of special nuclear material. From the original isotopic...

Miller, James Christopher

2009-05-15T23:59:59.000Z

303

Worker Involvement Improves Safety at Hanford Site's Plutonium...  

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

RICHLAND, Wash. - Employees at the Hanford site are working together to find new and innovative ways to stay safe at the Plutonium Finishing Plant, one of the site's most...

304

Mastering the art of plutonium pit production to ensure national...  

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

- and final - plutonium pit for replacement in existing W88 warheads. The W88 is a thermonuclear weapon designed by LANL in the late 1980s for the U.S. Navy and deployed on...

305

Plutonium Immobilization Project System Design Description for Can Loading System  

SciTech Connect

The purpose of this System Design Description (SDD) is to specify the system and component functions and requirements for the Can Loading System and provide a complete description of the system (design features, boundaries, and interfaces), principles of operation (including upsets and recovery), and the system maintenance approach. The Plutonium Immobilization Project (PIP) will immobilize up to 13 metric tons (MT) of U.S. surplus weapons usable plutonium materials.

Kriikku, E.

2001-02-15T23:59:59.000Z

306

Recovery of weapon plutonium as feed material for reactor fuel  

SciTech Connect

This report presents preliminary considerations for recovering and converting weapon plutonium from various US weapon forms into feed material for fabrication of reactor fuel elements. An ongoing DOE study addresses the disposition of excess weapon plutonium through its use as fuel for nuclear power reactors and subsequent disposal as spent fuel. The spent fuel would have characteristics similar to those of commercial power spent fuel and could be similarly disposed of in a geologic repository.

Armantrout, G.A.; Bronson, M.A.; Choi, Jor-Shan [and others

1994-03-16T23:59:59.000Z

307

Fuel bundle design for enhanced usage of plutonium fuel  

DOE Patents (OSTI)

A nuclear fuel bundle includes a square array of fuel rods each having a concentration of enriched uranium and plutonium. Each rod of an interior array of the rods also has a concentration of gadolinium. The interior array of rods is surrounded by an exterior array of rods void of gadolinium. By this design, usage of plutonium in the nuclear reactor is enhanced. 10 figs.

Reese, A.P.; Stachowski, R.E.

1995-08-08T23:59:59.000Z

308

Plutonium metal and oxide container weld development and qualification  

SciTech Connect

Welds were qualified for a container system to be used for long-term storage of plutonium metal and oxide. Inner and outer containers are formed of standard tubing with stamped end pieces gas-tungsten-arc (GTA) welded onto both ends. The weld qualification identified GTA parameters to produce a robust weld that meets the requirements of the Department of Energy standard DOE-STD-3013-94, ``Criteria for the Safe Storage of Plutonium Metals and Oxides.``

Fernandez, R.; Horrell, D.R.; Hoth, C.W.; Pierce, S.W.; Rink, N.A.; Rivera, Y.M.; Sandoval, V.D.

1996-01-01T23:59:59.000Z

309

Wastes from plutonium conversion and scrap recovery operations  

SciTech Connect

This report deals with the handling of defense-related wastes associated with plutonium processing. It first defines the different waste categories along with the techniques used to assess waste content. It then discusses the various treatment approaches used in recovering plutonium from scrap. Next, it addresses the various waste management approaches necessary to handle all wastes. Finally, there is a discussion of some future areas for processing with emphasis on waste reduction. 91 refs., 25 figs., 4 tabs.

Christensen, D.C.; Bowersox, D.F.; McKerley, B.J.; Nance, R.L.

1988-03-01T23:59:59.000Z

310

Mobile workstation for decontamination and decommissioning operations  

SciTech Connect

This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The project has three phases. In this the first phase, an existing teleoperated worksystem, the Remote Work Vehicle (developed for use in the Three Mile Island Unit 2 Reactor Building basement), was enhanced for telerobotic performance of several D&D operations. Its ability to perform these operations was then assessed through a series of tests in a mockup facility that contained generic structures and equipment similar to those that D&D work machines will encounter in DOE facilities. Building upon the knowledge gained through those tests and evaluations, a next generation mobile worksystem, the RWV II, and a more advanced controller will be designed, integrated and tested in the second phase, which is scheduled for completion in January 1995. The third phase of the project will involve testing of the RWV II in the real DOE facility.

Whittaker, W.L.; Osborn, J.F.; Thompson, B.R. [Carnegie-Mellon Univ., Pittsburgh, PA (United States). Robotics Inst.

1993-10-01T23:59:59.000Z

311

Supercritical Fluid Extraction of Plutonium and Americium from Soil  

SciTech Connect

Supercritical fluid extraction (SFE) of plutonium and americium from soil was successfully demonstrated using supercritical fluid carbon dioxide solvent augmented with organophosphorus and beta-diketone complexants. Spiked Idaho soils were chemically and radiologically characterized, then extracted with supercritical fluid carbon dioxide at 2,900 psi and 65 C containing varying concentrations of tributyl phosphate (TBP) and thenoyltrifluoroacetone (TTA). A single 45 minute SFE with 2.7 mol% TBP and 3.2 mol% TTA provided as much as 88% {+-} 6.0 extraction of americium and 69% {+-} 5.0 extraction of plutonium. Use of 5.3 mol% TBP with 6.8 mol% of the more acidic beta-diketone hexafluoroacetylacetone (HFA) provided 95% {+-} 3.0 extraction of americium and 83% {+-} 5.0 extraction of plutonium in a single 45 minute SFE at 3,750 psi and 95 C. Sequential chemical extraction techniques were used to chemically characterize soil partitioning of plutonium and americium in pre-SFE soil samples. Sequential chemical extraction techniques demonstrated that spiked plutonium resides primarily (76.6%) in the sesquioxide fraction with minor amounts being absorbed by the oxidizable fraction (10.6%) and residual fractions (12.8%). Post-SFE soils subjected to sequential chemical extraction characterization demonstrated that 97% of the oxidizable, 78% of the sesquioxide and 80% of the residual plutonium could be removed using SFE. These preliminary results show that SFE may be an effective solvent extraction technique for removal of actinide contaminants from soil.

Fox, R.V.; Mincher, B.J.

2002-05-23T23:59:59.000Z

312

Supercritical Fluid Extraction of Plutonium and Americium from Soil  

SciTech Connect

Supercritical fluid extraction (SFE) of plutonium and americium from soil was successfully demonstrated using supercritical fluid carbon dioxide solvent augmented with organophosphorus and beta-diketone complexants. Spiked Idaho soils were chemically and radiologically characterized, then extracted with supercritical fluid carbon dioxide at 2,900 psi and 65C containing varying concentrations of tributyl phosphate (TBP) and thenoyltrifluoroacetone (TTA). A single 45 minute SFE with 2.7 mol% TBP and 3.2 mol% TTA provided as much as 88% 6.0 extraction of americium and 69% 5.0 extraction of plutonium. Use of 5.3 mol% TBP with 6.8 mol% of the more acidic beta-diketone hexafluoroacetylacetone (HFA) provided 95% 3.0 extraction of americium and 83% 5.0 extraction of plutonium in a single 45 minute SFE at 3,750 psi and 95C. Sequential chemical extraction techniques were used to chemically characterize soil partitioning of plutonium and americium in pre-SFE soil samples. Sequential chemical extraction techniques demonstrated that spiked plutonium resides primarily (76.6%) in the sesquioxide fraction with minor amounts being absorbed by the oxidizable fraction (10.6%) and residual fractions (12.8%). Post-SFE soils subjected to sequential chemical extraction characterization demonstrated that 97% of the oxidizable, 78% of the sesquioxide and 80% of the residual plutonium could be removed using SFE. These preliminary results show that SFE may be an effective solvent extraction technique for removal of actinide contaminants from soil.

Fox, Robert Vincent; Mincher, Bruce Jay

2002-08-01T23:59:59.000Z

313

Facility Safety  

Directives, Delegations, and Requirements

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.

2002-05-20T23:59:59.000Z

314

Facility Safety  

Directives, Delegations, and Requirements

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.

2000-11-20T23:59:59.000Z

315

Facility Safety  

Directives, Delegations, and Requirements

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.

2005-12-22T23:59:59.000Z

316

Facility Safety  

Directives, Delegations, and Requirements

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.

2013-06-21T23:59:59.000Z

317

CX-009613: Categorical Exclusion Determination | Department of...  

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

CX-009613: Categorical Exclusion Determination Testing, Calibration, and Training of Mobile Plutonium Facility (MPF) Equipment CX(s) Applied: B3.6 Date: 11162012 Location(s):...

318

CX-011347: Categorical Exclusion Determination | Department of...  

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

CX-011347: Categorical Exclusion Determination Infrastructure Modification for the Mobile Plutonium Facility (MPF) at the 645-N Complex CX(s) Applied: B1.15 Date: 09132013...

319

CX-009104: Categorical Exclusion Determination | Department of...  

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

CX-009104: Categorical Exclusion Determination Infrastructure Modification for the Mobile Plutonium Facility (MPF) at the 645-N Complex CX(s) Applied: B1.15 Date: 08292012...

320

Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities  

E-Print Network (OSTI)

in it and how nuclear material flows between facilities. The goals of the safeguards system were established next, using the normal IAEA standards for the non-detection and false alarm probabilities. The 5 MWe Reactor was modeled for both plutonium production...

Rauch, Eric B.

2010-07-14T23:59:59.000Z

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


321

EIS-0089: PUREX Plant and Uranium Oxide Plant Facilities, Hanford Site, Richland, Washington  

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

The U.S. Department of Energy developed this statement to evaluate the environmental impacts of resumption of operations of the PUREX/Uranium Oxide facilities at the Hanford Site to produce plutonium and other special nuclear materials for national defense needs.

322

Design-only conceptual design report for pit disassembly and conversion facility. Rev 0  

SciTech Connect

This design-only conceptual design report (DOCDR) was prepared to support a funding request by the Department of Energy (DOE)-Office of Fissile Material Disposition (OFMD) for engineering design of the Pit Disassembly and Conversion Facility (PDCF) Project No. 99-D-141. The PDCF will be used to disassemble the nation`s inventory of surplus nuclear weapons pits and convert the plutonium recovered from those pits into a form suitable for storage, international inspection, and final disposition. The PDCF is a complex consisting of a hardened building that will contain the plutonium processes in a safe and secure manner, and conventional buildings and structures that will house support personnel, systems, and equipment. The PDCF uses the Advanced Recovery and Integrated Extraction System (ARIES), a low waste, modular pyroprocessing system to convert pits to plutonium oxide. The PDCF project consists of engineering and design, and construction of the buildings and structures, and engineering and design, procurement, installation, testing and start-up of equipment to disassemble pits and convert plutonium in pits to oxide form. The facility is planned to operate for 10 years, averaging 3.5 metric tons (3.86 tons) of plutonium metal per year. On conclusion of operations, the PDCF will be decontaminated and decommissioned.

Zygmunt, S.; Christensen, L.; Richardson, C.

1997-12-12T23:59:59.000Z

323

Closure Report for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada  

SciTech Connect

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 366 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended).

none,

2013-12-31T23:59:59.000Z

324

Roaming and investments in the mobile internet market  

Science Journals Connector (OSTI)

This model discusses mobile network operators' (MNOs) incentives to invest in their network facilities such as new 4G networks under various regimes of data roaming charge regulation. Given an induced externality of investments (spillovers) due to the ... Keywords: Investment spillover, Mobile internet, National roaming, Regulation

Torben StHmeier

2012-09-01T23:59:59.000Z

325

Interim Action Determination Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF)  

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

Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF) Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF) The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS), DOE/EIS-0283-S2. DOE is evaluating, among many other things, the environmental impacts of any design and operations changes to the MFFF, which is under construction at the Savannah River Site near Aiken, South Carolina. DOE

326

Interim Action Determination Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF)  

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

Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF) Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF) The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS), DOE/EIS-0283-S2. DOE is evaluating, among many other things, the environmental impacts of any design and operations changes to the MFFF, which is under construction at the Savannah River Site near Aiken, South Carolina. DOE

327

Mobile Media Poetics  

E-Print Network (OSTI)

J.L. and Sey, A. 2007. Mobile Communication and Society: AG. 2006. Cell Phone Culture: Mobile Technology in EverydayPortable, Pedestrian: Mobile Phones in Japanese Life, Ito,

Raley, Rita

2009-01-01T23:59:59.000Z

328

Scope for denaturizing weapons-grade plutonium in a subcritical heavy-water blanket of candu type  

Science Journals Connector (OSTI)

The following features occur in denaturing weapons plutonium by irradiating a mixture of plutonium and neptunium as oxides in a neutron flux: 1) ...

