Success in behaviour-based safety at Los Alamos National Laboratory's plutonium facility

Energy Technology Data Exchange (ETDEWEB)

Wieneke, R E [Los Alamos National Laboratory, NMT Division, Los Alamos, NM (United States); Balkey, J J; Kleinsteuber, J F [Los Alamos National Laboratory, NMT Division, Los Alamos, NM (United States)

2001-07-01

Los Alamos National Laboratory's (LANL's) Plutonium Facility is responsible for a wide variety of actinide processing operations in support of the United States Department of Energy's (DOE's) stockpile stewardship of the nation's nuclear arsenal. Both engineered and administrative controls are used to mitigate hazards inherent in these activities. Nuclear facilities have engineered safety systems that are extensively evaluated and documented, and are monitored regularly for operability and performance. Personnel undergo comprehensive training, including annual recertification of their operations. They must thoroughly understand the hazards involved in their work and the controls that are in place to mitigate those hazards. A series of hazard-control plans and work instructions are used to define and authorize the work that is done. Primary hazards associated with chemicals and radioactive materials are well controlled with minimal risk to the workforce and public. The majority of injuries are physical or ergonomic in nature. In an effort to increase safety awareness and to decrease accidents and incidents, a program focusing on the identification and elimination of unsafe behaviours was initiated. Workers are trained on how to conduct safety observations and given guidance on specific behaviours to note. Observations are structured to have minimal impact upon workload and are shared by the entire workforce. This program has effectively decreased a low accident rate and will make long-term sustainability possible. (author)

Success in behaviour-based safety at Los Alamos National Laboratory's plutonium facility

International Nuclear Information System (INIS)

Wieneke, R.E.; Balkey, J.J.; Kleinsteuber, J.F.

2001-01-01

Los Alamos National Laboratory's (LANL's) Plutonium Facility is responsible for a wide variety of actinide processing operations in support of the United States Department of Energy's (DOE's) stockpile stewardship of the nation's nuclear arsenal. Both engineered and administrative controls are used to mitigate hazards inherent in these activities. Nuclear facilities have engineered safety systems that are extensively evaluated and documented, and are monitored regularly for operability and performance. Personnel undergo comprehensive training, including annual recertification of their operations. They must thoroughly understand the hazards involved in their work and the controls that are in place to mitigate those hazards. A series of hazard-control plans and work instructions are used to define and authorize the work that is done. Primary hazards associated with chemicals and radioactive materials are well controlled with minimal risk to the workforce and public. The majority of injuries are physical or ergonomic in nature. In an effort to increase safety awareness and to decrease accidents and incidents, a program focusing on the identification and elimination of unsafe behaviours was initiated. Workers are trained on how to conduct safety observations and given guidance on specific behaviours to note. Observations are structured to have minimal impact upon workload and are shared by the entire workforce. This program has effectively decreased a low accident rate and will make long-term sustainability possible. (author)

Recent developments in the Los Alamos National Laboratory Plutonium Facility Waste Tracking System-automated data collection pilot project

International Nuclear Information System (INIS)

Martinez, B.; Montoya, A.; Klein, W.

1999-01-01

The waste management and environmental compliance group (NMT-7) at the Los Alamos National Laboratory has initiated a pilot project for demonstrating the feasibility and utility of automated data collection as a solution for tracking waste containers at the Los Alamos National Laboratory Plutonium Facility. This project, the Los Alamos Waste Tracking System (LAWTS), tracks waste containers during their lifecycle at the facility. LAWTS is a two-tiered system consisting of a server/workstation database and reporting engine and a hand-held data terminal-based client program for collecting data directly from tracked containers. New containers may be added to the system from either the client unit or from the server database. Once containers are in the system, they can be tracked through one of three primary transactions: Move, Inventory, and Shipment. Because LAWTS is a pilot project, it also serves as a learning experience for all parties involved. This paper will discuss many of the lessons learned in implementing a data collection system in the restricted environment. Specifically, the authors will discuss issues related to working with the PPT 4640 terminal system as the data collection unit. They will discuss problems with form factor (size, usability, etc.) as well as technical problems with wireless radio frequency functions. They will also discuss complications that arose from outdoor use of the terminal (barcode scanning failures, screen readability problems). The paper will conclude with a series of recommendations for proceeding with LAWTS based on experience to date

Implementing waste minimization at an active plutonium processing facility: Successes and progress at technical area (TA) -55 of the Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Balkey, J.J.; Robinson, M.A.; Boak, J.

1997-12-01

The Los Alamos National Laboratory has ongoing national security missions that necessitate increased plutonium processing. The bulk of this activity occurs at Technical Area -55 (TA-55), the nations only operable plutonium facility. TA-55 has developed and demonstrated a number of technologies that significantly minimize waste generation in plutonium processing (supercritical CO{sub 2}, Mg(OH){sub 2} precipitation, supercritical H{sub 2}O oxidation, WAND), disposition of excess fissile materials (hydride-dehydride, electrolytic decontamination), disposition of historical waste inventories (salt distillation), and Decontamination & Decommissioning (D&D) of closed nuclear facilities (electrolytic decontamination). Furthermore, TA-55 is in the process of developing additional waste minimization technologies (molten salt oxidation, nitric acid recycle, americium extraction) that will significantly reduce ongoing waste generation rates and allow volume reduction of existing waste streams. Cost savings from reduction in waste volumes to be managed and disposed far exceed development and deployment costs in every case. Waste minimization is also important because it reduces occupational exposure to ionizing radiation, risks of transportation accidents, and transfer of burdens from current nuclear operations to future generations.

Implementing waste minimization at an active plutonium processing facility: Successes and progress at technical area (TA) -55 of the Los Alamos National Laboratory

International Nuclear Information System (INIS)

Balkey, J.J.; Robinson, M.A.; Boak, J.

1997-01-01

The Los Alamos National Laboratory has ongoing national security missions that necessitate increased plutonium processing. The bulk of this activity occurs at Technical Area -55 (TA-55), the nations only operable plutonium facility. TA-55 has developed and demonstrated a number of technologies that significantly minimize waste generation in plutonium processing (supercritical CO 2 , Mg(OH) 2 precipitation, supercritical H 2 O oxidation, WAND), disposition of excess fissile materials (hydride-dehydride, electrolytic decontamination), disposition of historical waste inventories (salt distillation), and Decontamination ampersand Decommissioning (D ampersand D) of closed nuclear facilities (electrolytic decontamination). Furthermore, TA-55 is in the process of developing additional waste minimization technologies (molten salt oxidation, nitric acid recycle, americium extraction) that will significantly reduce ongoing waste generation rates and allow volume reduction of existing waste streams. Cost savings from reduction in waste volumes to be managed and disposed far exceed development and deployment costs in every case. Waste minimization is also important because it reduces occupational exposure to ionizing radiation, risks of transportation accidents, and transfer of burdens from current nuclear operations to future generations

Comparative distribution of plutonium in contaminated ecosystems at Oak Ridge, Tennessee, and Los Alamos, New Mexico

International Nuclear Information System (INIS)

Dahlman, R.C.; Garten, C.T. Jr.; Hakonson, T.E.

1980-01-01

The distribution of plutonium was compared in portions of forest ecosystems at Oak Ridge, TN, and Los Alamos, NM, which were contaminated by liquid effluents. Inventories of plutonium in soil at the two sites were generally similar, but a larger fraction of the plutonium was associated with biota at Los Alamos than at Oak Ridge. Most (99.7 to 99.9%) of the plutonium was present in the soil, and very little (0.1 to 0.3%) was in biotic components. Comparative differences in distributions within the two ecosystems appeared to be related to individual contamination histories and greater physical transport of plutonium in soil to biotic surfaces at Los Alamos

Human factors aspects of the major upgrade to control systems at the Los Alamos National Laboratory Plutonium Facility

International Nuclear Information System (INIS)

Higgins, J.; Pope, N.

1997-01-01

The Plutonium Facility (TA-55) at Los Alamos National Laboratory (LANL) has been in operation for over 15 years. It handles projects such as: stockpile maintenance, surveillance, and dismantlement; pit rebuild; plutonium power source fabrication for long duration spacecraft missions (e.g., Cassini); nuclear materials technology research; nuclear materials storage; and remediation of nuclear waste. The Operations Center of TA-55 is the nerve center of the facility where operators are on duty around the clock and monitor several thousand data points using the Facility Control System (FCS). The FCS monitors, displays, alarms, and provides some limited control of the following systems; HVAC, fire detection and suppression, radiation detection, electrical, and other miscellaneous systems. The FCS was originally based on late 1970s digital technology, which is not longer supported by the vendors. Additionally, the equipment failure rates increased notably in the 1990s. Thus, plans were put into place to upgrade and replace the FCS hardware, software, and display components with modernized equipment. The process was complicated by the facts that: the facility was operational and could not be totally closed for the modifications; complete documentation was not available for the existing system; the Safety Analyses for the facility were in the process of being upgraded at the same time; and of course limited time and budgets. This paper will discuss the human factors aspects of the design, installation, and testing of the new FCS within the above noted constraints. Particular items to be discussed include the functional requirements definition, operating experience review, screen designs, test program, operator training, and phased activation of the new circuits in an operational facility

Development of the Los Alamos National Laboratory Plutonium Facility decontamination room

International Nuclear Information System (INIS)

Mosso, J.S.; Smith, F.E.; Owen, M.J.; Treadaway, W.A.

1987-01-01

For several years the Health Protection Group attempted to remedy the problem of a facility to adequately handle personnel plutonium contamination incidents. Through the efforts of our Quality Circle a presentation was made to management, which immediately appropriated space and funds for the construction of a complete decontamination facility. 9 refs

Options for converting excess plutonium to feed for the MOX fuel fabrication facility

Energy Technology Data Exchange (ETDEWEB)

Watts, Joe A [Los Alamos National Laboratory; Smith, Paul H [Los Alamos National Laboratory; Psaras, John D [Los Alamos National Laboratory; Jarvinen, Gordon D [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Joyce, Jr., Edward L [Los Alamos National Laboratory

2009-01-01

The storage and safekeeping of excess plutonium in the United States represents a multibillion-dollar lifecycle cost to the taxpayers and poses challenges to National Security and Nuclear Non-Proliferation. Los Alamos National Laboratory is considering options for converting some portion of the 13 metric tons of excess plutonium that was previously destined for long-term waste disposition into feed for the MOX Fuel Fabrication Facility (MFFF). This approach could reduce storage costs and security ri sks, and produce fuel for nuclear energy at the same time. Over the course of 30 years of weapons related plutonium production, Los Alamos has developed a number of flow sheets aimed at separation and purification of plutonium. Flow sheets for converting metal to oxide and for removing chloride and fluoride from plutonium residues have been developed and withstood the test oftime. This presentation will address some potential options for utilizing processes and infrastructure developed by Defense Programs to transform a large variety of highly impure plutonium into feedstock for the MFFF.

Hazards and accident analyses, an integrated approach, for the Plutonium Facility at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Pan, P.Y.; Goen, L.K.; Letellier, B.C.; Sasser, M.K.

1995-01-01

This paper describes an integrated approach to perform hazards and accident analyses for the Plutonium Facility at Los Alamos National Laboratory. A comprehensive hazards analysis methodology was developed that extends the scope of the preliminary/process hazard analysis methods described in the AIChE Guidelines for Hazard Evaluations. Results fro the semi-quantitative approach constitute a full spectrum of hazards. For each accident scenario identified, there is a binning assigned for the event likelihood and consequence severity. In addition, each accident scenario is analyzed for four possible sectors (workers, on-site personnel, public, and environment). A screening process was developed to link the hazard analysis to the accident analysis. Specifically the 840 accident scenarios were screened down to about 15 accident scenarios for a more through deterministic analysis to define the operational safety envelope. The mechanics of the screening process in the selection of final scenarios for each representative accident category, i.e., fire, explosion, criticality, and spill, is described

Extrinsic and intrinsic complexities of the Los Alamos plutonium processing facility

International Nuclear Information System (INIS)

Bearse, R.C.; Roberts, N.J.; Longmire, V.L.

1985-01-01

Analysis of the data obtained in one year of plutonium accounting at Los Alamos reveals significant complexity. Much of this complexity arises from the complexity of the processes themselves. Additional complexity is induced by errors in the data entry process. It is important to note that there is no evidence that this complexity is adversely affecting the accounting in the plant. The authors have been analyzing transaction data from fiscal year 1983 processing. This study involved 62,595 transactions. The data have been analyzed using the relational database program INGRES on a VAX 11/780 computer. This software allows easy manipulation of the original data and subsets drawn from it. The authors have been attempting for several years to understand the global features of the TA-55 accounting data. This project has underscored several of the system's complexities

Extrinsic and intrinsic complexities of the Los Alamos Plutonium Processing Facility

International Nuclear Information System (INIS)

Bearse, R.C.; Longmire, V.L.; Roberts, N.J.

1985-01-01

Analysis of the data obtained in one year of plutonium accounting at Los Alamos reveals significant complexity. Much of this complexity arises from the complexity of the processes themselves. Additional complexity is induced by errors in the data entry process. It is important to note that there is no evidence that this complexity is adversely affecting the accounting in the plant. We have been analyzing transaction data from fiscal year 1983 processing. This study involved 62,595 transactions. The data have been analyzed using the relational database program INGRES on a VAX 11/780 computer. This software allows easy manipulation of the original data and subsets drawn from it. We have been attempting for several years to understand the global features of the TA-55 accounting data. This project has underscored several of the system's complexities. Examples that will be reported here include audit trails, lot-name multiplicity, etc

Nondestructive assay system development for a plutonium scrap recovery facility

International Nuclear Information System (INIS)

Hsue, S.T.; Baker, M.P.

1984-01-01

A plutonium scrap recovery facility is being constructed at the Savannah River Plant (SRP). The safeguards groups of the Los Alamos National Laboratory have been working since the early design stage of the facility with SRP and other national laboratories to develop a state-of-the-art assay system for this new facility. Not only will the most current assay techniques be incorporated into the system, but also the various nondestructive assay (NDA) instruments are to be integrated with an Instrument Control Computer (ICC). This undertaking is both challenging and ambitious; an entire assay system of this type has never been done before in a working facility. This paper will describe, in particular, the effort of the Los Alamos Safeguards Assay Group in this endeavor. Our effort in this project can be roughly divided into three phases: NDA development, system integration, and integral testing. 6 references

Summary of recent studies of soil plutonium in the Los Alamos and Trinity Site environs

International Nuclear Information System (INIS)

Nyhan, J.W.; Hakonson, T.E.

1976-01-01

The first plutonium was sent to the Los Alamos Scientific Laboratory (LASL) in 1944 from the Oak Ridge and Hanford reactors for use in synthesizing the first atomic bomb, which was subsequently detonated at Trinity Site in New Mexico. During the last 32 years the LASL has developed an outstanding capability in many scientific fields required to support research in weapons technology and in other uses of nuclear energy. The fabrication and experimental activities required for this effort have resulted in additions of plutonium in industrial effluents to Los Alamos soils, just as the Trinity soils received fallout plutonium after the 1945 Trinity detonation. Formal radioecology-soils studies relative to soil-actinide relationships has been mainly field-oriented and complements transuranic research dealing with the biota of several study areas. The current soil actinide research performed within three liquid effluent-receiving areas at Los Alamos and along the fallout pathway of Trinity, the first nuclear detonation, are summarized

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

International Nuclear Information System (INIS)

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

1998-03-01

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

Plutonium metal preparation and purification at Los Alamos, 1984

International Nuclear Information System (INIS)

Christensen, D.C.; Williams, J.D.; McNeese, J.A.; Fife, K.W.

1984-01-01

Plutonium metal preparation and purification are well established at Los Alamos. Metal is prepared by calcothermic reduction of both PuF 4 and PuO 2 . Metal is purified by halide slagging, casting, and electrorefining. The product from the production sequence is ultrapure plutonium metal. All of the processes involve high temperature operation and all but casting involve molten salt media. Development efforts are fourfold: (1) recover plutonium values from residues; (2) reduce residue generation through process improvements and changes; (3) recycle of reagents, and (4) optimize and integrate all processes into a close-loop system. Plutonium residues are comprised of oxides, chlorides, colloidal metal suspensions, and impure metal heels. Pyrochemical recovery techniques are under development to address each residue. In addition, we are looking back at each residue generation step and are making process changes to reduce plutonium content in each residue. Reagent salt is the principle media used in pyrochemical processing. The regeneration and recycle of these reagents will both reduce our waste handling and operating expense. The fourth area, process optimization, involves both existing processes and new process developments. A status of efforts in all four of these areas will be summarized

Waste minimization and the goal of an environmentally benign plutonium processing facility: A strategic plan

International Nuclear Information System (INIS)

Pillay, K.K.S.

1994-02-01

To maintain capabilities in nuclear weapons technologies, the Department of Energy (DOE) has to maintain a plutonium processing facility that meets all the current and emerging standards of environmental regulations. A strategic goal to transform the Plutonium Processing Facility at Los Alamos into an environmentally benign operation is identified. A variety of technologies and systems necessary to meet this goal are identified. Two initiatives now in early stages of implementation are described in some detail. A highly motivated and trained work force and a systems approach to waste minimization and pollution prevention are necessary to maintain technical capabilities, to comply with regulations, and to meet the strategic goal

Review of epidemiologic studies at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Voelz, G.L.; Wilkinson, G.S.; Acquavella, J.F.; Reyes, M.; McInroy, J.F.

1982-01-01

Epidemiologic studies at Los Alamos are directed toward understanding potential health risks associated with activities pertaining to national energy and defense needs. Currently this research focuses on evaluating the effects of plutonium exposure in man. The major programs consist of (1) epidemiologic studies of the incidence of disease and mortality among plutonium and other workers at six Department of Energy (DOE) contractor facilities (Los Alamos, Rocky Flats, Mound, Savannah River, Hanford, and Oak Ridge), and (2) measurement of plutonium and other radionuclides in human tissues. Currently, investigations of mortality for Pantex workers and the surrounding general population are also being conducted for DOE in support of an Environment Impact Statement. This paper places emphasis on the activities of the national epidemiologic study of plutonium workers. The purpose of the plutonium workers study is to: (1) investigate whether adverse health effects are associated with exposures to plutonium, (2) explore whether adverse health effects are associated with exposure to transuranic elements, other radioisotopes, and hazardous substances that are found in nuclear facilities making routine use of plutonium, and (3) to describe in detail the nature of such health effects should they be discovered

Mortality through 1990 among white male workers at the Los Alamos National Laboratory: Considering exposures to plutonium and external ionizing radiation

International Nuclear Information System (INIS)

Wiggs, L.D.; Johnson, E.R.; Cox-DeVore, C.A.; Voelz, G.L.

1994-01-01

A cohort mortality study was conducted of 15,727 white men employed by the Los Alamos National Laboratory, a nuclear research and development facility. Some of the workers at this facility have been exposed to various forms of ionizing radiation and other potentially hazardous materials. These analyses focused on whole-body ionizing radiation exposures and internal depositions of plutonium. The results indicated that overall mortality among this cohort is quite low, even after nearly 30 y of follow-up. No cause of death was significantly elevated among plutonium-exposed workers when compared with their unexposed coworkers; however, a rate ratio for lung cancer of 1.78 (95% CI = 0.79-3.99) was observed. A case of osteogenic sarcoma, a type of cancer related to plutonium exposure in animal studies, was also observed. Dose-response relationships for whole-body dose from external ionizing radiation and tritium were observed for cancers of the brain/central nervous system, the esophagus, and Hodgkin's disease. 34 refs., 1 fig., 7 tabs

Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

International Nuclear Information System (INIS)

Salazar, M.D.

1998-01-01

Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel

Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

Energy Technology Data Exchange (ETDEWEB)

Salazar, M.D.

1998-12-01

Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel.

Distribution of plutonium and cesium in alluvial soils of the Los Alamos environs

International Nuclear Information System (INIS)

Nyhan, J.W.; Miera, F.R. Jr.; Peters, R.J.

1976-01-01

The alluvial soils of three liquid waste disposal areas at Los Alamos were sampled to determine plutonium and cesium distributional relationships and correlations with soil physical-chemical properties. Radionuclide concentrations were determined for soil samples as a function of soil depth and distance from the waste outfall. The cesium-plutonium data were correlated with levels of organic carbon, carbonates, exchangeable and water-soluble cations, pH, cation exchange capacity, bulk density, surface area and geometric particle size of these soils. The distribution patterns of soil plutonium and cesium were also compared to the waste use history of the three study areas

Preparation of fused chloride salts for use in pyrochemical plutonium recovery operations at Los Alamos

Energy Technology Data Exchange (ETDEWEB)

Fife, K.W.; Bowersox, D.F.; Christensen, D.C.; Williams, J.D.

1986-07-01

The Plutonium Metal Technology Group at Los Alamos routinely uses pyrochemical processes to produce and purify plutonium from impure sources. The basic processes (metal production, metal purification, and residue treatment) involve controlling oxidation and reduction reactions between plutonium and its compounds in molten salts. Current production methods are described, as well as traditional approaches and recent developments in the preparation of solvent salts for electrorefining, molten salt extraction, lean metal (pyroredox) purification, and direct oxide reduction.

Preparation of fused chloride salts for use in pyrochemical plutonium recovery operations at Los Alamos

International Nuclear Information System (INIS)

Fife, K.W.; Bowersox, D.F.; Christensen, D.C.; Williams, J.D.

1986-07-01

The Plutonium Metal Technology Group at Los Alamos routinely uses pyrochemical processes to produce and purify plutonium from impure sources. The basic processes (metal production, metal purification, and residue treatment) involve controlling oxidation and reduction reactions between plutonium and its compounds in molten salts. Current production methods are described, as well as traditional approaches and recent developments in the preparation of solvent salts for electrorefining, molten salt extraction, lean metal (pyroredox) purification, and direct oxide reduction

Los Alamos County Fire Department LAFD: TA-55 PF-4 Facility Familiarization Tour, OJT 55260

Energy Technology Data Exchange (ETDEWEB)

Rutherford, Victor Stephen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-07-13

Los Alamos National Laboratory (LANL) will conduct familiarization tours for Los Alamos County Fire Department (LAFD) personnel at the Plutonium Facility (PF-4) at Technical Area (TA)-55. These familiarization tours are official LANL business; the purpose of these tours is to orient the firefighters to the facility so that they can respond efficiently and quickly to a variety of emergency situations. This orientation includes the ingress and egress of the area and buildings, layout and organization of the facility, evacuation procedures and assembly points, and areas of concern within the various buildings at the facility. LAFD firefighters have the skills and abilities to perform firefighting operations and other emergency response tasks that cannot be provided by other LANL personnel who have the required clearance level. This handout provides details of the information, along with maps and diagrams, to be presented during the familiarization tours. The handout will be distributed to the trainees at the time of the tour. A corresponding checklist will also be used as guidance during the familiarization tours to ensure that all required information is presented to LAFD personnel.

Studies on persons exposed to plutonium

International Nuclear Information System (INIS)

Voelz, G.L.; Stebbings, J.H.; Hempelmann, L.H.; Haxton, L.K.; York, D.A.

1978-01-01

The results of four studies of persons exposed, or potentially exposed, to plutonium are summarized. The studies are: a five-year update on clinical examinations and health experience of 26 Manhattan District workers heavily exposed at Los Alamos in 1944 to 1945; a 30-year mortality follow-up of 224 white male workers with plutonium body burdens of 10 nCi or more; a review of cancer mortality rates between 1950 and 1969 among Los Alamos County, New Mexico, male residents, all of whom have worked in or have lived within a few kilometers of a major plutonium plant and other nuclear facilities; and a review of cancer incidence rates between 1969 and 1974 in male residents of Los Alamos County. No excess of mortality due to any cause was observed in the 224 male subjects with the highest plutonium exposures at Los Alamos. Clinical examinations of the Manhattan District workers, whose average age in 1976 was 56 years, show them to be active persons with diseases that are not unusual for their ages. The two deaths in this group over the past 30 years have not been due to cancer. Mortality and incidence data indicate no excess of lung cancer in Los Alamos County males

In-line measurement of plutonium and americium in mixed solutions

International Nuclear Information System (INIS)

Li, T.K.

1981-01-01

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 5 g/L within a 2000-s count time

An MCNP model of glove boxes in a plutonium processing facility

International Nuclear Information System (INIS)

Dooley, D.E.; Kornreich, D.E.

1998-01-01

Nuclear material processing usually occurs simultaneously in several glove boxes whose primary purpose is to contain radioactive materials and prevent inhalation or ingestion of radioactive materials by workers. A room in the plutonium facility at Los Alamos National Laboratory has been slated for installation of a glove box for storing plutonium metal in various shapes during processing. This storage glove box will be located in a room containing other glove boxes used daily by workers processing plutonium parts. An MCNP model of the room and glove boxes has been constructed to estimate the neutron flux at various locations in the room for two different locations of the storage glove box and to determine the effect of placing polyethylene shielding around the storage glove box. A neutron dose survey of the room with sources dispersed as during normal production operations was used as a benchmark to compare the neutron dose equivalent rates calculated by the MCNP model

Final environmental assessment: TRU waste drum staging building, Technical Area 55, Los Alamos National Laboratory

International Nuclear Information System (INIS)

1996-01-01

Much of the US Department of Energy's (DOE's) research on plutonium metallurgy and plutonium processing is performed at Los Alamos National Laboratory (LANL), in Los Alamos, New Mexico. LANL's main facility for plutonium research is the Plutonium Facility, also referred to as Technical Area 55 (TA-55). The main laboratory building for plutonium work within the Plutonium Facility (TA-55) is the Plutonium Facility Building 4, or PF-4. This Environmental Assessment (EA) analyzes the potential environmental effects that would be expected to occur if DOE were to stage sealed containers of transuranic (TRU) and TRU mixed waste in a support building at the Plutonium Facility (TA-55) that is adjacent to PF-4. At present, the waste containers are staged in the basement of PF-4. The proposed project is to convert an existing support structure (Building 185), a prefabricated metal building on a concrete foundation, and operate it as a temporary staging facility for sealed containers of solid TRU and TRU mixed waste. The TRU and TRU mixed wastes would be contained in sealed 55-gallon drums and standard waste boxes as they await approval to be transported to TA-54. The containers would then be transported to a longer term TRU waste storage area at TA-54. The TRU wastes are generated from plutonium operations carried out in PF-4. The drum staging building would also be used to store and prepare for use new, empty TRU waste containers

Preventing pollution from plutonium processing

International Nuclear Information System (INIS)

Pillay, K.K.S.

1993-01-01

The plutonium processing facility at Los Alamos has adopted the strategic goal of becoming a facility that processes plutonium in a way that produces only environmentally benign waste streams. Pollution prevention through source reduction and environmentally sound recycling are being pursued. General approaches to waste reductions are administrative controls, modification of process technologies, and additional waste polishing. Recycling of waste materials, such as spent acids and salts, are technical possibilities and are being pursued to accomplish additional waste reduction. Liquid waste stream polishing to remove final traces of plutonium and hazardous chemical constituents is accomplished through (a) process modifications, (b) use of alternative chemicals and sorbents for residue removal, (c) acid recycling, and (d) judicious use of a variety of waste polishing technologies. Technologies that show promise in waste minimization and pollution prevention are identified. Working toward this goal of pollution prevention is a worthwhile endeavor, not only for Los Alamos, but for the Nuclear Complex of the future

Preventing pollution from plutonium processing

International Nuclear Information System (INIS)

Pillay, K.K.S.

1995-01-01

The plutonium processing facility at Los Alamos has adopted the strategic goal of becoming a facility that processes plutonium in a way that produces only environmentally benign waste streams. Pollution prevention through source reduction and environmentally sound recycling are being pursued. General approaches to waste reductions are administrative controls, modification of process technologies, and additional waste polishing. Recycling of waste materials, such as spent acids and salts, are technical possibilities and are being pursued to accomplish additional waste reduction. Liquid waste stream polishing to remove final traces of plutonium and hazardous chemical constituents is accomplished through process modifications, use of alternative chemicals and sorbents for residue removal, acid recycling, and judicious use of a variety of waste polishing technologies. Technologies that show promise in waste minimization and pollution prevention are identified. Working toward this goal of pollution prevention is a worthwhile endeavor , not only for Los Alamos, but for the Nuclear Complex of the future. (author) 12 refs.; 2 figs

Customer service model for waste tracking at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Dorries, Alison M.; Montoya, Andrew J.; Ashbaugh, Andrew E.