G. V. Kiselev; L. A. Myrtsymova

1996-12-01T23:59:59.000Z

329

Treatability studies for uranium and plutonium contaminated soils using physical separation methods. Environmental Assessment  

SciTech Connect

The Nevada Field Office of the Department of Energy (DOE/NV) has stated in the Environmental Restoration and Waste Management (ERWM) Site Specific Plan for the Nevada Test Site (NTS) that DOE/NV is committed to achieving compliance with all applicable environmental laws, regulations, guidelines, and agreements covering operations at the NTS. The primary DOE/NV objective identified by the Site-Specific Plan is to comply with all laws and regulations aimed at protecting human health and the environment. These include Nevada statutes and regulations which may be applicable, including federally delegated authorities. This environmental assessment discusses limited bench-scale soil treatability testing of physical processes for decontamination of plutonium- and uranium-contaminated soil. The proposed location of these studies would be the Treatability Testing Facility (TTF), Building 3124 at Test Cell ``All in Area 25 of the NTS.

none,

1992-07-01T23:59:59.000Z

330

Fluorination of incinerator ash by hydrofluorination or ammonium bifluoride fusion for plutonium recovery  

SciTech Connect

Incinerator ash containing small quantities of plutonium has been accumulating across the defense complex for many years. Although the total Pu inventory is small, the ash is a nondiscardable residue which presents storage and accountability difficulties. The work discussed here is the result of a joint exploratory effort between members of Savannah River Laboratory and Los Alamos National Laboratory to compare two proposed pyrochemical pretreatments of incinerator ash prior to aqueous processing. These experiments attempted to determine the relative effectiveness of hydrofluorination and ammonium bifluoride fusion as head-end operations for a two step aqueous recovery method. The two pretreatments are being considered as possible second generation enhancements for the New Special Recovery Facility nearing operation at Savannah River Plant. Experimental results and potential engineering concerns are discussed. 3 figs.

Fink, S.D.; Gray, J.H.; Kent, S.J.; Apgar, S.A.

1989-01-01T23:59:59.000Z

331

February 13, 1995, Board announcement of a Public Meeting on the DOE Plutonium Vulnerability Study  

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

§552b), §552b), notice is hereby given of the following Board meeting and staff briefing: FEDERAL REGISTER CITATION OF PREVIOUS ANNOUNCEMENT: Previously announced in the February 14, 1995, Federal Register. PREVIOUSLY ANNOUNCED TIME AND DATE OF THE MEETING: 2:00 p.m., February 21, 1995. CHANGES IN THE MEETING: The Board is broadening the scope of matters to be considered by adding the following information: The Board will also convene a panel of nationally-recognized experts to discuss the DOE Plutonium Vulnerability Study and to address questions that may arise from the results of this study. CONTACT PERSON FOR MORE INFORMATION: Robert M. Andersen, General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, N.W., Suite 700, Washington, D.C. 20004, (202) 208-6387.

332

PUREX/UO{sub 3} facilities deactivation lessons learned: History  

SciTech Connect

In May 1997, a historic deactivation project at the PUREX (Plutonium URanium EXtraction) facility at the Hanford Site in south-central Washington State concluded its activities (Figure ES-1). The project work was finished at $78 million under its original budget of $222.5 million, and 16 months ahead of schedule. Closely watched throughout the US Department of Energy (DOE) complex and by the US Department of Defense for the value of its lessons learned, the PUREX Deactivation Project has become the national model for the safe transition of contaminated facilities to shut down status.

Gerber, M.S.

1997-11-25T23:59:59.000Z

333

Solubility of Plutonium (IV) Oxalate During Americium/Curium Pretreatment  

SciTech Connect

Approximately 15,000 L of solution containing isotopes of americium and curium (Am/Cm) will undergo stabilization by vitrification at the Savannah River Site (SRS). Prior to vitrification, an in-tank pretreatment will be used to remove metal impurities from the solution using an oxalate precipitation process. Material balance calculations for this process, based on solubility data in pure nitric acid, predict approximately 80 percent of the plutonium in the solution will be lost to waste. Due to the uncertainty associated with the plutonium losses during processing, solubility experiments were performed to measure the recovery of plutonium during pretreatment and a subsequent precipitation process to prepare a slurry feed for a batch melter. A good estimate of the plutonium content of the glass is required for planning the shipment of the vitrified Am/Cm product to Oak Ridge National Laboratory (ORNL).The plutonium solubility in the oxalate precipitation supernate during pretreatment was 10 mg/mL at 35 degrees C. In two subsequent washes with a 0.25M oxalic acid/0.5M nitric acid solution, the solubility dropped to less than 5 mg/mL. During the precipitation and washing steps, lanthanide fission products in the solution were mostly insoluble. Uranium, and alkali, alkaline earth, and transition metal impurities were soluble as expected. An elemental material balance for plutonium showed that greater than 94 percent of the plutonium was recovered in the dissolved precipitate. The recovery of the lanthanide elements was generally 94 percent or higher except for the more soluble lanthanum. The recovery of soluble metal impurities from the precipitate slurry ranged from 15 to 22 percent. Theoretically, 16 percent of the soluble oxalates should have been present in the dissolved slurry based on the dilution effects and volumes of supernate and wash solutions removed. A trace level material balance showed greater than 97 percent recovery of americium-241 (from the beta dec ay of plutonium-241) in the dissolved precipitate, a value consistent with the recovery of europium, the americium surrogate.In a subsequent experiment, the plutonium solubility following an oxalate precipitation to simulate the preparation of a slurry feed for a batch melter was 21 mg/mL at 35 degrees C. The increase in solubility compared to the value measured during the pretreatment experiment was attributed to the increased nitrate concentration and ensuing increase in plutonium complexation. The solubility of the plutonium following a precipitant wash with 0.1M oxalic acid was unchanged. The recovery of plutonium from the precipitate slurry was greater than 97 percent allowing an estimation that approximately 92 percent of the plutonium in Tank 17.1 will report to the glass. The behavior of the lanthanides and soluble metal impurities was consistent with the behavior seen during the pretreatment experiment. A trace level material balance showed that 99.9 percent of the americium w as recovered from the precipitate slurry. The overall recovery of americium from the pretreatment and feed preparation processes was greater than 97 percent, which was consistent with the measured recovery of the europium surrogate.

Rudisill, T.S.

1999-08-11T23:59:59.000Z

334

E-Print Network 3.0 - analyzing plutonium gamma-ray Sample Search...  

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

plutonium gamma-ray Search Powered by Explorit Topic List Advanced Search Sample search results for: analyzing plutonium gamma-ray Page: << < 1 2 3 4 5 > >> 1 n December 30, 1958,...

335

An analysis of the impact of having uranium dioxide mixed in with plutonium dioxide  

SciTech Connect

An assessment was performed to show the impact on airborne release fraction, respirable fraction, dose conversion factor and dose consequences of postulated accidents at the Plutonium Finishing Plant involving uranium dioxide rather than plutonium dioxide.

MARUSICH, R.M.

1998-10-21T23:59:59.000Z

336

Hanford Site Workers Meet Challenging Performance Goal at Plutonium Finishing Plant  

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

RICHLAND, Wash. Safely and methodically, piece by piece, workers at the Hanford sites Plutonium Finishing Plant are surpassing goals for removing hazardous tanks once used in the plutonium production process.

337

Amarillo National Resource Center for Plutonium. Quarterly technical progress report, February 1, 1998--April 30, 1998  

SciTech Connect

Activities from the Amarillo National Resource Center for Plutonium are described. Areas of work include materials science of nuclear and explosive materials, plutonium processing and handling, robotics, and storage.

NONE

1998-06-01T23:59:59.000Z

338

Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1, 1997--July 31, 1997  

SciTech Connect

Progress summaries are provided from the Amarillo National Center for Plutonium. Programs include the plutonium information resource center, environment, public health, and safety, education and training, nuclear and other material studies.

NONE

1997-09-01T23:59:59.000Z

339

Demo of below ground site that once held the Plutonium Recycle...  

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

Demo of below ground site that once held the Plutonium Recycle Test Reactor at Hanford Demo of below ground site that once held the Plutonium Recycle Test Reactor at Hanford...

340

Assessment of plutonium exposures for an epidemiological study of US nuclear workers  

Science Journals Connector (OSTI)

......Institute for Occupational Safety and Health (NIOSH) 5555...Institute for Occupational Safety and Health (NIOSH) is...plutonium workers at the Rocky Flats Plant, Wilkinson et al...plutonium workers at the Rocky Flats Plant: a case-control......

R. D. Daniels; C. J. Lodwick; M. K. Schubauer-Berigan; H. B. Spitz

2006-04-01T23:59:59.000Z

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


341

The Effect of Sedimentation on Plutonium Transport in Fourmile Branch  

SciTech Connect

The major mechanisms of radioactive material transport and fate in surface water are sources, dilution, advection and dispersion of radionuclides by flow and surface waves, radionuclide decay, and interaction between sediment and radionuclides. STREAM II, an aqueous transport module of the Savannah River Site emergency response WIND system, accounts for the source term, and the effects of dilution, advection and dispersion. Although the model has the capability to account for nuclear decay, due to the short time interval of interest for emergency response, the effect of nuclear decay is very small and so it is not employed. The interactions between the sediment and radionuclides are controlled by the flow conditions and physical and chemical characteristics of the radionuclides and the sediment constituents. The STREAM II version used in emergency response must provide results relatively quickly; it therefore does not model the effects of sediment deposition/resuspension. This study estimates the effects of sediment deposition/resuspension on aqueous plutonium transport in Fourmile Branch. There are no measured data on plutonium transport through surface water available for direct model calibration. Therefore, a literature search was conducted to find the range of plutonium partition coefficients based on laboratory experiments and field measurements. A sensitivity study of the calculated plutonium peak concentrations as a function of the input parameter of partition coefficient was then performed. Finally, an estimation of the plutonium partition coefficient was made for the Fourmile Branch.

Chen, K.F.

2002-02-21T23:59:59.000Z

342

PLUTONIUM/HIGH-LEVEL VITRIFIED WASTE BDBE DOSE CALCULATION  

SciTech Connect

The purpose of this calculation is to provide a dose consequence analysis of high-level waste (HLW) consisting of plutonium immobilized in vitrified HLW to be handled at the proposed Monitored Geologic Repository at Yucca Mountain for a beyond design basis event (BDBE) under expected conditions using best estimate values for each calculation parameter. In addition to the dose calculation, a plutonium respirable particle size for dose calculation use is derived. The current concept for this waste form is plutonium disks enclosed in cans immobilized in canisters of vitrified HLW (i.e., glass). The plutonium inventory at risk used for this calculation is selected from Plutonium Immobilization Project Input for Yucca Mountain Total Systems Performance Assessment (Shaw 1999). The BDBE examined in this calculation is a nonmechanistic initiating event and the sequence of events that follow to cause a radiological release. This analysis will provide the radiological releases and dose consequences for a postulated BDBE. Results may be considered in other analyses to determine or modify the safety classification and quality assurance level of repository structures, systems, and components. This calculation uses best available technical information because the BDBE frequency is very low (i.e., less than 1.0E-6 events/year) and is not required for License Application for the Monitored Geologic Repository. The results of this calculation will not be used as part of a licensing or design basis.

J.A. Ziegler

2000-11-20T23:59:59.000Z

343

PRESSURE DEVELOPMENT IN SEALED CONTAINERS WITH PLUTONIUM BEARING MATERIALS  

SciTech Connect

Gas generation by plutonium-bearing materials in sealed containers has been studied. The gas composition and pressure are determined over periods from months to years. The Pu-bearing materials studied represent those produced by all of the major processes used by DOE in the processing of plutonium and include the maximum amount of water (0.5% by weight) allowed by DOE's 3013 Standard. Hydrogen generation is of high interest and the Pu-bearing materials can be classed according to how much hydrogen is generated. Hydrogen generation by high-purity plutonium oxides packaged under conditions typical for actual 3013 materials is minimal, with very low generation rates and low equilibrium pressures. Materials with chloride salt impurities have much higher hydrogen gas generation rates and result in the highest observed equilibrium hydrogen pressures. Other materials such as those with high metal oxide impurities generate hydrogen at rates in between these extremes. The fraction of water that is converted to hydrogen gas as equilibrium is approached ranges from 0% to 25% under conditions typical of materials packaged to the 3013 Standard. Generation of both hydrogen and oxygen occurs when liquid water is present. The material and moisture conditions that result in hydrogen and oxygen generation for high-purity plutonium oxide and chloride salt-bearing plutonium oxide materials have been characterized. Other gases that are observed include nitrous oxide, carbon dioxide, carbon monoxide, and methane.

Duffey, J.; Livingston, R.

2010-02-01T23:59:59.000Z

344

Future is new focus at energy department`s Rocky Flats facility  

SciTech Connect

After several years of intensive effort to address radioactive pollution threatening nearby communities, officials at the Energy Department`s Rocky Flats plant now are turning their attention to the site`s plutonium buildings and finding a cleanup challenge of equally daunting proportions. Containing and mopping up off-site soil and water contamination remains the first priority at the Colorado facility, but site environmental managers say the huge volumes of plutonium and associated radioactive waste stored in Rocky Flats` aging building pose increasingly urgent safety concerns.

Lobsenz, G.

1993-11-12T23:59:59.000Z

345

Facility Safety  

Directives, Delegations, and Requirements

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.

1995-10-13T23:59:59.000Z

346

Facility Safety  

Directives, Delegations, and Requirements

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.