2010-01-01

The deployment of any new software system in a production facility will always face multiple hurtles in reaching a successful acceptance. However, a new waste tracking system was required at the plutonium processing facility at Los Alamos National Laboratory (LANL) where waste processing must be integrated to handle Special Nuclear Materials tracking requirements. Waste tracking systems can enhance the processing of waste in production facilities when the system is developed with a focus on customer service throughout the project life cycle. In March 2010 Los Alamos National Laboratory Waste Technical Services (WTS) replaced the aging systems and infrastructure that were being used to support the plutonium processing facility. The Waste Technical Services (WTS) Waste Compliance and Tracking System (WCATS) Project Team, using the following customer service model, succeeded in its goal to meet all operational and regulatory requirements, making waste processing in the facility more efficient while partnering with the customer.

A Study of the Stability and Characterization Plutonium Dioxide and Chemical Characterization [of] Rocky Flats and Los Alamos Plutonium-Containing Incinerator Ash

International Nuclear Information System (INIS)

Ray, A.K.; Boettger, J.C.; Behrens, Robert G.

1999-01-01

In the presentation ''A Study of the Stability and Characterization of Plutonium Dioxide'', the authors discuss their recent work on actinide stabilities and characterization, in particular, plutonium dioxide PuO 2 . Earlier studies have indicated that PuO 2 has the fluorite structure of CaF 2 and typical oxide semiconductor properties. However, detailed results on the bulk electronic structure of this important actinide oxide have not been available. The authors have used all-electron, full potential linear combinations Gaussian type orbitals fitting function (LCGTO-FF) method to study PuO 2 . The LCGTO-FF technique characterized by its use of three independent GTO basis sets to expand the orbitals, charge density, and exchange-correlation integral kernels. Results will be presented on zero pressure using both the Hedin-Lundquist local density approximation (LDA) model or the Perdew-Wang generalized gradient approximation (GGA) model. Possibilities of different characterizations of PuO 2 will be explored. The paper ''Chemical Characterization Rocky Flats and Los Alamos Plutonium-Containing Incinerator Ash'' describes the results of a comprehensive study of the chemical characteristics of virgin, calcined and fluorinated incinerator ash produced at the Rocky Flats Plant and at the Los Alamos National Laboratory prior to 1988. The Rocky Flats and Los Alamos virgin, calcined, and fluorinated ashes were also dissolved using standard nitrate dissolution chemistry. Corresponding chemical evaluations were preformed on the resultant ash heel and the results compared with those of the virgin ash. Fluorination studies using FT spectroscopy as a diagnostic tool were also performed to evaluate the chemistry of phosphorus, sulfur, carbon, and silicon containing species in the ash. The distribution of plutonium and other chemical elements with the virgin ash, ash heel, fluorinated ash, and fluorinated ash heel particulates were studied in detail using microprobe analysis. Some

Mortality study of Los Alamos workers with higher exposures to plutonium

International Nuclear Information System (INIS)

Voelz, G.L.; Wilkinson, G.S.; Healy, J.W.; McInroy, J.F.; Tietjen, G.L.

1983-01-01

A group of white male workers with the highest internal depositions of plutonium at the Los Alamos National Laboratory was selected in 1974 for a study of mortality. This group of 224 persons includes all those with an estimated deposition (in 1974) of 10 nanocuries or more of plutonium, principally 239 Pu but also in some cases 238 Pu. Follow-up of these workers is 100% complete through 1980. Smoking histories were obtained on all persons. Exposure histories for external radiation and plutonium were reviewed for each subject. Standardized mortality ratios (SMR) were calculated using rates for white males in the United States population, adjusted for age and year of death. SMRs are low for all causes of death (56; 95% CI 40, 75) or for all malignant neoplasms (54; 95% CI 23,106). Cancers of interest for plutonium exposures, including cancers of bone, lung, liver, and bone marrow/lymphatic systems, were infrequent or absent. The absence of a detectable excess of cancer deaths is consistent with the low calculated risk to these workers using current radiation risk coefficients. An alternate theory that suggests much higher risk of lung cancer due to synergistic effects of smoking and inhaled insoluble plutonium particles is not supported by this study

Seismic qualification of equipment for the TA-55 Plutonium Processing Facility

International Nuclear Information System (INIS)

Pellette, P.R.; Endebrock, E.G.; Giles, P.M.; Shaw, R.H.

1977-04-01

The techniques employed by the Los Alamos Scientific Laboratory (LASL) for the seismic qualification of internal equipment for the TA-55 Plutonium Facility are discussed. The structural analysis of the plutonium building and critical associated structures was performed by the Architect-Engineer (A-E), and the calculations were checked by LASL. The specifications and procedures used by LASL produced dramatic improvement in the responses by qualified vendors to the seismic requirements. There was an increase from about a 20% bid ratio to greater than 90% because prospective vendors could be competitive without having had previous seismic experience with their equipment. The equipment seismic qualification for TA-55 is in compliance with the Code of Federal Regulations, Nuclear Regulatory Commission (NRC) Guides, Energy Research and Development Administration (ERDA) Manual Chapters and Appendices, and Institute of Electrical and Electronic Engineers (IEEE) Standard 344

Los Alamos racquetball contamination incident

International Nuclear Information System (INIS)

McAtee, J.L.; Stafford, R.G.; Dowdy, E.J.; Prestwood, R.J.

1985-01-01

Several employees of the Los Alamos Plutonium Facility were found to have low levels of radioactivity on their hands and clothing when they arrived for work one morning. The initial concern was that the stringent contamination or material controls at the facility had failed, and that one or more of the employees had either accidentally or intentionally removed plutonium from the Laboratory premises. Fortunately, however, an investigation revealed that the source of the radioactivity was radon daughters electrostatically collected upon the surface of the racquetball and transferred by physical contact to the employees during an early morning racquetball game. This paper describes the events leading to the discovery of this phenomenon. 1 figure

Destructive analysis capabilities for plutonium and uranium characterization at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Tandon, Lav; Kuhn, Kevin J.; Drake, Lawrence R.; Decker, Diana L.; Walker, Laurie F.; Colletti, Lisa M.; Spencer, Khalil J.; Peterson, Dominic S.; Herrera, Jaclyn A.; Wong, Amy S.

2010-01-01

Los Alamos National Laboratory's (LANL) Actinide Analytical Chemistry (AAC) group has been in existence since the Manhattan Project. It maintains a complete set of analytical capabilities for performing complete characterization (elemental assay, isotopic, metallic and non metallic trace impurities) of uranium and plutonium samples in different forms. For a majority of the customers there are strong quality assurance (QA) and quality control (QC) objectives including highest accuracy and precision with well defined uncertainties associated with the analytical results. Los Alamos participates in various international and national programs such as the Plutonium Metal Exchange Program, New Brunswick Laboratory's (NBL' s) Safeguards Measurement Evaluation Program (SME) and several other inter-laboratory round robin exercises to monitor and evaluate the data quality generated by AAC. These programs also provide independent verification of analytical measurement capabilities, and allow any technical problems with analytical measurements to be identified and corrected. This presentation will focus on key analytical capabilities for destructive analysis in AAC and also comparative data between LANL and peer groups for Pu assay and isotopic analysis.

Transport and deposition of plutonium-contaminated sediments by fluvial processes, Los Alamos Canyon, New Mexico

International Nuclear Information System (INIS)

Graf, W.L.

1996-01-01

Between 1945 and 1952 the development of nuclear weapons at Los Alamos National Laboratory, New Mexico, resulted in the disposal of plutonium into the alluvium of nearby Acid and (to a lesser degree) DP Canyons. The purpose of this paper is to explore the connection between the disposal sites and the main river, a 20 km link formed by the fluvial system of Acid, Pueblo, DP, and Los Alamos Canyons. Empirical data from 15 yr of annual sediment sampling throughout the canyon system has produced 458 observations of plutonium concentration in fluvial sediments. These data show that, overall, mean plutonium concentrations in fluvial sediment decline from 10,000 fCi/g near the disposal area to 100 fCi/g at the confluence of the canyon system and the Rio Grande. Simulations using a computer model for water, sediment, and plutonium routing in the canyon system show that discharges as large as the 25 yr event would fail to develop enough transport capacity to completely remove the contaminated sediments from Pueblo Canyon. Lesser flows would move some materials to the Rio Grande by remobilization of stored sediments. The simulations also show that the deposits and their contaminants have a predictable geography because they occur where stream power is low, hydraulic resistance is high, and the geologic and/or geomorphic conditions provide enough space for storage. 38 refs., 13 figs., 1 tab

Independent Review of Siesmic Performance Assessments for the Plutonium Facility PF-4

Energy Technology Data Exchange (ETDEWEB)

Whittaker, Andrew [State Univ. of New York (SUNY), Buffalo, NY (United States); Goen, Lawrence Kenneth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kennedy, Robert [RPK Structural Mechanics, San Diego, CA (United States); McDonald, Brian [Exponent, Los Angeles, CA (United States); Morgan, Troy [Exponent, Los Angeles, CA (United States); Wyllie, Loring [Degenkolb Engineers, San Francisco, CA (United States)

2015-11-25

The Plutonium Facility, designated PF-4, is located in Technical Area 55 at the Los Alamos National Laboratory (LANL). The facility is a one-story rectangular structure above a complete basement; the building was constructed of cast-in-place reinforced concrete, with small interior frames of structural steel. The plan dimensions of the building are 265’×284’. The overall height of the building varies between 39’-0” at the north and south ends, and 40’-6” at the center ridge. The programmatic work performed in the building is vital to our national security and its functions and storage purposes are not replicated elsewhere in the United States Department of Energy (DOE).

Plutonium metal burning facility

International Nuclear Information System (INIS)

Hausburg, D.E.; Leebl, R.G.

1977-01-01

A glove-box facility was designed to convert plutonium skull metal or unburned oxide to an oxide acceptable for plutonium recovery and purification. A discussion of the operation, safety aspects, and electrical schematics are included

Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume 2, Appendix B, Part 3: Los Alamos National Laboratory site assessment team report

International Nuclear Information System (INIS)

1994-09-01

Environmental safety and health (ES and H) vulnerabilities are defined as conditions or weaknesses that may lead to unnecessary or increased radiation exposure of the workers, release of radioactive materials to the environment, or radiation exposure of the public. In response to the initiative by the Secretary of Energy, Los Alamos National Laboratory (LANL) has performed a self assessment of the ES and H vulnerabilities of plutonium inventories at the laboratory. The objective of this site-specific self assessment is to identify and report ES and H vulnerabilities associated with the storage, handling, and processing of plutonium and maintenance of plutonium-contaminated facilities. This self-assessment of ES and H vulnerabilities and validation by a peer group is not another compliance audit or fault-finding exercise. It has a fact finding mission to develop a database of potential environment, safety, and health vulnerabilities that may lead to unnecessary or increased radiation exposure of the workers, release of radioactive materials to the environment, or radiation exposure of the public

Ventilation design modifications at Los Alamos Scientific Laboratory major plutonium operational areas

International Nuclear Information System (INIS)

Stafford, R.G.; Gallimore, J.C. Jr.; Mitchell, R.N.; Maraman, W.J.; McNeese, W.D.

1975-01-01

Major ventilation design modifications in plutonium operational areas at Los Alamos have occurred during the past two years. An additional stage of HEPA filters has been added to DP West glove-box process exhaust resulting in significant effluent reductions. The additional stage of HEPA filters is unique in that each filter may be individually DOP tested. Radiological filter efficiencies of each process exhaust stage is presented. DP West room air ventilation systems have been modified to incorporate a single stage of HEPA filters in contrast to a previous American Air Filter PL-24 filtration system. Plutonium effluent reductions of 10 2 to 10 3 have resulted in these new systems. Modified DOP testing procedures for room air filtration systems are discussed. Major plutonium areas of the CMR Building utilizing Aerosolve 95 process exhaust filtration systems have been upgraded with two stages of HEPA filters. Significant reductions in effluent are evident. A unique method of DOP testing each bank of HEPA filters is discussed. Radiological efficiencies of both single and two-stage filters are discussed. (U.S.)

Recent trends of plutonium facilities and their control

Energy Technology Data Exchange (ETDEWEB)

Muto, T [Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works

1974-02-01

Much interest has been focussed on Pu recycle since the oil crisis because of an expected shortage of enriched uranium. Plutonium handling techniques and plutonium fuel fabricating facilities should be developed to meet the future demand of plutonium, but the radioactive property of plutonium to be reprocessed from spent fuel and recycled plutonium is remarkably different, and it has to be handled safely. Technical criteria for plutonium facilities are specified in the USAEC regulatory guides and other rules. Some of these criteria are location condition, quality of confinement, protection against accidents and so on. The control conditions for plutonium facilities are exposure control, criticality control, measurement control and new system of safeguard. These problems are under development to meet the future requirement for the safe handling of Pu material.

Nuclear criticality safety aspects of emergency response at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

Baker, J.S.

2003-01-01

Emergency response at Los Alamos National Laboratory (LANL) is handled through a graded approach depending on the specific emergency situation . LANL maintains a comprehensive capability to respond to events ranging from minor facility events (alerts) through major community events (general emergencies), including criticality accidents . Criticality safety and emergency response apply to all activities involving significant quantities of fissile material at LANL, primarily at Technical Area 18 (TA-18, the Los Alamos Critical Experiments Facility) and Technical Area 55 (TA-55, the Plutonium Facility). This discussion focuses on response to a criticality accident at TA-55; the approach at TA-18 is comparable .

Automation of process accountability flow diagrams at Los Alamos National Laboratory's Plutonium Facility

International Nuclear Information System (INIS)

Knepper, P.; Whiteson, R.; Strittmatter, R.; Mousseau, K.

1999-01-01

Many industrial processes (including reprocessing activities; nuclear fuel fabrication; and material storage, measurement and transfer) make use of process flow diagrams. These flows can be used for material accountancy and for data analysis. At Los Alamos National Laboratory (LANL), the Technical Area (TA)-55 Plutonium Facility is home to various research and development activities involving the use of special nuclear material (SNM). A facility conducting research and development (R and D) activities using SNM must satisfy material accountability guidelines. All processes involving SNM or tritium processing, at LANL, require a process accountability flow diagram (PAFD). At LANL a technique was developed to generate PAFDs that can be coupled to a relational database for use in material accountancy. These techniques could also be used for propagation of variance, measurement control, and inventory difference analysis. The PAFD is a graphical representation of the material flow during a specific process. PAFDs are currently stored as PowerPoint files. In the PowerPoint format, the data captured by the PAFD are not easily accessible. Converting the PAFDs to an accessible electronic format is desirable for several reasons. Any program will be able to access the data contained in the PAFD. For the PAFD data to be useful in applications such as an expert system for data checking, SNM accountability, inventory difference evaluation, measurement control, and other kinds of analysis, it is necessary to interface directly with the information contained within the PAFD. The PAFDs can be approved and distributed electronically, eliminating the paper copies of the PAFDs and ensuring that material handlers have the current PAFDs. Modifications to the PAFDs are often global. Storing the data in an accessible format would eliminate the need to manually update each of the PAFDs when a global change has occurred. The goal was to determine a software package that would store the

Ventilation design for new plutonium recovery facility

International Nuclear Information System (INIS)

Oliver, A.J.; Amos, C.L.

1975-01-01

In 1972 the Atomic Energy Commission (AEC) issued revised guidelines on ''Minimum Design Criteria for New Plutonium Facilities.'' With these criteria as guidelines, a new Plutonium Recovery Facility is being designed and constructed at the AEC Rocky Flats Plant. The methods by which the confinement of contamination and air treatment are being handled in this facility are described. (U.S.)

Accumulation and transport of soil plutonium in liquid waste discharge areas at Los Alamos

International Nuclear Information System (INIS)

Hakonson, T.E.; Nyhan, J.W.; Purtymun, W.D.

1975-01-01

Plutonium inventory estimates for the upper 12.5 cm of sediment in Mortandad Canyon, Los Alamos, New Mexico, did not reflect all the Pu added to the canyon during a 7 month interval. The methods used in this study indicate that about 2 mCi 238 Pu and 0 mCi 239 ' 240 Pu were added to the canyon during the interval compared with known additions of 5.5 mCi 238 Pu and 0.4 mCi 239 ' 240 Pu. The discrepancy likely was the result of the large sampling variability indicating that inventory changes in this order (i.e. up to 17 percent) are not detectable with any certainty. However, factors other than sampling variability may be involved, including losses of plutonium to depths exceeding 12.5 cm

Geomorphology of plutonium in the Northern Rio Grande

Energy Technology Data Exchange (ETDEWEB)

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

1993-03-01

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.

Geomorphology of plutonium in the Northern Rio Grande

International Nuclear Information System (INIS)

Graf, W.L.

1993-03-01

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

Matrix Characterization of Plutonium Residues by Alpha-Particle Self-Interrogation

International Nuclear Information System (INIS)

Prettyman, T.H.; Foster, L.A.; Staples, P.

1998-01-01

Legacy plutonium residues often have inadequate item descriptions. Nondestructive characterization can help segregate these items for reprocessing or provide information needed for disposal or storage. Alpha particle-induced gamma-ray spectra contain a wealth of information that can be used for matrix characterization. We demonstrate how this information can be used for item identification. Gamma-ray spectra were recorded at the Los Alamos Plutonium Facility from a variety of legacy, plutonium-processing residues and product materials. The comparison and analysis of these spectra are presented

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

Energy Technology Data Exchange (ETDEWEB)

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

2010-01-01

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

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

International Nuclear Information System (INIS)

Cournoyer, Michael E.; Nixon, Archie E.; Dodge, Robert L.; Fife, Keith W.; Sandoval, Arnold M.; Garcia, Vincent E.

2010-01-01

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

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

International Nuclear Information System (INIS)

Cournoyer, Michael E.; Nixon, Archie E.; Fife, Keith W.; Sandoval, Arnold M.; Garcia, Vincent E.; Dodge, Robert L.

2011-01-01

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 Actinide Processing Group at TA-55 uses one-meter or longer 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 glovebox as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste volume generation by almost 2½ 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

Design of an integrated non-destructive plutonium assay facility

International Nuclear Information System (INIS)

Moore, C.B.

1984-01-01

The Department of Energy requires improved technology for nuclear materials accounting as an essential part of new plutonium processing facilities. New facilities are being constructed at the Savannah River Plant by the Du Pont Company, Operating Contractor, to recover plutonium from scrap and waste material generated at SRP and other DOE contract processing facilities. This paper covers design concepts and planning required to incorporate state-of-the-art plutonium assay instruments developed at several national laboratories into an integrated, at-line nuclear material accounting facility operating in the production area. 3 figures

Computerized plutonium laboratory-stack monitoring system

International Nuclear Information System (INIS)

Stafford, R.G.; DeVore, R.K.

1977-01-01

The Los Alamos Scientific Laboratory has recently designed and constructed a Plutonium Research and Development Facility to meet design criteria imposed by the United States Energy Research and Development Administration. A primary objective of the design criteria is to assure environmental protection and to reliably monitor plutonium effluent via the ventilation exhaust systems. A state-of-the-art facility exhaust air monitoring system is described which establishes near ideal conditions for evaluating plutonium activity in the stack effluent. Total and static pressure sensing manifolds are incorporated to measure average velocity and integrated total discharge air volume. These data are logged at a computer which receives instrument data through a multiplex scanning system. A multipoint isokinetic sampling assembly with associated instrumentation is described. Continuous air monitors have been designed to sample from the isokinetic sampling assembly and transmit both instantaneous and integrated stack effluent concentration data to the computer and various cathode ray tube displays. The continuous air monitors also serve as room air monitors in the plutonium facility with the primary objective of timely evacuation of personnel if an above tolerance airborne plutonium concentration is detected. Several continuous air monitors are incorporated in the ventilation system to assist in identification of release problem areas

CHARACTERIZATION OF CURRENTLY GENERATED TRANUSRANIC WASTE AT THE LOS ALAMOS NATIONAL LABORATORY'S PLUTONIUM PRODUCTION FACILITY

International Nuclear Information System (INIS)

Dodge, Robert L.; Montoya, Andy M.

2003-01-01

By the time the Waste Isolation Pilot Plant (WIPP) completes its Disposal Phase in FY 2034, the Department of Energy (DOE) will have disposed of approximately 109,378 cubic meters (m3) of Transuranic (TRU) waste in WIPP (1). If DOE adheres to its 2005 Pollution Prevention Goal of generating less than 141m3/yr of TRU waste, approximately 5000 m3 (4%) of that TRU waste will be newly generated (2). Because of the overwhelming majority (96%) of TRU waste destined for disposal at WIPP is legacy waste, the characterization and certification requirements were developed to resolve those issues related to legacy waste. Like many other DOE facilities Los Alamos National Laboratory (LANL) has a large volume (9,010m3) of legacy Transuranic Waste in storage (3). Unlike most DOE facilities LANL will generate approximately 140m3 of newly generated TRU waste each year3. LANL's certification program was established to meet the WIPP requirements for legacy waste and does not take advantage of the fundamental differences in waste knowledge between newly generated and legacy TRU waste

Detection and measurement of gamma-ray self-attenuation in plutonium residues

International Nuclear Information System (INIS)

Prettyman, T.H.; Foster, L.A.; Estep, R.J.

1996-01-01

A new method to correct for self-attenuation in gamma-ray assays of plutonium is presented. The underlying assumptions of the technique are based on a simple but accurate physical model of plutonium residues, particularly pyrochemical salts, in which it is assumed that the plutonium is divided into two portions, each of which can be treated separately from the standpoint of gamma-ray analysis: a portion that is in the form of plutonium metal shot; and a dilute portion that is mixed with the matrix. The performance of the technique is evaluated using assays of plutonium residues by tomographic gamma scanning at the Los Alamos Plutonium Facility. The ability of the method to detect saturation conditions is examined

Decontamination and demolition of a former plutonium processing facility's process exhaust system, firescreen, and filter plenum buildings

International Nuclear Information System (INIS)

LaFrate, P.J. Jr.; Stout, D.S.; Elliott, J.W.

1996-01-01

The Los Alamos National Laboratory (LANL) Decommissioning Project has decontaminated, demolished, and decommissioned a process exhaust system, two filter plenum buildings, and a firescreen plenum structure at Technical Area 21 (TA-2 1). The project began in August 1995 and was completed in January 1996. These high-efficiency particulate air (HEPA) filter plenums and associated ventilation ductwork provided process exhaust to fume hoods and glove boxes in TA-21 Buildings 2 through 5 when these buildings were active plutonium and uranium processing and research facilities. This paper summarizes the history of TA-21 plutonium and uranium processing and research activities and provides a detailed discussion of integrated work process controls, characterize-as-you-go methodology, unique engineering controls, decontamination techniques, demolition methodology, waste minimization, and volume reduction. Also presented in detail are the challenges facing the LANL Decommissioning Project to safely and economically decontaminate and demolish surplus facilities and the unique solutions to tough problems. This paper also shows the effectiveness of the integrated work package concept to control work through all phases

Decontamination and demolition of a former plutonium processing facility's process exhaust system, firescreen, and filter plenum buildings

International Nuclear Information System (INIS)

LaFrate, P.J. Jr.; Stout, D.S.; Elliott, J.W.

1996-01-01

The Los Alamos National Laboratory (LANL) Decommissioning Project has decontaminated, demolished, and decommissioned a process exhaust system, two filter plenum buildings, and a firescreen plenum structure at Technical Area 21 (TA-21). The project began in August 1995 and was completed in January 1996. These high-efficiency particulate air (HEPA) filter plenums and associated ventilation ductwork provided process exhaust to fume hoods and glove boxes in TA-21 Buildings 2 through 5 when these buildings were active plutonium and uranium processing and research facilities. This paper summarizes the history of TA-21 plutonium and uranium processing and research activities and provides a detailed discussion of integrated work process controls, characterize-as-you-go methodology, unique engineering controls, decontamination techniques, demolition methodology, waste minimization, and volume reduction. Also presented in detail are the challenges facing the LANL Decommissioning Project to safely and economically decontaminate and demolish surplus facilities and the unique solutions to tough problems. This paper also shows the effectiveness of the integrated work package concept to control work through all phases

233-S Plutonium Concentration Facility data quality objectives

International Nuclear Information System (INIS)

Encke, D.B.

1996-08-01

This document is a summary of the decision-making associated with the Data Quality Objective process that pertains to the characterization activities in the 233-S Plutonium Concentration Facility at the Hanford Site in Richland, Washington. The 233-S Plutonium Concentration Facility is located adjacent to, and north of, the REDOX Plant. The facility was used to concentrate the plutonium nitrate product solution from the REDOX facility. The 233-S Pipe Gallery, Control Room, SWP Change Room, Toilet, Equipment Room and the Electrical Cubicle are currently scheduled for decontamination and cleanout to support future demolition (D and D). Identification of the radiological contamination and presence of hazardous materials is needed to allow for disposal of the D and D debris

Guide to good practices at plutonium facilities

International Nuclear Information System (INIS)

Faust, L.G.; Brackenbush, L.W.; Carter, L.A.; Endres, G.W.R.; Glenn, R.D.; Jech, J.J.; Selby, J.M.; Smith, R.C.; Waite, D.A.; Walsh, W.P.

1977-09-01

This manual establishes guidelines and principles for use in setting up a sound radiation protection program for work with plutonium. The guidance presented is based on the experiences of Energy Research and Development Administration (ERDA) contractors and those portions of private industry concerned with the operation of plutonium facilities, specifically with the fabrication of mixed oxide reactor fuel. The manual is directed primarily to those facilities which have as their sole purpose the handling of large quantities of plutonium for military or industrial uses. It is not intended for use by facilities engaged in reactor or chemical separation operations nor for partial or occasional use by analytical laboratories; while these facilities would find the manual beneficial, it would be incomplete for their needs. The manual addresses good practices that should be observed by management, staff and designers, since the benefits of a good radiation protection program are the result of their joint efforts. Methods for the diagnostic evaluation of internally deposited Pu are included

Los Alamos Critical Assemblies Facility

International Nuclear Information System (INIS)

Malenfant, R.E.

1981-06-01

The Critical Assemblies Facility of the Los Alamos National Laboratory has been in existence for thirty-five years. In that period, many thousands of measurements have been made on assemblies of 235 U, 233 U, and 239 Pu in various configurations, including the nitrate, sulfate, fluoride, carbide, and oxide chemical compositions and the solid, liquid, and gaseous states. The present complex of eleven operating machines is described, and typical applications are presented

Systems work for Plutonium Fuel Production Facility (PFPF) near-real-time accounting

International Nuclear Information System (INIS)

Picard, R.R.; Hafer, J.F.; Pillay, K.K.S.; Takahashi, S.; Ohtani, T.; Eguchi, K.; Seya, M.

1990-01-01

A joint effort by the Los Alamos National Laboratory and the Power Reactor and Nuclear Fuel Development Corporation of Japan examines materials accounting for the Plutonium Fuel Production Facility. A unique feature of the systems work is a sophisticated data generator. This software follows individual items throughout the process, creating detailed data files for variance propagation. The data generator deals with user-specified process operations and handles related accounting problems, such as the tracking of individual measurements through numerous blending and splitting procedure, frequent decay correction (important for large inventories), scrap recovery, and automated determination of static inventory. There is no need to rely on simplified assumptions regarding process operation and material measurement. Also, the joint study applies recent theoretical work on stratified inspection of nonhomogeneous inventories and sequential analysis of MUF -- D. 4 refs

Los Alamos transuranic waste size reduction facility

International Nuclear Information System (INIS)

Briesmeister, A.; Harper, J.; Reich, B.; Warren, J.L.

1982-01-01

To facilitate disposal of transuranic (TRU) waste, Los Alamos National Laboratory designed and constructed the Size Reduction Facility (SRF) during the period 1977 to 1981. This report summarizes the engineering development, installation, and early test operations of the SRF. The facility incorporates a large stainless steel enclosure fitted with remote handling and cutting equipment to obtain an estimated 4:1 volume reduction of gloveboxes and other bulky metallic wastes

Los Alamos transuranic waste size reduction facility

International Nuclear Information System (INIS)

Briesmeister, A.; Harper, J.; Reich, B.; Warren, J.L.

1982-01-01

A transuranic (TRU) Waste Size Reduction Facility (SRF) was designed and constructed at the Los Alamos National Laboratory during the period of 1977 to 1981. This paper summarizes the engineering development, installation, and early test operations of the SRF. The facility incorporates a large stainless steel enclosure fitted with remote handling and cutting equipment to obtain an estimated 4:1 volume reduction of gloveboxes and other bulky metallic wastes

Health physics manual of good practices for plutonium facilities. [Contains glossary

Energy Technology Data Exchange (ETDEWEB)

Brackenbush, L.W.; Heid, K.R.; Herrington, W.N.; Kenoyer, J.L.; Munson, L.F.; Munson, L.H.; Selby, J.M.; Soldat, K.L.; Stoetzel, G.A.; Traub, R.J.

1988-05-01

This manual consists of six sections: Properties of Plutonium, Siting of Plutonium Facilities, Facility Design, Radiation Protection, Emergency Preparedness, and Decontamination and Decommissioning. While not the final authority, the manual is an assemblage of information, rules of thumb, regulations, and good practices to assist those who are intimately involved in plutonium operations. An in-depth understanding of the nuclear, physical, chemical, and biological properties of plutonium is important in establishing a viable radiation protection and control program at a plutonium facility. These properties of plutonium provide the basis and perspective necessary for appreciating the quality of control needed in handling and processing the material. Guidance in selecting the location of a new plutonium facility may not be directly useful to most readers. However, it provides a perspective for the development and implementation of the environmental surveillance program and the in-plant controls required to ensure that the facility is and remains a good neighbor. The criteria, guidance, and good practices for the design of a plutonium facility are also applicable to the operation and modification of existing facilities. The design activity provides many opportunities for implementation of features to promote more effective protection and control. The application of ''as low as reasonably achievable'' (ALARA) principles and optimization analyses are generally most cost-effective during the design phase. 335 refs., 8 figs., 20 tabs.

Evaluation of the neutron self-interrogation approach for assay of plutonium in high materials

International Nuclear Information System (INIS)

Russo, P.A.; Menlove, H.O.; Fife, K.W.; West, M.H.

1987-01-01

The pyrochemical scrap recovery processes, designed to extract impurities from plutonium metal and compounds, generate a variety of plutonium-laden residues consisting of high (α,n) matrices of varying chemical composition, and often containing grams to tens of grams of americium. For such materials, multiplication corrections based on real neutron coincidence count rate, R, and total neutron count rate, T, measurements cannot be applied because of the large, unknown, and variable (α,n) component in the total neutron emission rate. A study of the prototype self-interrogation assay method is in progress at the Los Alamos plutonium facility. In the self-interrogation approach, the assay signature R(IF)/T is a function of effective fissile plutonium content, where R(IF) is the induced fission component of the measured reals rate, and T is the measured, (α,n)-dominated totals rate. The present study includes a calibration effort using standards consisting of mixtures of PuO 2 and PuF 4 in a salt-strip matrix. The neutron measurements of the standards and the process materials have been performed at the Los Alamos Plutonium Facility. The precision and accuracy of the self-interrogation method applied to pyrochemical residues is examined in this study

The Pajarito Site operating procedures for the Los Alamos Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.

1991-12-01

Operating procedures consistent with DOE Order 5480.6, and the American National Standard Safety Guide for the Performance of Critical Experiments are defined for the Los Alamos Critical Experiments Facility (LACEF) of the Los Alamos National Laboratory. These operating procedures supersede and update those previously published in 1983 and apply to any criticality experiment performed at the facility. 11 refs

Comparative distribution of plutonium in contaminated ecosystems at Oak Ridge, Tennessee and Los Alamos, New Mexico

International Nuclear Information System (INIS)

Dahlman, R.C.; Garten, C.T. Jr.; Hakonson, T.E.

1977-04-01

Most of the plutonium entering aquatic and terrestrial ecosystems of the United States originates from nuclear weapons testing and from the burnup of the SNAP-9A satellite power source (Hanson 1975). But in the future, local ecosystems may receive small quantities of Pu released from nuclear facilities such as those at Oak Ridge, Los Alamos and other sites. The purpose of this paper is to compare and contrast the distribution of Pu in two contaminated ecosystems which are representative of humid and semi-arid environments of the United States. Results summarized in terms of inventories for the respective ecosystems several decades after initial contamination are used to anticipate the longer term (i.e., decades or centuries) behavior of Pu in the environment. One important question is whether the availability of this element to plants and other organisms will change after it is subjected to weathering and ecological processes of the environment. It is pointed out that potential radiological toxicity and long physical half-lives of Pu dictate that its behavior in ecosystems be understood

Comparative distribution of plutonium in contaminated ecosystems at Oak Ridge, Tennessee and Los Alamos, New Mexico

Energy Technology Data Exchange (ETDEWEB)

Dahlman, R.C.; Garten, C.T. Jr.; Hakonson, T.E.

1977-04-01

Most of the plutonium entering aquatic and terrestrial ecosystems of the United States originates from nuclear weapons testing and from the burnup of the SNAP-9A satellite power source (Hanson 1975). But in the future, local ecosystems may receive small quantities of Pu released from nuclear facilities such as those at Oak Ridge, Los Alamos and other sites. The purpose of this paper is to compare and contrast the distribution of Pu in two contaminated ecosystems which are representative of humid and semi-arid environments of the United States. Results summarized in terms of inventories for the respective ecosystems several decades after initial contamination are used to anticipate the longer term (i.e., decades or centuries) behavior of Pu in the environment. One important question is whether the availability of this element to plants and other organisms will change after it is subjected to weathering and ecological processes of the environment. It is pointed out that potential radiological toxicity and long physical half-lives of Pu dictate that its behavior in ecosystems be understood.

National Plutonium Workers' Study: considerations and preliminary results

International Nuclear Information System (INIS)

Acquavella, J.F.; Wilkinson, G.S.

1983-03-01

The National Plutonium Workers' Study developed from the clinical follow-up of workers with body burdens in excess of 10 nCi. The importance of plutonium to energy and weapons development and the uncertainty about its biological effects motivated the formation of an epidemiologic study of more than 125,000 workers at six Department of Energy facilities. This report reviews recent results from The National Plutonium Workers' Study, including an analysis of cancer mortality among workers at the Rocky Flats Plant and a study of malignant melanoma among employees at Los Alamos National Laboratory. The problems inherent in large-scale epidemiologic studies, as well as the future directions for the study, are discussed

Metering management at the plutonium research and development facilities

International Nuclear Information System (INIS)

Hirata, Masaru; Miyamoto, Fujio; Kurosawa, Makoto; Abe, Jiro; Sakai, Haruyuki; Suzuki, Tsuneo.

1996-01-01

Nuclear fuel research laboratory of the Oarai Research Laboratory of the Japan Atomic Energy Research Institute is an R and D facility to treat with plutonium and processes various and versatile type samples in chemical and physical form for use of various experimental researches even though on much small amount. Furthermore, wasted and plutonium samples are often transported to other KMP and MBA such as radioactive waste management facility, nuclear reactor facility and so forth. As this facility is a place to treat plutonium important on the safeguards, it is a facility necessary for detection and allowance actions and for detail managements on the metering management data to report to government and IAEA in each small amount sample and different configuration. In this paper, metering management of internationally regulated matters and metering management system using a work station newly produced in such small scale facility were introduced. (G.K.)

Accountability control system in plutonium fuel facility

International Nuclear Information System (INIS)

Naruki, Kaoru; Aoki, Minoru; Mizuno, Ohichi; Mishima, Tsuyoshi

1979-01-01

More than 30 tons of plutonium-uranium mixed-oxide fuel have been manufactured at the Plutonium Facility in PNC for JOYO, FUGEN and DCA (Deuterium Critical Assembly) and for the purpose of irradiation tests. This report reviews the nuclear material accountability control system adopted in the Plutonium Facility. Initially, the main objective of the system was the criticality control of fissible materials at various stages of fuel manufacturing. The first part of this report describes the functions and the structure of the control system. A flow chart is provided to show the various stages of material flow and their associated computer files. The system is composed of the following three sub-systems: procedures of nuclear material transfer; PIT (Physical Inventory Taking); data retrieval, report preparation and file maintenance. OMR (Optical Mark Reader) sheets are used to record the nuclear material transfer. The MUF (Materials Unaccounted For) are evaluated by PIT every three months through computer processing based on the OMR sheets. The MUF ratio of Pu handled in the facility every year from 1966 to 1977 are presented by a curve, indicating that the MUF ratio was kept well under 0.5% for every project (JOYO, FUGEN, and DCA). As for the Pu safeguards, the MBA (Material Balance Area) and the KMP (Key Measurement Point) in the facility of PNC are illustrated. The general idea of the projected PINC (Plutonium Inventory Control) system in PNC is also shortly explained. (Aoki, K.)

R.4. Innovative concept for plutonium finishing facility

International Nuclear Information System (INIS)

Bertolotti, G.; Laguerie, I.V. de; Richter, R.; Gillet, B.

1998-01-01

After complete shutdown of the units of the previous UP2 plant, the new R4 facility will ensure the purification of Plutonium of the UP2-800 plant for the whole range of fuel to be reprocessed in the years to come. This facility features four main units: - Purification of plutonium nitrate; - Conversion into plutonium oxide; - PuO 2 conditioning into cans; Acid recovery. An extensive R and D program resulted in significant innovations. From a technological aspect the centrifugal extractor and the sub-critical tube bundle tank contributed to the reduction of the building dimensions. The extensive use of on-line analyses enables a more efficient follow-up of the process while minimizing the effluent production. On the other hand, the organization of the building which consists in grouping the rooms presenting the same risk of dispersal of nuclear materials also contributed to reduce the active zone volume. This facility, as any other facilities on the LA HAGUE site, will be remotely operated. (author)

An autoradiographical method using an imaging plate for the analyses of plutonium contamination in a plutonium handling facility

International Nuclear Information System (INIS)

Takasaki, Koji; Sagawa, Naoki; Kurosawa, Shigeyuki; Mizuniwa, Harumi

2011-01-01

An autoradiographical method using an imaging plate (IP) was developed to analyze plutonium contamination in a plutonium handling facility. The IPs were exposed to ten specimens having a single plutonium particle. Photostimulated luminescence (PSL) images of the specimens were taken using a laser scanning machine. One relatively large spot induced by α-radioactivity from plutonium was observed in each PSL image. The plutonium-induced spots were discriminated by a threshold derived from background and the size of the spot. A good relationship between the PSL intensities of the spots and α-radioactivities measured using a radiation counter was obtained by least-square fitting, taking the fading effect into consideration. This method was applied to workplace monitoring in an actual uranium-plutonium mixed oxide (MOX) fuel fabrication facility. Plutonium contaminations were analyzed in ten other specimens having more than two plutonium spots. The α-radioactivities of plutonium contamination were derived from the PSL images and their relative errors were evaluated from exposure time. (author)

The influence of plutonium concentration and solution flow rate on the effective capacity of macroporous anion exchange resin

International Nuclear Information System (INIS)

Marsh, S.F.; Gallegos, T.D.

1987-07-01

The principal aqueous process used to recover and purify plutonium at the Los Alamos Plutonium Facility is anion exchange in nitric acid. Previous studies with gel-type anion exchange resin have shown an inverse relationship between plutonium concentration in the feed solution and the optimum flow rate for this process. Because gel-type resin has been replaced with macroporous resin at Los Alamos, the relationship between plutonium concentration and solution flow rate was reexamined with the selected Lewatit MP-500-FK resin using solutions of plutonium in nitric acid and in nitric acid with high levels of added nitrate salts. Our results with this resin differ significantly from previous data obtained with gel-type resin. Flow-rate variation from 10 to 80 liters per hour had essentially no effect on the measured quantities of plutonium sorbed by the macroporous resin. However, the effect of plutonium concentration in the feed solutions was pronounced, as feed solutions that contained the highest concentrations of plutonium also produced the highest resin loadings. The most notable effect of high concentrations of dissolved nitrate salts in these solutions was an increased resin capacity for plutonium at low flow rates. 16 refs., 7 figs., 2 tabs

Skeletons in the closet: Implementation of the packaging program at Los Alamos

International Nuclear Information System (INIS)

Ricketts, T.E.

1997-11-01

In May 1994, The Defense Nuclear Facility Safety Board (DNFSB) issued recommendation 94-1 to the Secretary of Energy indicating the need for improved remediation efforts within the defense nuclear facilities complex. The primary concern was for the safety of the workers, the public, and the environment as a result of improperly stabilized and packaged fissile materials. The DNFSB recommended that an integrated plan be formulated to convert the identified materials to forms or conditions suitable for safe interim storage. In addition, the DNFSB recommended that plutonium metal and oxides (> 50 weight-percent plutonium) be stabilized and packaged in accordance with the criteria stated in the DOE storage standard (DOE-STD-3013). In response to the recommendations, DOE requested input from all the defense-related sites and as a result, individual Site Integrated Stabilization and Management Plans (SISMP) were established. The following 2 milestones are identified in the Los Alamos SISMP: (1) stabilize high-risk vault items and recover the plutonium as oxide for packaging to meet the long-term storage standard by September 1997; (2) stabilize the remaining residue inventory and recover the plutonium as oxide. Repackage the existing plutonium metal and oxide (> 50% plutonium assay) for long-term storage by May 2002

Design of plutonium processing facilities

International Nuclear Information System (INIS)

Derbyshire, W.; Sills, R.J.

1982-01-01

Five considerations for the design of plutonium processing facilities are identified. These are: Toxicity, Radiation, Criticality, Containment and Remote Operation. They are examined with reference to reprocessing spent nuclear fuel and application is detailed both for liquid and dry processes. (author)

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

International Nuclear Information System (INIS)

French, Sean B.; Shuman, Robert

2012-01-01

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.

Interim Storage of Plutonium in Existing Facilities

International Nuclear Information System (INIS)

Woodsmall, T.D.

1999-01-01

'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

Decommissioning and Decontamination Program: Battelle Plutonium Facility, Environmental assessment

International Nuclear Information System (INIS)

1979-09-01

This assessment describes the decontamination of Battelle-Columbus Plutonium Facility and removal from the site of all material contamination which was associated with or produced by the Plutonium Facility. Useable uncontaminated material will be disposed of by procedures normally employed in scrap declaration and transfer. Contaminated waste will be transported to approved radioactive waste storage sites. 5 refs., 1 fig

Facility effluent monitoring plan determinations for the 200 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-11-01

The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

Minimum Analytical Chemistry Requirements for Pit Manufacturing at Los Alamos National Laboratory; TOPICAL

International Nuclear Information System (INIS)

Moy, Ming M.; Leasure, Craig S.

1998-01-01

Analytical chemistry is one of several capabilities necessary for executing the Stockpile Stewardship and Management Program at Los Alamos National Laboratory (LANL). Analytical chemistry capabilities reside in the Chemistry Metallurgy Research (CMR) Facility and Plutonium Facility (TA-55). These analytical capabilities support plutonium recovery operations, plutonium metallurgy, and waste management. Analytical chemistry capabilities at both nuclear facilities are currently being configured to support pit manufacturing. This document summarizes the minimum analytical chemistry capabilities required to sustain pit manufacturing at LANL. By the year 2004, approximately$16 million will be required to procure analytical instrumentation to support pit manufacturing. In addition,$8.5 million will be required to procure glovebox enclosures. An estimated 50% increase in costs has been included for installation of analytical instruments and glovebox enclosures. However, no general and administrative (G and A) taxes have been included. If an additional 42.5/0 G and A tax were to be incurred, approximately$35 million would be required over the next five years to prepare analytical chemistry to support a 50-pit-per-year manufacturing capability by the year 2004

Plutonium metal exchange program : current status and statistical analysis

Energy Technology Data Exchange (ETDEWEB)

Tandon, L. (Lav); Eglin, J. L. (Judith Lynn); Michalak, S. E. (Sarah E.); Picard, R. R.; Temer, D. J. (Donald J.)

2004-01-01

The Rocky Flats Plutonium (Pu) Metal Sample Exchange program was conducted to insure the quality and intercomparability of measurements such as Pu assay, Pu isotopics, and impurity analyses. The Rocky Flats program was discontinued in 1989 after more than 30 years. In 2001, Los Alamos National Laboratory (LANL) reestablished the Pu Metal Exchange program. In addition to the Atomic Weapons Establishment (AWE) at Aldermaston, six Department of Energy (DOE) facilities Argonne East, Argonne West, Livermore, Los Alamos, New Brunswick Laboratory, and Savannah River are currently participating in the program. Plutonium metal samples are prepared and distributed to the sites for destructive measurements to determine elemental concentration, isotopic abundance, and both metallic and nonmetallic impurity levels. The program provides independent verification of analytical measurement capabilies for each participating facility and allows problems in analytical methods to be identified. The current status of the program will be discussed with emphasis on the unique statistical analysis and modeling of the data developed for the program. The discussion includes the definition of the consensus values for each analyte (in the presence and absence of anomalous values and/or censored values), and interesting features of the data and the results.

Status of the pit disassembly and conversion facility

International Nuclear Information System (INIS)

Wood, Warren T.; Christensen, Lowell T.

2000-01-01

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 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 at LANL. The Los Alamos National Laboratory is the lead for technical design oversight of the PDCF. Technical data gained from the ARIES demonstrations is integral for the proper design of the PDCF

Tritium handling facilities at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Anderson, J.L.; Damiano, F.A.; Nasise, J.E.

1975-01-01

A new tritium facility, recently activated at the Los Alamos Scientific Laboratory, is described. The facility contains a large drybox, associated gas processing system, a facility for handling tritium gas at pressures to approximately 100 MPa, and an effluent treatment system which removes tritium from all effluents prior to their release to the atmosphere. The system and its various components are discussed in detail with special emphasis given to those aspects which significantly reduce personnel exposures and atmospheric releases. (auth)

Progress at LAMPF [Los Alamos Meson Physics Facility], January-December 1987

International Nuclear Information System (INIS)

Poelakker, K.

1988-09-01

This report is the annual progress report of MP Division of the Los Alamos National Laboratory. Included are brief reports on research done at LAMPF by researchers from other institutions and other Los Alamos Divisions. These reports included the following topics: Nuclear and particle physics; Atomic and molecular physics; Materials science; Radiation-effects studies; Biomedical research and instrumentation; Nuclear chemistry; Radioisotope production and accelerator facilities development and operation

A vision for environmentally conscious plutonium processing

International Nuclear Information System (INIS)

Avens, L.R.; Eller, P.G.; Christensen, D.C.; Miller, W.L.

1998-01-01

Regardless of individual technical and political opinions about the uses of plutonium, it is virtually certain that plutonium processing will continue on a significant global scale for many decades for the purposes of national defense, nuclear power and remediation. An unavoidable aspect of plutonium processing is that radioactive contaminated gas, liquid, and solid streams are generated. These streams need to be handled in a manner that is not only in full compliance with today's laws,but also will be considered environmentally and economically responsible now and in the future. In this regard, it is indeed ironic that the multibillion dollar and multidecade radioactive cleanup mortgage that the US Department of Energy (and its Russian counterpart) now owns resulted from waste management practices that were at the time in full legal compliance. The theme of this paper is that recent dramatic advances in actinide science and technology now make it possible to drastically minimize or even eliminate the problematic waste streams of traditional plutonium processing operations. Advanced technology thereby provides the means to avoid passing on to our children and grandchildren significant environmental and economic legacies that traditional processing inevitably produces. This paper will describe such a vision for plutonium processing that could be implemented fully within five years at a facility such as the Los Alamos Plutonium Facility (TA55). As a significant bonus, even on this short time scale, the initial technology investment is handsomely returned in avoided waste management costs

A probabilistic risk assessment of the LLNL Plutonium facility's evaluation basis fire operational accident

International Nuclear Information System (INIS)

Brumburgh, G.

1994-01-01

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

Plutonium production story at the Hanford site: processes and facilities history

Energy Technology Data Exchange (ETDEWEB)

Gerber, M.S., Westinghouse Hanford

1996-06-20

This document tells the history of the actual plutonium production process at the Hanford Site. It contains five major sections: Fuel Fabrication Processes, Irradiation of Nuclear Fuel, Spent Fuel Handling, Radiochemical Reprocessing of Irradiated Fuel, and Plutonium Finishing Operations. Within each section the story of the earliest operations is told, along with changes over time until the end of operations. Chemical and physical processes are described, along with the facilities where these processes were carried out. This document is a processes and facilities history. It does not deal with the waste products of plutonium production.

Aqueous nitrate flowsheet optimization and enhancement using the ATLAS facility

International Nuclear Information System (INIS)

Schreiber, S.B.; Punjak, W.A.; Yarbro, S.L.

1993-08-01

The Advanced Testing Line for Actinide Separations (ATLAS) is a pilot plant of all aqueous nitrate plutonium recovery and purification operations within the Los Alamos Plutonium Facility. The main unit operations include dissolution, anion exchange, precipitations, evaporation, calcination, and waste stream polishing. In the current political environment, the emphasis has been redirected from the traditional goal of recovering a pure plutonium product to that of generating ''clean'' effluents while placing the plutonium into a form suitable for long term storage. The ATLAS facility is uniquely suited to fulfill this new role in the development and demonstration of new or revisited technologies. This report summarizes recent work in equipment improvements to the batch dissolver, an evaluation of homogeneous hydroxide precipitations, a demonstration of nitric acid recycle, and the preparation of neptunium and plutonium standards

Status of 241Am recovery and purification at Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Ramsey, H.D.; Clifton, D.G.; Hayter, S.W.; Penneman, R.A.; Christensen, E.L.

1980-01-01

Americium recovery was initiated at Los Alamos Scientific Laboratory (LASL) in the late 1940's. The early procedures separated gram quantities of americium from large amounts of impurities including plutonium and the rare earths. Ion exchange procedures were developed for further purification. Until recently, no routine processing of americium has been done at LASL for several years. The increasing demand for americium in oil-well logging instruments and other uses led LASL to develop and install a process to recover larger quantities of americium. The LASL process was developed around the chemistry of americium that had been elucidated both at LASL and at other facilities. Presently, the americium feed is obtained as a by-product from a plutonium purification process at the new plutonium facility at LASL. This feed filtrate from a peroxide precipitation process is precipitated as a slurry of hydroxides, filtered, dissolved in nitric acid, and passed through an anion exchange column to remove any residual plutonium. The americium, contained in the effluent, is precipitated as the oxalate and calcined to the oxide. Americium is also available in other highly salted acidic process streams. These should lend themselves to solvent extraction. Developmental work has been promising, and a dibutyl butyl phosphate-kerosene extraction process is being brought on-line

Seismic safety of the LLL plutonium facility (Building 332)

International Nuclear Information System (INIS)

Torkarz, F.J.; Shaw, G.

1980-01-01

This report states the basis for the Lawrence Livermore Laboratory's assurance to the public that the plutonium operations at the Laboratory pose essentially no risk to anyone's health or safety, either under normal circumstances or in the event of an earthquake or a fire. The report is intended for a general audience, and so for the most part it is not highly technical. It summarizes the steps taken to ensure the seismic safety of the plutonium facility (Bldg. 332). It describes plutonium and its potential hazard and how the facility copes with that hazard. It recounts the geologic investigations and interpretations that led to the design-basis earthquake (DBE) for the Livermore site, and presents a summary analysis of the facility structure in relation to the DBE. An appendix presents a quantitative calculation of the health risk to the public associated with the worst-case hypothetical fire. The document supports the conclusions that the facility will continue to function safely after the maximum earthquake ground motion to which it may be subjected and that there is no evidence of a potential for surface offset under it

A vision for environmentally conscious plutonium processing

International Nuclear Information System (INIS)

Avens, L.R.; Eller, P.G.; Christensen, D.C.; Miller, W.L.

1998-01-01

Regardless of individual technical and political opinions about the uses of plutonium, it is virtually certain that plutonium processing will continue on a significant global scale for many decades for the purposes of national defense, nuclear power, and remediation. An unavoidable aspect of plutonium processing is that radioactively contaminated gas, liquid, and solid waste streams are generated. These streams need to be handled in a manner that not only is in full compliance with today's laws but also will be considered environmentally and economically responsible now and in the future. In this regard, it is indeed ironic that the multibillion dollar and multidecade radioactive cleanup mortgage that the US Department of Energy (and its Russian counterpart) now owns resulted from waste management practices that were at the time in full legal compliance. It is now abundantly evident that in the long run, these practices have proven to be neither environmentally nor economically sound. Recent dramatic advances in actinide science and technology now make it possible to drastically minimize or even eliminate the problematic waste streams of traditional plutonium processing operations. Advanced technology thereby provides the means to avoid passing on to children and grandchildren significant environmental and economic legacies that traditional processing inevitably produces. The authors describe such a vision for plutonium processing that could be implemented fully within 5 yr at a facility such as the Los Alamos National Laboratory Plutonium Facility (TA55). As a significant bonus, even on this short timescale, the initial technology investment is handsomely returned in avoided waste management costs

Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume II, part 3: Los Alamos National Laboratory working group assessment team report

International Nuclear Information System (INIS)

1994-09-01

The Los Alamos National Laboratory (LANL) was established in 1943 with its sole mission to develop a fission bomb. Since that time, the mission of the Laboratory has expanded to include not only the primary one of nuclear weapon stockpile stewardship, but also one that supports energy, biomedical, environmental, and physical research. As part of the Laboratory's primary and diverse missions, many forms of plutonium materials are used and stored. Over the years of production and use of plutonium at Department of Energy (DOE) sites, some events have occurred that were unexpected and that have resulted in environmental, safety, and/or health concerns. Some of these events have led to improvements that will preclude these concerns from arising again. However, the end of the cold war and the expansion of the Laboratory mission have introduced the possibility of new vulnerabilities

Los Alamos Transuranic Waste Size Reduction Facility

International Nuclear Information System (INIS)

Harper, J.; Warren, J.

1987-06-01

The Los Alamos Transuranic (TRU) Waste Size Reduction Facility (SRF) is a production oriented prototype. The facility is operated to remotely cut and repackage TRU contaminated metallic wastes (e.g., glove boxes, ducting and pipes) for eventual disposal at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The resulting flat sections are packaged into a tested Department of Transportation Type 7A metal container. To date, the facility has successfully processed stainless steel glove boxes (with and without lead shielding construction) and retention tanks. We have found that used glove boxes generate more cutting fumes than do unused glove boxes or metal plates - possibly due to deeply embedded chemical residues from years of service. Water used as a secondary fluid with the plasma arc cutting system significantly reduces visible fume generation during the cutting of used glove boxes and lead-lined glove boxes. 2 figs., 1 tab

Weapons Engineering Tritium Facility, Building 205, Technical Area 16: Los Alamos National Laboratory, Los Alamos, New Mexico

International Nuclear Information System (INIS)

1991-04-01

The Weapons Engineering Tritium Facility (WETF) was planned by the US Department of Energy (DOE) to retain at Los Alamos National Laboratory the capability of repackaging small quantities of tritium to exacting specifications. Small quantities of tritium are required for energy research and development activities and for research on nuclear weapons test devices carried out as part of the laboratory mission. The WETF is an improved design proposed to replace an aging Los Alamos facility where tritium has been repackaged for many years. This Environmental Assessment evaluates the environmental consequences to be expected from operating the new facility, for which construction was completed in 1984, compared with those from continuing to operate the old facility. The document was prepared for compliance with NEPA. In operation, the WETF will incorporate state-of-the-art systems for containing tritium in glove boxes and capturing any tritium released into the glove box exhaust system and the laboratory atmosphere. Liquid discharges from the WETF would contain less than 1% of the tritium found in effluents from the present facility. Effluent streams would be surface discharges and would not enter the aquifer from which municipal water supplies are drawn. The quantity of solid radioactive waste generated at the WETF would be approximately the same as that generated at the present facility. The risk to the public from normal tritium-packaging operations would be significantly less from the WETF than from the present facility. The proposed action will reduce the adverse environmental impacts caused by tritium repackaging by substantially reducing the amount of tritium that escapes to the environment. 35 refs., 3 figs., 21 tabs

Towards an advanced hadron facility at Los Alamos

International Nuclear Information System (INIS)

Thiessen, H.A.