2012-12-04T23:59:59.000Z

347

Mobile Agent Software Applied in Maintenance Scheduling X. Xu M. Kezunovic  

E-Print Network (OSTI)

Mobile Agent Software Applied in Maintenance Scheduling X. Xu M. Kezunovic Department of Electrical different entities is required. In this paper, the mobile agent software is applied in the facility and the ISO respectively, and the mobile agent takes care of the communication and coordination between

348

Interstitial incorporation of plutonium into a low-dimensional potassium borate  

E-Print Network (OSTI)

D. Plutonium uptake by brucite and hydroxylated periclase.4), pyrochlore (4,23-25), brucite (26), and several other

Wang, Shuao

2014-01-01T23:59:59.000Z

349

Production-scale plutonium-neptunium separation and residue recovery at Rocky Flats Plant  

SciTech Connect

An anion exchange process to recover plutonium from plutonium - 0.5% neptunium residues has been investigated on a production scale. The plutonium was effectively recovered and separated from neptunium using Rohm and Haas Amberlite IRA-938 (20 to 50 mesh) macroreticular anion exchange resin. During this process, 58.3 kg of plutonium containing less than 100 g Np/g Pu has been recovered.

Martella, L.L.; Guyer, R.H.; Leak, W.C.; Thomas, R.L. (eds.)

1987-05-26T23:59:59.000Z

350

ARM - Facility News Article  

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

Sunphotometer to Obtain Additional Aerosol Data in Niamey Sunphotometer to Obtain Additional Aerosol Data in Niamey Bookmark and Share Located nearby the AMF ground instruments, the sunphotometer, in the foreground, requires an unobstructed hemispheric view of the sky to obtain its measurements. Located nearby the AMF ground instruments, the sunphotometer, in the foreground, requires an unobstructed hemispheric view of the sky to obtain its measurements. In early August, a new Cimel sunphotometer (CSPHOT) was deployed at the ARM Mobile Facility site in Niamey, Niger, as part of the ongoing RADAGAST field campaign. The CSPHOT measures the solar and sky radiance at various wavelengths in the visible and near-infrared spectrum (340, 380, 440, 500, 670, 870, 936, 1020 nm). From these measurements, a number of aerosol

351

CSER 96-027: storage of cemented plutonium residue containers in 55 gallon drums  

SciTech Connect

A nuclear criticality safety analysis has been performed for the storage of residual plutonium cementation containers, produced at the Plutonium Finishing Plant, in 55 gallon drums. This CSER increases the limit of total plutonium stored in each 55 gallon drum from 100 to 200 grams.

Watson, W.T.

1997-01-20T23:59:59.000Z

352

Relativistic density functional theory modeling of plutonium and americium higher oxide molecules  

E-Print Network (OSTI)

Relativistic density functional theory modeling of plutonium and americium higher oxide molecules of plutonium and americium higher oxide molecules Andréi Zaitsevskii,1,2,a) Nikolai S. Mosyagin,2,3 Anatoly V of plutonium and americium higher oxide molecules (actinide oxidation states VI through VIII) by two

Titov, Anatoly

353

NNSA's Global Threat Reduction Initiative Completes First Plutonium  

National Nuclear Security Administration (NNSA)

Completes First Plutonium Completes First Plutonium Shipment | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > NNSA's Global Threat Reduction Initiative Completes First ... NNSA's Global Threat Reduction Initiative Completes First Plutonium Shipment Posted By NNSA Public Affairs NNSA Blog The United States and Sweden announced today at the 2012 Nuclear Security

354

NNSA's Global Threat Reduction Initiative Completes First Plutonium  

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

Completes First Plutonium Completes First Plutonium Shipment | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > NNSA's Global Threat Reduction Initiative Completes First ... NNSA's Global Threat Reduction Initiative Completes First Plutonium Shipment Posted By NNSA Public Affairs NNSA Blog The United States and Sweden announced today at the 2012 Nuclear Security

355

Subcritical Noise Measurements with a Nickel-Reflected Plutonium Sphere  

SciTech Connect

Subcritical measurements were conducted with an a-phase plutonium sphere reflected by nickel hemishells using the 252Cf Source-Driven Noise Analysis (CSDNA) method to provide criticality safety benchmark data. Measured configurations included a bare plutonium sphere as well as the plutonium sphere reflected by the following nickel thicknesses: 1.27, 2.54, 3.81, 5.08, and 7.62 cm. A certain ratio of spectral quantities was measured for each configuration which varies linearly with the keff of the system. In addition, two types of Monte Carlo calculations were employed: a modified version of MCNP to calculate the ratio of spectral quantities and a KCODE calculation. From the measured and computed quantities the multiplication of each configuration can be approximated. A comprehensive uncertainty analysis was then performed that includes uncertainties in the geometry and materials present in the system in addition to the uncertainties in the method and nuclear data.

Jesson D. Hutchinson; John D. Bess

2009-11-01T23:59:59.000Z

356

Preliminary safety evaluation for the plutonium stabilization and packaging system  

SciTech Connect

This Preliminary Safety Evaluation (PSE) describes and analyzes the installation and operation of the Plutonium Stabilization and Packaging System (SPS) at the Plutonium Finishing Plant (PFP). The SPS is a combination of components required to expedite the safe and timely storage of Plutonium (Pu) oxide. The SPS program will receive site Pu packages, process the Pu for storage, package the Pu into metallic containers, and safely store the containers in a specially modified storage vault. The location of the SPS will be in the 2736- ZB building and the storage vaults will be in the 2736-Z building of the PFP, as shown in Figure 1-1. The SPS will produce storage canisters that are larger than those currently used for Pu storage at the PFP. Therefore, the existing storage areas within the PFP secure vaults will require modification. Other modifications will be performed on the 2736-ZB building complex to facilitate the installation and operation of the SPS.

Shapley, J.E., Fluor Daniel Hanford

1997-03-14T23:59:59.000Z

357

Recovery of plutonium from electrorefining anode heels at Savannah River  

SciTech Connect

In a joint effort, the Savannah River Laboratory (SRL), Savannah River Plant (SRP), and the Rocky Flats Plant (RFP) have developed two processes to recover plutonium from electrorefining anode heel residues. Aqueous dissolution of anode heel metal was demonstrated at SRL on a laboratory scale and on a larger pilot scale using either sulfamic acid or nitric acid-hydrazine-fluoride solutions. This direct anode heel metal dissolution requires the use of a geometrically favorable dissolver. The second process developed involves first diluting the plutonium in the anode heel residues by alloying with aluminum. The alloyed anode heel plutonium can then be dissolved using a nitric acid-fluoride-mercury(II) solution in large non-geometrically favorable equipment where nuclear safety is ensured by concentration control.

Gray, J H; Gray, L W; Karraker, D G

1987-03-01T23:59:59.000Z

358

Supercritical fluid carbon dioxide cleaning of plutonium parts  

SciTech Connect

Supercritical fluid carbon dioxide is under investigation in this work for use as a cleaning solvent for the final cleaning of plutonium parts. These parts must be free of organic residue to avoid corrosion in the stockpile. Initial studies on stainless steel and full-scale mock-up parts indicate that the oils of interest are easily and adequately cleaned from the metal surfaces with supercritical fluid carbon dioxide. Results from compatibility studies show that undesirable oxidation or other surface reactions are not occurring during exposure of plutonium to the supercritical fluid. Cleaning studies indicate that the oils of interest are removed from the plutonium surface under relatively mild conditions. These studies indicate that supercritical fluid carbon dioxide is a very promising cleaning medium for this application.

Hale, S.J.

1991-12-31T23:59:59.000Z

359

Status of the Pit Disassembly and Conversion Facility  

SciTech Connect

A planned new facility, the Pit Disassembly and Conversion Facility (PDCF) will be used to disassemble the nation`s inventory of surplus nuclear weapons pits and convert the plutonium recovered from those pits into a form suitable for storage, international inspection, and final disposition. Sized to handle 35 metric tons of plutonium from pits and other sources over its 10-year operating life, the PDCF will apply the Advanced Recovery and Integrated Extraction System (ARIES) technology. ARIES process technology has been developed at Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL) and an integrated system is being demonstrated LANL. Four sites were considered for locating the PDCF: Pantex Plant, Savannah River Site (SRS), Idaho National Engineering and Environmental Laboratory (INEEL), and Hanford Site. Each site offers a different opportunity for constructing the PDCF, ranging from a new building at Pantex Plant to using an existing building at Hanford Site or INEEL. The Surplus Plutonium Disposition Environmental Impact Statement was prepared by the Department of Energy (DOE) Office of Fissile Materials Disposition (OFMD) to aid in site selection. This paper describes the initial scoping activities, preconceptual and conceptual design work, and the status of the PDCF.

Zygmunt, S. [Los Alamos National Lab., NM (United States); Peko, D. [Dept. of Energy, Washington, DC (United States). Office of Fissile Materials Disposition

1998-12-31T23:59:59.000Z

360

Nuclear disarmament, disposal of military plutonium and international security problems  

SciTech Connect

One of the major issues of the current debate deals with the question: what does real nuclear disarmament actually involve? It becomes more and more obvious for many experts that it can no longer be limited to the reduction or elimination of delivery vehicles alone, but must necessarily cove the warheads and the fissile materials recovered from them, which should totally or partially be committed to peaceful use and placed under appropriate international safeguards, thus precluding their re-use for as weapons. There are various options as to how to solve the problems of disposal of fissile materials released from weapons. The optimal choice can only be made on the basis of a thorough study. This study should treat the disposal of weapon-grade plutonium and weapon-grade uranium as separate problems. The possible options for plutonium disposition currently discussed are as follows: (a) Storage in a form or under conditions not suitable for use in the production of new types of nuclear weapons. This option seems to be most natural and inevitable at the first phase, subject to determination of storage period, volume, and technology. Besides, the requirements of the international nuclear weapons nonproliferation regime could be met easily. Safe, secure, and controlled temporary storage may provide an appropriate solution of disposal of weapon-grade plutonium in the near future. (b) Energy utilization (conversion) of weapon-grade plutonium. The most efficient option of utilization of plutonium appears to be for nuclear power generation. This option does not exclude storage, but considers it as a temporary phase, which can, however, be a prolonged one: its length is determined by the political decisions made and possibilities existing to transfer plutonium for processing.

Slipchenko, V.S.; Rybatchenkov, V. [Ministry of Foreign Affairs of the Russian Federation, Moscow (Russian Federation). Arms Control and Disarmament Dept.

1995-12-31T23:59:59.000Z

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


361

Healthcare mobile information flow  

Science Journals Connector (OSTI)

There are a variety of mobile technologies currently available that have increased the potential for healthcare practitioners to access clinical decision support resources delivered over an array of mobile devices as a component of clinical workflow. ... Keywords: Clinical Decision Support, Ehrs, Healthcare, Healthcare Mobile Technology, Ipads In Healthcare, Market Drivers, Mobile Devices, Smartphones In Healthcare

Victor Camlek

2011-01-01T23:59:59.000Z

362

Assessment of Plutonium-238 (Pu-238) Production Alternatives  

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

Plutonium-238 Plutonium-238 Production Alternatives Briefing for Nuclear Energy Advisory Committee April 21, 2008 Dennis Miotla Deputy Assistant Secretary for Nuclear Power Deployment Miotla - April 2008 NEAC Mtg - DM183874 (2) Statement of Work Desired end state: - Reliable, sustainable, affordable supply of Pu-238 suitable for NASA applications Assumptions: - NASA obtains funding for planned missions - Russia is out of material to sell to US - DOE maintains balance of radioisotope power source infrastructure during period of depleted supply Independently evaluate the Pu-238 heat source requirements for NASA's mission projections and assess Pu-238 production assumptions, strategy and alternatives for meeting those requirements Miotla - April 2008 NEAC Mtg - DM183874 (3)

363

Elemental composition in sealed plutoniumberyllium neutron sources  

Science Journals Connector (OSTI)

Abstract Five sealed plutoniumberyllium (PuBe) neutron sources from various manufacturers were disassembled. Destructive chemical analyses for recovered PuBe materials were conducted for disposition purposes. A dissolution method for PuBe alloys was developed for quantitative plutonium (Pu) and beryllium (Be) assay. Quantitation of Be and trace elements was performed using plasma based spectroscopic instruments, namely inductively coupled plasma mass spectrometry (ICP-MS) and atomic emission spectrometry (ICP-AES). Pu assay was accomplished by an electrochemical method. Variations in trace elemental contents among the five PuBe sources are discussed.

N. Xu; K. Kuhn; D. Gallimore; A. Martinez; M. Schappert; D. Montoya; E. Lujan; K. Garduno; L. Tandon

2015-01-01T23:59:59.000Z

364

ARIES: A mobile robot inspector  

SciTech Connect

ARIES (Autonomous Robotic Inspection Experimental System) is a mobile robot inspection system being developed for the Department of Energy (DOE) to survey and inspect drums containing mixed and low-level radioactive waste stored in warehouses at DOE facilities. The drums are typically stacked four high and arranged in rows with three-foot aisle widths. The robot will navigate through the aisles and perform an autonomous inspection operation, typically performed by a human operator. It will make real-time decisions about the condition of the drums, maintain a database of pertinent information about each drum, and generate reports.

Byrd, J.S.