1988-01-01

In the 1987 workshop, it was pointed out that activation of the accelerator is a serious problem. At this workshop, it was suggested that a new type of slow extraction system is needed to reduce the activation. We report on the response to this need. The Los Alamos plan is reviewed including as elements the long lead-time R and D in preparation for a 1993 construction start, a menu of accelerator designs, improved losses at injection and extraction time, active participation in the development of PSR, and accelerated hardware R and D program, and close collaboration with TRIUMF. We review progress on magnets and power supplies, on ceramic vacuum chambers, and on ferrite-turned rf systems. We report on the plan for a joint TRIUMF-Los Alamos main-ring cavity to be tested in PSR in 1989. The problem of beam losses is discussed in detail and a recommendation for a design procedure for the injection system is made. This recommendation includes taking account of single Coulomb scattering, a painting scheme for minimizing foil hits, and a collimator and dump system for containing the expected spills. The slow extraction problem is reviewed and progress on an improved design is discussed. The problem of designing the accelerators for minimum operation and maintenance cost is briefly discussed. The question of the specifications for an advanced hadron facility is raised and it is suggested that the Los Alamos Proposal of a dual energy machine - 1.6 GeV and 60 GeV - is a better match to the needs of the science program than the single-energy proposals made elsewhere. It is suggested that design changes need be made in all of the world's hadron facility proposals to prepare for high-intensity operation

Los Alamos Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.

1991-01-01

The Critical Experiments Facility of the Los Alamos National Laboratory has been in existence for 45 years. In that period of time, thousands of measurements have been made on assemblies containing every fissionable material in various configurations that included bare metal and compounds of the nitrate, sulfate, fluoride, carbide, and oxide. Techniques developed or applied include Rossi-α, source-jerk, rod oscillator, and replacement measurements. Many of the original measurements of delay neutrons were performed at the site, and a replica of the Hiroshima weapon was operated at steady state to assist in evaluating the relative biological effectiveness (RBE) of neutrons. Solid, liquid, and gas fissioning systems were run at critical. Operation of this original critical facility has demonstrated the margin of safety that can be obtained through remote operation. Eight accidental excursions have occurred on the site, ranging from 1.5 x 10 16 to 1.2 x 10 17 fissions, with no significant exposure to personnel or damage to the facility beyond the machines themselves -- and in only one case was the machine damaged beyond further use. The present status of the facility, operating procedures, and complement of machines will be described in the context of programmatic activity. New programs will focus on training, validation of criticality alarm systems, experimental safety assessment of process applications, and dosimetry. Special emphasis will be placed on the incorporation of experience from 45 years of operation into present procedures and programs. 3 refs

Technical report for generic site add-on facility for plutonium polishing

International Nuclear Information System (INIS)

1998-06-01

The purpose of this report is to provide environmental data and reference process information associated with incorporating plutonium polishing steps (dissolution, impurity removal, and conversion to oxide powder) into the genetic-site Mixed-Oxide Fuel Fabrication Facility (MOXFF). The incorporation of the plutonium polishing steps will enable the removal of undesirable impurities, such as gallium and americium, known to be associated with the plutonium. Moreover, unanticipated impurities can be removed, including those that may be contained in (1) poorly characterized feed materials, (2) corrosion products added from processing equipment, and (3) miscellaneous materials contained in scrap recycle streams. These impurities will be removed to the extent necessary to meet plutonium product purity specifications for MOX fuels. Incorporation of the plutonium polishing steps will mean that the Pit Disassembly and Conversion Facility (PDCF) will need to produce a plutonium product that can be dissolved at the MOXFF in nitric acid at a suitable rate (sufficient to meet overall production requirements) with the minimal usage of hydrofluoric acid, and its complexing agent, aluminum nitrate. This function will require that if the PDCF product is plutonium oxide powder, that powder must be produced, stored, and shipped without exceeding a temperature of 600 C

A proposal for a Los Alamos international facility for transmutations (LIFT)

International Nuclear Information System (INIS)

Venneri, F.; Williamson, M.A.; Li, Ning; Doolen, G.

1996-01-01

The major groups engaged in transmutation research are converging towards a common objective and similar technology. It is now possible to envision an international program of research aimed at the destruction of reactor-generated (and other) nuclear waste using a series of multipurpose experimental facilities in the near future. Los Alamos National Laboratory, as the home of the highest power LINAC and a very active transmutation technology project, is the ideal host for the first of such facilities. The next step in the international program (a facility 10 times more powerful, for engineering-scale demonstrations) could be built in Europe, where there is substantial interest in the construction of such a device in the framework of international cooperation. A series of experiments at Las Alamos could explore the key transmutation technologies. Liquid lead loops, a liquid lead spallation target, and a large size liquid lead facility with provision for irradiation, cooling and diagnostics of several types of 'transmutation assemblies', where different transmutation concepts will be tested in different media and environments, from transmutation of fission products to destruction by fission of higher actinides, to other waste management applications. The engineering-scale facility, which will follow the initial testing phase, will extend the best concepts to full scale implementation

Shuffler calibration and measurement of mixtures of uranium and plutonium TRU-waste in a plant environment

International Nuclear Information System (INIS)

Hurd, J.R.

1998-01-01

The active-passive shuffler installed and certified a few years ago in Los Alamos National Laboratory's plutonium facility has now been calibrated for different matrices to measure Waste Isolation Pilot Plant (WIPP)-destined transuranic (TRU)-waste. Little or no data presently exist for these types of measurements in plant environments where there may be sudden large changes in the neutron background radiation which causes distortions in the results. Measurements and analyses of twenty-two 55-gallon drums, consisting of mixtures of varying quantities of uranium and plutonium, have been recently completed at the plutonium facility. The calibration and measurement techniques, including the method used to separate out the plutonium component, will be presented and discussed. Particular attention will be directed to those problems identified as arising from the plant environment. The results of studies to quantify the distortion effects in the data will be presented. Various solution scenarios will be indicated, along with those adopted here

Los Alamos Transuranic Waste Size Reduction Facility

International Nuclear Information System (INIS)

Harper, J.; Warren, J.

1987-01-01

The Los Alamos Transuranic (TRU) Waste Size Reduction Facility (SRF) is a production oriented prototype completed in 1981 and later modified during 1986 to enhance production. The facility is operated to remotely cut (with a plasma arc torch) and repackage TRU contaminated metallic wastes (e.g., glove boxes, ducting and pipes) for eventual disposal at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The resulting flat sections are packaged into a tested Department of Transportation Type 7A metal container. To date, the facility has successfully processed stainless steel glove boxes (with and without lead shielding construction) and retention tanks. It was found that used glove boxes generate more cutting fumes than do unused glove boxes or metal plates - possibly due to deeply embedded chemical residues from years of service. Water used as a secondary fluid with the plasma arc cutting system significantly reduces visible fume generation during the cutting of used glove boxes and lead-lined glove boxes

Dismantlement and decontamination of a plutonium-238 facility at SRS

International Nuclear Information System (INIS)

Smith, R.H. Jr.; Hootman, H.E.

1994-01-01

There has been very little, documented decontamination and decommissioning (D ampersand D) experience on which to project cleanup costs and schedules for plutonium facilities at SRS and other DOE sites. A portion of the HB-Line, a plutonium-238 processing facility at SRS, has been undergoing D ampersand D intermittently since 1984. Although this cleanup effort was not originally intended to quantify results, some key data have been project has demonstrated effective methods of accumulated, and the performing D ampersand D work, and has demonstrated cleanup equipment and techniques under conditions of high contamination. Plutonium facilities where D ampersand D is already underway provide an opportunity for' timely field testing of characterization, size reduction, and decontamination techniques. Some data are presented here; however, more specific tests and data may be obtained during the remainder of this project. This project has been recommended as a candidate test facility for a DOE planned ''Integrated D ampersand D Demonstration'' managed by EM-50 to develop and demonstrate technology for D ampersand D and surplus facilities deactivation. Both the remainder of this project and the Integrated D ampersand D Demonstration Program can benefit from a joint effort, and the, overall costs should be reduced

Disposition of TA-33-21, a plutonium contaminated experimental facility

International Nuclear Information System (INIS)

Cox, E.J.; Garde, R.; Valentine, A.M.

1975-01-01

The report discusses the decontamination, demolition and disposal of a plutonium contaminated experimental physics facility which housed physics experiments with plutonium from 1951 until 1960. The results of preliminary decontamination efforts in 1960 are reported along with health physics, waste management, and environmental aspects of final disposition work accomplished during 1974 and 1975. (auth)

PROJECT EXPERIENCE REPORT DEMOLITION OF HANFORDS 233-S PLUTONIUM CONCENTRATION FACILITY

International Nuclear Information System (INIS)

BERLIN, G.T.; ORGILL, T.K.

2004-01-01

This report provides a summary of the preparation, operations, innovative work practices, and lessons learned associated with demolition of the 2334 Plutonium Concentration Facility. This project represented the first open-air demolition of a highly-contaminated plutonium facility at the Hanford Site. This project may also represent the first plutonium facility in the US. Department of Energy (DOE) complex to have been demolished without first decontaminating surfaces to near ''free release'' standards. Demolition of plutonium contaminated structures, if not properly managed, can subject cleanup personnel and the environment to significant risk. However, with proper sequencing and innovative use of commercially available equipment, materials, and services, this project demonstrated that a plutonium processing facility can be demolished while avoiding the need to perform extensive decontamination or to construct large enclosures. This project utilized an excavator with concrete shears, diamond circular saws, water misting and fogging equipment, commercially available fixatives and dust suppressants, conventional mobile crane and rigging services, and near real-time modeling of meteorological and radiological conditions. Following a significant amount of preparation, actual demolition of the 233-S Facility began in October 2003 and was completed in late April 2004. The knowledge and experience gained on this project are important to the Hanford Site as additional plutonium processing facilities are scheduled for demolition in the near future. Other sites throughout the DOE Complex may also be faced with similar challenges. Numerous innovations and effective work practices were implemented on this project. Accordingly, a series of ''Lessons Learned and Innovative Practices Fact Sheets'' were developed and are included as an appendix to this report. This collection of fact sheets is not intended to capture every innovative work practice and lesson learned, but rather

PROJECT EXPERIENCE REPORT DEMOLITION OF HANFORDS 233-S PLUTONIUM CONCENTRATION FACILITY

International Nuclear Information System (INIS)

BERLIN, G.T.

2004-01-01

This report provides a summary of the preparation, operations, innovative work practices, and lessons learned associated with demolition of the 2334 Plutonium Concentration Facility. This project represented the first open-air demolition of a highly-contaminated plutonium facility at the Hanford Site. This project may also represent the first plutonium facility in the US. Department of Energy (DOE) complex to have been demolished without first decontaminating surfaces to near ''free release'' standards. Demolition of plutonium contaminated structures, if not properly managed, can subject cleanup personnel and the environment to significant risk. However, with proper sequencing and innovative use of commercially available equipment, materials, and services, this project demonstrated that a plutonium processing facility can be demolished while avoiding the need to perform extensive decontamination or to construct large enclosures. This project utilized an excavator with concrete shears, diamond circular saws, water misting and fogging equipment, commercially available fixatives and dust suppressants, conventional mobile crane and rigging services, and near real-time modeling of meteorological and radiological conditions. Following a significant amount of preparation, actual demolition of the 2333 Facility began in October 2003 and was completed in late April 2004. The knowledge and experience gained on this project are important to the Hanford Site as additional plutonium processing facilities are scheduled for demolition in the near future. Other sites throughout the DOE Complex may also be faced with similar challenges. Numerous innovations and effective work practices were implemented on this project. Accordingly, a series of ''Lessons Learned and Innovative Practices Fact Sheets'' were developed and are included as an appendix to this report. This collection of fact sheets is not intended to capture every innovative work practice and lesson learned, but rather to

Inventory difference analysis at Los Alamos Plutonium Facility

International Nuclear Information System (INIS)

Zardecki, A.; Armstrong, J.M.; Longmire, V.; Strittmatter, R.B.

1997-01-01

The authors have developed a prototype computer program that reads directly the inventory entries from a Microsoft Access data base. Based on historical data, the program then displays temporal trends and constructs a library of rules that encapsulates the system behavior. The following analysis of inventory data is illustrated by using a combination of realistic and simulated facility examples. Potential payoffs of this methodology include a reduction in time and resources needed to perform statistical tests and broad applicability to Department of Energy needs--for example, treaty verification

Site Selection for Surplus Plutonium Disposition Facilities at the Savannah River Site

International Nuclear Information System (INIS)

Wike, L.D.

2000-01-01

A site selection study was conducted to evaluate locations for the proposed Surplus Plutonium Disposition Facilities. Facilities to be located include the Mixed Oxide (MOX) Fuel Fabrication Facility, the Pit Disassembly and Conversion Facility (PDCF), and the Plutonium Immobilization Project (PIP) facility. Objectives of the study include: (1) Confirm that the Department of Energy (DOE) selected locations for the MOX and PDCF were suitable based on selected siting criteria, (2) Recommend a site in the vicinity of F Area that is suitable for the PIP, and (3) Identify alternative suitable sites for one or more of these facilities in the event that further geotechnical characterization or other considerations result in disqualification of a currently proposed site

A probabilistic risk assessment of the LLNL Plutonium Facility's evaluation basis fire operational accident. Revision 1

International Nuclear Information System (INIS)

Brumburgh, G.P.

1995-01-01

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous programmatic activities involving plutonium to include device fabrication, development of improved and/or unique fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed in July 1994 to address operational safety and acceptable risk to employees, the public, government property, and the environmental. This paper outlines the PRA analysis of the Evaluation Basis Fire (EBF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

Next generation storage facility

International Nuclear Information System (INIS)

Schlesser, J.A.

1994-01-01

With diminishing requirements for plutonium, a substantial quantity of this material requires special handling and ultimately, long-term storage. To meet this objective, we at Los Alamos, have been involved in the design of a storage facility with the goal of providing storage capabilities for this and other nuclear materials. This paper presents preliminary basic design data, not for the structure and physical plant, but for the container and arrays which might be configured within the facility, with strong emphasis on criticality safety features

Six-kilogram-scale electrorefining of plutonium metal

International Nuclear Information System (INIS)

Mullins, L.J.; Morgan, A.N.; Apgar, S.A. III; Christensen, D.C.

1982-09-01

The electrorefining of metallic plutonium scrap to produce high purity metal has been an established procedure at Los Alamos since 1964. This is a batch process and was limited to 4-kg plutonium because of criticality safety considerations. Improvements in critical mass measurements have permitted us to develop a process for 6-kg plutonium. The 6-kg process is now operational. The increased size of the process, together with other improvements which have been made, makes plutonium electrorefining the principal industrial tool for processing and purifying metallic plutonium scrap

Update of epidemiologic studies of plutonium-workers

International Nuclear Information System (INIS)

Voelz, G.L.; Wilkinson, G.S.; Acquavella, J.F.; Tietjen, G.L.; Brackbill, R.M.; Reyes, M.; Wiggs, L.D.

1981-01-01

Retrospective and prospective epidemiologic studies are being conducted as part of a national survey of plutonium workers at four Department of Energy facilities (Los Alamos, NM; Rocky Flats, CO; Mound Laboratory, OH; and Savannah River, SC). A preliminary analysis of mortality was done for all white males who have worked at the Rocky Flats Plant during the period 1952 to 1979. The 452 observed deaths were significantly fewer than the 831 expected for all causes. The 107 deaths due to all malignant neoplasms were also significantly fewer than the 167 expected from these diseases. Expected deaths were derived from age and calendar-specific death rates for US white males. Deaths reported for benign and unspecified neoplasms numbered eight versus an expected two, a significant elevation. These tumors, all intracranial, are the subject of a case-control study to be reported later. Subdividing the cohort on the basis of plutonium exposures and external radiation exposures results in similar overall findings. The benign and unspecified neoplasms, however, were not significantly high in the plutonium-exposed group

Initial electron-beam characterizations for the Los Alamos APEX Facility

Energy Technology Data Exchange (ETDEWEB)

Lumpkin, A.H.; Feldman, R.B.; Apgar, S.A.; Feldman, D.W.; O' Shea, P.G. (Los Alamos National Lab., NM (United States)); Fiorito, R.B.; Rule, D.W. (Naval Surface Warfare Center, Silver Spring, MD (United States))

1991-01-01

The ongoing upgrade of the Los Alamos Free-Electron Laser (FEL) Facility involves the addition of a photoelectric injector (PEI) and acceleration capability to about 40 MeV. The electron-beam and high-speed diagnostics provide key measurements of charge, beam position and profile, divergence emittance, energy (centroid, spread, slew, and extraction efficiency), micropulse duration, and phase stability. Preliminary results on the facility include optical transition radiation interferometer measurements of divergence (1 to 2 mrad), FEL extraction efficiency (0.6 {plus minus} 0.2%), and drive laser phase stability (< 2 ps (rms)). 10 refs.

Initial electron-beam characterizations for the Los Alamos APEX Facility

Energy Technology Data Exchange (ETDEWEB)

Lumpkin, A.H.; Feldman, R.B.; Apgar, S.A.; Feldman, D.W.; O`Shea, P.G. [Los Alamos National Lab., NM (United States); Fiorito, R.B.; Rule, D.W. [Naval Surface Warfare Center, Silver Spring, MD (United States)

1991-12-31

The ongoing upgrade of the Los Alamos Free-Electron Laser (FEL) Facility involves the addition of a photoelectric injector (PEI) and acceleration capability to about 40 MeV. The electron-beam and high-speed diagnostics provide key measurements of charge, beam position and profile, divergence emittance, energy (centroid, spread, slew, and extraction efficiency), micropulse duration, and phase stability. Preliminary results on the facility include optical transition radiation interferometer measurements of divergence (1 to 2 mrad), FEL extraction efficiency (0.6 {plus_minus} 0.2%), and drive laser phase stability (< 2 ps [rms]). 10 refs.

Fifty years of plutonium exposure to the Manhattan Project plutonium workers: an update.

Science.gov (United States)

Voelz, G L; Lawrence, J N; Johnson, E R

1997-10-01

Twenty-six white male workers who did the original plutonium research and development work at Los Alamos have been examined periodically over the past 50 y to identify possible health effects from internal plutonium depositions. Their effective doses range from 0.1 to 7.2 Sv with a median value of 1.25 Sv. As of the end of 1994, 7 individuals have died compared with an expected 16 deaths based on mortality rates of U.S. white males in the general population. The standardized mortality ratio (SMR) is 0.43. When compared with 876 unexposed Los Alamos workers of the same period, the plutonium worker's mortality rate was also not elevated (SMR = 0.77). The 19 living persons have diseases and physical changes characteristic of a male population with a median age of 72 y (range = 69 to 86 y). Eight of the twenty-six workers have been diagnosed as having one or more cancers, which is within the expected range. The underlying cause of death in three of the seven deceased persons was from cancer, namely cancer of prostate, lung, and bone. Mortality from all cancers was not statistically elevated. The effective doses from plutonium to these individuals are compared with current radiation protection guidelines.

Los Alamos contribution to target diagnostics on the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Mack, J.M.; Baker, D.A.; Caldwell, S.E. [and others

1994-07-01

The National Ignition Facility (NIF) will have a large suite of sophisticated target diagnostics. This will allow thoroughly diagnosed experiments to be performed both at the ignition and pre-ignition levels. As part of the national effort Los Alamos National Laboratory will design, construct and implement a number of diagnostics for the NIF. This paper describes Los Alamos contributions to the ``phase I diagnostics.`` Phase I represents the most fundamental and basic measurement systems that will form the core for most work on the NIF. The Los Alamos effort falls into four categories: moderate to hard X-ray (time resolved imaging neutron spectroscopy- primarily with neutron time of flight devices; burn diagnostics utilizing gamma ray measurements; testing measurement concepts on the TRIDENT laser system at Los Alamos. Because of the high blast, debris and radiation environment, the design of high resolution X-ray imaging systems present significant challenges. Systems with close target proximity require special protection and methods for such protection is described. The system design specifications based on expected target performance parameters is also described. Diagnosis of nuclear yield and burn will be crucial to the NIF operation. Nuclear reaction diagnosis utilizing both neutron and gamma ray detection is discussed. The Los Alamos TRIDENT laser system will be used extensively for the development of new measurement concepts and diagnostic instrumentation. Some its potential roles in the development of diagnostics for NIF are given.

Los Alamos contribution to target diagnostics on the National Ignition Facility

International Nuclear Information System (INIS)

Mack, J.M.; Baker, D.A.; Caldwell, S.E.

1994-01-01

The National Ignition Facility (NIF) will have a large suite of sophisticated target diagnostics. This will allow thoroughly diagnosed experiments to be performed both at the ignition and pre-ignition levels. As part of the national effort Los Alamos National Laboratory will design, construct and implement a number of diagnostics for the NIF. This paper describes Los Alamos contributions to the ''phase I diagnostics.'' Phase I represents the most fundamental and basic measurement systems that will form the core for most work on the NIF. The Los Alamos effort falls into four categories: moderate to hard X-ray (time resolved imaging neutron spectroscopy- primarily with neutron time of flight devices; burn diagnostics utilizing gamma ray measurements; testing measurement concepts on the TRIDENT laser system at Los Alamos. Because of the high blast, debris and radiation environment, the design of high resolution X-ray imaging systems present significant challenges. Systems with close target proximity require special protection and methods for such protection is described. The system design specifications based on expected target performance parameters is also described. Diagnosis of nuclear yield and burn will be crucial to the NIF operation. Nuclear reaction diagnosis utilizing both neutron and gamma ray detection is discussed. The Los Alamos TRIDENT laser system will be used extensively for the development of new measurement concepts and diagnostic instrumentation. Some its potential roles in the development of diagnostics for NIF are given

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

International Nuclear Information System (INIS)

Behrens, R.G.; Buck, E.C.; Dietz, N.L.; Bates, J.K.; Van Deventer, E.; Chaiko, D.J.

1995-09-01

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 2 PuO 2-x , and Pu 4 O 7 phases, of about 1μm 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 μm to liberate the plutonium from the surrounding inert matrix

Los Alamos Neutron Science Center (LANSCE) Nuclear Science Facilities

Energy Technology Data Exchange (ETDEWEB)

Nelson, Ronald Owen [Los Alamos National Laboratory; Wender, Steve [Los Alamos National Laboratory

2015-06-19

The Los Alamos Neutron Science Center (LANSCE) facilities for Nuclear Science consist of a high-energy "white" neutron source (Target 4) with 6 flight paths, three low-energy nuclear science flight paths at the Lujan Center, and a proton reaction area. The neutron beams produced at the Target 4 complement those produced at the Lujan Center because they are of much higher energy and have shorter pulse widths. The neutron sources are driven by the 800-MeV proton beam of the LANSCE linear accelerator. With these facilities, LANSCE is able to deliver neutrons with energies ranging from a milli-electron volt to several hundreds of MeV, as well as proton beams with a wide range of energy, time and intensity characteristics. The facilities, instruments and research programs are described briefly.

In search of plutonium: A nonproliferation journey

Science.gov (United States)

Hecker, Siegfried

2010-02-01

In February 1992, I landed in the formerly secret city of Sarov, the Russian Los Alamos, followed a few days later by a visit to Snezhinsk, their Livermore. The briefings we received of the Russian nuclear weapons program and tours of their plutonium, reactor, explosives, and laser facilities were mind boggling considering the Soviet Union was dissolved only two months earlier. This visit began a 17-year, 41 journey relationship with the Russian nuclear complex dedicated to working with them in partnership to protect and safeguard their weapons and fissile materials, while addressing the plight of their scientists and engineers. In the process, we solved a forty-year disagreement about the plutonium-gallium phase diagram and began a series of fundamental plutonium science workshops that are now in their tenth year. At the Yonbyon reprocessing facility in January 2004, my North Korean hosts had hoped to convince me that they have a nuclear deterrent. When I expressed skepticism, they asked if I wanted to see their ``product.'' I asked if they meant the plutonium; they replied, ``Well, yes.'' Thus, I wound up holding 200 grams of North Korean plutonium (in a sealed glass jar) to make sure it was heavy and warm. So began the first of my six journeys to North Korea to provide technical input to the continuing North Korean nuclear puzzle. In Trombay and Kalpakkam a few years later I visited the Indian nuclear research centers to try to understand how India's ambitious plans for nuclear power expansion can be accomplished safely and securely. I will describe these and other attempts to deal with the nonproliferation legacy of the cold war and the new challenges ahead. )

Innovations in Los Alamos alpha box design

International Nuclear Information System (INIS)

Ledbetter, J.M.; Dowler, K.E.; Cook, J.H.

1985-01-01

Destructive examinations of irradiated fuel pins containing plutonium fuel must be performed in shielded hot cells with strict provisions for containing the plutonium. Alpha boxes provide containment for the plutonium, toxic fission products, and other hazardous highly radioactive materials. The alpha box contains windows for viewing and a variety of transfer systems specially designed to allow transfers in and out of the alpha box without spread of the hazardous materials that are contained in the box. Alpha boxes have been in use in the Wing 9 hot cells at Los Alamos National Laboratory for more than 20 years. Features of the newly designed alpha boxes are presented

Seismic evaluation of the LLNL plutonium facility (Building 332)

International Nuclear Information System (INIS)

Hall, W.J.; Sozen, M.A.

1982-03-01

The expected performance of the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (Building 332) subjected to earthquake ground motion has been evaluated. Anticipated behavior of the building, glove boxes, ventilation system and other systems critical for containment of plutonium is described for three severe postulated earthquake excitations. Based upon this evaluation, some damage to the building, glove boxes and ventilation system would be expected but no collapse of any structure is anticipated as a result of the postulated earthquake ground motions

Los Alamos High-Brightness Accelerator FEL (HIBAF) facility

Energy Technology Data Exchange (ETDEWEB)

Cornelius, W.D.; Bender, S.; Meier, K.; Thode, L.E.; Watson, J.M.

1989-01-01

The 10-/mu/m Los Alamos free-electron laser (FEL) facility is being upgraded. The conventional electron gun and bunchers have been replaced with a much more compact 6-MeV photoinjector accelerator. By adding existing parts from previous experiments, the primary beam energy will be doubled to 40 MeV. With the existing 1-m wiggler (/lambda//sub w/ = 2.7 cm) and resonator, the facility can produce photons with wavelengths from 3 to 100 /mu/m when lasing on the fundamental mode and produce photons in the visible spectrum with short-period wigglers or harmonic operation. After installation of a 150/degree/ bend, a second wiggler will be added as an amplifier. The installation of laser transport tubes between the accelerator vault and an upstairs laboratory will provide experimenters with a radiation-free environment for experiments. Although the initial experimental program of the upgraded facility will be to test the single accelerator-master oscillator/power amplifier configuration, some portion of the operational time of the facility can be dedicated to user experiments. 13 refs., 5 figs., 6 tabs.

An improved, computer-based, on-line gamma monitor for plutonium anion exchange process control

International Nuclear Information System (INIS)

Pope, N.G.; Marsh, S.F.

1987-06-01

An improved, low-cost, computer-based system has replaced a previously developed on-line gamma monitor. Both instruments continuously profile uranium, plutonium, and americium in the nitrate anion exchange process used to recover and purify plutonium at the Los Alamos Plutonium Facility. The latest system incorporates a personal computer that provides full-feature multichannel analyzer (MCA) capabilities by means of a single-slot, plug-in integrated circuit board. In addition to controlling all MCA functions, the computer program continuously corrects for gain shift and performs all other data processing functions. This Plutonium Recovery Operations Gamma Ray Energy Spectrometer System (PROGRESS) provides on-line process operational data essential for efficient operation. By identifying abnormal conditions in real time, it allows operators to take corrective actions promptly. The decision-making capability of the computer will be of increasing value as we implement automated process-control functions in the future. 4 refs., 6 figs

Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

International Nuclear Information System (INIS)

Salazar, M.; Elder, J.

1992-08-01

The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program

Guide of good practices for occupational radiological protection in plutonium facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-06-01

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.

Keeping the Momentum and Nuclear Forensics at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Steiner, Robert Ernest; Dion, Heather M.; Dry, Donald E.; Kinman, William Scott; LaMont, Stephen Philip; Podlesak, David; Tandon, Lav

2016-01-01

LANL has 70 years of experience in nuclear forensics and supports the community through a wide variety of efforts and leveraged capabilities: Expanding the understanding of nuclear forensics, providing training on nuclear forensics methods, and developing bilateral relationships to expand our understanding of nuclear forensic science. LANL remains highly supportive of several key organizations tasked with carrying forth the Nuclear Security Summit messages: IAEA, GICNT, and INTERPOL. Analytical chemistry measurements on plutonium and uranium matrices are critical to numerous programs including safeguards accountancy verification measurements. Los Alamos National Laboratory operates capable actinide analytical chemistry and material science laboratories suitable for nuclear material and environmental forensic characterization. Los Alamos National Laboratory uses numerous means to validate and independently verify that measurement data quality objectives are met. Numerous LANL nuclear facilities support the nuclear material handling, preparation, and analysis capabilities necessary to evaluate samples containing nearly any mass of an actinide (attogram to kilogram levels).

Keeping the Momentum and Nuclear Forensics at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Steiner, Robert Ernest [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dion, Heather M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dry, Donald E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kinman, William Scott [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); LaMont, Stephen Philip [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Podlesak, David [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tandon, Lav [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-07-22

LANL has 70 years of experience in nuclear forensics and supports the community through a wide variety of efforts and leveraged capabilities: Expanding the understanding of nuclear forensics, providing training on nuclear forensics methods, and developing bilateral relationships to expand our understanding of nuclear forensic science. LANL remains highly supportive of several key organizations tasked with carrying forth the Nuclear Security Summit messages: IAEA, GICNT, and INTERPOL. Analytical chemistry measurements on plutonium and uranium matrices are critical to numerous programs including safeguards accountancy verification measurements. Los Alamos National Laboratory operates capable actinide analytical chemistry and material science laboratories suitable for nuclear material and environmental forensic characterization. Los Alamos National Laboratory uses numerous means to validate and independently verify that measurement data quality objectives are met. Numerous LANL nuclear facilities support the nuclear material handling, preparation, and analysis capabilities necessary to evaluate samples containing nearly any mass of an actinide (attogram to kilogram levels).

HENC performance evaluation and plutonium calibration

International Nuclear Information System (INIS)

Menlove, H.O.; Baca, J.; Pecos, J.M.; Davidson, D.R.; McElroy, R.D.; Brochu, D.B.

1997-10-01

The authors have designed a high-efficiency neutron counter (HENC) to increase the plutonium content in 200-L waste drums. The counter uses totals neutron counting, coincidence counting, and multiplicity counting to determine the plutonium mass. The HENC was developed as part of a Cooperative Research and Development Agreement between the Department of Energy and Canberra Industries. This report presents the results of the detector modifications, the performance tests, the add-a-source calibration, and the plutonium calibration at Los Alamos National Laboratory (TA-35) in 1996

Plutonium helps probe protein, superconductor

International Nuclear Information System (INIS)

Anon.

1990-01-01

Scientists are finding that plutonium can be a useful research tool that may help them answer important questions in fields as diverse as biochemistry and solid-state physics. This paper reports that U.S. research involving plutonium is confined to the Department of Energy's national laboratories and centers around nuclear weapons technology, waste cleanup and disposal, and health effects. But at Los Alamos National Laboratory, scientists also are using plutonium to probe the biochemical behavior of calmodulin, a key calcium-binding protein that mediates calcium-regulated processes in biological systems. At Argonne National Laboratory, another team is trying to learn how a superconductor's properties are affected by the 5f electrons of an actinide like plutonium

The current status and possible future of the Los Alamos spallation radiation effects facility

Energy Technology Data Exchange (ETDEWEB)

Borden, M.J.; Sommer, W.F. [Los Alamos National Laboratory, NM (United States)

1995-10-01

The Los Alamos Spallation Radiation Effects Facility (LASREF) has been configured for both proton and spallation neutron irradiations since 1985. The facility makes use of the Los Alamos Meson Physics Facility 1 mA 800 MeV proton beam. Environment controlled proton and neutron irradiations have been demonstrated over the past nine years. The current copper beam stop configuration produces a maximum measured neutron flux of 4.6 x 10{sup 17} m{sup {minus}2}s{sup {minus}1} for energies greater than 1 KeV. The maximum proton flux at the center of Gaussian shaped beam is 1.2 x 10{sup 14} protons cm{sup {minus}2}s{sup {minus}1} with beam spot diameter of 3.5 cm at 2{sigma}. Previously published work has shown that the neutron flux can be increased by a factor of ten by changing the beam stop to tungsten and decreasing the diameter. Expertise exists at Los Alamos to further optimize this design to tailor neutron production and spectrum. Consideration and preliminary planning has also been done for increasing the LAMPF proton current from 1 mA to a few mA with a possible maximum of 10 mA. An upgrade of this type would produce current densities comparable to those proposed for the Accelerator-Driven Transmutation Technologies (ADTT) programs.

Assay of low-level plutonium effluents

International Nuclear Information System (INIS)

Hsue, S.T.; Hsue, F.; Bowersox, D.F.

1981-01-01

In the plutonium recovery section at the Los Alamos National Laboratory, an effluent solution is generated that contains low plutonium concentration and relatively high americium concentration. Nondestructive assay of this solution is demonstrated by measuring the passive L x-rays following alpha decay. Preliminary results indicate that an average deviation of 30% between L x-ray and alpha counting can be achieved for plutonium concentrations above 10 mg/L and Am/Pu ratios of up to 3; for plutonium concentrations less than 10 mg/L, the average deviation is 40%. The sensitivity of the L x-ray assay is approx. 1 mg Pu/L

Documentation of acceptable knowledge for LANL Plutonium Facility transuranic waste streams

International Nuclear Information System (INIS)

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

1998-01-01

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

Hazardous waste treatment facility and skid-mounted treatment systems at Los Alamos

International Nuclear Information System (INIS)

Lussiez, G.W.; Zygmunt, S.J.

1993-01-01

To centralize treatment, storage, and staging areas for hazardous wastes, Los Alamos National Laboratory has designed a 12,000-ft 2 hazardous waste treatment facility. The facility will house a treatment room for each of four kinds of wastes: nonradioactive characteristic wastes, nonradioactive listed wastes radioactive characteristic wastes, and radioactive listed wastes. The facility will be used for repacking labpacks, bulking small organic waste volumes, processing scintillation vials, treating reactives such as lithium hydride and pyrophoric uranium, treating contaminated solids such as barium sand, and treating plating wastes. The treated wastes will then be appropriately disposed of. This report describes the integral features of the hazardous waste treatment facility

Some nuclear safety aspects of the Los Alamos accelerator based converion concept

Energy Technology Data Exchange (ETDEWEB)

Gudowski, W.; Moeller, E. [Royal Institute of Technology, Stockholm (Sweden); Venneri, F. [Los Alamos National Laboratory, NM (United States)

1995-10-01

The detailed analysis of the few parameters important for the safety of the accelerator-driven plutonium burner concept developed at Los Alamos National Laboratory was performed. The plutonium load, optimal thermalization of the neutron spectrum and temperature reactivity coefficients were investigated. The calculations revealed the strong positive temperature reactivity coeffecient. The ways to solve this problem are suggested.

Passive neutron survey of the 233-S Plutonium Concentration Facility

International Nuclear Information System (INIS)

1996-08-01

A passive neutron survey was performed at the 233-S Plutonium Concentration Facility (located at the Hanford Site in Richland, Washington) during late 1994 and early 1995. Four areas were surveyed: an abandoned filter box and pipe trench, column laydown trench, load-out hood, and process hood. The primary purpose of the survey was to identify locations that had plutonium to help direct decontamination and decommissioning activities. A secondary purpose of the survey was to determine the quantity of material when its presence was identified

Decontamination and decommissioning criteria for use in design of new plutonium facilities

International Nuclear Information System (INIS)

Paschall, R.K.

1975-01-01

Decontamination and decommissioning (D and D) criteria were assembled for use in designing new plutonium facilities. These criteria were gathered from literature searches and visits to many plutonium facilities around the country. The recommendations of reports and experienced personnel were used. Since total D and D costs can be millions of dollars, improved designs to facilitate D and D will result in considerable savings in cost and time and will help to leave the site for unrestricted future use after D and D. Finally, better design will reduce hazards and improve safety during the D and D effort

Validation of MCNP6 Version 1.0 with the ENDF/B-VII.1 Cross Section Library for Plutonium Metals, Oxides, and Solutions on the High Performance Computing Platform Moonlight

Energy Technology Data Exchange (ETDEWEB)

Chapman, Bryan Scott [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gough, Sean T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-12-05

This report documents a validation of the MCNP6 Version 1.0 computer code on the high performance computing platform Moonlight, for operations at Los Alamos National Laboratory (LANL) that involve plutonium metals, oxides, and solutions. The validation is conducted using the ENDF/B-VII.1 continuous energy group cross section library at room temperature. The results are for use by nuclear criticality safety personnel in performing analysis and evaluation of various facility activities involving plutonium materials.

Disposition of PUREX facility tanks D5 and E6 uranium and plutonium solutions

International Nuclear Information System (INIS)

Harty, D.P.

1993-12-01

Approximately 9 kilograms of plutonium and 5 metric tons of uranium in a 1 molar nitric acid solution are being stored in two PUREX facility vessels, tanks D5 and E6. The plutonium was accumulated during cleanup activities of the plutonium product area of the PUREX facility. Personnel at PUREX recently completed a formal presentation to the Surplus Materials Peer Panel (SMPP) regarding disposition of the material currently in these tanks. The peer panel is a group of complex-wide experts who have been chartered by EM-64 (Office of Site and Facility Transfer) to provide a third party independent review of disposition decisions. The information presented to the peer panel is provided in the first section of this report. The panel was generally receptive to the information provided at that time and the recommendations which were identified

Disposition of plutonium as non-fertile fuel for water reactors

International Nuclear Information System (INIS)

Chidester, K.; Eaton, S.L.; Ramsey, K.B.

1998-01-01

This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The original intent of this project was to investigate the possible use of a new fuel form as a means of dispositioning the declared surplus inventory of weapons-grade plutonium. The focus soon changed, however, to managing the larger and rapidly growing inventories of plutonium arising in commercial spent nuclear fuel through implementation of a new fuel form in existing nuclear reactors. LANL embarked on a parallel path effort to study fuel performance using advanced physics codes, while also demonstrating the ability to fabricate a new fuel form using standard processes in LANL's Plutonium Facility. An evolutionary fuel form was also examined which could provide enhanced performance over standard fuel forms, but which could be implemented in a much shorter time frame than a completely new fuel form. Recent efforts have focused on implementation of results into global energy models and development of follow-on funding to continue this research

Lung cancers already produced by plutonium inhalation

International Nuclear Information System (INIS)

Anon.

1981-01-01

This chapter presents the basis for the author's estimate that plutonium particulates have already committed approximately 950,000 persons worldwide to a lung-cancer death, and that more will be so committed in the future, even if no more plutonium is dispersed in the environment. The author's calculations are based on fallout data from atmospheric bomb testing, and on two sets of workers exposed to plutonium: one group at the Rocky Flats Plant in Colorado, and the other at the Los Alamos Laboratory who were involved in the Manhattan Project

Aqueous Nitrate Recovery Line at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Finstad, Casey Charles [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-06-15

This powerpoint is part of the ADPSM Plutonium Engineering Lecture Series, which is an opportunity for new hires at LANL to get an overview of work done at TA55. It goes into detail about the aqueous nitrate recovery line at Los Alamos National Laboratory.

Los Alamos science. Volume 4, No. 7

International Nuclear Information System (INIS)

Cooper, N.G.

1983-01-01

A history of the Los Alamos National Laboratory over its 40 years is presented. The evolution of the laboratory is broken down into the Oppenheimer years, the Bradbury years, the Agnew years and the Kerr years. The weapons program is described including nuclear data, early reactors, computing and computers, plutonium, criticality, weapon design and field testing

Process control and safeguards system plutonium inventory conrol for MOX fuel facility

International Nuclear Information System (INIS)

Mishima, T.; Aoki, M.; Muto, T.; Amanuma, T.

1979-01-01

The plutonium inventory control (PINC) system is a real-time material accountability control system that is expected to be applied to a new large-scale plutonium fuel production facility for both fast breeder reactor and heavy water reactor at the Power Reactor and Nuclear Development Corporation. The PINC is basically a system for material control but is expected to develop into a whole facility control system, including criticality control, process control, quality control, facility protection, and so forth. Under PINC, every process and storage area is divided into a unit area, which is the smallest unit for both accountability and process control. Item and material weight automatically are accounted for at every unit area, and data are simultaneously treated by a computer network system. Sensors necessary for the system are being developed. 9 figures

Morbidity and mortality in Los Alamos County, New Mexico. I. Methodological issues and preliminary results

International Nuclear Information System (INIS)

Stebbings, J.H. Jr.; Voelz, G.L.

1981-01-01

Cancer among Los Alamos County, New Mexico, male residents, all of whom have worked in or have lived within a few kilometers of a major plutonium plant and other nuclear facilities, has been reviewed with respect to mortality between 1950 and 1969 and incidence between 1969 and 1974. Several potentially causal occupational exposures have existed. Higher than expected incidence, currently, of cancers of the colon and rectum appears to be explained better by socioeconomic than occupational factors. Healthy worker and healthy military effects, white ethnicity, and migration are discussed as intervening variables relevant to interpreting mortality data in counties dominated by a single major facility. The utility of county data bases in the study of single local area mortality rates is reviewed

Dosimetry at the Los Alamos Critical Experiments Facility: Past, present, and future

International Nuclear Information System (INIS)

Malenfant, R.E.

1993-10-01

Although the primary reason for the existence of the Los Alamos Critical Experiments Facility is to provide basic data on the physics of systems of fissile material, the physical arrangements and ability to provide sources of radiation have led to applications for all types of radiation dosimetry. In the broad definition of radiation phenomena, the facility has provided sources to evaluate biological effects, radiation shielding and transport, and measurements of basic parameters such as the evaluation of delayed neutron parameters. Within the last 15 years, many of the radiation measurements have been directed to calibration and intercomparison of dosimetry related to nuclear criticality safety. Future plans include (1) the new applications of Godiva IV, a bare-metal pulse assembly, for dosimetry (including an evaluation of neutron and gamma-ray room return); (2) a proposal to relocate the Health Physics Research Reactor from the Oak Ridge National Laboratory to Los Alamos, which will provide the opportunity to continue the application of a primary benchmark source to radiation dosimetry; and (3) a proposal to employ SHEBA, a low-enrichment solution assembly, for accident dosimetry and evaluation

Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

Energy Technology Data Exchange (ETDEWEB)

Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae [NESS, Daejeon (Korea, Republic of)

2016-10-15

In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF.

Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

International Nuclear Information System (INIS)

Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae

2016-01-01

In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF

Safety analysis of the Los Alamos critical experiments facility: burst operation of Skua

International Nuclear Information System (INIS)

Orndoff, J.D.; Paxton, H.C.; Wimett, T.F.

1979-05-01

A detailed consideration of the Skua burst assembly is presented, thereby supplementing the facility safety analysis report covering the operation of other critical assemblies at Los Alamos. As with these assemblies the small fission-product inventory, ambient pressure, and moderate temperatures in Skua are amenable to straightforward measures to ensure the protection of the public

Los Alamos National Laboratory DOE M441.1-1 implementation

International Nuclear Information System (INIS)

Worl, Laura A.; Veirs, D. Kirk; Smith, Paul H.; Yarbro, Tresa F.; Stone, Timothy A.

2010-01-01

Loss of containment of nuclear material stored in containers such as food-pack cans, paint cans, or taped slip lid cans has generated concern about packaging requirements for interim storage of nuclear materials in working facilities such as the plutonium facility at Los Alamos National Laboratory (LANL). The Department of Energy (DOE) issued DOE M 441.1-1, Nuclear Materials Packaging Manual on March 7, 2008 in response to the Defense Nuclear Facilities Safety Board Recommendation 2005-1. The Manual directs DOE facilities to follow detailed packaging requirements to protect workers from exposure to nuclear materials stored outside of approved engineered-contamination barriers. Los Alamos National Laboratory has identified the activities that will be performed to bring LANL into compliance with DOE M 441.1-1. These include design, qualification and procurement of new containers, repackaging based on a risk-ranking methodology, surveillance and maintenance of containers, and database requirements. The primary purpose is to replace the out-dated nuclear material storage containers with more robust containers that meet present day safety and quality standards. The repackaging campaign is supported by an integrated risk reduction methodology to prioritize the limited resources to the highest risk containers. This methodology is systematically revised and updated based on the collection of package integrity data. A set of seven nested packages with built-in filters have been designed. These range in size from 1 qt. to 10 gallon. Progress of the testing to meet Manual requirements will be given. Due to the number of packages at LANL, repackaging to achieve full compliance will take five to seven years.

Recent development in pyrochemistry at Los Alamos

International Nuclear Information System (INIS)

McNeese, J.A.; Fife, K.W.; Williams, J.D.

1984-01-01

Recent developments in pyrochemical processing at Los Alamos include the recovery of plutonium from anodes and impure metal by pyroredox and new molten salt handling and purification techniques. The anode is dissolved in a ZnCl 2 KCl salt to form PuCl 3 and a zinc and impurities button. Calcium reduction of the PuCl 3 yields 95 to 98% pure plutonium. New techniques for transferring molten salt from a purification or regeneration vessel to molds has been successfully developed and demonstrated. Additional salt work involving recycle of direct oxide reduction salts using anhydrous hydrogen chloride, phosgene, and chlorine gases is under way. 13 figures, 1 table

In Plant Measurement and Analysis of Mixtures of Uranium and Plutonium TRU-Waste Using a 252Cf Shuffler Instrument

International Nuclear Information System (INIS)

Hurd, J.R.

1998-01-01

The active-passive 252 Cf shuffler instrument, installed and certified several years ago in Los Alamos National Laboratory's plutonium facility, has now been calibrated for different matrices to measure Waste Isolation Pilot Plant (WIPP)-destined transuranic (TRU)-waste. Little or no data currently exist for these types of measurements in plant environments where sudden large changes in the neutron background radiation can significantly distort the results. Measurements and analyses of twenty-two 55-gallon drums, consisting of mixtures of varying quantities of uranium and plutonium in mostly noncombustible matrices, have been recently completed at the plutonium facility. The calibration and measurement techniques, including the method used to separate out the plutonium component, will be presented and discussed. Calculations used to adjust for differences in uranium enrichment from that of the calibration standards will be shown. Methods used to determine various sources of both random and systematic error will be indicated. Particular attention will be directed to those problems identified as arising from the plant environment. The results of studies to quantify the aforementioned distortion effects in the data will be presented. Various solution scenarios will be outlined, along with those adopted here

Continuous Material Balance Reconciliation for a Modern Plutonium Processing Facility

International Nuclear Information System (INIS)

CLARK, THOMASG.

2004-01-01

This paper describes a safeguards approach that can be deployed at any modern plutonium processing facility to increase the level of safeguards assurance and significantly reduce the impact of safeguards on process operations. One of the most perplexing problems facing the designers of plutonium processing facilities is the constraint placed upon the limit of error of the inventory difference (LEID). The current DOE manual constrains the LEID for Category I and II material balance areas to 2 per cent of active inventory up to a Category II quantity of the material being processed. For 239Pu a Category II quantity is two kilograms. Due to the large material throughput anticipated for some of the modern plutonium facilities, the required LEID cannot be achieved reliably during a nominal two month inventory period, even by using state-of-the-science non-destructive assay (NDA) methods. The most cost-effective and least disruptive solution appears to be increasing the frequency of material balance closure and thus reducing the throughput being measured during each inventory period. Current inventory accounting practices and systems can already provide the book inventory values at any point in time. However, closing the material balance with measured values has typically required the process to be cleaned out, and in-process materials packaged and measured. This process requires one to two weeks of facility down time every two months for each inventory, thus significantly reducing productivity. To provide a solution to this problem, a non-traditional approach is proposed that will include using in-line instruments to provide measurement of the process materials on a near real-time basis. A new software component will be developed that will operate with the standard LANMAS application to provide the running material balance reconciliation, including the calculation of the inventory difference and variance propagation. The combined measurement system and software

Safety analysis of the Los Alamos critical experiments facility: burst operation of Skua

International Nuclear Information System (INIS)

Orndoff, J.D.; Paxton, H.C.; Wimett, T.F.

1980-12-01

Detailed consideration of the Skua burst assembly is provided, thereby supplementing the facility Safety Analysis Report covering the operation of other critical assemblies at the Los Alamos Scientific Laboratory. As with these assemblies the small fission-product inventory, ambient pressure, and moderate temperatures in Skua are amenable to straightforward measures to ensure the protection of the public

Characterization of transuranic solid wastes from a plutonium processing facility

International Nuclear Information System (INIS)

Mulkin, R.

1975-06-01

Transuranic-contaminated wastes generated in the processing areas of the Plutonium Chemistry and Metallurgy Group at the Los Alamos Scientific Laboratory (LASL) were studied in detail to identify their chemical and physical composition. Nondestructive Assay (NDA) equipment was developed to measure transuranic activity at the 10-nCi/g level in low-density residues typically found in room-generated waste. This information will supply the Waste Management Program with a more positive means of identifying concerns in waste storage and the challenge of optimizing the system of waste form, packaging, and environment of the storage area for 20-yr retrievable waste. A positive method of measuring transuranic activity in waste at the 10-nCi/g level will eliminate the need for administrative control in a sensitive area, and will provide the economic advantage of minimizing the volume of waste stored as retrievable waste. (U.S.)

Applications of inventory difference tool at Los Alamos Plutonium Facility

International Nuclear Information System (INIS)

Hench, K.W.; Longmire, V.; Yarbro, T.F.; Zardecki, A.

1998-01-01

A prototype computer program reads the inventory entries directly from the Microsoft Access database. Based on historical data, the program then displays temporal trends and constructs a library of rules that encapsulate the system behavior. The analysis of inventory data is illustrated using a combination of realistic and simulated facility examples. Potential payoffs of this methodology include a reduction in time and resources needed to perform statistical tests and a broad applicability to DOE needs such as treaty verification

Analysis results from the Los Alamos 2D/3D program

International Nuclear Information System (INIS)

Boyack, B.E.; Cappiello, M.W.; Stumpf, H.; Shire, P.; Gilbert, J.; Hedstrom, J.

1986-01-01

Los Alamos National Laboratory is a participant in the 2D/3D program. Activities conducted at Los Alamos National Laboratory in support of 2D/3D program goals include analysis support of facility design, construction, and operation; provision of boundary and initial conditions for test facility operations based on analysis of pressurized water reactors; performance of pretest and posttest predictions and analyses; and use of experimental results to validate and assess the single- and multidimensional nonequilibrium features in the Transient Reactor Analysis Code (TRAC). During Fiscal Year 1986, Los Alamos conducted analytical assessment activities using data from the Cylindrical Core Test Facility and the Slab Core Test Facility. Los Alamos also continued to provide support analysis for the planning of Upper Plenum Test Facility experiments. Finally, Los Alamos either completed or is currently working on three areas of TRAC modeling improvement. In this paper, Los Alamos activities during Fiscal Year 1986 are summarized; several significant accomplishments are described in more detail to illustrate the work activities at Los Alamos

History and stabilization of the Plutonium Finishing Plant (PFP) complex, Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Gerber, M.S., Fluor Daniel Hanford

1997-02-18

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.

Challenges using a 252Cf shuffler instrument in a plant environment to measure mixtures of uranium and plutonium transuranic waste

International Nuclear Information System (INIS)

Hurd, J.R.

1999-01-01

An active-passive 252 Cf shuffler instrument, installed and certified several years ago at Los Alamos National Laboratory's plutonium facility, has now been calibrated for different matrices to measure Waste Isolation Pilot Plant (WIPP)-destined transuranic (TRU) waste. Little or no data currently exist for these types of measurements in plant environments where sudden large changes in the neutron background radiation can significantly distort the results. Measurements and analyses of twenty-two 55-gallon drums, consisting of mixtures of varying quantities of uranium and plutonium in mostly noncombustible matrices, have been recently completed at the plutonium facility. The calibration and measurement techniques, including the method used to separate out the plutonium component, will be presented and discussed. Calculations used to adjust for differences in uranium enrichment from that of the calibration standards will be shown. Methods used to determine various sources of both random and systematic error will be indicated. Particular attention will be directed to those problems identified as arising from the plant environment. The results of studies to quantify the aforementioned distortion effects in the data will be presented. Various solution scenarios will be outlined, along with those adopted here

Automatic beam position control at Los Alamos Spallation Radiation Effects Facility (LASREF)

International Nuclear Information System (INIS)

Oothoudt, M.; Pillai, C.; Zumbro, M.

1997-01-01

Historically the Los Alamos Spallation Radiation Effects Facility (LASREF) has used manual methods to control the position of the 800 kW, 800 MeV proton beam on targets. New experiments, however, require more stringent position control more frequently than can be done manually for long periods of time. Data from an existing harp is used to automatically adjust steering magnets to maintain beam position to required tolerances

Applications of molten salts in plutonium processing

International Nuclear Information System (INIS)

Bowersox, D.F.; Christensen, D.C.; Williams, J.D.

1987-01-01

Plutonium is efficiently recovered from scrap at Los Alamos by a series of chemical reactions and separations conducted at temperatures ranging from 700 to 900 0 C. These processes usually employ a molten salt or salt eutectic as a heat sink and/or reaction medium. Salts for these operations were selected early in the development cycle. The selection criteria are being reevaluated. In this article we describe the processes now in use at Los Alamos and our studies of alternate salts and eutectics

Analysis results from the Los Alamos 2D/3D program

International Nuclear Information System (INIS)

Boyack, B.E.; Cappiello, M.W.; Harmony, S.C.; Shire, P.R.; Siebe, D.A.

1987-01-01

Los Alamos National Laboratory is a participant in the 2D/3D program. Activities conducted at Los Alamos National Laboratory in support of 2D/3D program goals include analysis support of facility design, construction, and operation; provision of boundary and initial conditions for test-facility operations based on analysis of pressurized water reactors; performance of pretest and posttest predictions and analyses; and use of experimental results to validate and assess the single- and multi-dimensional, nonequilibrium features in the Transient Reactor Analysis Code (TRAC). During fiscal year 1987, Los Alamos conducted analytical assessment activities using data from the Slab Core Test Facility, The Cylindrical Core Test Facility, and the Upper Plenum Test Facility. Finally, Los Alamos continued work to provide TRAC improvements. In this paper, Los Alamos activities during fiscal year 1987 will be summarized; several significant accomplishments will be described in more detail to illustrate the work activities at Los Alamos

Plutonium microstructures. Part 1

International Nuclear Information System (INIS)

Cramer, E.M.; Bergin, J.B.

1981-09-01

This report is the first of three parts in which Los Alamos and Lawrence Livermore National Laboratory metallographers exhibit a consolidated set of illustrations of inclusions that are seen in plutonium metal as a consequence of inherent and tramp impurities, alloy additions, and thermal or mechanical treatments. This part includes illustrations of nonmetallic and intermetallic inclusions characteristic of major impurity elements as an aid to identifying unknowns. It also describes historical aspects of the increased purity of laboratory plutonium samples, and it gives the composition of the etchant solutions and describes the etching procedure used in the preparation of each illustrated sample. 25 figures

Preliminary evaluation of the potential for plutonium release from burial grounds at Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Wheeler, M.L.; Smith, W.J.; Gallegos, A.F.