1995-12-31T23:59:59.000Z

365

Minutes of the 28th Annual Plutonium Sample Exchange Meeting. Part II: metal sample exchange  

SciTech Connect

Contents of this publication include the following list of participating laboratories; agenda; attendees; minutes of October 25 and 26 meeting; and handout materials supplied by speakers. The handout materials cover the following: statistics and reporting; plutonium - chemical assay 100% minus impurities; americium neptunium, uranium, carbon and iron data; emission spectroscopy data; plutonium metal sample exchange; the calorimetry sample exchange; chlorine determination in plutonium metal using phyrohydrolysis; spectrophotometric determination of 238-plutonium in oxide; plutonium measurement capabilities at the Savannah River Plant; and robotics in radiochemical laboratory.

Not Available

1984-01-01T23:59:59.000Z

366

Environmental Impact Statement for the Proposed Production of Plutonium - 238 for Use in Advanced Radioisotope Power Systems for Future Space Missions  

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

98 98 Federal Register / Vol. 63, No. 192 / Monday, October 5, 1998 / Notices DEPARTMENT OF ENERGY Environmental Impact Statement for the Proposed Production of Plutonium- 238 for Use in Advanced Radioisotope Power Systems for Future Space Missions AGENCY: Department of Energy (DOE). ACTION: Notice of Intent. SUMMARY: Pursuant to the National Environmental Policy Act (NEPA), DOE announces its intent to prepare an environmental impact statement (EIS) for the proposed production of plutonium-238 (Pu-238) using one or more DOE research reactors and facilities. The Pu-238 would be used in advanced radioisotope power systems for potential future space missions. Without a long-term supply of Pu-238, DOE would not be able to provide the radioisotope power systems that may be required for these potential future space

367

Long-term risk from actinides in the environment: Modes of mobility. 1998 annual progress report  

SciTech Connect

'The mobility of actinides in surface soils is a key issue of concern at several DOE facilities in arid and semiarid environments, including Rocky Flats, Hanford, Nevada Test Site, Idaho National Engineering Laboratory, and Los Alamos National Laboratory and the Waste Isolation Pilot Plant (WIPP). Key sources of uncertainty in assessing Pu mobility are the magnitudes of mobility resulting from three modes of transport: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depend on numerous environmental factors and they compete with one another, particularly for actinides in very shallow soils ({approximately} 1 \\265m). The overall goal of the study is to quantify the mobility of soil actinides from all three modes. The authors study is using field measurements, laboratory experiments, and ecological modeling to address these three processes at three DOE facilities where actinide kinetics are of concern: WIPP, Rocky Flats, and Hanford. Wind erosion is being measured with suite of monitoring equipment, water erosion is being studied with rainfall simulation experiments, vertical migration is being studied in controlled laboratory experiments, and the three processes are being integrated using ecological modeling. Estimates for clean up of soil actinides for the extensive tracts of DOE land range to hundreds of billion $ in the US Without studies of these processes, unnecessary clean-up of these areas may waste billions of dollars and cause irreparable ecological damage through the soil removal. Further, the outcomes of litigation against DOE are dependent on quantifying the mobility of actinides in surface soils. This report provides a summary of work for the first year of a 3-year project; subcontracts to collaborating institutions (Colorado State University and New Mexico State University) were not in place until late December 1997, and hence this report focuses on the results of the 5 months from January through May 1998. The major result to date is a review of literature on the potential for using soil concentrations of {sup 137}Cs and {sup 241}Am as tracers for plutonium in soil. Measurements of {sup 239}Pu contamination in the environment are expensive and time consuming, requiring radiochemical analysis and alpha spectroscopy. They evaluated the literature for measurements of {sup 137}Cs and {sup 241}Am, both of which are more cost-effectively measured by gamma spectrometry, as tracers for Pu in soil. Their results indicate that: significant positive correlation exists between Pu, Cs, and Am in soils and sediments at several locations including Rocky Flats, Los Alamos, and Hanford; atmospheric transport of Pu and Cs from worldwide fallout is essentially the same; the attachment of Pu and Cs to soil particles of various size is very similar; both Pu and Cs movement in the environment correlate well with soil and sediment particle movements; a significant correlation between Pu, Cs, and Am was found in soil as a function of depth, indicating similar vertical migration behavior (most of the activity of these radionuclides is confined to the top 10--20 cm of soil at virtually all locations); most Pu and Cs are strongly absorbed onto clay and organic matter in soils and there is essentially very little leaching of Pu, Am and Cs through soil columns. Based on the above information, they believe that {sup 137}Cs and {sup 241}Am are excellent tracers for both {sup 239}Pu and soil particle transport processes in clay, mineral bearing and/or organic soils. Therefore, Cs and Am would be good tracers for the proposed water erosion and vertical migration work, at least for both Rocky Flats and Hanford. The correlation between Pu and Cs may not be as strong in sandy soil (e.g. WIPP site), however, examination of more data is needed.'

Breshears, D.D.; Whicker, J.J. [Los Alamos National Lab., NM (US); Ibrahim, S.A.; Whicker, F.W.; Hakonson, T.E. [Colorado State Univ., Fort Collins, CO (US); Kirchner, T. [New Mexico State Univ., Las Cruces, NM (US)

1998-06-01T23:59:59.000Z

368

SGP Central Facility  

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

Central Facility Central Facility SGP Related Links Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Fact Sheet Images Information for Guest Scientists Contacts SGP Central Facility The ARM Climate Research Facility deploys specialized remote sensing instruments in a fixed location at the site to gather atmospheric data of unprecedented quality, consistency, and completeness. More than 30 instrument clusters have been placed around the site; the central facility; and the boundary, intermediate, and extended facilities. The locations for the instruments were chosen so that the measurements reflect conditions

369

ARM - SGP Central Facility  

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

Central Facility Central Facility SGP Related Links Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Fact Sheet Images Information for Guest Scientists Contacts SGP Central Facility The ARM Climate Research Facility deploys specialized remote sensing instruments in a fixed location at the site to gather atmospheric data of unprecedented quality, consistency, and completeness. More than 30 instrument clusters have been placed around the site; the central facility; and the boundary, intermediate, and extended facilities. The locations for the instruments were chosen so that the measurements reflect conditions

370

NREL: Energy Systems Integration Facility - Facility Design  

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

371

Plutonium Focus Area research and development plan. Revision 1  

SciTech Connect

The Department of Energy (DOE) committed to a research and development program to support the technology needs for converting and stabilizing its nuclear materials for safe storage. The R and D Plan addresses five of the six material categories from the 94-1 Implementation Plan: plutonium (Pu) solutions, plutonium metals and oxides, plutonium residues, highly enriched uranium, and special isotopes. R and D efforts related to spent nuclear fuel (SNF) stabilization were specifically excluded from this plan. This updated plan has narrowed the focus to more effectively target specific problem areas by incorporating results form trade studies. Specifically, the trade studies involved salt; ash; sand, slag, and crucible (SS and C); combustibles; and scrub alloy. The plan anticipates possible disposition paths for nuclear materials and identifies resulting research requirements. These requirements may change as disposition paths become more certain. Thus, this plan represents a snapshot of the current progress and will continue to be updated on a regular basis. The paper discusses progress in safeguards and security, plutonium stabilization, special isotopes stabilization, highly-enriched uranium stabilization--MSRE remediation project, storage technologies, engineered systems, core technology, and proposed DOE/Russian technology exchange projects.

NONE

1996-11-01T23:59:59.000Z

372

Risk analysis of shipping plutonium pits and mixed oxide fuel  

E-Print Network (OSTI)

, one possible option that has been identified for disposition of excess U.S. weapons plutonium is the transformation into mixed oxide (MOX) fuel, that then would be used as fuel in a commercial nuclear power plant. Any such process will involve...

Caldwell, Amy Baker

2012-06-07T23:59:59.000Z

373

Disposition of weapons-grade plutonium in Westinghouse reactors  

E-Print Network (OSTI)

We have studied the feasibility of using weapons-grade plutonium in the form of mixed-oxide (MOX) fuel in existing Westinghouse reactors. We have designed three transition cycles from an all LEU core to a partial MOX core. We found that four...

Alsaed, Abdelhalim Ali

2012-06-07T23:59:59.000Z

374

NUCLEAR ARMS DISMANTLING NAS urges steps to safeguard plutonium  

Science Journals Connector (OSTI)

Plutonium from tens of thousands of nuclear weapons being dismantled by the U.S. and the former Soviet Union presents "a clear and present danger" to international security, warns a report issued last week by a National Academy of Sciences panel.Steps ...

1994-01-31T23:59:59.000Z

375

Characterization of plutonium in Maxey Flats radioactive trench leachates  

SciTech Connect

Plutonium in trench leachates at the Maxey Flats radioactive waste disposal site exists as dissolved species, primarily complexes of the tetravalent ion with strong organic ligands such as ethylenediaminetetraacetic acid. The complexes are not sorbed well by sediment and are only partly precipitated by ferric hydroxide. These results indicate the importance of isolating radioactive waste from organic matter. 3 tables.

Cleveland, J.M.; Rees, T.F.

1981-06-26T23:59:59.000Z

376

System specification for the plutonium stabilization and packaging system  

SciTech Connect

This document describes functional design requirements for the Plutonium Stabilization and Packaging System (Pu SPS), as required by DOE contract DE-AC03-96SF20948 through contract modification 9 for equipment in Building 707 at Rocky Flats Environmental Technology Site (RFETS).

NONE

1996-07-01T23:59:59.000Z

377

Source terms for plutonium aerosolization from nuclear weapon accidents  

SciTech Connect

The source term literature was reviewed to estimate aerosolized and respirable release fractions for accidents involving plutonium in high-explosive (HE) detonation and in fuel fires. For HE detonation, all estimates are based on the total amount of Pu. For fuel fires, all estimates are based on the amount of Pu oxidized. I based my estimates for HE detonation primarily upon the results from the Roller Coaster experiment. For hydrocarbon fuel fire oxidation of plutonium, I based lower bound values on laboratory experiments which represent accident scenarios with very little turbulence and updraft of a fire. Expected values for aerosolization were obtained from the Vixen A field tests, which represent a realistic case for modest turbulence and updraft, and for respirable fractions from some laboratory experiments involving large samples of Pu. Upper bound estimates for credible accidents are based on experiments involving combustion of molten plutonium droplets. In May of 1991 the DOE Pilot Safety Study Program established a group of experts to estimate the fractions of plutonium which would be aerosolized and respirable for certain nuclear weapon accident scenarios.

Stephens, D.R.

1995-07-01T23:59:59.000Z

378

Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas  

SciTech Connect

This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01T23:59:59.000Z

379

Reactor-Based Plutonium Disposition: Opportunities, Options, and Issues  

SciTech Connect

The end of the Cold War has created a legacy of surplus fissile materials (plutonium and highly enriched uranium) in the United States (U.S.) and the former Soviet Union. These materials pose a danger to national and international security. During the past few years, the U.S. and Russia have engaged in an ongoing dialog concerning the safe storage and disposition of surplus fissile material stockpiles. In January 1997, the Department of Energy (DOE) announced the U. S. would pursue a dual track approach to rendering approximately 50 metric tons of plutonium inaccessible for use in nuclear weapons. One track involves immobilizing the plutonium by combining it with high-level radioactive waste in glass or ceramic ''logs''. The other method, referred to as reactor-based disposition, converts plutonium into mixed oxide (MOX) fuel for nuclear reactors. The U.S. and Russia are moving ahead rapidly to develop and demonstrate the technology required to implement the MOX option in their respective countries. U.S. MOX fuel research and development activities were started in the 1950s, with irradiation of MOX fuel rods in commercial light water reactors (LWR) from the 1960s--1980s. In all, a few thousand MOX fuel rods were successfully irradiated. Though much of this work was performed with weapons-grade or ''near'' weapons-grade plutonium--and favorable fuel performance was observed--the applicability of this data for licensing and use of weapons-grade MOX fuel manufactured with modern fuel fabrication processes is somewhat limited. The U.S. and Russia are currently engaged in an intensive research, development, and demonstration program to support implementation of the MOX option in our two countries. This paper focuses on work performed in the U.S. and provides a brief summary of joint U.S./Russian work currently underway.

Greene, S.R.

1999-07-17T23:59:59.000Z

380

Accelerator-driven transmutation of plutonium and nuclear waste  

SciTech Connect

The ultimate disposition of spent reactor fuel and processed high-level nuclear waste (HLW) has been a subject of much concern and little progress since the dawn of the nuclear era. In the United States today, the spent fuel from more than 110 commercial light water reactors continues to be stored onsite while highly toxic liquid HLW continues to be stored in tanks at several U.S. Department of Energy sites. The management policy that has been followed in the United States for the past 12 yr is defined by the Nuclear Waste Policy Act (NWPA) of 1982 and its subsequent amendment of 1987. The NWPA requires the disposal of spent fuel assemblies in geologic waste repositories, the first of which will presumably be located at Yucca Mountain, Nevada. The pace of the process for implementing the Yucca Mountain repository discussed in a recent General Accounting Office (GAO) assessment, remains frustratingly slow. By GAO estimation, an operational permanent waste repository at Yucca Mountain could be delayed beyond the 2020 time frame. The approach to formulating an acceptable HLW disposal strategy has always involved serious consideration of nonproliferation issues. Most recently, the nuclear weapon build-down following the Cold War has stimulated the need for the United States and Russia to dispose of surplus plutonium. Consideration of this has motivated (a) a recognition that all plutonium is a proliferation hazard and (b) a renewed debate on the best approach to dispose of plutonium in general. From an international perspective, there is little agreement on the best strategy for the ultimate disposition of HLW and plutonium. This paper discusses the concept of transmutation of plutonium.