1977-02-01

An analysis was made of a number of natural phenomena which could result in the release of plutonium from radioactive wastes buried at the Los Alamos Scientific Laboratory (LASL). Background information concerning the history and practice of radioactive waste disposal at LASL is provided. The potential impact of buried radioactive wastes on the environment is addressed through the mechanisms and rates by which the radionuclides can enter the environment. Only mechanisms independent of human activity are considered. They are divided into two classes, acute and chronic. The acute release mechanisms considered are earthquakes, meteorite impacts, and tornadoes. These have been typified by low occurrence probabilities (10 -6 to 10 -7 /yr). The chronic mechanisms that have been considered are release through uptake by plant roots, exposure by soil erosion, and transport by soil water. The rates of these processes are low, but may result in radionuclide release over long time periods. The analysis of uptake by plant roots was made using an environmental model currently under development; the model is discussed in some detail

Data Mining Techniques to Estimate Plutonium, Initial Enrichment, Burnup, and Cooling Time in Spent Fuel Assemblies

Energy Technology Data Exchange (ETDEWEB)

Trellue, Holly Renee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fugate, Michael Lynn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tobin, Stephen Joesph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-03-19

The Next Generation Safeguards Initiative (NGSI), Office of Nonproliferation and Arms Control (NPAC), National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE) has sponsored a multi-laboratory, university, international partner collaboration to (1) detect replaced or missing pins from spent fuel assemblies (SFA) to confirm item integrity and deter diversion, (2) determine plutonium mass and related plutonium and uranium fissile mass parameters in SFAs, and (3) verify initial enrichment (IE), burnup (BU), and cooling time (CT) of facility declaration for SFAs. A wide variety of nondestructive assay (NDA) techniques were researched to achieve these goals [Veal, 2010 and Humphrey, 2012]. In addition, the project includes two related activities with facility-specific benefits: (1) determination of heat content and (2) determination of reactivity (multiplication). In this research, a subset of 11 integrated NDA techniques was researched using data mining solutions at Los Alamos National Laboratory (LANL) for their ability to achieve the above goals.

Soil plutonium and cesium in stream channels and banks of Los Alamos liquid effluent-receiving areas

International Nuclear Information System (INIS)

Nyhan, J.W.; White, G.C.; Trujillo, G.

1982-01-01

Stream channel sediments and adjacent bank soils found in three intermittent streams used for treated liquid effluent disposal at Los Alamos, New Mexico were sampled to determine the distribution of 238 Pu, sup(239,240)Pu and 137 Cs. Radionuclide concentrations and inventories were determined as functions of distance downstream from the waste outfall and from the center of the stream channel, soil sampling depth, stream channel-bank physiography, and the waste use history of each disposal area. Radionuclide concentrations in channel sediments were inversely related to distances up to 10 km downstream from the outfalls. For sites receiving appreciable waste effluent additions, contaminant concentrations in bank soils decreased with perpendicular distances greater than 0.38 m from the stream channel, and with stream bank sampling depths greater than 20-40 cm. Concentrations and total inventories of radionuclides in stream bank soils generally decreased as stream bank height increased. Inventory estimates of radionuclides in channel sediments exhibited coefficients of variation that ranged 0.41-2.6, reflecting the large variation in radionuclide concentrations at each site. Several interesting temporal relationships of these radionuclides in intermittent streams were gleaned from the varying waste use histories of the three effluent-receiving areas. Eleven years after liquid wastes were added to one canyon, the major radionuclide inventories were found in the stream bank soils, unlike most of the other currently-used receiving areas. A period of time greater than 6 yr seems to be required before the plutonium in liquid wastes currently added to the canyon is approximately equilibrated with the plutonium in the bank soils. These observations are discussed relative to waste management practices in these southwestern intermittent streams. (author)

Soil plutonium and cesium in stream channels and banks of Los Alamos liquid effluent-receiving areas.

Science.gov (United States)

Nyhan, J W; White, G C; Trujillo, G

1982-10-01

Stream channel sediments and adjacent bank soils found in three intermittent streams used for treated liquid effluent disposal at Los Alamos, New Mexico were sampled to determine the distribution of 238Pu, 239,240Pu and 137Cs. Radionuclide concentrations and inventories were determined as functions of distance downstream from the waste outfall and from the center of the stream channel, soil sampling depth, stream channel-bank physiography, and the waste use history of each disposal area. Radionuclide concentrations in channel sediments were inversely related to distances up to 10 km downstream from the outfalls. For sites receiving appreciable waste effluent additions, contaminant concentrations in bank soils decreased with perpendicular distances greater than 0.38 m from the stream channel, and with stream bank sampling depths greater than 20-40 cm. Concentrations and total inventories of radionuclides in stream bank soils generally decreased as stream bank height increased. Inventory estimates of radionuclides in channel sediments exhibited coefficients of variation that ranged 0.41-2.6, reflecting the large variation in radionuclide concentrations at each site. Several interesting temporal relationships of these radionuclides in intermittent streams were gleaned from the varying waste use histories of the three effluent-receiving areas. Eleven yr after liquid wastes were added to one canyon, the major radionuclide inventories were found in the stream bank soils, unlike most of the other currently-used receiving areas. A period of time greater than 6 yr seems to be required before the plutonium in liquid wastes currently added to the canyon is approximately equilibrated with the plutonium in the bank soils. These observations are discussed relative to waste management practices in these southwestern intermittent streams.

Development of advanced mixed oxide fuels for plutonium management

International Nuclear Information System (INIS)

Eaton, S.; Beard, C.; Buksa, J.; Butt, D.; Chidester, K.; Havrilla, G.; Ramsey, K.

1997-01-01

A number of advanced Mixed Oxide (MOX) fuel forms are currently being investigated at Los Alamos National Laboratory that have the potential to be effective plutonium management tools. Evolutionary Mixed Oxide (EMOX) fuel is a slight perturbation on standard MOX fuel, but achieves greater plutonium destruction rates by employing a fractional nonfertile component. A pure nonfertile fuel is also being studied. Initial calculations show that the fuel can be utilized in existing light water reactors and tailored to address different plutonium management goals (i.e., stabilization or reduction of plutonium inventories residing in spent nuclear fuel). In parallel, experiments are being performed to determine the feasibility of fabrication of such fuels. Initial EMOX pellets have successfully been fabricated using weapons-grade plutonium. (author)

Development of advanced mixed oxide fuels for plutonium management

International Nuclear Information System (INIS)

Eaton, S.; Beard, C.; Buksa, J.; Butt, D.; Chidester, K.; Havrilla, G.; Ramsey, K.

1997-06-01

A number of advanced Mixed Oxide (MOX) fuel forms are currently being investigated at Los Alamos National Laboratory that have the potential to be effective plutonium management tools. Evolutionary Mixed Oxide (EMOX) fuel is a slight perturbation on standard MOX fuel, but achieves greater plutonium destruction rates by employing a fractional nonfertile component. A pure nonfertile fuel is also being studied. Initial calculations show that the fuel can be utilized in existing light water reactors and tailored to address different plutonium management goals (i.e., stabilization or reduction of plutonium inventories residing in spent nuclear fuel). In parallel, experiments are being performed to determine the feasibility of fabrication of such fuels. Initial EMOX pellets have successfully been fabricated using weapons-grade plutonium

Stack released plutonium in the environment of a nuclear fuel reprocessing facility

International Nuclear Information System (INIS)

Horton, J.H.; Sanders, S.M.; Corey, J.C.

1979-01-01

Chemical separations facilities at the Savannah River Plant have released very small quantities of plutonium to the environment since 1955. Characterization studies of airborne particulates from the process stack show that the plutonium is nearly always attached to nonradioactive particles. The geometric mean diameter of plutonium-bearing particulates in the stack gas is 5.43 μm. Most of the particles contain less than 10 -15 Ci of 239 Pu. Studies with cascade impactors 1.1 m above the ground indicated that the average annual air concentration was 612 x 10 -18 Ci/m 3 (less than 0.1% of the maximum permissible concentration recommended by the ICRP). Cropping studies showed plutonium concentrations of 3 x 10 -3 pCi/g in wheat, 5.5 x 10 -4 in soybeans, and 1.7 x 10 -4 in corn. The 70-year dose-to-bone from ingesting 10 5 g of grain would be less than 1 mrem

Optimization of air-sparged plutonium oxalate/hydroxide precipitators

International Nuclear Information System (INIS)

VanderHeyden, W.B.; Yarbro, S.L.; Fife, K.W.

1997-04-01

The high cost of waste management and experimental work makes numerical modeling an inexpensive and attractive tool for optimizing and understanding complex chemical processes. Multiphase open-quotes bubbleclose quotes columns are used extensively at the Los Alamos Plutonium Facility for a variety of different applications. No moving parts and efficient mixing characteristics allow them to be used in glovebox operations. Initially, a bubble column for oxalate precipitations is being modeled to identify the effect of various design parameters such as, draft tube location, air sparge rate and vessel geometry. Two-dimensional planar and axisymmetric models have been completed and successfully compared to literature data. Also, a preliminary three-dimensional model has been completed. These results are discussed in this report along with future work

Evaluation of the DYMAC demonstration program. Phase III report

International Nuclear Information System (INIS)

Malanify, J.J.; Bearse, R.C.

1980-01-01

An accountancy system based on the Dynamic Materials Accountability (DYMAC) System has been in operation at the Plutonium Processing Facility at the Los Alamos National Laboratory since January 1978. This system, now designated the Plutonium Facility/Los Alamos Safeguards System (PF/LASS), has enhanced nuclear material accountability and process control at the Los Alamos facility. The nondestructive assay instruments and the central computer system are operating accurately and reliably. As anticipated, several uses of the system, notably scrap control and quality control, have developed in addition to safeguards. The successes of this experiment strongly suggest that implementation of DYMAC-based systems should be attempted at other facilities

Risk-based analysis for prioritization and processing in the Los Alamos National Laboratory 94-1 program

International Nuclear Information System (INIS)

Boerigter, S.T.; DeMuth, N.S.; Tietjen, G.

1996-10-01

A previous report, open-quotes Analysis of LANL Options for Processing Plutonium Legacy Materials,close quotes LA-UR-95-4301, summarized the development of a risk-based prioritization methodology for the Los Alamos National Laboratory (LANL) Plutonium Facility at Technical Area-55 (TA-55). The methodology described in that report was developed not only to assist processing personnel in prioritizing the remediation of legacy materials but also to evaluate the risk impacts of schedule modifications and changes. Several key activities were undertaken in the development of that methodology. The most notable was that the risk assessments were based on statistically developed data from sampling containers in the vault and evaluating their condition; the data from the vault sampling programs were used as the basis for risk estimates. Also, the time-dependent behavior of the legacy materials was explicitly modeled and included in the risk analysis. The results indicated that significant reductions in program risk can be achieved by proper prioritization of the materials for processing

SNM holdup assessment of Los Alamos exhaust ducts

International Nuclear Information System (INIS)

Marshall, R.S.

1994-02-01

Fissile material holdup in glovebox and fume hood exhaust ducting has been quantified for all Los Alamos duct systems. Gamma-based, nondestructive measurements were used to quantify holdup. The measurements were performed during three measurement campaigns. The first campaign, Phase I, provided foot-by-foot, semiquantitative measurement data on all ducting. These data were used to identify ducting that required more accurate (quantitative) measurement. Of the 280 duct systems receiving Phase I measurements, 262 indicated less than 50 g of fissile holdup and 19 indicated fissile holdup of 50 or more grams. Seven duct systems were measured in a second campaign, called Series 1, Phase II. Holdup estimates on these ducts ranged from 421 g of 235 U in a duct servicing a shut-down uranium-machining facility to 39 g of 239 Pu in a duct servicing an active plutonium-processing facility. Measurements performed in the second campaign proved excessively laborious, so a third campaign was initiated that used more efficient instrumentation at some sacrifice in measurement quality. Holdup estimates for the 12 duct systems measured during this third campaign ranged from 70 g of 235 U in a duct servicing analytical laboratories to 1 g of 235 U and 1 g of 239 Pu in a duct carrying exhaust air to a remote filter building. These quantitative holdup estimates support the conclusion made at the completion of the Phase I measurements that only ducts servicing shut-down uranium operations contain about 400 g of fissile holdup. No ventilation ducts at Los Alamos contain sufficient fissile material holdup to present a criticality safety concern

Liquid waste treatment at plutonium fuels fabrication facility, 2

International Nuclear Information System (INIS)

Matsumoto, Ken-ichi; Itoh, Ichiroh; Ohuchi, Jin; Miyo, Hiroaki

1974-01-01

The economics in the management of the radioactive liquid waste from Plutonium Fuels Fabrication Facility with sludge-blanket type flocculators has been evaluated. (1) Cost calculation: The cost of chemicals and electricity to treat 1 cubic meter of liquid waste is about 876 yen, while the total operating cost is 250 thousand yen per cubic meter in the case of 140 m 3 /year treatment. These figures are much higher than those for ordinary wastes, due to the particular operation against plutonium. (2) Proposal of the closed system for liquid waste treatment at PFFF: In the case of a closed system using evaporator, ion exchange column and rotary-kiln calciner, the operating cost is estimated at 40 thousand yen per cubic meter of liquid waste. Final radioactivity of treated liquid is below 10 -8 micro curies/ml. (Mori, K.)

Los Alamos National Laboratory and Lawrence Livermore National Laboratory Plutonium Sustainment Monthly Program Report - March 2012

International Nuclear Information System (INIS)

McLaughlin, Anastasia Dawn; Storey, Bradford G.; Bowidowicz, Martin; Robertson, William G.; Hobson, Beverly F.

2012-01-01

In March of 2012 the Plutonium Sustainment program at LANL completed or addressed the following high-level activities: (1) Delivered Revision 2 of the Plutonium Sustainment Manufacturing Study, which incorporated changes needed due to the release of the FY2013 President's Budget and the delay in the Chemistry and Metallurgy Research Replacement Nuclear Facility (CMRRNF). (2) W87 pit type development activities completed a detailed process capability review for the flowsheet in preparation for the Engineering Development Unit Build. (3) Completed revising the Laser Beam Welding schedule to address scope and resource changes. (4) Completed machining and inspecting the first set of high-fidelity cold parts on Precitech 2 for Gemini. (5) The Power Supply Assembly Area started floor cutting with a concrete saw and continued legacy equipment decommissioning. There are currently no major issues associated with achieving MRT L2 Milestones 4195-4198 or the relevant PBIs associated with Plutonium Sustainment. There are no budget issues associated with FY12 final budget guidance. Table 1 identifies all Baseline Change Requests (BCRs) that were initiated, in process, or completed during the month. The earned value metrics overall for LANL are within acceptable thresholds, so no high-level recovery plan is required. Each of the 5 major LANL WBS elements is discussed in detail.

LASL experience in decontamination of the environment

International Nuclear Information System (INIS)

Ahlquist, A.J.

1981-01-01

This discussion represents one part of a major effort in soil decontamination at the Los Alamos site. A contaminated industrial waste line in the Los Alamos townsite was removed, and a plutonium incineration facility, and a filter building contaminated with actinium-227 were dismantled. The former plutonium handling facility has been decontaminated, and canyons and an old firing site contaminated with strontium-90 have been surveyed

Progress on plutonium stabilization

Energy Technology Data Exchange (ETDEWEB)

Hurt, D. [Defense Nuclear Facilities Safety Board, Washington, DC (United States)

1996-05-01

The Defense Nuclear Facilities Safety Board has safety oversight responsibility for most of the facilities where unstable forms of plutonium are being processed and packaged for interim storage. The Board has issued recommendations on plutonium stabilization and has has a considerable influence on DOE`s stabilization schedules and priorities. The Board has not made any recommendations on long-term plutonium disposition, although it may get more involved in the future if DOE develops plans to use defense nuclear facilities for disposition activities.

Progress on plutonium stabilization

International Nuclear Information System (INIS)

Hurt, D.

1996-01-01

The Defense Nuclear Facilities Safety Board has safety oversight responsibility for most of the facilities where unstable forms of plutonium are being processed and packaged for interim storage. The Board has issued recommendations on plutonium stabilization and has has a considerable influence on DOE's stabilization schedules and priorities. The Board has not made any recommendations on long-term plutonium disposition, although it may get more involved in the future if DOE develops plans to use defense nuclear facilities for disposition activities

Inventory extension at the Nuclear Materials Storage Facility

International Nuclear Information System (INIS)

Stanbro, W.D.; Longmire, V.; Olinger, C.T.; Argo, P.E.

1996-09-01

The planned renovation of the Nuclear Material Storage Facility (NMSF) at Los Alamos National Laboratory will be a significant addition to the plutonium storage capacity of the nuclear weapons complex. However, the utility of the facility may be impaired by an overly conservative approach to performing inventories of material in storage. This report examines options for taking advantage of provisions in Department of Energy orders to extend the time between inventories. These extensions are based on a combination of modern surveillance technology, facility design features, and revised operational procedures. The report also addresses the possibility that NMSF could be the site of some form of international inspection as part of the US arms control and nonproliferation policy

Automated System Calibration and Verification of the Position Measurements for the Los Alamos Isotope Production Facility and the Switchyard Kicker Facilities

Science.gov (United States)

Barr, D.; Gilpatrick, J. D.; Martinez, D.; Shurter, R. B.

2004-11-01

The Los Alamos Neutron Science Center (LANSCE) facility at Los Alamos National Laboratory has constructed both an Isotope Production Facility (IPF) and a Switchyard Kicker (XDK) as additions to the H+ and H- accelerator. These additions contain eleven Beam Position Monitors (BPMs) that measure the beam's position throughout the transport. The analog electronics within each processing module determines the beam position using the log-ratio technique. For system reliability, calibrations compensate for various temperature drifts and other imperfections in the processing electronics components. Additionally, verifications are periodically implemented by a PC running a National Instruments LabVIEW virtual instrument (VI) to verify continued system and cable integrity. The VI communicates with the processor cards via a PCI/MXI-3 VXI-crate communication module. Previously, accelerator operators performed BPM system calibrations typically once per day while beam was explicitly turned off. One of this new measurement system's unique achievements is its automated calibration and verification capability. Taking advantage of the pulsed nature of the LANSCE-facility beams, the integrated electronics hardware and VI perform calibration and verification operations between beam pulses without interrupting production beam delivery. The design, construction, and performance results of the automated calibration and verification portion of this position measurement system will be the topic of this paper.

Seismic vulnerability study Los Alamos Meson Physics Facility (LAMPF)

International Nuclear Information System (INIS)

Salmon, M.; Goen, L.K.

1995-01-01

The Los Alamos Meson Physics Facility (LAMPF), located at TA-53 of Los Alamos National Laboratory (LANL), features an 800 MeV proton accelerator used for nuclear physics and materials science research. As part of the implementation of DOE Order 5480.25 and in preparation for DOE Order 5480.28, a seismic vulnerability study of the structures, systems, and components (SSCs) supporting the beam line from the accelerator building through to the ends of die various beam stops at LAMPF has been performed. The study was accomplished using the SQUG GIP methodology to assess the capability of the various SSCs to resist an evaluation basis earthquake. The evaluation basis earthquake was selected from site specific seismic hazard studies. The goals for the study were as follows: (1) identify SSCs which are vulnerable to seismic loads; and (2) ensure that those SSCs screened during die evaluation met the performance goals required for DOE Order 5480.28. The first goal was obtained by applying the SQUG GIP methodology to those SSCS represented in the experience data base. For those SSCs not represented in the data base, information was gathered and a significant amount of engineering judgment applied to determine whether to screen the SSC or to classify it as an outlier. To assure the performance goals required by DOE Order 5480.28 are met, modifications to the SQUG GIP methodology proposed by Salmon and Kennedy were used. The results of this study ire presented in this paper

Preliminary report of the comparison of multiple non-destructive assay techniques on LANL Plutonium Facility waste drums

International Nuclear Information System (INIS)

Bonner, C.; Schanfein, M.; Estep, R.

1999-01-01

Prior to disposal, nuclear waste must be accurately characterized to identify and quantify the radioactive content. The DOE Complex faces the daunting task of measuring nuclear material with both a wide range of masses and matrices. Similarly daunting can be the selection of a non-destructive assay (NDA) technique(s) to efficiently perform the quantitative assay over the entire waste population. In fulfilling its role of a DOE Defense Programs nuclear User Facility/Technology Development Center, the Los Alamos National Laboratory Plutonium Facility recently tested three commercially built and owned, mobile nondestructive assay (NDA) systems with special nuclear materials (SNM). Two independent commercial companies financed the testing of their three mobile NDA systems at the site. Contained within a single trailer is Canberra Industries segmented gamma scanner/waste assay system (SGS/WAS) and neutron waste drum assay system (WDAS). The third system is a BNFL Instruments Inc. (formerly known as Pajarito Scientific Corporation) differential die-away imaging passive/active neutron (IPAN) counter. In an effort to increase the value of this comparison, additional NDA techniques at LANL were also used to measure these same drums. These are comprised of three tomographic gamma scanners (one mobile unit and two stationary) and one developmental differential die-away system. Although not certified standards, the authors hope that such a comparison will provide valuable data for those considering these different NDA techniques to measure their waste as well as the developers of the techniques

Quality control activities in support of the plutonium workers study. Assessment of coding consistency for data collected at Rocky Flats

International Nuclear Information System (INIS)

Reyes, M.; Wilkinson, G.S.; Acquavella, J.F.

1984-03-01

The Plutonium Workers Study is a multifaceted epidemiologic investigation of workers at six Department of Energy (DOE) facilities: Los Alamos, Rocky Flats, Mound, Savannah River, Oak Ridge, and Hanford. Information from a variety of record sources has been collected and abstracted for these studies. This report considers the accuracy of the demographic, occupational, and radiation exposure data collected for studies at Rocky Flats. the majority of the information was accurately abstracted, and analyses based on these data may be conducted

Systems concepts for DOE facilities: analysis of PF/LASS data

International Nuclear Information System (INIS)

Bearse, R.C.; Shirk, D.G.; Marshall, R.S.; Thomas, C.C. Jr.

1982-06-01

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

Sampling and Analysis Plan for the 233-S Plutonium Concentration Facility

International Nuclear Information System (INIS)

Mihalic, M.A.

1998-02-01

This Sampling and Analysis Plan (SAP) provides the information and instructions to be used for sampling and analysis activities in the 233-S Plutonium Concentration Facility. The information and instructions herein are separated into three parts and address the Data Quality Objective (DQO) Summary Report, Quality Assurance Project Plan (QAP), and SAP

Los Alamos National Laboratory plans for a laboratory microfusion facility

International Nuclear Information System (INIS)

Harris, D.B.

1988-01-01

Los Alamos National Laboratory is actively participating in the National Laboratory Microfusion Facility (LMF) Scoping Study. We are currently performing a conceptual design study of a krypton-fluoride laser system that appears to meet all of the diver requirements for the LMF. A new theory of amplifier module scaling has been developed recently and it appears that KrF amplifier modules can be scaled up to output energies much larger than thought possible a few years ago. By using these large amplifier modules, the reliability and availability of the system is increased and its cost and complexity is decreased. Final cost figures will be available as soon as the detailed conceptual design is complete

Improved practices for packaging transuranic waste at Los Alamos National Laboratory (LA-UR-09-03293) - 16280

International Nuclear Information System (INIS)

Goyal, Kapil K.; Carson, Peter H.

2009-01-01

Transuranic (TRU) waste leaving the Plutonium Facility at Los Alamos National Laboratory (LANL) is packaged using LANL's waste acceptance criteria for onsite storage. Before shipment to the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico, each payload container is subject to rigorous characterization to ensure compliance with WIPP waste acceptance criteria and Department of Transportation regulations. Techniques used for waste characterization include nondestructive examination by WIPP-certified real-time radiography (RTR) and nondestructive assay (NDA) of containers, as well as headspace gas sampling to ensure that hydrogen and other flammable gases remain at safe levels during transport. These techniques are performed under a rigorous quality assurance program to confirm that results are accurate and reproducible. If containers are deemed problematic, corrective action is implemented before they are shipped to WIPP. A defensive approach was used for many years to minimize the number of problematic drums. However, based on review of data associated with headspace gas sampling, NDA and RTR results, and enhanced coordination with the entities responsible for waste certification, many changes have been implemented to facilitate packaging of TRU waste drums with higher isotopic loading at the Plutonium Facility at an unprecedented rate while ensuring compliance with waste acceptance criteria. This paper summarizes the details of technical changes and related administrative coordination activities, such as information sharing among the certification entities, generators, waste packagers, and shippers. It discusses the results of all such cumulative changes that have been implemented at the Plutonium Facility and gives readers a preview of what LANL has accomplished to expeditiously certify and dispose of newly generated TRU waste. (authors)

Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design

International Nuclear Information System (INIS)

Stone, Timothy Amos

2010-01-01

Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design and performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program

Plutonium storage criteria

Energy Technology Data Exchange (ETDEWEB)

Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

1996-05-01

The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

Measurement and instrumentation techniques for monitoring plutonium and uranium particulates released from nuclear facilities

International Nuclear Information System (INIS)

Nero, A.V. Jr.

1976-08-01

The purpose of this work has been an analysis and evaluation of the state-of-the-art of measurement and instrumentation techniques for monitoring plutonium and uranium particulates released from nuclear facilities. The occurrence of plutonium and uranium in the nuclear fuel cycle, the corresponding potential for releases, associated radiological protection standards and monitoring objectives are discussed. Techniques for monitoring via decay radiation from plutonium and uranium isotopes are presented in detail, emphasizing air monitoring, but also including soil sampling and survey methods. Additionally, activation and mass measurement techniques are discussed. The availability and prevalence of these various techniques are summarized. Finally, possible improvements in monitoring capabilities due to alterations in instrumentation, data analysis, or programs are presented

Ambient air sampling for radioactive air contaminants at Los Alamos National Laboratory: A large research and development facility

International Nuclear Information System (INIS)

Eberhart, C.F.

1998-01-01

This paper describes the ambient air sampling program for collection, analysis, and reporting of radioactive air contaminants in and around Los Alamos National Laboratory (LANL). Particulate matter and water vapor are sampled continuously at more than 50 sites. These samples are collected every two weeks and then analyzed for tritium, and gross alpha, gross beta, and gamma ray radiation. The alpha, beta, and gamma measurements are used to detect unexpected radionuclide releases. Quarterly composites are analyzed for isotopes of uranium ( 234 U, 235 U, 238 U), plutonium ( 238 Pu, 239/249 Pu), and americium ( 241 Am). All of the data is stored in a relational database with hard copies as the official records. Data used to determine environmental concentrations are validated and verified before being used in any calculations. This evaluation demonstrates that the sampling and analysis process can detect tritium, uranium, plutonium, and americium at levels much less than one percent of the public dose limit of 10 millirems. The isotopic results also indicate that, except for tritium, off-site concentrations of radionuclides potentially released from LANL are similar to typical background measurements

Los Alamos Hot-Cell-Facility modifications for examining FFTF fuel pins

International Nuclear Information System (INIS)

Campbell, B.M.; Ledbetter, J.M.

1982-01-01

Commissioned in 1960, the Wing 9 Hot Cell Facility at Los Alamos was recently modified to meet the needs of the 1980s. Because fuel pins from the Fast Flux Test Facility (FFTF) at the Hanford Engineering Development Laboratory (HEDL) are too long for examination in the original hot cells, we modified cells to accommodate longer fuel pins and to provide other capabilities as well. For instance, the T-3 shipping cask now can be opened in an inert atmosphere that can be maintained for all nondestructive and destructive examinations of the fuel pins. The full-length pins are visually examined and photographed, the wire wrap is removed, and fission gas is sampled. After the fuel pin is cropped, a cap is seal-welded on the section containing the fuel column. This section is then transferred to other cells for gamma-scanning, radiography, profilometry, sectioning for metallography, and chemical analysis

Plutonium Reclamation Facility incident response project progress report

Energy Technology Data Exchange (ETDEWEB)

Austin, B.A.

1997-11-25

This report provides status of Hanford activities in response to process deficiencies highlighted during and in response to the May 14, 1997, explosion at the Plutonium Reclamation Facility. This report provides specific response to the August 4, 1997, memorandum from the Secretary which requested a progress report, in 120 days, on activities associated with reassessing the known and evaluating new vulnerabilities (chemical and radiological) at facilities that have been shut down, are in standby, are being deactivated or have otherwise changed their conventional mode of operation in the last several years. In addition, this report is intended to provide status on emergency response corrective activities as requested in the memorandum from the Secretary on August 28, 1997. Status is also included for actions requested in the second August 28, 1997, memorandum from the Secretary, regarding timely notification of emergencies.

Plutonium Reclamation Facility incident response project progress report

International Nuclear Information System (INIS)

Austin, B.A.

1997-01-01

This report provides status of Hanford activities in response to process deficiencies highlighted during and in response to the May 14, 1997, explosion at the Plutonium Reclamation Facility. This report provides specific response to the August 4, 1997, memorandum from the Secretary which requested a progress report, in 120 days, on activities associated with reassessing the known and evaluating new vulnerabilities (chemical and radiological) at facilities that have been shut down, are in standby, are being deactivated or have otherwise changed their conventional mode of operation in the last several years. In addition, this report is intended to provide status on emergency response corrective activities as requested in the memorandum from the Secretary on August 28, 1997. Status is also included for actions requested in the second August 28, 1997, memorandum from the Secretary, regarding timely notification of emergencies

Los Alamos Meson Physics Facility high-resolution-spectrometer dipole magnets: a summary report

International Nuclear Information System (INIS)

Kozlowski, T.; Madland, D.G.; Rolfe, R.; Smith, W.E.; Spencer, J.E.; Tanaka, N.; Thiessen, H.A.; Varghese, P.; Wilkerson, L.C.

1982-12-01

This report explains the design, fabrication, measurement, optimization, and installation of two 122 metric ton electromagnets for the High Resolution Proton Spectrometer at the Los Alamos Meson Physics Facility. These two magnets are the principal components of the proton spectrometer, which has an energy resolution of less than or equal to 10 - 4 FWHM. Many technical problems occurred during fabrication, measurement, and optimization, and the majority have been successfully solved. We hope that this report will help others planning similar projects

OPEN AIR DEMOLITION OF FACILITIES HIGHLY CONTAMINATED WITH PLUTONIUM

International Nuclear Information System (INIS)

LLOYD, E.R.

2007-01-01

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

Use of lasers at the Los Alamos Hot-Cell Facility

International Nuclear Information System (INIS)

Lazarus, M.E.

1983-01-01

An optical profilometer that uses a Techmet LaserMike scanning, focused, laser-beam, optical micrometer is installed in a remote alpha-gamma containment cell at the Los Alamos Hot-Cell Facility. A hot-cell extension chamber provides the nominal 30-cm (12-in.) working distance required by the LaserMike and, at the same time, keeps the LaserMike components outside the high-radiation-containment environment. This system provides measurement accuracy better than +- 5 μm (0.0002 in.) on diameters between 2 and 13 mm (0.88 and 0.5 in.) at a rate of 33 measurements per second. The Hot-Cell Facility also uses a Korad 20-J-output ruby pulsed laser to drill a hole in reactor-fuel-element cladding to sample fission gas. The laser is then used to reweld the hole so that the fuel element will not be contaminated and may be stored without an alpha-containment barrier. The wall thickness of the fuel elements sampled varies from 0.25 to 0.50 mm (0.010 to 0.020 in.)

Addressing mixed waste in plutonium processing

International Nuclear Information System (INIS)

Christensen, D.C.; Sohn, C.L.; Reid, R.A.

1991-01-01

The overall goal is the minimization of all waste generated in actinide processing facilities. Current emphasis is directed toward reducing and managing mixed waste in plutonium processing facilities. More specifically, the focus is on prioritizing plutonium processing technologies for development that will address major problems in mixed waste management. A five step methodological approach to identify, analyze, solve, and initiate corrective action for mixed waste problems in plutonium processing facilities has been developed

RCRA facility investigation for the townsite of Los Alamos, New Mexico

International Nuclear Information System (INIS)

Dorries, A.M.; Conrad, R.C.; Nonno, L.M.

1992-01-01

During World War II, Los Alamos, New Mexico was established as an ideal location for the secrecy and safety needed for the research and development required to design a nuclear fission bomb. Experiments carried out in the 1940s generated both radioactive and hazardous waste constituents on what is presently part of the Los Alamos townsite. Under the RCRA permit issued to Los alamos national Laboratory in 1990, the Laboratory is scheduled for investigation of its solid waste management units (SWMUs). The existing information on levels of radioactivity on the townsite is principally data from soil samples taken during the last site decontamination in 1976, little information on the presence of hazardous constituents exists today. This paper addresses pathway analysis and a preliminary risk assessment for current residents of the Los Alamos townsite. The estimated dose levels, in mrem per year, show that the previously decontaminated SWMU areas on the Los Alamos townsite will not contribute a radiation dose of any concern to the current residents

French en engineering and operation rules for plutonium facilities

International Nuclear Information System (INIS)

Bertolotti, G.; Drain, F.; Dubois, G.; Monnatte, J.; Mathieu, P.

1998-01-01

COGEMA is operating large size purifying and conditioning plutonium facilities at LA HAGUE and MOX fuels fabrication plant at Marcoule. A high safety standard is recognised for these facilities. It is mainly based on : - prevention of spreading of radioactive materials to workers and environment by physical barriers ensuring static containment and by a cascade of pressure differentials ensuring dynamic containment, - radiation shielding and remote controlled processes ensuring very low dose to workers, - prevention of criticality accident by criticality control methods and double contingency principle, - prevention of fire risks by control of ignition sources, adequate management of combustible materials, physical separation between zones where there is a risk of fire and the remainder of the facility. The facilities are operated while respecting safety requirements as described in the General Operating Rules. The equipment involved in safety functions are monitored and periodically checked. Continuous improvement by incorporation of feed back of safety experience results in: - effective decrease of exposure to operating staff; - reduction of solid waste, liquid and gaseous effluents; - no significant incident recorded. (author)

Design of an error-free nondestructive plutonium assay facility

International Nuclear Information System (INIS)

Moore, C.B.; Steward, W.E.

1987-01-01

An automated, at-line nondestructive assay (NDA) laboratory is installed in facilities recently constructed at the Savannah River Plant. The laboratory will enhance nuclear materials accounting in new plutonium scrap and waste recovery facilities. The advantages of at-line NDA operations will not be realized if results are clouded by errors in analytical procedures, sample identification, record keeping, or techniques for extracting samples from process streams. Minimization of such errors has been a primary design objective for the new facility. Concepts for achieving that objective include mechanizing the administrative tasks of scheduling activities in the laboratory, identifying samples, recording and storing assay data, and transmitting results information to process control and materials accounting functions. These concepts have been implemented in an analytical computer system that is programmed to avoid the obvious sources of error encountered in laboratory operations. The laboratory computer exchanges information with process control and materials accounting computers, transmitting results information and obtaining process data and accounting information as required to guide process operations and maintain current records of materials flow through the new facility

Surplus plutonium disposition draft environmental impact statement. Volume 2

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. Volume 2 contains the appendices to the report and describe the following: Federal Register notices; contractor nondisclosure statement; adjunct melter

Los Alamos, Hiroshima, Nagasaki - a personal recollection

International Nuclear Information System (INIS)

Morrison, P.

1995-01-01

The author, a physicist participating in the Manhattan Project, recalls his experiences and work in the laboratories at the time which marked the onset of the nuclear era, the construction of the first uranium and plutonium bombs in Los Alamos, and the hidious effects shown to the world by the nuclear bombing of Japan. His thoughts and memories presented 50 years after the nuclear destruction of Hiroshima and Nagasaki, and now that the Cold War has ended, call for a global ban of nuclear weapons. (orig.) [de

A feasibility study for the storage of plutonium pits in non-partitioned warehouse facilities

International Nuclear Information System (INIS)

James, D.; Parameswaren, S.; Nagendran, S.

1999-02-01

It is projected that up to 20,000 plutonium pits will be stored at Pantex for up to 50 years. The proposed storage system has to meet longevity, safety and cost requirements. Thermal, mechanical, chemical, nuclear criticality and safety performance characteristics of any proposed plutonium container design need to be formally analyzed. Plutonium generates thermal energy as it decays. The generated thermal energy may cause excessive rise of temperature. For safety and other considerations, it is important that the plutonium temperature remains relatively constant and no hot spots develop. Plutonium containers should not be disassembled for routine monitoring and there are various reasons for the need to monitor the plutonium non-obtrusively. Therefore, accurate predictions of the temperature distribution within the storage container based upon external monitoring within the storage facility needs to be developed. A heat transfer analysis of the storage container is required. The heat transfer analysis, however, requires the knowledge of the temperature and velocity of the air circulating around the containers in order to determine the heat transferred to the air from the containers by convection. Therefore, a complete flow field analysis is required prior to performing the conduction analysis of each pit. The objective of this research is, therefore, to develop and validate a numerical model to predict the temperature distribution within the plutonium storage container as a function of the ambient air temperature within the warehouse

Development of an expert system for analysis of plutonium processing operations

International Nuclear Information System (INIS)

Boeringter, S.T.; Fasel, J.H.; Kornreich, D.E.

2001-01-01

At Los Alamos National Laboratory (LANL) an expert system has been developed for the analysis and assessment of plutonium processing operations. This system is based upon an object-oriented simulation environment specifically developed for the needs of nuclear material processing. The simulation environment, called the ''Process Modeling System'' (ProMoS), contains a library of over 250 plutonium-based unit process operations ranging from analytical chemistry, oxide operations, recycle and recovery, waste management, and component fabrication. (author)

Surplus plutonium disposition draft environmental impact statement. Summary

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel

Contaminant monitoring of biota downstream of a radioactive liquid waste treatment facility, Los Alamos National Laboratory

International Nuclear Information System (INIS)

Bennett, K.D.; Biggs, J.R.; Fresquez, P.R.

1996-01-01

Small mammals, plants, and sediments were sampled at one upstream location (Site 1) and two downstream locations (Site 2 and Site 3) from the National Pollution Discharge Elimination System (NPDES) outfall number-sign 051-051 in Mortandad Canyon, Los Alamos National Laboratory, Los Alamos, New Mexico. The purpose of the sampling was to identify radionuclides potentially present, to quantitatively estimate and compare the amount of radionuclide uptake at specific locations (Site 2 and Site 3) within Mortandad Canyon to an upstream site (Site 1), and to identify the primary mode (inhalation/ingestion or surface contact) of contamination to small mammals. Three composite samples of at least five animals per sample were collected at each site. The pelt was separated from the carcass of each animal and both were analyzed independently. In addition, three composite samples were also collected for plants and sediments at each site. Samples were analyzed for americium ( 241 Am), strontium ( 90 Sr), plutonium ( 238 Pu and 239 Pu), and total uranium (U). With the exception of total U, all mean radionuclide concentrations in small mammal carcasses and sediments were significantly higher at Site 2 than Site 1 or Site 3. No differences were detected in the mean radionuclide concentration of plant samples between sites. However, some radionuclide concentrations found at all three sites were higher than regional background. No differences were found between mean carcass radionuclide concentrations and mean pelt radionuclide concentrations, indicating that the two primary modes of contamination may be equally occurring

Plutonium Disposition Now exclamation point

International Nuclear Information System (INIS)

Buckner, M.R.

1995-01-01

A means for use of existing processing facilities and reactors for plutonium disposition is described which requires a minimum capital investment and allows rapid implementation. The scenario includes interim storage and processing under IAEA control, and fabrication into MOX fuel in existing or planned facilities in Europe for use in operating reactors in the two home countries. Conceptual studies indicate that existing Westinghouse four-loop designs can safety dispose of 0.94 MT of plutonium per calendar year. Thus, it would be possible to consume the expected US excess stockpile of about 50 MT in two to three units of this type, and it is highly likely that a comparable amount of the FSU excess plutonium could be deposed of in a few VVER-1000's. The only major capital project for this mode of plutonium disposition would be the weapons-grade plutonium processing which could be done in a dedicated international facility or using existing facilities in the US and FSU under IAEA control. This option offers the potential for quick implementation at a very low cost to the governments of the two countries

Radioisotope research and development at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Peterson, E.J.

1993-01-01

Throughout its fifty year history, Los Alamos National Laboratory has conducted research and development in the production, isolation, purification, and application of radioactive isotopes. Initially this work supported the weapons development mission of the Laboratory. Over the years the work has evolved to support basic and applied research in many diverse fields, including nuclear medicine, biomedical studies, materials science, environmental research and the physical sciences. In the early 1970s people in the Medical Radioisotope Research Program began irradiating targets at the Los Alamos Meson Physics Facility (LAMPF) to investigate the production and recovery of medically important radioisotopes. Since then spallation production using the high intensity beam at LAMPF has become a significant source of many important radioisotopes. Los Alamos posesses other facilities with isotope production capabilities. Examples are the Omega West Reactor (OWR) and the Van de Graaf Ion Beam Facility (IBF). Historically these facilities have had limited availability for radioisotope production, but recent developments portend a significant radioisotope production mission in the future

History of PUQFUA: plutonium body burden (Q) from urine assays

International Nuclear Information System (INIS)

Lawrence, J.N.P.

1978-10-01

PUQFUA is a FORTRAN computer program that calculates plutonium body burdens (Q) from urine assay data. This report describes the historical development of the program at the Los Alamos Scientific Laboratory (LASL) since 1959. After a review of the basic techniques used in the original PUQFUA, its deficiencies are listed. The procedures used to improve the program and correct the deficiencies are described. Appendixes provide a detailed discussion of the evaluation made of the analytical errors in the plutonium urine assay program at LASL from 1944 to 1978

Underground science initiatives at Los Alamos

International Nuclear Information System (INIS)

Simmons, L.M. Jr.

1985-01-01

Recently, the Los Alamos National Laboratory has proposed two major new initiatives in underground science. Following the dissolution of the original gallium solar neutrino collaboration, Los Alamos has formed a new North American collaboration. We briefly review the rationale for solar neutrino research, outline the proposal and new Monte Carlo simulations, and describe the candidate locations for the experiment. Because there is no dedicated deep underground site in North America suitable for a wide range of experiments, Los Alamos has conducted a survey of possible sites and developed a proposal to create a new National Underground Science Facility. This paper also reviews that proposal

Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume I: Summary

International Nuclear Information System (INIS)

1994-11-01

At the conclusion of the Cold War, the Department of Energy (DOE) stopped plutonium processing for nuclear weapons production. Facilities used for that purpose now hold significant quantities of plutonium in various forms. Unless properly stored and handled, plutonium can present environment, safety and health (ES ampersand H) hazards. Improperly stored plutonium poses a variety of hazards. When containers or packaging fail to fully protect plutonium metal from exposure to air, oxidation can occur and cause packaging failures and personnel contamination. Contamination can also result when plutonium solutions leak from bottles, tanks or piping. Plutonium in the form of scrap or residues generated by weapons production are often very corrosive, chemically reactive and difficult to contain. Buildings and equipment that are aging, poorly maintained or of obsolete design contribute to the overall problem. Inadvertent accumulations of plutonium of any form in sufficient quantities within facilities can result in nuclear criticality events that could emit large amounts of radiation locally. Contamination events and precursors of criticality events are causing safety and health concerns for workers at the Department's plutonium facilities. Contamination events also potentially threaten the public and the surrounding environment

Calculation of displacement and helium production at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF) irradiation facility

International Nuclear Information System (INIS)

Wechsler, M.S.; Davidson, D.R.; Greenwood, L.R.; Sommer, W.F.

1984-01-01

CT: Differential and total displacement and helium production rates are calculated for copper irradiated by spallation neutrons and 760 MeV protons at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF). The calculations are performed using the SPECTER and VNMTC computer codes, the latter being specially designed for spallation radiation damage calculations. For comparison, similar SPECTER calculations are also described for irradiation of copper in EBR-II and RTNS-II. The results indicate substantial contributions to the displacement and helium production rates due to neutrons in the high-energy tail (above 20 MeV) of the LAMPF spallation neutron spectrum. Still higher production rates are calculated for irradiations in the direct proton beam. These results will provide useful background information for research to be conducted at a new irradiation facility at LAMPF

Material handling for the Los Alamos National Laboratory Nuclear Storage Facility

International Nuclear Information System (INIS)

Pittman, P.; Roybal, J.; Durrer, R.; Gordon, D.

1999-01-01

This paper will present the design and application of material handling and automation systems currently being developed for the Los Alamos National Laboratory (LANL) Nuclear Material Storage Facility (NMSF) renovation project. The NMSF is a long-term storage facility for nuclear material in various forms. The material is stored within tubes in a rack called a basket. The material handling equipment range from simple lift assist devices to more sophisticated fully automated robots, and are split into three basic systems: a Vault Automation System, an NDA automation System, and a Drum handling System. The Vault Automation system provides a mechanism to handle a basket of material cans and to load/unload storage tubes within the material vault. In addition, another robot is provided to load/unload material cans within the baskets. The NDA Automation System provides a mechanism to move material within the small canister NDA laboratory and to load/unload the NDA instruments. The Drum Handling System consists of a series of off the shelf components used to assist in lifting heavy objects such as pallets of material or drums and barrels

Decontamination of Battelle-Columbus' Plutonium Facility. Final report

International Nuclear Information System (INIS)

Rudolph, A.; Kirsch, G.; Toy, H.L.

1984-01-01

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

Gamma-ray isotopic analysis development at Los Alamos

Energy Technology Data Exchange (ETDEWEB)

Thomas E. Sampson

1999-11-01

This report describes the development history and characteristics of software developed in the Safeguards Science and Technology group at Los Alamos for gamma-ray isotopic analysis. This software analyzes the gamma-ray spectrum from measurements performed on actinide samples (principally plutonium and uranium) of arbitrary size, geometry, and physical and chemical composition. The results are obtained without calibration using only fundamental tabulated nuclear constants. Characteristics of the current software versions are discussed in some detail and many examples of implemented measurement systems are shown.

Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility

International Nuclear Information System (INIS)

Rugg, J.E.

1996-08-01

The 100, 200, 300 and 1100 Areas of the Hanford Site were placed on the U. S. Environmental Protection Agency's National Priorities List in November 1989 under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Located in the 200 Area is the deactivated 233-S Plutonium Concentration Facility (used in the REDOX process). The facility has undergone severe degradation due to exposure to extreme weather conditions. An expedited response is proposed to ensure protection of human health and the environment. The Department of Energy, Richland Operations Office (RL) in cooperation with the Washington State Department of Ecology, has prepared this Engineering Evaluation/Cost Analysis pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health or the environment, and that an expedited removal action is warranted for decommissioning of the facility

Operational advanced materials control and accountability system

International Nuclear Information System (INIS)

Malanify, J.J.; Bearse, R.C.; Christensen, E.L.

1980-01-01

An accountancy system based on the Dynamic Materials Accountability (DYMAC) System has been in operation at the Plutonium Processing Facility at the Los Alamos Scientific Laboratory (LASL) since January 1978. This system, now designated the Plutonium Facility/Los Alamos Safeguards System (PF/LASS), has enhanced nuclear material accountability and process control at the LASL facility. The nondestructive assay instruments and the central computer system are operating accurately and reliably. As anticipated, several uses of the system have developed in addition to safeguards, notably scrap control and quality control. The successes of this experiment strongly suggest that implementation of DYMAC-based systems should be attempted at other facilities. 20 refs

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

International Nuclear Information System (INIS)

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

1995-01-01

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

Radiological safety aspects of handling plutonium

International Nuclear Information System (INIS)

Sundararajan, A.R.

2016-01-01

Department of Atomic Energy in its scheme of harnessing the nuclear energy for electrical power generation and strategic applications has given a huge role to utilization of plutonium. In the power production programme, fast reactors with plutonium as fuel are expected to play a major role. This would require establishing fuel reprocessing plants to handle both thermal and fast reactor fuels. So in the nuclear fuel cycle facilities variety of chemical, metallurgical, mechanical operations have to be carried out involving significant inventories of "2"3"9 Pu and associated radionuclides. Plutonium is the most radiotoxic radionuclide and therefore any facility handling it has to be designed and operated with utmost care. Two problems of major concern in the protection of persons working in plutonium handling facilities are the internal exposure to the operating personnel from uptake of plutonium and transplutonic nuclides as they are highly radiotoxic and the radiation exposure of hands and eye lens during fuel fabrication operations especially while handling recycled high burn up plutonium. In view of the fact that annual limit for intake is very small for "2"3"9Pu and its radiation emission characteristics are such that it is a huge challenge for the health physicists to detect Pu in air and in workers. This paper discusses the principles and practices followed in providing radiological surveillance to workers in plutonium handling areas. The challenges in protecting the workers from receiving exposures to hands and eye lens in handling high burn up plutonium are also discussed. The sites having Pu fuel cycle facilities should have trained medical staff to handle cases involving excessive intake of plutonium. (author)

Plutonium stabilization and storage research in the DNFSB 94-1 core technology program

International Nuclear Information System (INIS)

Eller, P.G.; Avens, L.R.; Roberson, G.D.

1998-04-01

Recommendation 94-1 of the Defense Nuclear Facility Safety Board (DNFSB) addresses legacy actinide materials left in the US nuclear defense program pipeline when the production mission ended in 1989. The Department of Energy (DOE) Implementation Plan responding to this recommendation instituted a Core Technology program to augment the knowledge base about general chemical and physical processing and storage behavior and to assure safe interim nuclear material storage, until disposition policies are formulated. The Core Technology program focuses on plutonium, in concert with a complex-wide applied R/D program administered by Los Alamos National Laboratory. This paper will summarize the Core Technology program's first two years, describe the research program for FY98, and project the overall direction of the program in the future

Studies of plutonium in human tracheobronchial lymph nodes

International Nuclear Information System (INIS)

McInroy, J.F.; Stewart, M.W.; Moss, W.D.

1976-01-01

Since 1959, tissues from 70 occupationally exposed former employees of the Los Alamos Scientific Laboratory have been examined following autopsy. Exposure in most cases was to inhaled plutonium oxide aerosols. Chemical analyses of selected tissues were performed to determine the amount of plutonium retained in the body at the time of death. On the basis of the measured tissue concentrations of plutonium, extrapolations of total-body burdens were made. Thirty-three of the measured cases had plutonium depositions in the tracheobronchial lymph nodes ranging from 0.1 to 4000 dpm per gram of tissue (0.05 to 1800 pCi/g). The duration of exposures ranged from 4 to 30 years. Microscopic examination of representative sections of these lymph nodes revealed no abnormalities other than those which were directly attributable to the basic disease that caused the demise of the various persons in this study. The size distribution of plutonium particles in nodes from one individual was determined by exposing tissue sections to nuclear track film. The estimated mass median diameter of the particles was 0.3 μm, and the distribution had a geometric standard deviation of 1.6. It is estimated that 95 percent of the individual particles had corresponding plutonium concentrations between 0.001 and 0.22 pCi

Probabilistic risk assessment for the Los Alamos Meson Physics Facility worst-case design-basis accident

International Nuclear Information System (INIS)

Sharirli, M.; Butner, J.M.; Rand, J.L.; Macek, R.J.; McKinney, S.J.; Roush, M.L.

1992-01-01

This paper presents results from a Los Alamos National Laboratory Engineering and Safety Analysis Group assessment of the worse-case design-basis accident associated with the Clinton P. Anderson Meson Physics Facility (LAMPF)/Weapons Neutron Research (WNR) Facility. The primary goal of the analysis was to quantify the accident sequences that result in personnel radiation exposure in the WNR Experimental Hall following the worst-case design-basis accident, a complete spill of the LAMPF accelerator 1L beam. This study also provides information regarding the roles of hardware systems and operators in these sequences, and insights regarding the areas where improvements can increase facility-operation safety. Results also include confidence ranges to incorporate combined effects of uncertainties in probability estimates and importance measures to determine how variations in individual events affect the frequencies in accident sequences

Recent LAMPF [Los Alamos Meson Physics Facility] research using muons

International Nuclear Information System (INIS)

Bradbury, J.N.

1987-01-01

In addition to the core programs in nuclear and particle physics, diverse experiments have been carried out that address interdisciplinary and applied topics at the Los Alamos Meson Physics Facility (LAMPF). These include muon-spin-relaxation experiments to study magnetic dynamics in spin glasses and electronic structure in heavy-fermion superconductors; muon channeling experiments to provide information on pion stopping sites in crystals; tomographic density reconstruction studies using proton energy loss; and radiation-effects experiments to explore microstructure evolution and to characterize materials for fusion devices and high-intensity accelerators. Finally, the catalysis of the d-t fusion reaction using negative muons has been extensively investigated with some surprising results including a stronger than linear dependence of the mesomolecular formation rate on target density and the observation of 150 fusions per muon under certain conditions. Recent results in those programs involving pions and muons interacting with matter are discussed

The radiological hazard of plutonium isotopes and specific plutonium mixtures

International Nuclear Information System (INIS)

Heindel, G.; Clow, J.; Inkret, W.; Miller, G.

1995-11-01

The US Department of Energy defines the hazard categories of its nuclear facilities based upon the potential for accidents to have significant effects on specific populations and the environment. In this report, the authors consider the time dependence of hazard category 2 (significant on-site effects) for facilities with inventories of plutonium isotopes and specific weapons-grade and heat-source mixtures of plutonium isotopes. The authors also define relative hazard as the reciprocal of the hazard category 2 threshold value and determine its time dependence. The time dependence of both hazard category 2 thresholds and relative hazards are determined and plotted for 10,000 years to provide useful information for planning long-term storage or disposal facilities

Los Alamos Spheromak Program

International Nuclear Information System (INIS)

Knox, S.O.; Barnes, C.W.; Fernandez, J.C.

1985-01-01

The Los Alamos Spheromak Program consists of two experimental facilities. The confinement physics of sustained and decaying spheromaks are being studied in CTX, which has an extensive array of diagnostics. Experiments are directed towards extending the physics understanding of the spheromak as a magnetic confinement concept. Electrodes for the production of clean sustained spheromaks are developed on the Electrode Facility, which is more flexible in terms of experimental modifications. Improvements to helicity sources and elecrodes which are proven on the Electrode Facility are then considered for incorporation onto CTX

Plutonium storage phenomenology

International Nuclear Information System (INIS)

Szempruch, R.

1995-12-01

Plutonium has been produced, handled, and stored at Department of Energy (DOE) facilities since the 1940s. Many changes have occurred during the last 40 years in the sources, production demands, and end uses of plutonium. These have resulted in corresponding changes in the isotopic composition as well as the chemical and physical forms of the processed and stored plutonium. Thousands of ordinary food pack tin cans have been used successfully for many years to handle and store plutonium. Other containers have been used with equal success. This paper addressees the exceptions to this satisfactory experience. To aid in understanding the challenges of handling plutonium for storage or immobilization the lessons learned from past storage experience and the necessary countermeasures to improve storage performance are discussed

Accumulation and transport of soil plutonium in liquid waste discharge areas at Los Alamos

International Nuclear Information System (INIS)

Hakonson, T.E.; Nyhan, J.W.; Purtymun, W.D.

1976-01-01

Plutonium inventory estimates for the surface 12.5 cm of soil in Mortandad Canyon did not reflect all the plutonium added to the canyon during a 7 month interval. The methods used in this study indicated that about 2 mCi 238 Pu and 0 mCisup(239,240)Pu were added to the canyon during the interval, compared with known additions of 5.5 mCi 238 Pu and 0.4 mCisup(239,240)Pu. The discrepancy likely was the result of the large sampling variability, indicating that inventory changes in this order (i.e. up to 17%) are not detectable with any certainty. However, factors other than sampling variability may be involved, including losses of plutonium to depths exceeding 12.5 cm. The relative distribution of plutonium within the canyon demonstrates that transport has occurred beyond the extent of surface water and that runoff from summer rainstorms can serve as a radionuclide transport vector in landscapes exhibiting these hydrologic features. There was a highly significant relationship between suspended sediment concentrations and total amounts of radioactivity in water. The flow rates achieved during the runoff event play an important part in determining the total amount of sediment and thus radioactivity transported downstream. The storm runoff event sampled during this study resulted in the downstream transport of about 1-2% of the sediment inventories of plutonium. (author)

Engineering study of generic site criteria for selected DOE plutonium facilities

International Nuclear Information System (INIS)

Kingsbury, R.J.; Greenwood, J.M.; Sandoval, M.D.