Berwald, D.H. [Grumman Aerospace Corp., Bethpage, NY (United States)

1995-12-31T23:59:59.000Z

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


381

HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX  

SciTech Connect

Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after ~4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

Kyser, E. A.; King, W. D.

2012-07-31T23:59:59.000Z

382

HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX  

SciTech Connect

Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after {approx}4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

Kyser, E.; King, W.

2012-04-25T23:59:59.000Z

383

4858 recreation facility [n  

Science Journals Connector (OSTI)

plan. recr. (Installation and equipment provided for recreation; ? simply-provided recreation facility , ? well-provided recreation facility ...

2010-01-01T23:59:59.000Z

384

Facilities | Argonne National Laboratory  

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

Engineering Research Facility Distributed Energy Research Center Engine Research Facility Heat Transfer Laboratory Tribology Laboratory Transportation Beamline at the Advanced...

385

Influence of Sources on Plutonium Mobility and Oxidation State Transformations in Vadose Zone Sediments  

Science Journals Connector (OSTI)

Today, 34 metric tons of Pu is planned to be shipped back to SRS from the Pantex site and converted into commercial reactor fuel. ... Existing Pu waste stored in the site's 49 waste tanks is also presently being processed into glass logs for eventual disposal in a yet-unnamed federal repository. ... The transport of Pu potentially released from spent nuclear fuel disposal and storage sites will be dependent on its interaction with mineral surfaces and speciation in the subsurface. ...

Daniel I. Kaplan; Brian A. Powell; Martine C. Duff; Deniz I. Demirkanli; Miles Denham; Robert A. Fjeld; Fred J. Molz

2007-10-03T23:59:59.000Z

386

Search Technology Goes Mobile  

Science Journals Connector (OSTI)

The competition among search providers to attract users and increase advertising revenues has moved to the wireless battlefield, and vendors are now promoting new mobile services. Keywords: wireless technology, mobile services, search

Linda Dailey Paulson

2005-08-01T23:59:59.000Z

387

Safety Shoe Mobile  

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

Safety and Training Safety Notices Safety Shoe Mobile The Safety Shoe Mobile comes to Argonne every Monday on the following schedule: 200 Area: 0800 - 1200 360 Area: 1300 - 1630...

388

Tandem mobile robot system  

SciTech Connect

A robotic vehicle system for terrain navigation mobility provides a way to climb stairs, cross crevices, and navigate across difficult terrain by coupling two or more mobile robots with a coupling device and controlling the robots cooperatively in tandem.

Buttz, James H. (Albuquerque, NM); Shirey, David L. (Albuquerque, NM); Hayward, David R. (Albuquerque, NM)

2003-01-01T23:59:59.000Z

389

Ion mobility sensor system  

DOE Patents (OSTI)

An ion mobility sensor system including an ion mobility spectrometer and a differential mobility spectrometer coupled to the ion mobility spectrometer. The ion mobility spectrometer has a first chamber having first end and a second end extending along a first direction, and a first electrode system that generates a constant electric field parallel to the first direction. The differential mobility spectrometer includes a second chamber having a third end and a fourth end configured such that a fluid may flow in a second direction from the third end to the fourth end, and a second electrode system that generates an asymmetric electric field within an interior of the second chamber. Additionally, the ion mobility spectrometer and the differential mobility spectrometer form an interface region. Also, the first end and the third end are positioned facing one another so that the constant electric field enters the third end and overlaps the fluid flowing in the second direction.

Xu, Jun; Watson, David B.; Whitten, William B.

2013-01-22T23:59:59.000Z

390

Autonomous Virtual Mobile Nodes  

E-Print Network (OSTI)

This paper presents a new abstraction for virtual infrastructure in mobile ad hoc networks. An AutonomousVirtual Mobile Node (AVMN) is a robust and reliable entity that is designed to cope with theinherent difficulties ...

Dolev, Shlomi

2005-06-15T23:59:59.000Z

391

Facility Representatives  

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

063-2011 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 approved for use by all DOE/National Nuclear Security Administration (NNSA) Components. 2. The revision to this DOE standard was developed by a working group consisting of headquarters and field participants. Beneficial comments (recommendations,

392

Facility Representatives  

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

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 all DOE Components. 2. The revision to this DOE standard was developed by a working group consisting of headquarters and field participants. Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should

393

Facility Type!  

Office of Legacy Management (LM)

ITY: 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 GUN-I OWNED ----- LEEE!? M!s LE!Ps2 -LdJG?- ---L .ANDS ILJILDINGS X2UIPilENT IRE OR RAW HA-I-L :INAL PRODUCT IASTE Z. RESIDUE I I kility l pt I ,-- 7- ,+- &!d,, ' IN&"E~:EW AT SITE -' ---------------- , . Control 0 AEC/tlED managed operations

394

Research Facility,  

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

Collecting and Delivering the Data Collecting 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 must be of sufficient quality to be useful and must be documented such that users will be able to clearly understand the meaning and organization of the data. Final, quality-assured data sets are stored in the Data Archive and are freely accessible to the general scientific community. Preliminary data may be shared among field campaign participants during and shortly following the campaign. To facilitate sharing of preliminary data, the ARM Data Archive establishes restricted access capability, limited to participants and data managers.

395

Manhattan Project: Seaborg and Plutonium Chemistry, Met Lab, 1942-1944  

Office of Scientific and Technical Information (OSTI)

Glenn T. Seaborg looks through a microscope at the world's first sample of pure plutonium, Met Lab, August 20, 1942. SEABORG AND PLUTONIUM CHEMISTRY Glenn T. Seaborg looks through a microscope at the world's first sample of pure plutonium, Met Lab, August 20, 1942. SEABORG AND PLUTONIUM CHEMISTRY (Met Lab, 1942-1944) Events > The Plutonium Path to the Bomb, 1942-1944 Production Reactor (Pile) Design, 1942 DuPont and Hanford, 1942 CP-1 Goes Critical, December 2, 1942 Seaborg and Plutonium Chemistry, 1942-1944 Final Reactor Design and X-10, 1942-1943 Hanford Becomes Operational, 1943-1944 While the Met Lab labored to make headway on pile (reactor) design, Glenn T. Seaborg (right) and his coworkers were trying to learn enough about transuranium chemistry to ensure that plutonium could be chemically separated from the uranium that would be irradiated in a production pile. Using lanthanum fluoride as a carrier, Seaborg isolated a weighable sample of plutonium in August 1942. At the same time, Isadore Perlman and William J. Knox explored the peroxide method of separation; John E. Willard studied various materials to determine which best adsorbed (gathered on its surface) plutonium; Theodore T. Magel and Daniel K. Koshland, Jr., researched solvent-extraction processes; and Harrison S. Brown and Orville F. Hill performed experiments into volatility reactions. Basic research on plutonium's chemistry continued as did work on radiation and fission products.

396

Mobile Conference Connection Conferencing  

E-Print Network (OSTI)

Mobile Conference Connection Conferencing · Help increase productivity while out of the office-mail meeting invitations from your mobile device · Access to "Click to Join" features · Initiate an Instant or other mobile devices can provide a quick and efficient means to respond to work demands. But, what

397

Vision for Mobile Robots  

Science Journals Connector (OSTI)

...1992 research-article Vision for Mobile Robots Michael Brady Han Wang Localized...determine scene structure for a mobile robot using stereo or structure from motion. It is argued that a mobile robot may not need to compute depth explicitly...

1992-01-01T23:59:59.000Z

398

Mobile Technology Management  

Directives, Delegations, and Requirements

The order establishes requirements, assigns responsibilities, and provides guidance for federal mobile technology management and employee use of both government furnished and personally-owned mobile devices within DOE and NNSA. Establishes requirements for use of User Agreements to govern mobile devices used for official duties. Does not cancel other directives.

2014-05-15T23:59:59.000Z

399

Auctioning Bulk Mobile Messages  

Science Journals Connector (OSTI)

The search for enablers of continued growth of SMS traffic, as well as the take-off of the more diversified MMS message contents, open up for enterprises the potential of bulk use of mobile messaging, instead of essentially one-by-one use. In parallel, ... Keywords: EMS, MMS, SMS, auctions, mobile commerce, mobile operators, multi-attribute auctions

S. Meij; L. -F. Pau

2006-05-01T23:59:59.000Z

400

Using vulnerability assessments to design facility safeguards and security systems  

SciTech Connect

The Weapons Complex Reconfiguration (WCR) Program is meant to prepare the Department of Energy (DOE) weapons complex to meet the needs of the next century through construction of now facilities or upgrades-in-place at existing facilities. This paper describes how a vulnerability (VA) was used to identify potential S&S features for the conceptual design for a plutonium storage facility as part of the WCR Program. We distinguish those features of the design that need to be investigated at the conceptual stage from those that can be evaluated later. We also examined what protection features may allow reduced S&S operating costs, with the main focus on protective force costs. While some of these concepts hold the promise for significantly reducing life-cycle protective force costs, their use depends on resolving long-standing tradeoffs between S&S and safety, which are discussed in the study.

Snell, M.; Jaeger, C.

1994-08-01T23:59:59.000Z

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


401

Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program  

SciTech Connect

This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

402

Harrisburg Facility Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Harrisburg Facility Biomass Facility Harrisburg Facility Biomass Facility Jump to: navigation, search Name Harrisburg Facility Biomass Facility Facility Harrisburg Facility Sector Biomass Facility Type Landfill Gas Location Dauphin County, Pennsylvania Coordinates 40.2734277°, -76.7336521° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.2734277,"lon":-76.7336521,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

403

Brookhaven Facility Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Brookhaven Facility Biomass Facility Brookhaven Facility Biomass Facility Jump to: navigation, search Name Brookhaven Facility Biomass Facility Facility Brookhaven Facility Sector Biomass Facility Type Landfill Gas Location Suffolk County, New York Coordinates 40.9848784°, -72.6151169° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.9848784,"lon":-72.6151169,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

404

BNL | Mobile Aerosol Observing System (MAOS)  

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

Mobile Aerosol Observing System (MAOS) Mobile Aerosol Observing System (MAOS) The Mobile Aerosol Observing System (MAOS) is a platform and instrument suite for Intensive Operation Periods (IOPs) to conduct in situ measurements of aerosols and their precursors. MAOS is part of the ARM Climate Research Facility. Physically MAOS is contained in two 20' SeaTainers custom adapted to provide a sheltered laboratory environment for operators and instruments even under harsh conditions. The two structures are designated MAOS-A and MAOS-C for Aerosol and Chemistry respectively. Although independent, with separate data systems, inlets and power distribution, the two structures are normally a single operating unit. The two enclosures comprising MAOS are designed for rapid deployment. All components (except for the Radar Wind Profiler) are transported internally

405

SMALL-SCALE TESTING OF PLUTONIUM (IV) OXALATE PRECIPITATION AND CALCINATION TO PLUTONIUM OXIDE TO SUPPORT THE MOX FEED MISSION  

SciTech Connect

The H-Canyon facility will be used to dissolve Pu metal for subsequent purification and conversion to plutonium dioxide (PuO{sub 2}) using Phase II of HB-Line. To support the new mission, SRNL conducted a series of experiments to produce calcined plutonium (Pu) oxide and measure the physical properties and water adsorption of that material. This data will help define the process operating conditions and material handling steps for HB-Line. An anion exchange column experiment produced 1.4 L of a purified 52.6 g/L Pu solution. Over the next nine weeks, seven Pu(IV) oxalate precipitations were performed using the same stock Pu solution, with precipitator feed acidities ranging from 0.77 M to 3.0 M nitric acid and digestion times ranging from 5 to 30 minutes. Analysis of precipitator filtrate solutions showed Pu losses below 1% for all precipitations. The four larger precipitation batches matched the target oxalic acid addition time of 44 minutes within 4 minutes. The three smaller precipitation batches focused on evaluation of digestion time and the oxalic acid addition step ranged from 25-34 minutes because of pump limitations in the low flow range. Following the precipitations, 22 calcinations were performed in the range of 610-690 C, with the largest number of samples calcined at either 650 or 635 C. Characterization of the resulting PuO{sub 2} batches showed specific surface areas in the range of 5-14 m{sup 2}/g, with 16 of the 22 samples in the range of 5-10 m2/g. For samples analyzed with typical handling (exposed to ambient air for 15-45 minutes with relative humidities of 20-55%), the moisture content as measured by Mass Spectrometry ranged from 0.15 to 0.45 wt % and the total mass loss at 1000 C, as measured by TGA, ranged from 0.21 to 0.58 wt %. For the samples calcined between 635 and 650 C, the moisture content without extended exposure ranged from 0.20 to 0.38 wt %, and the TGA mass loss ranged from 0.26 to 0.46 wt %. Of these latter samples, the samples calcined at 650 C generally had lower specific surface areas and lower moisture contents than the samples calcined at 635 C, which matches expectations from the literature. Taken together, the TGA-MS results for samples handled at nominally 20-50% RH, without extended exposure, indicate that the Pu(IV) oxalate precipitation process followed by calcination at 635-650 C appears capable of producing PuO{sub 2} with moisture content < 0.5 wt% as required by the 3013 Standard. Exposures of PuO{sub 2} samples to ambient air for 3 or more hours generally showed modest mass gains that were primarily gains in moisture content. These results point to the need for a better understanding of the moisture absorption of PuO{sub 2} and serve as a warning that extended exposure times, particularly above the 50% RH level observed in this study will make the production of PuO{sub 2} with less than 0.5 wt % moisture more challenging. Samples analyzed in this study generally contained approximately 2 monolayer equivalents of moisture. In this study, the bulk of the moisture released from samples below 300 C, as did a significant portion of the CO{sub 2}. Samples in this study consistently released a minor amount of NO in the 40-300 C range, but no samples released CO or SO{sub 2}. TGA-MS results also showed that MS moisture content accounted for 80 {+-} 8% of the total mass loss at 1000 C measured by the TGA. The PuO{sub 2} samples produced had particles sizes that typically ranged from 0.2-88 {micro}m, with the mean particle size ranging from 6.4-9.3 {micro}m. The carbon content of ten different calcination batches ranged from 190-480 {micro}g C/g Pu, with an average value of 290 {micro}g C/g Pu. A statistical review of the calcination conditions and resulting SSA values showed that in both cases tested, calcination temperature had a significant effect on SSA, as expected from literature data. The statistical review also showed that batch size had a significant effect on SSA, but the narrow range of batch sizes tested is a compelling reason to set aside that result until tests

Crowder, M.; Pierce, R.; Scogin, J.; Daniel, G.; King, W.

2012-06-25T23:59:59.000Z

406

Hanford MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site (SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. Hanford has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 1 facility. In all, a total of three LA MOX fuel fabrication options were identified by Hanford that could accommodate the program. In every case, only minor modification would be required to ready any of the facilities to accept the equipment necessary to accomplish the LA program.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

407

U.S. and Russia Sign Plan for Russian Plutonium Disposition | Department of  

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

Sign Plan for Russian Plutonium Disposition Sign Plan for Russian Plutonium Disposition U.S. and Russia Sign Plan for Russian Plutonium Disposition November 19, 2007 - 4:31pm Addthis Will Eliminate Enough Russian Plutonium for Thousands of Nuclear Weapons WASHINGTON, DC -U.S. Secretary of Energy Samuel W. Bodman and Russian Federal Atomic Energy Agency Director Sergey Kiriyenko have signed a joint statement outlining a plan to dispose of 34 metric tons of surplus plutonium from Russia's weapons program. Under the new plan, the United States will cooperate with Russia to convert Russian weapon-grade plutonium into mixed oxide fuel (MOX) and irradiate the MOX fuel in the BN-600 fast reactor, currently operating at the Beloyarsk nuclear power plant, and in the BN-800 fast reactor, currently under construction at the same site. The United States and Russia also

408

The United States Plutonium Balance, 1944-2009 | National Nuclear Security  

National Nuclear Security Administration (NNSA)

United States Plutonium Balance, 1944-2009 | National Nuclear Security United States Plutonium Balance, 1944-2009 | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The United States Plutonium Balance, 1944-2009 Home > Our Mission > Managing the Stockpile > Plutonium Pits > The United States Plutonium Balance, 1944-2009 The United States Plutonium Balance, 1944-2009

409

An MS-DOS-based program for analyzing plutonium gamma-ray spectra  

SciTech Connect

A plutonium gamma-ray analysis system that operates on MS-DOS-based computers has been developed for the International Atomic Energy Agency (IAEA) to perform in-field analysis of plutonium gamma-ray spectra for plutonium isotopics. The program titled IAEAPU consists of three separate applications: a data-transfer application for transferring spectral data from a CICERO multichannel analyzer to a binary data file, a data-analysis application to analyze plutonium gamma-ray spectra, for plutonium isotopic ratios and weight percents of total plutonium, and a data-quality assurance application to check spectral data for proper data-acquisition setup and performance. Volume 3 contains the software listings for these applications.

Ruhter, W.D.; Buckley, W.M.

1989-09-07T23:59:59.000Z

410

Stabilization, Packaging, and Storage of Plutonium-Bearing Materials  

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

DOE-STD-3013-2000 September 2000 Superseding DOE-STD-3013-99 November 1999 DOE STANDARD STABILIZATION, PACKAGING, AND STORAGE OF PLUTONIUM-BEARING MATERIALS U.S. Department of Energy AREA PACK Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-3013-2000 iii ABSTRACT This Standard provides guidance for the stabilization, packaging and safe storage of plutonium-

411

Plutonium Removal from Sweden: Fact Sheet | National Nuclear Security  

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

Removal from Sweden: Fact Sheet | National Nuclear Security Removal from Sweden: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Plutonium Removal from Sweden: Fact Sheet Fact Sheet Plutonium Removal from Sweden: Fact Sheet Mar 27, 2012 Sweden has been a global leader on nonproliferation, and was one of the

412

Plutonium Finishing Plan (PFP) Treatment and Storage Unit Interim Status Closure Plan  

SciTech Connect

This document describes the planned activities and performance standards for closing the Plutonium Finishing Plant (PFP) Treatment and Storage Unit. The PFP Treatment and Storage Unit is located within the 234-52 Building in the 200 West Area of the Hanford Facility. Although this document is prepared based upon Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the PFP Treatment and Storage Unit manages transuranic mixed (TRUM) waste, there are many controls placed on management of the waste. Based on the many controls placed on management of TRUM waste, releases of TRUM waste are not anticipated to occur in the PFP Treatment and Storage Unit. Because the intention is to clean close the PFP Treatment and Storage Unit, postclosure activities are not applicable to this closure plan. To clean close the unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or is environmentally impractical, the closure plan will be modified to address required postclosure activities. The PFP Treatment and Storage Unit will be operated to immobilize and/or repackage plutonium-bearing waste in a glovebox process. The waste to be processed is in a solid physical state (chunks and coarse powder) and will be sealed into and out of the glovebox in closed containers. The containers of immobilized waste will be stored in the glovebox and in additional permitted storage locations at PFP. The waste will be managed to minimize the potential for spills outside the glovebox, and to preclude spills from reaching soil. Containment surfaces will be maintained to ensure integrity. In the unlikely event that a waste spill does occur outside the glovebox, operating methods and administrative controls will require that waste spills be cleaned up promptly and completely, and a notation will be made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

PRIGNANO, A.L.

2000-07-01T23:59:59.000Z

413

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP Project W-460  

SciTech Connect

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

WEISS, E.V.

2000-03-06T23:59:59.000Z

414

Dose Rates from Plutonium Metal and Beryllium Metal in a 9975 Shipping Container  

SciTech Connect

A parametric study was performed of the radiation dose rates that might be produced if plutonium metal and beryllium metal were shipped in the 9975 shipping package. These materials consist of heterogeneous combinations plutonium metal and beryllium. The plutonium metal content varies up to 4.4 kilograms while the beryllium metal varies up to 4 kilograms. This paper presents the results of that study.

Nathan, S.J.

2002-02-04T23:59:59.000Z

415

Manhattan Project: Piles and Plutonium, 1939-1942  

Office of Scientific and Technical Information (OSTI)

Enrico Fermi PILES AND PLUTONIUM Enrico Fermi PILES AND PLUTONIUM (1939-1942) Events > Early Government Support, 1939-1942 Einstein's Letter, 1939 Early Uranium Research, 1939-1941 Piles and Plutonium, 1939-1941 Reorganization and Acceleration, 1940-1941 The MAUD Report, 1941 A Tentative Decision to Build the Bomb, 1941-1942 The Uranium Committee's first report, issued on November 1, 1939, recommended that, despite the uncertainty of success, the government should immediately obtain four tons of graphite and fifty tons of uranium oxide. This recommendation led to the first outlay of government funds -- $6,000 in February 1940 -- and reflected the importance attached to the Fermi-Szilard pile (reactor) experiments already underway at Columbia University. Building upon the Fission chain reaction work performed in 1934 demonstrating the value of moderators in producing slow neutrons, Enrico Fermi thought that a mixture of the right moderator and natural uranium could produce a self-sustaining fission chain reaction. Fermi and Leo Szilard increasingly focused their attention on carbon in the form of graphite. Perhaps graphite could slow down, or moderate, the neutrons coming from the fission reaction, increasing the probability of their causing additional fissions in sustaining the chain reaction. A pile containing a large amount of natural uranium could then produce enough secondary neutrons to keep a reaction going.

416

An isotopic analysis system for plutonium samples enriched in sup 238 Pu  

SciTech Connect

We have designed and built a gamma-ray spectrometer system that measures the relative plutonium isotopic abundances of plutonium oxide enriched in {sup 238}Pu. The first system installed at Westinghouse Savannah River Company was tested and evaluated on plutonium oxide in stainless steel EP60/61 containers. {sup 238}Pu enrichments ranged from 20% to 85%. Results show that 200 grams of plutonium oxide in an EP60.61 container can be measured with {plus minus}0.3% precision and better than {plus minus}1.0% accuracy in the specific power using a counting time of 50 minutes. 3 refs., 2 figs.

Ruhter, W.D.; Camp, D.C.

1991-08-01T23:59:59.000Z

417

Project Management Plan to Maintain Safe and Compliant Conditions at the Plutonium Finishing Plant (PFP)  

SciTech Connect

This Project Management Plan presents the overall plan, description, mission, and workscope for the Plutonium Finishing Plant (PFP) maintain safe and compliant conditions project at PFP.

COX, G.J.

1999-10-25T23:59:59.000Z

418

Voluntary Protection Program Onsite Review, Plutonium Finishing Plant Closure Project- May 2007  

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

Evaluation to determine whether Plutonium Finishing Plant Closure Project is continuing to perform at a level deserving DOE-VPP Star recognition.

419

E-Print Network 3.0 - analytique du plutonium Sample Search Results  

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

Collection: Mathematics 2 Home -Yahoo -My Yahoo -News Alerts -Help FREE Web-enabled Cell Phone Summary: radioactivity over that period. Traces of plutonium in depleted...

420

DOE Will Dispose of 34 Metric Tons of Plutonium by Turning it...  

National Nuclear Security Administration (NNSA)

plutonium to meet the non-proliferation goals agreed to by the United States and Russia in September 2000. Eliminating immobilization from the disposition pathway saves...

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


421

E-Print Network 3.0 - accelerator-based plutonium conversion...  

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

Physics Group Collection: Materials Science 79 Assessment of size-fractionated species of curium-244 via alpha spectrometry in groundwater Summary: and plutonium from the SRS heavy...

422

E-Print Network 3.0 - accidentally released plutonium Sample...  

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

to a density where fission can occur. The uranium and plutonium... in the secondary burn and increase the temperature until fusion starts. The energy released by ... Source:...

423

E-Print Network 3.0 - americium-containing uranium plutonium...  

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

and plutonium... - action raises the temperature even higher and burns more of the fis- ... Source: Gilfoyle, Jerry - Department of Physics, University of Richmond...

424

Workers Create Demolition Zone at Hanford Sites Plutonium Finishing Plant  

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

RICHLAND, Wash. In recent weeks, the look of Hanford sites Plutonium Finishing Plant has changed as crews removed or demolished eight buildings surrounding it.

425

STUDIES IN THE NUCLEAR CHEMISTRY OF PLUTONIUM, AMERICIUM, AND CURIUM AND MASSES OF THE HEAVIEST ELEMENTS  

E-Print Network (OSTI)

CHEMISTRY OF PLUTONIUM, AMERICIUM, AND CURIUM AND THE MASSESTO ION EXCHANGE SEPARATIONS OF AMERICIUM AND CURIUM A. B.5. Tartrate elutions of americium and curium from Dowex-50

Glass, Richard Alois

2011-01-01T23:59:59.000Z

426

Conceptual Design for the Pilot-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory  

SciTech Connect

This report describes a conceptual design for a pilot-scale capability to produce plutonium oxide for use as exercise and reference materials, and for use in identifying and validating nuclear forensics signatures associated with plutonium production. This capability is referred to as the Pilot-scale Plutonium oxide Processing Unit (P3U), and it will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including plutonium dioxide (PuO2) dissolution, purification of the Pu by ion exchange, precipitation, and conversion to oxide by calcination.

Lumetta, Gregg J.; Meier, David E.; Tingey, Joel M.; Casella, Amanda J.; Delegard, Calvin H.; Edwards, Matthew K.; Jones, Susan A.; Rapko, Brian M.

2014-08-05T23:59:59.000Z

427

International Facility Management Association Strategic Facility  

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

Facility Management Association Facility Management Association Strategic Facility Planning: A WhIte PAPer Strategic Facility Planning: A White Paper on Strategic Facility Planning © 2009 | International Facility Management Association For additional information, contact: 1 e. Greenway Plaza, Suite 1100 houston, tX 77046-0104 USA P: + 1-713-623-4362 F: + 1-713-623-6124 www.ifma.org taBle OF cOntentS PreFace ......................................................... 2 executive Summary .................................... 3 Overview ....................................................... 4 DeFinitiOn OF Strategic Facility Planning within the Overall cOntext OF Facility Planning ................. 5 SPecializeD analySeS ................................ 9 OrganizatiOnal aPPrOacheS tO SFP ... 10 the SFP PrOceSS .......................................

428

Hanford Facility Beryllium Fact Sheet Building Number/Name:  

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

Waste Isolation Pilot Plant (WIPP). Waste plutonium residues processed in 234-5Z included Rocky Flats Environmental Technology Site (RFETS) plutonium waste that contained up to...

429

Facilities Services Overview & Discussion  

E-Print Network (OSTI)

& Finance Facilities Services Director: Jeff Butler Human Resources Administrative Services Engineering) Environmental Services Morrison (3) Admin Services Evans (1) Human Resources Engineering (4) ·EngineeringFacilities Services Overview & Discussion Jeff Butler Director ­ Facilities Services November 2011

Maxwell, Bruce D.

430

Ad Hoc Mobile Networking and General Mobility Issues Ramon Lawrence  

E-Print Network (OSTI)

Ad Hoc Mobile Networking and General Mobility Issues Ramon Lawrence Department of Computer Science of networking and mobility come many interesting opportunities and difficult problems. Mobile computing allows around in the environment. Unfortunately, to support this mobility places several restrictive restraints

Lawrence, Ramon

431

Fuel Fabrication Facility  

National Nuclear Security Administration (NNSA)

Construction of the Mixed Oxide Fuel Fabrication Facility Construction of the Mixed Oxide Fuel Fabrication Facility November 2005 May 2007 June 2008 May 2012...

432

Sandia National Laboratories: Facilities  

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

Center in Vermont Achieves Milestone Installation On September 23, 2014, in Concentrating Solar Power, Energy, Facilities, National Solar Thermal Test Facility, News, News &...

433

from Isotope Production Facility  

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

Cancer-fighting treatment gets boost from Isotope Production Facility April 13, 2012 Isotope Production Facility produces cancer-fighting actinium 2:32 Isotope cancer treatment...

434

Programs & User Facilities  

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

Facilities Programs & User Facilities Enabling remarkable discoveries and tools that transform our understanding of energy and matter and advance national, economic, and energy...

435

Facility Data Policy  

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

Facility Data Policy About ESnet Our Mission The Network ESnet History Governance & Policies ESnet Policy Board ESCC Acceptable Use Policy Facility Data Policy Career Opportunities...

436

ARM - Facility News Article  

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

November 15, 2005 Facility News More Server Power Improves Performance at the ARM Data Management Facility Bookmark and Share Recently, several new Sun servers joined the...

437

ARM - Facility News Article  

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

approximately 22,500 square kilometers, or the approximate area of a modern climate model grid cell. Centered around the SGP Central Facility, these extended facilities are...

438

Nuclear Facilities | Department of Energy  

Energy Savers (EERE)

Nuclear Facilities Nuclear Facilities Nuclear Facilities Locator Map Numerical map data points indicate two or more nuclear facilities in the same geographic location. Nuclear...

439

Mobile media search  

Science Journals Connector (OSTI)

This panel paper presents motivations for discussing mobile media search and contains statements from the panelists who are industry research leaders in this field.

Berna Erol; Jordan Cohen; Minoru Etoh; Hsiao-Wuen Hon; Jiebo Luo; Johan Schalkwyk

2009-04-01T23:59:59.000Z

440

Mobile Ice Nucleus Spectrometer  

SciTech Connect

This first year report presents results from a computational fluid dynamics (CFD) study to assess the flow and temperature profiles within the mobile ice nucleus spectrometer.

Kulkarni, Gourihar R.; Kok, G. L.

2012-05-07T23:59:59.000Z

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


441

Facility Representative Program: 2003 Facility Representative Workshop  

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

3 Facility Representative Workshop 3 Facility Representative Workshop May 13 - 15, 2003 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Day 1: Tuesday, May 13, 2003 Theme: Program Successes and Challenges 8:00 a.m. John Evans, Facility Representative Program Manager 8:15 a.m. Welcome Kathleen Carlson Manager, Nevada Site Office 8:30 a.m. Keynote Address Savannah River Site and Facility Reps - A Shared History and Common Future Jeffrey M. Allison Manager, Savannah River Operations Office 9:00 a.m. Videotaped Remarks from the Deputy Secretary Kyle E. McSlarrow, Deputy Secretary of Energy 9:10 a.m. Facility Representative of the Year Presentation Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board

442

NREL: Research Facilities - Test and User Facilities  

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

Test and User Facilities 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 new control schemes and equipment for reducing loads on wind turbine components. Learn more about the Advanced Research Turbines on our Wind Research website. Back to Top D Distributed Energy Resources Test Facility This facility was designed to assist the distributed power industry in the

443

Facility Representative Program: 2000 Facility Representative Workshop  

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

0 Facility Representative Workshop 0 Facility Representative Workshop May 16-18, 2000 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Tuesday, May 16, 2000 Theme for Day 1: Sustaining the Success of the Facility Representative Program 8:00 a.m. - Opening Remarks - Joe Arango, Facility Representative Program Manager 8:05 a.m. - Welcome - Kenneth Powers, Deputy Manager Nevada Operations Office 8:15 a.m. - Deputy Secretary Remarks - T. J. Glauthier, Deputy Secretary of Energy 8:30 a.m. - Keynote Address - Jerry Lyle, Assistant Manager for Environmental Management, Idaho Operations Office 9:00 a.m. - Facility Representative of the Year Presentation - Mark B. Whitaker, Departmental Representative 9:30 a.m. - Break 9:50 a.m. - Program Results and Goals - Joe Arango, Facility Representative Program Manager

444

BUILDING MOBILE EXPERIENCES Frank Bentley  

E-Print Network (OSTI)

BUILDING MOBILE EXPERIENCES Frank Bentley Principal Staff Research Scientist Motorola Mobility of teaching mobile apps class at MIT ! Strong believer in user-inspired innovation ! Have brought several new? ! Investigating the interaction between people and mobile computing devices ! Creating compelling mobile

Glinz, Martin

445

INVESTIGATION OF PLUTONIUM AND URANIUM UPTAKE INTO MCU SOLVENT AND NEXT GENERATION SOLVENT  

SciTech Connect

At the request of the Savannah River Remediation (SRR) customer, the Savannah River National Laboratory (SRNL) examined the plutonium (Pu) and uranium (U) uptake into the Next Generation Solvent (NGS) that will be used at the Salt Waste Processing Facility (SWPF). SRNL examined archived samples of solvent used in Extraction-Scrub-Strip (ESS) tests, as well as samples from new tests designed explicitly to examine the Pu and U uptake. Direct radiocounting for Pu and U provided the best results. Using the radiocounting results, we found that in all cases there were <3.41E-12 g Pu/g of NGS and <1.17E-05 g U/g of NGS in multiple samples, even after extended contact times and high aqueous:organic volume phase ratios. These values are conservative as they do not allow for release or removal of the actinides by scrub, strip, or solvent wash processes. The values do not account for extended use or any increase that may occur due to radiolytic damage of the solvent.

Peters, T.; Fink, S.

2012-01-06T23:59:59.000Z

446

Decontamination and size reduction of plutonium contaminated process exhaust ductwork and glove boxes  

SciTech Connect

The Los Alamos National Laboratory (LANL) Decommissioning Program has decontaminated and demolished two filter plenum buildings at Technical Area 21 (TA-21). During the project a former hot cell was retrofitted to perform decontamination and size reduction of highly Pu contaminated process exhaust (1,100 ft) and gloveboxes. Pu-238/239 concentrations were as high a 1 Ci per linear foot and averaged approximately 1 mCi/ft. The Project decontamination objective was to reduce the plutonium contamination on surfaces below transuranic levels. If possible, metal surfaces were decontaminated further to meet Science and Ecology Group (SEG) waste classification guidelines to enable the metal to be recycled at their facility in oak Ridge, Tennessee. Project surface contamination acceptance criteria for low-level radioactive waste (LLRW), transuranic waste, and SEG waste acceptance criteria will be presented. Ninety percent of all radioactive waste for the project was characterized as LLRW. Twenty percent of this material was shipped to SEG. Process exhaust and glove boxes were brought to the project decontamination area, an old hot cell in Building 4 North. This paper focuses on process exhaust and glovebox decontamination methodology, size reduction techniques, waste characterization, airborne contamination monitoring, engineering controls, worker protection, lessons learned, and waste minimization. Decontamination objectives are discussed in detail.

LaFrate, P.; Elliott, J.; Valasquez, M.

1996-11-15T23:59:59.000Z

447

Over Batch Analysis for the LLNL Plutonium Packaging System (PuPS)  

SciTech Connect

This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria (Reference 1, Section 6.a.3) about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (B332). Based on the material handling discussed in Section 2.3, there are only three errors that could result in a shipping container being over batched. These are: incorrect measurement of the item, selecting the wrong item to package, and packaging two items into a single shipping container. The analysis in Section 3 shows that the first two events are incredible because of the controls that exist at LLNL. The third event is physically impossible. Therefore, it is incredible for an item to be shipped to SRS that is more than 1.0 kg of fissile materials over batched.

Riley, D; Dodson, K

2007-11-19T23:59:59.000Z

448

Evaluation of moisture limits for uranium and plutonium mixed oxides to support on-site transportation packaging  

SciTech Connect

This report contains supporting documentation for onsite shipment of uranium and plutonium mixed oxide materials in the 9975 package.

Livingston, R.R.

2000-08-09T23:59:59.000Z

449

Criteria for Preparing and Packaging Plutonium Metals and Oxides for Long-Term Storage  

SciTech Connect

This Standard provides criteria for packaging of plutonium metals and stabilized oxides for storage periods of at least 50 years. To meet the criteria, plutonium-bearing materials must be in stable forms and be packaged in containers designed to maintain their integrity both under normal storage conditions and during anticipated handling accidents.

NONE

1994-12-01T23:59:59.000Z

450

Amarillo National Resource Center for Plutonium. Quarterly technical progress report, August 1, 1996--October 31, 1996  

SciTech Connect

This report from the Amarillo National Resource Center for Plutonium describes progress in the following areas: electronic resource library; the senior technical review group; environment, health, and safety and remedial action activities; communications, education, and training; and plutonium and other materials.

NONE

1996-11-26T23:59:59.000Z

451

History and stabilization of the Plutonium Finishing Plant (PFP) complex, Hanford Site  

SciTech Connect

The 231-Z Isolation Building or Plutonium Metallurgy Building is located in the Hanford Site`s 200 West Area, approximately 300 yards north of the Plutonium Finishing Plant (PFP) (234-5 Building). When the Hanford Engineer Works (HEW) built it in 1944 to contain the final step for processing plutonium, it was called the Isolation Building. At that time, HEW used a bismuth phosphate radiochemical separations process to make `AT solution,` which was then dried and shipped to Los Alamos, New Mexico. (AT solution is a code name used during World War II for the final HEW product.) The process was carried out first in T Plant and the 224-T Bulk Reduction Building and B Plant and the 224-B Bulk Reduction Building. The 224-T and -B processes produced a concentrated plutonium nitrate stream, which then was sent in 8-gallon batches to the 231-Z Building for final purification. In the 231-Z Building, the plutonium nitrate solution underwent peroxide `strikes` (additions of hydrogen peroxide to further separate the plutonium from its carrier solutions), to form the AT solution. The AT solution was dried and shipped to the Los Alamos Site, where it was made into metallic plutonium and then into weapons hemispheres.` The 231-Z Building began `hot` operations (operations using radioactive materials) with regular runs of plutonium nitrate on January 16, 1945.

Gerber, M.S., Fluor Daniel Hanford

1997-02-18T23:59:59.000Z

452

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement  

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

This EIS analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives. The original EIS is available at http://energy.gov/nepa/downloads/eis-0283-final-environmental-impact-sta....

453

Assessment of plutonium exposures for an epidemiological study of US nuclear workers  

Science Journals Connector (OSTI)

......In a study of mortality among plutonium workers at the Rocky Flats Plant, Wilkinson et al.(2) separated workers into...and internal lung doses among plutonium workers at the Rocky Flats Plant: a case-control study. Am. J. Epidemiol......

R. D. Daniels; C. J. Lodwick; M. K. Schubauer-Berigan; H. B. Spitz

2006-04-01T23:59:59.000Z

454

Implications of Plutonium isotopic separation on closed fuel cycles and repository design  

SciTech Connect

Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation. This would have large impacts on LWR closed fuel cycles and waste management. If Pu-240 is removed before recycling plutonium as mixed oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, Americium, and Curium. Pu-240 is a fertile material and thus can be replaced by U-238. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Eliminating fertile Pu-240 and Pu-242 reduces the plutonium content in MOX fuel and simplifies fabrication. Reducing production of Pu-241 reduces production of Am-241 - the primary heat generator in spent nuclear fuels after several decades. Reducing heat generating Am-241 would reduce repository cost and waste toxicity. Avoiding Am- 241 avoids its decay product Np-237, a nuclide that partly controls long-term oxidizing repository performance. Most of these benefits also apply to LWR plutonium recycled into fast reactors. There are benefits for plutonium isotopic separation in fast reactor fuel cycles (particularly removal of Pu-242) but the benefits are less. (author)

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave. Cambridge, MA 20129 (United States)

2013-07-01T23:59:59.000Z

455

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons  

SciTech Connect

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the Fission Options'' provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium.

Omberg, R.P. (Westinghouse Hanford Co., Richland, WA (United States)); Walter, C.E. (Lawrence Livermore National Lab., CA (United States))

1993-02-05T23:59:59.000Z

456

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons  

SciTech Connect

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the ``Fission Options`` provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium.

Omberg, R.P. [Westinghouse Hanford Co., Richland, WA (United States); Walter, C.E. [Lawrence Livermore National Lab., CA (United States)

1993-02-05T23:59:59.000Z

457

Japan modifies plans for plutonium in wake of protests over shipments  

Science Journals Connector (OSTI)

... Tokyo. Growing international concern over Japan's plans to ship large amounts of weapons-grade plutonium from Europe has encouraged the ... to ship large amounts of weapons-grade plutonium from Europe has encouraged the head of Japan's most powerful organization for research and development of nuclear power to suggest a new ...

David Swinbanks

1992-10-22T23:59:59.000Z

458

Safety of CANDU reactors utilizing plutonium-enriched mixed-oxide fuel  

SciTech Connect

Substantial quantities of plutonium have become available as a result of nuclear arms reduction agreements. Irradiation of plutonium enriched fuel in Canadian deuterium uranium (CANDU) heavy water moderated and cooled reactors, of which there are 22 in operation in Canada, has been evaluated as a means of managing it. This paper summarizes the results of a study of reactor safety.

Chan, P.; Feinroth, H.; Luxat, J.; Pendergast, D.

1994-12-31T23:59:59.000Z

459

Auto-Networking Technologies for IPv6 Mobile Ad Hoc Networks  

E-Print Network (OSTI)

Auto-Networking Technologies for IPv6 Mobile Ad Hoc Networks Jaehoon Jeong, Jungsoo Park for IPv6 mobile ad hoc networks. The auto-networking technologies consist of IPv6 unicast address. These technologies are based on IPv6's inherent autoconfiguration facility, which can provide ad hoc users

Jeong, Jaehoon "Paul"

460

Commissioning for Federal Facilities  

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

Guide describes building commissioning, recommissioning, retrocommissioning, and continuous commissioning for federal facilities.

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


461

NetInf Mobile Node Architecture and Mobility Management based on LISP Mobile Node  

E-Print Network (OSTI)

NetInf Mobile Node Architecture and Mobility Management based on LISP Mobile Node Muhammad Shoaib an architecture for Network of Information mobile node (NetInf MN). It bears characteristics and features of basic a virtual node layer for mobility management in the Network of Information. Therefore, by adopting

Paris-Sud XI, Université de

462

Jebeile. The Mobile Subject Assistant THE MOBILE SUBJECT ASSISTANT: A MOBILE COURSE TOOL  

E-Print Network (OSTI)

Jebeile. The Mobile Subject Assistant THE MOBILE SUBJECT ASSISTANT: A MOBILE COURSE TOOL of Wollongong ABSTRACT: The rapid adoption rate of mobile phones coupled with advancements in supporting technologies suggests mobile phones may now be a viable tool for classroom use. In this paper we introduce

Rubinstein, Benjamin

463

Criticality experiments with mixed plutonium and uranium nitrate solution at a plutonium fraction of 0.5 in slab and cylindrical geometry  

SciTech Connect

A series of critical experiments was completed with mixed plutonium-uranium solutions having Pu/(Pu + U) ratios of approximately 0.5. These experiments were a part of the Criticality Data Development Program between the United States Department of Energy (USDOE), and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of, and data from, the experiments are included in this report. The experiments were performed with mixed plutonium-uranium solutions in cylindrical and slab geometries and included measurements with a water reflector, a concrete reflector, and without an added reflector. The concentration was varied from 112 to 332 g (Pu + U)/liter. The ratio of plutonium to total heavy metal (plutonium plus uranium) was 52% for all experiments.

Lloyd, R.C.

1986-12-01T23:59:59.000Z

464

Systems concepts for DOE facilities: analysis of PF/LASS data  

SciTech Connect

We have analyzed Plutonium Facility/Los Alamos Safeguards System (PF/LASS) data for the Fast Flux Test Facility (FFTF) process. Highlights of the work are: the PF/LASS data base provides useful information for accountability purposes, some measurement code assignments appear to be in error, some other data are erroneous, and material in process (MIP) and cumulative sum (CUSUM) charts are powerful indicators of trouble areas. From these studies we recommend re-examination of instrument biases, adoption of new naming procedures for collection batches, improvement of measurement code assignment reliability, revision of round-off procedures, and strengthening of measurement control procedures.

Bearse, R.C.; Shirk, D.G.; Marshall, R.S.; Thomas, C.C. Jr.

1982-06-01T23:59:59.000Z

465

Investigation into the feasibility of alternative plutonium shipping forms  

SciTech Connect

Pacific Northwest Laboratory (PNL), operated for the Department of Energy by the Battelle Memorial Institute, is conducting a study for the Nuclear Regulatory Commission on the feasibility of altering current plutonium shipping forms to reduce or eliminate the airborne dispersibility of PuO/sub 2/ which might occur during a shipping accident. Plutonium used for fuel fabrication is currently shipped as a PuO/sub 2/ powder with a significant fraction in the respirable size range. If the high-strength container is breached due to stresses imposed during a transportation accident, the PuO/sub 2/ powder could be subject to airborne dispersion. The available information indicated that a potential accident involving fire accompanied by crush/impact forces would lead to failure of current surface shipping containers (no assumptions were made on the possibility of such a severe accident). Criteria were defined for an alternate shipping form to mitigate the effects of such an accident. Candidate techniques and materials were evaluated as alternate shipping forms by a task team consisting of personnel from PNL and Rockwell Hanford Operations (RHO). At this time, the most promising candidate for an alternate plutonium shipping form appears to be pressing PuO/sub 2/ into unsintered (green) pellets. These green pellets satisfy the criteria for a less dispersible form without requiring significant process changes. Discussions of all candidates considered are contained in a series of appendices. Recommendations for further investigations of the applicability of green pellets as an alternate shipping form are given, including the need for a cost-benefit study.

Mishima, J.; Lindsey, C.G.

1983-06-01T23:59:59.000Z

466

SRS MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site(SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. SRS has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 2 or 3 facility with storage of bulk PuO{sub 2} and assembly, storage, and shipping of fuel bundles in an S and S Category 1 facility. The total Category 1 approach, which is the recommended option, would be done in the 221-H Canyon Building. A facility that was never in service will be removed from one area, and a hardened wall will be constructed in another area to accommodate execution of the LA fuel fabrication. The non-Category 1 approach would require removal of process equipment in the FB-Line metal production and packaging glove boxes, which requires work in a contamination area. The Immobilization Hot Demonstration Program equipment in the Savannah River Technology Center would need to be removed to accommodate pellet fabrication. This work would also be in a contaminated area.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

467

"Mobile money" services permit  

E-Print Network (OSTI)

"Mobile money" services permit cell phone users to send small amounts of money via text message to their friends and relatives. There are over 90 mobile money services in the world today, mainly in emergingTure oF Money october 2012 - April 2013 Muriel Ansley reynolds exhibit GAllery For the full exhibit checklist

Loudon, Catherine

468

Mobility for Offshore Drilling  

Science Journals Connector (OSTI)

Mobility for Offshore Drilling ... New type unit designed by Humble Oil to operate in Gulf of Mexico in 30 to 70 feet deep water ... HUMBLE OIL & REFINING is inviting bids on construction of a new type of mobile drilling platform to be used in offshore operations. ...

1956-03-26T23:59:59.000Z

469

NISTIR 7617 Mobile Forensic  

E-Print Network (OSTI)

NISTIR 7617 Mobile Forensic Reference Materials: AMethodologyandReification WayneJansen AurélienDelaitre i #12;Mobile Forensic Reference Materials: A Methodology and Reification Wayne Jansen Aurélien of forensic tools. It describes an application and data set developed to populate identity modules

470

E-Print Network 3.0 - astra critical facility Sample Search Results  

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

results for: astra critical facility Page: << < 1 2 3 4 5 > >> 1 FoneAstra: Enabling Remote Monitoring of Vaccine Cold-Chains Using Commodity Mobile Phones Summary: FoneAstra:...

471

Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities  

SciTech Connect

This second report in a series of three reviews possible safeguards approaches for the new transuranic (TRU) fuel fabrication processes to be deployed at AFCF specifically, the ceramic TRU (MOX) fuel fabrication line and the metallic (pyroprocessing) line. The most common TRU fuel has been fuel composed of mixed plutonium and uranium dioxide, referred to as MOX. However, under the Advanced Fuel Cycle projects custom-made fuels with higher contents of neptunium, americium, and curium may also be produced to evaluate if these minor actinides can be effectively burned and transmuted through irradiation in the ABR. A third and final report in this series will evaluate and review the advanced safeguards approach options for the ABR. In reviewing and developing the advanced safeguards approach for the new TRU fuel fabrication processes envisioned for AFCF, the existing international (IAEA) safeguards approach at the Plutonium Fuel Production Facility (PFPF) and the conceptual approach planned for the new J-MOX facility in Japan have been considered as a starting point of reference. The pyro-metallurgical reprocessing and fuel fabrication process at EBR-II near Idaho Falls also provided insight for safeguarding the additional metallic pyroprocessing fuel fabrication line planned for AFCF.

Durst, Philip C.; Ehinger, Michael H.; Boyer, Brian; Therios, Ike; Bean, Robert; Dougan, A.; Tolk, K.

2007-12-15T23:59:59.000Z

472

Introduction to Mobile Information Retrieval  

Science Journals Connector (OSTI)

The new frontier of mobile information retrieval will combine context awareness and content adaptation. Keywords: mobile information retrieval, context awareness, content adaptation, mobile search, location-based search, user profiling, user personalization

Flora S. Tsai; Minoru Etoh; Xing Xie; Wang-Chien Lee; Qiang Yang

2010-01-01T23:59:59.000Z

473

Enhancing mobile browsing and reading  

E-Print Network (OSTI)

Although the web browser has become a standard interface for information access on the Web, the mobile web browser on the smartphone does not hold the same interest to mobile users. A survey with 11 mobile users shows that ...

Yu, Chen-Hsiang

474

Mobile Malware Propagation and Defense  

E-Print Network (OSTI)

5.2 Scanner errors in mobile data . . . . . . . . 5.2.113th ACM International Conference on Mobile Computing andGao. An Epidemic Model of Mobile Phone Virus. In Proceedings

Zyba, Gjergji

475

U.S. Removes Nine Metric Tons of Plutonium From Nuclear Weapons Stockpile |  

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

Removes Nine Metric Tons of Plutonium From Nuclear Weapons Removes Nine Metric Tons of Plutonium From Nuclear Weapons Stockpile U.S. Removes Nine Metric Tons of Plutonium From Nuclear Weapons Stockpile September 17, 2007 - 2:41pm Addthis Declaration Reinforces U.S. Commitment to Nonproliferation VIENNA, AUSTRIA - Secretary of Energy Samuel W. Bodman today announced that the Department of Energy's National Nuclear Security Administration (NNSA) will remove nine metric tons of plutonium from further use as fissile material in U.S. nuclear weapons, signifying the Bush Administration's ongoing commitment to nonproliferation. Nine metric tons of plutonium is enough material to make over 1,000 nuclear weapons. The Secretary made today's announcement while speaking before the International Atomic Energy Agency's annual general conference.

476

LANL Produces First Plutonium Pit in 14 Years | National Nuclear Security  

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

Produces First Plutonium Pit in 14 Years | National Nuclear Security Produces First Plutonium Pit in 14 Years | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > LANL Produces First Plutonium Pit in 14 Years LANL Produces First Plutonium Pit in 14 Years April 22, 2003 Los Alamos, NM LANL Produces First Plutonium Pit in 14 Years

477

U.S. Removes Nine Metric Tons of Plutonium From Nuclear Weapons Stockpile |  

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

U.S. Removes Nine Metric Tons of Plutonium From Nuclear Weapons U.S. Removes Nine Metric Tons of Plutonium From Nuclear Weapons Stockpile U.S. Removes Nine Metric Tons of Plutonium From Nuclear Weapons Stockpile September 17, 2007 - 2:41pm Addthis Declaration Reinforces U.S. Commitment to Nonproliferation VIENNA, AUSTRIA - Secretary of Energy Samuel W. Bodman today announced that the Department of Energy's National Nuclear Security Administration (NNSA) will remove nine metric tons of plutonium from further use as fissile material in U.S. nuclear weapons, signifying the Bush Administration's ongoing commitment to nonproliferation. Nine metric tons of plutonium is enough material to make over 1,000 nuclear weapons. The Secretary made today's announcement while speaking before the International Atomic Energy Agency's annual general conference.