1980-09-01

The objectives of this study were to identify criteria that would be applied to selection of a site for plutonium facilities such as those at the Rocky Flats Plant, to establish the relative importance of these criteria, and to identify suitable areas within the United States for location of plutonium facilities with respect to these criteria. Sources of the site criteria identified include federal laws, federal agency regulations, state laws and regulations, and requirements associated with operations to be performed at the site. The criteria identified during the study were organized into 14 major categories. The relative importnace of each category and each criterion within the categories were established using group decision-making techniques. The major criteria categories, their assigned weight on a scale of 1 to 10, and their relative priority ranks are as follows: geology/seismicity; public safety; environmental impact; meteorology; hydrology; topography; transportation; utilities; personnel; safeguards/security; land area and availability; land use compatibility; and, public acceptance. A suitability analysis of the continental United States was performed using only those criteria that could be mapped at a national scale. Suitability was assessed with respect to each of these criteria, and individual suitability maps were prepared. A composite suitability map was generated using computerized overlay techniques. This map provides a starting point for identifying specific candidate sites if an actual site selection were to be conducted

Plutonium and the Rio Grande: Environmental change and contamination in the nuclear age

International Nuclear Information System (INIS)

Graf, W.L.

1994-01-01

An attempt is made to analyze questions concerning the issue of plutonium in the Rio Grande. The author describes in great detail how he arrived at the conclusions. The objective has been to produce research that is absolutely transparent, so that its results can be fairly evaluated and duplicated by anyone. The results of this work show that plutonium from Los Alamos National Laboratory and atmospheric fallout has been deposited along the Rio Grande in small, though detectable, quantities in certain predictable places

Lessons learned from decommissioning projects at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Salazar, M.

1995-01-01

This paper describes lessons learned over the last 20 years from 12 decommissioning projects at Los Alamos National Laboratory. These lessons relate both to overall program management and to management of specific projects during the planning and operations phases. The issues include waste management; the National Environmental Policy Act (NEPA); the Resource Conservation and Recovery Act (RCRA); the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); contracting; public involvement; client/customer interface; and funding. Key elements of our approach are to be proactive; follow the observation method; perform field activities concurrently; develop strategies to keep reportable incidents from delaying work; seek and use programs, methods, etc., in existence to shorten learning curves; network to help develop solutions; and avoid overstudying and overcharacterizing. This approach results in preliminary plans that require very little revision before implementation, reasonable costs and schedules, early acquisition of permits and NEPA documents, preliminary characterization reports, and contracting documents. Our track record is good -- the last four projects (uranium and plutonium-processing facility and three research reactors) have been on budget and on schedule

CONTAMINATED PROCESS EQUIPMENT REMOVAL FOR THE DECOMMISSIONG AND DECONTAMINATION OF THE 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINISHING PLANT

International Nuclear Information System (INIS)

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

2007-01-01

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

Research opportunities at the proposed Los Alamos XUV-FEL user facility

International Nuclear Information System (INIS)

Conradson, S.D.; Newman, B.E.

1990-01-01

This paper reports that within the last several years a number of meetings and conferences have addressed the unique scientific opportunities which would result from the development of an RF-linac FEL user facility accessing the XUV and mid-IR spectral regions. The capabilities of a number of linear and nonlinear spectroscopies would be enhanced by one or more features of the FEL output, e.g., its free tunability in these regions, transform-limited linewidth, high peak power and brightness, time structure, and the possibility of multi-color pump-probe experiments utilizing the coordinated output from more than one FEL oscillator. These advances would in turn benefit a variety of scientific areas. In the realm of basic science, experiments or measurements which ether require an FEL or where increased sensitivity would be advantageous can be found in quantum, atomic, cluster, molecular, and condensed matter physics, magnetic materials, surface science and catalysis, non-linear spectroscopy, and biophysics and -chemistry and physics, advanced fabrication processes, medical applications, and others. These applications form the basis for the specifications of the FEL and for the design of the laboratories for the proposed FEL user facility at Los Alamos

Current developments of fuel fabrication technologies at the plutonium fuel production facility, PFPF

International Nuclear Information System (INIS)

Asakura, K.; Aono, S.; Yamaguchi, T.; Deguchi, M.

2000-01-01

The Japan Nuclear Cycle Development Institute, JNC, designed, constructed and has operated the Plutonium Fuel Production Facility, PFPF, at the JNC Tokai Works to supply MOX fuels to the proto-type Fast Breeder Reactor, FBR, 'MONJU' and the experimental FBR 'JOYO' with 5 tonMOX/year of fabrication capability. Reduction of personal radiation exposure to a large amount of plutonium is one of the most important subjects in the development of MOX fabrication facility on a large scale. As the solution of this issue, the PFPF has introduced automated and/or remote controlled equipment in conjunction with computer controlled operation scheme. The PFPF started its operation in 1988 with JOYO reload fuel fabrication and has demonstrated MOX fuel fabrication on a large scale through JOYO and MONJU fuel fabrication for this decade. Through these operations, it has become obvious that several numbers of equipment initially installed in the PFPF need improvements in their performance and maintenance for commercial utilization of plutonium in the future. Furthermore, fuel fabrication of low density MOX pellets adopted in the MONJU fuel required a complete inspection because of difficulties in pellet fabrication compared with high density pellet for JOYO. This paper describes new pressing equipment with a powder recovery system, and pellet finishing and inspection equipment which has multiple functions, such as grinding measurements of outer diameter and density, and inspection of appearance to improve efficiency in the pellet finishing and inspection steps. Another development of technology concerning an annular pellet and an innovative process for MOX fuel fabrication are also described in this paper. (author)

Electronic structure, phase transitions and diffusive properties of elemental plutonium

Science.gov (United States)

Setty, Arun; Cooper, B. R.

2003-03-01

We present a SIC-LDA-LMTO based study of the electronic structure of the delta, alpha and gamma phases of plutonium, and also of the alpha and gamma phases of elemental cerium. We find excellent agreement with the experimental densities and magnetic properties [1]. Furthermore, detailed studies of the computational densities of states for delta plutonium, and comparison with the experimental photoemission spectrum [2], provide evidence for the existence of an unusual fluctuating valence state. Results regarding the vacancy formation and self-diffusion in delta plutonium will be presented. Furthermore, a study of interface diffusion between plutonium and steel (technologically relevant in the storage of spent fuel) or other technologically relevant alloys will be included. Preliminary results regarding gallium stabilization of delta plutonium, and of plutonium alloys will be presented. [1] M. Dormeval et al., private communication (2001). [2] A. J. Arko, J. J. Joyce, L. Morales, J. Wills, and J. Lashley et. al., Phys. Rev. B, 62, 1773 (2000). [3] B. R. Cooper et al, Phil. Mag. B 79, 683 (1999); B.R. Cooper, Los Alamos Science 26, 106 (2000)); B.R. Cooper, A.K. Setty and D.L.Price, to be published.

Environmental assessment for the proposed CMR Building upgrades at the Los Alamos National Laboratory, Los Alamos, New Mexico. Final document

International Nuclear Information System (INIS)

1997-01-01

In order to maintain its ability to continue to conduct uninterrupted radioactive and metallurgical research in a safe, secure, and environmentally sound manner, the US Department of Energy (DOE) proposes to upgrade the Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Building. The building was built in the early 1950s to provide a research and experimental facility for analytical chemistry, plutonium and uranium chemistry, and metallurgy. Today, research and development activities are performed involving nuclear materials. A variety of radioactive and chemical hazards are present. The CMR Building is nearing the end of its original design life and does not meet many of today's design codes and standards. The Proposed Action for this Environmental Assessment (EA) includes structural modifications to some portions of the CMR Building which do not meet current seismic criteria for a Hazard Category 2 Facility. Also included are upgrades and improvements in building ventilation, communications, monitoring, and fire protection systems. This EA analyzes the environmental effects of construction of the proposed upgrades. The Proposed Action will have no adverse effects upon agricultural and cultural resources, wetlands and floodplains, endangered and threatened species, recreational resources, or water resources. The Proposed Action would have negligible effects on human health and transportation, and would not pose a disproportionate adverse health or environmental impact on minority or low-income populations within an 80 kilometer (50 mile) radius of the CMR Building

Environmental assessment for the proposed CMR Building upgrades at the Los Alamos National Laboratory, Los Alamos, New Mexico. Final document

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-02-04

In order to maintain its ability to continue to conduct uninterrupted radioactive and metallurgical research in a safe, secure, and environmentally sound manner, the US Department of Energy (DOE) proposes to upgrade the Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Building. The building was built in the early 1950s to provide a research and experimental facility for analytical chemistry, plutonium and uranium chemistry, and metallurgy. Today, research and development activities are performed involving nuclear materials. A variety of radioactive and chemical hazards are present. The CMR Building is nearing the end of its original design life and does not meet many of today`s design codes and standards. The Proposed Action for this Environmental Assessment (EA) includes structural modifications to some portions of the CMR Building which do not meet current seismic criteria for a Hazard Category 2 Facility. Also included are upgrades and improvements in building ventilation, communications, monitoring, and fire protection systems. This EA analyzes the environmental effects of construction of the proposed upgrades. The Proposed Action will have no adverse effects upon agricultural and cultural resources, wetlands and floodplains, endangered and threatened species, recreational resources, or water resources. The Proposed Action would have negligible effects on human health and transportation, and would not pose a disproportionate adverse health or environmental impact on minority or low-income populations within an 80 kilometer (50 mile) radius of the CMR Building.

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

International Nuclear Information System (INIS)

DiSabatino, A.

1998-01-01

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

LOS ALAMOS

International Nuclear Information System (INIS)

Anon.

1993-01-01

Following the historic observation of neutrinos in the mid-1950s by two Los Alamos scientists, Fred Reines and Clyde Cowan, Jr, using inverse beta decay, there has been a long and distinguished history of experimental neutrino physics at LAMPF, the Los Alamos Meson Physics Facility. LAMPF is the only meson factory to have had an experimental neutrino programme. In the late 1970s, the first LAMPF neutrino experiment used a 6-tonne water Cherenkov detector 7 metres from the beam stop. A collaboration of Yale, Los Alamos and several other institutions, this experiment searched for the forbidden decay of a muon into an electron and two neutrinos, and measured the reaction rate of a neutrino interacting with a deuteron to give two protons and an electron - the inverse of the reaction that drives the sun's primary energy source. The next LAMPF neutrino experiment, a UC Irvine/Maryland/Los Alamos collaboration, ran from 1982 through 1986 and measured the elastic scattering rate of electron neutrinos and protons, where both neutral and charged weak currents contribute. With its precision of about 15%, the experiment provided the first demonstration of (destructive) interference between the charged and neutral currents. More recent neutrino experiments at LAMPF have searched for neutrino oscillations, especially between muon- and electron-neutrinos. The newest experiment to pursue this physics (as well as oscillations in other channels) is LSND (July/ August, page 10 and cover). In addition to searching for these oscillations, LSND will measure neutrino-proton elastic scattering at low momentum transfer, providing a sensitive measure of the strange quark contribution to the proton spin. LSND began taking data in August. Los Alamos physicists have also been busy in neutrino physics experiments elsewhere. One such experiment looked at the beta decay of free molecular tritium to obtain an essentially model independent determination of the electron-neutrino mass. The

High-energy density physics at Los Alamos

International Nuclear Information System (INIS)

Byrnes, P.; Younger, S.M.

1993-03-01

This brochure describes the facilities of the Above Ground Experiments II (AGEX II) and the Inertial Confinement Fusion (ICF) programs at Los Alamo. Combined, these programs represent, an unparalleled capability to address important issues in high-energy density physics that are critical to the future defense, energy, and research needs of th e United States. The mission of the AGEX II program at Los Alamos is to provide additional experimental opportunities for the nuclear weapons program. For this purpose we have assembled at Los Alamos the broadest array of high-energy density physics facilities of any laboratory in the world. Inertial confinement fusion seeks to achieve thermonuclear burn on a laboratory scale through the implosion of a small quantity of deuterium and tritium fuel to very high Pressure and temperature.The Los Alamos ICF program is focused on target physics. With the largest scientific computing center in the world, We can perform calculations of unprecedented sophistication and precision. We field experiments at facilities worldwide-including our own Trident and Mercury lasers-to confirm our understanding and to provide the necessary data base to proceed toward the historic goal of controlled fusion in the laboratory. In addition to direct programmatic high-energy density physics is a nc scientific endeavor in itself. The ultrahigh magnetic fields produced in our high explosive pulsed-power generators can be used in awide variety of solid state physics and temperature superconductor studies. The structure and dynamics of planetary atmospheres can be simulated through the compression of gas mixtures

Basis and objectives of the Los Alamos accelerator driven transmutation technology project

International Nuclear Information System (INIS)

Bowman, C.D.

1997-01-01

The paper describes a new accelerator-based nuclear technology developed at Los Alamos National Laboratory which offers total destruction of the weapons Plutonium inventory, a solution to the commercial nuclear waste problem which greatly reduces or eliminates the requirement for geologic waste storage, and a system which generates potentially unlimited energy from Thorium fuel while destroying its own waste and operating in a new regime of nuclear safety

Plutonium vulnerability issues at Hanford's Plutonium Finishing Plant

International Nuclear Information System (INIS)

Feldt, E.; Templeton, D.W.; Tholen, E.

1995-01-01

The Plutonium Finishing Plant (PFP) at the Hanford, Washington Site was operated to produce plutonium (Pu) metal and oxide for national defense purposes. Due to the production requirements and methods utilized to meet national needs and the abrupt shutdown of the plant in the late 1980s, the plant was left in a condition that poses a risk of radiation exposure to plant workers, of accidental radioactive material release to the environment, and of radiation exposure to the public. In early 1994, an Environmental Impact Statement (EIS) to determine the best methods for cleaning out and stabilizing Pu materials in the PFP was started. While the EIS is being prepared, a number of immediate actions have been completed or are underway to significantly reduce the greatest hazards in the PFP. Recently, increased attention his been paid to Pu risks at Department of Energy (DOE) facilities resulting in the Department-wide Plutonium Vulnerability Assessment and a recommendation by the Defense Nuclear Facilities Safety Board (DNFSB) for DOE to develop integrated plans for managing its nuclear materials

Safe handling of plutonium: a panel report

Energy Technology Data Exchange (ETDEWEB)

1974-01-01

This guide results from a meeting of a Panel of Experts held by the International Atomic Energy Agency on 8 to 12 November 1971. It is directed to workers in research laboratories handling plutonium in gram amounts. Contents: aspects of the physical and chemical properties of plutonium; metabolic features of plutonium; facility design features for safe handling of plutonium (layout of facility, working zones, decontamination room, etc.); glove boxes; health surveillance (surveillance of environment and supervision of workers); emergencies; organization. Annexes: types of glove boxes; tables; mobile ..cap alpha.. air sampler; aerosol monitor; bio-assay limits of detection; examples of contamination control monitors.

Installation places of criticality accident detectors in the plutonium conversion development facility

International Nuclear Information System (INIS)

Sanada, Yukihisa; Tsujimura, Norio; Shimizu, Yoshio; Izaki, Kenji; Furuta, Sadaaki

2008-01-01

At the Plutonium Conversion Development Facility (PCDF) in the Nuclear Fuel Cycle Engineering Laboratories, the co-conversion technologies to purify the mixed plutonium and uranium nitrate solution discharged from a reprocessing plant have been developed. The probability of a criticality accident in PCDF is extremely low. However, the criticality accident alarm system (CAAS) has been in place since 1982 to reduce the radiation dose to workers in case of such a rare criticality accident. The CAAS contains criticality accident detector units (CADs), one unit consisting of three plastic scintillation detectors, and using the 2 out of 3 voting system for the purpose of high reliability. Currently, eight CADs are installed in PCDF evaluating the dose using a simple equation allowing for a safety margin. The purpose of this study is to show the determination procedures for the adequate relocation of the CADs which adequately ensures safety in PCDF. (author)

Preparation of high purity plutonium oxide for radiochemistry instrument calibration standards and working standards

International Nuclear Information System (INIS)

Wong, A.S.; Stalnaker, N.D.

1997-04-01

Due to the lack of suitable high level National Institute of Standards and Technology (NIST) traceable plutonium solution standards from the NIST or commercial vendors, the CST-8 Radiochemistry team at Los Alamos National Laboratory (LANL) has prepared instrument calibration standards and working standards from a well-characterized plutonium oxide. All the aliquoting steps were performed gravimetrically. When a 241 Am standardized solution obtained from a commercial vendor was compared to these calibration solutions, the results agreed to within 0.04% for the total alpha activity. The aliquots of the plutonium standard solutions and dilutions were sealed in glass ampules for long term storage

Plutonium Immobilization Can Loading Conceptual Design

Energy Technology Data Exchange (ETDEWEB)

Kriikku, E.

1999-05-13

'The Plutonium Immobilization Facility will encapsulate plutonium in ceramic pucks and seal the pucks inside welded cans. Remote equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. This report discusses the Plutonium Immobilization can loading conceptual design and includes a process block diagram, process description, preliminary equipment specifications, and several can loading issues. This report identifies loading pucks into cans and backfilling cans with helium as the top priority can loading development areas.'

Plutonium Immobilization Can Loading Conceptual Design

International Nuclear Information System (INIS)

Kriikku, E.

1999-01-01

'The Plutonium Immobilization Facility will encapsulate plutonium in ceramic pucks and seal the pucks inside welded cans. Remote equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. This report discusses the Plutonium Immobilization can loading conceptual design and includes a process block diagram, process description, preliminary equipment specifications, and several can loading issues. This report identifies loading pucks into cans and backfilling cans with helium as the top priority can loading development areas.'

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

Energy Technology Data Exchange (ETDEWEB)

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

1989-01-01

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.

Thermal and Physical Properties of Plutonium Dioxide Produced from the Oxidation of Metal: a Data Summary

Energy Technology Data Exchange (ETDEWEB)

Wayne, David M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2014-01-13

The ARIES Program at the Los Alamos National Laboratory removes plutonium metal from decommissioned nuclear weapons, and converts it to plutonium dioxide in a specially-designed Direct Metal Oxidation furnace. The plutonium dioxide is analyzed for specific surface area, particle size distribution, and moisture content. The purpose of these analyses is to certify that the plutonium dioxide powder meets or exceeds the specifications of the end-user, and the specifications for the packaging and transport of nuclear materials. Analytical results from plutonium dioxide from ARIES development activities, from ARIES production activities, from muffle furnace oxidation of metal, and from metal that was oxidized over a lengthy time interval in air at room temperature, are presented. The processes studied produce plutonium dioxide powder with distinct differences in measured properties, indicating the significant influence of oxidation conditions on physical properties.

Transportation of pyrochemical salts from Rocky Flats to Los Alamos

International Nuclear Information System (INIS)

Schreiber, S.B.

1997-01-01

Radioactive legacy wastes or residues are currently being stored on numerous Sites around the former Department of Energy's (DOE) Nuclear Weapons Complex. Since most of the operating facilities were shut down and have not operated since before the declared end to the Cold War in 1993, the historical method for treating these residues no longer exists. The risk associated with continued storage of these residues will dramatically increase with time. Thus, the DOE was directed by the Defense Nuclear Facility Safety Board in its Recommendation 94-1 to address and stabilize these residues and established an eight year time frame for doing so. There are only two options available to respond to this requirement: (1) restart existing facilities to treat and package the residues for disposal or (2) transport the residues to another operating facility within the Complex where they can be treated and packaged for disposal. This paper focuses on one such residue type, pyrochemical salts, produced at one Complex site, the Rocky Flats Plant located northwest of Denver, Colorado. One option for treating the salts is their shipment to Los Alamos, New Mexico, for handling at the Plutonium Facility. The safe transportation of these salts can be accomplished at present with several shipping containers including a DOT 6M, a DOE 9968, Type A or Type B quantity 55-gallon drum overpacks, or even the TRUPACT II. The tradeoffs between each container is examined with the conclusion that none of the available shipping containers is fully satisfactory. Thus, the advantageous aspects of each container must be utilized in an integrated and efficient way to effectively manage the risk involved. 1 fig

Rough order of magnitude cost estimate for immobilization of 50 MT of plutonium using existing facilities at Hanford: alternative 11B

International Nuclear Information System (INIS)

DiSabatino, A.

1998-01-01

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)

Surveillance and Maintenance Plan for the Plutonium Uranium Extraction (PUREX) Facility

International Nuclear Information System (INIS)

Woods, P.J.

1998-05-01

This document provides a plan for implementing surveillance and maintenance (S ampersand M) activities to ensure the Plutonium Uranium Extraction (PUREX) Facility is maintained in a safe, environmentally secure, and cost-effective manner until subsequent closure during the final disposition phase of decommissioning. This plan has been prepared in accordance with the guidelines provided in the U.S. Department of Energy (DOE), Office of Environmental Management (EM) Decommissioning Resource Manual (DOE/EM-0246) (DOE 1995), and Section 8.6 of TPA change form P-08-97-01 to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology, et al. 1996). Specific objectives of the S ampersand M program are: Ensure adequate containment of remaining radioactive and hazardous material. Provide security control for access into the facility and physical safety to surveillance personnel. Maintain the facility in a manner that will minimize potential hazards to the public, the environment, and surveillance personnel. Provide a plan for the identification and compliance with applicable environmental, safety, health, safeguards, and security requirements

Plutonium in the aquatic environment around the Rocky Flats facility

International Nuclear Information System (INIS)

Thompson, M.A.

1975-01-01

The Rocky Flats Plant of the United States Energy Research and Development Administration has been fabricating and chemically recovering plutonium for over 20 years. During that time, small amounts of plutonium have been released with liquid process and sanitary waste discharges. The liquid waste flows through a series of holding ponds from which it is discharged into a creek that is part of a municipal drinking water supply. The water flows for about 1.5 km between the last holding pond and the municipal drinking water reservoir. In addition, liquid wastes containing high levels of chemical contaminants and plutonium concentrations less than allowable drinking water standards have been discharged to large evaporation ponds. The fate of the plutonium in both the surface and subsurface aquatic environment has been extensively monitored and studied. It has been found that plutonium does not move very far or very rapidly through subsurface water. The majority of the plutonium released through surface water has been contained in the sediments of the plant holding ponds. Small amounts of plutonium have also been found in the sediments of the draining creek and in the sediments of the receiving reservoir. Higher than normal amounts of plutonium were released from the waste treatment plants during times when suspended solids were high. Various biological species have been examined and plutonium concentration factors determined. Considerably less than 1% of the 210 mCi of plutonium released has been detected in biological systems including man. After more than 20 years of large scale operations, no health or environmental hazard has been identified due to the release of small amounts of plutonium. (author)

Design-Only Conceptual Design Report: Plutonium Immobilization Plant

International Nuclear Information System (INIS)

DiSabatino, A.; Loftus, D.

1999-01-01

This design-only conceptual design report was prepared to support a funding request by the Department of Energy Office of Fissile Materials Disposition for engineering and design of the Plutonium Immobilization Plant, which will be used to immobilize up to 50 tonnes of surplus plutonium. The siting for the Plutonium Immobilization Plant will be determined pursuant to the site-specific Surplus Plutonium Disposition Environmental Impact Statement in a Plutonium Deposition Record of Decision in early 1999. This document reflects a new facility using the preferred technology (ceramic immobilization using the can-in-canister approach) and the preferred site (at Savannah River). The Plutonium Immobilization Plant accepts plutonium from pit conversion and from non-pit sources and, through a ceramic immobilization process, converts the plutonium into mineral-like forms that are subsequently encapsulated within a large canister of high-level waste glass. The final immobilized product must make the plutonium as inherently unattractive and inaccessible for use in nuclear weapons as the plutonium in spent fuel from commercial reactors and must be suitable for geologic disposal. Plutonium immobilization at the Savannah River Site uses: (1) A new building, the Plutonium Immobilization Plant, which will convert non-pit surplus plutonium to an oxide form suitable for the immobilization process, immobilize plutonium in a titanate-based ceramic form, place cans of the plutonium-ceramic forms into magazines, and load the magazines into a canister; (2) The existing Defense Waste Processing Facility for the pouring of high-level waste glass into the canisters; and (3) The Actinide Packaging and Storage Facility to receive and store feed materials. The Plutonium Immobilization Plant uses existing Savannah River Site infra-structure for analytical laboratory services, waste handling, fire protection, training, and other support utilities and services. The Plutonium Immobilization Plant

Comparison of neutron dose measured by Albedo TLD and etched tracks detector at PNC plutonium fuel facilities

International Nuclear Information System (INIS)

Tsujimura, N.; Momose, T.; Shinohara, K.; Ishiguro, H.

1996-01-01

Power Reactor and Nuclear Fuel Development Corporation (PNC) has fabricated Plutonium and Uranium Mixed OXide (MOX) fuel for FBR MONJU at Tokai works. In this site, PNC/Panasonic albedo TLDs/1/ are used for personnel neutron monitoring. And a part of workers wore Etched Tracks Detector (ETD) combined with TLD in order to check the accuracy of the neutron dose estimated by albedo TLD. In this paper, the neutron dose measured by TLD and ETD in the routine monitoring is compared at PNC plutonium fuel facilities. (author)

Surplus plutonium disposition draft environmental impact statement. Volume 1, Part A

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. This volume includes background information; purpose of and need for the proposed action; alternatives for disposition of surplus weapons useable plutonium; and

Science and Innovation at Los Alamos

Science.gov (United States)

Alamos National Laboratory Delivering science and technology to protect our nation and promote world stability Science & Innovation Collaboration Careers Community Environment Science & Innovation Facilities Science Pillars Research Library Science Briefs Science News Science Highlights Lab Organizations

Los Alamos National Laboratory Weapons Neutron Research Facility

International Nuclear Information System (INIS)

Woods, R.

1981-01-01

The Weapons Neutron Research (WNR) spallation neutron source utilizes 800-MeV protons from the Los Alamos Meson Physics linac. The proton beam transport system, the target systems, and the data acquisition and control system are described. Operating experience, present status, and planned improvements are discussed

Deposition and retention of plutonium in the United States general population

International Nuclear Information System (INIS)

McInroy, J.F.; Boyd, H.A.; Eutsler, B.C.

1979-01-01

Since 1959, a Los Alamos National Laboratory study has analyzed over 5000 tissues from 1100 individuals of the nonoccupationally exposed general population for fallout plutonium. These data have been useful in determining the tissue distributions and the annual baseline levels of environmental plutonium in the United States population. The effects of age, sex, date of death, cause of death and geographic location of resididence on the observed plutonium deposition have been evaluated. Because of the difference in biological turnover times of plutonium in the various organs of the body and the changing concentrations of plutonium in the atmosphere, the plutonium concentration ratios between tissues have changed as a function of time. However, our data indicate that over the past 10 years, the highest concentrations in the general population are found in the tracheobronchial lymph nodes and the liver and the lowest concentrations are in the spleen, gonads and kidney. The median body burdens of plutonium in the US population are estimated to have reached 12 pCi during the 1960's and have declined to about 2 pCi in 1977. Large errors in estimated skeletal burdens of plutonium may exist because of small specimen sample sizes and a lack of knowledge concerning the relative distribution of plutonium among the various bones of the human body

Remote handling in the Plutonium Immobilization Project: Plutonium conversion and first stage immobilization

International Nuclear Information System (INIS)

Brault, J.R.

2000-01-01

Since the break up of the Soviet Union at the end of the Cold War, the United States and Russia have been negotiating ways to reduce their nuclear stockpiles. Economics is one of the reasons behind this, but another important reason is safeguarding these materials from unstable organizations and countries. With the downsizing of the nuclear stockpiles, large quantities of plutonium are being declared excess and must be safely disposed of. The Savannah River Site (SRS) has been selected as the site where the immobilization facility will be located. Conceptual design and process development commenced in 1998. SRS will immobilize excess plutonium in a ceramic waste form and encapsulate it in vitrified high level waste in the Defense Waste Processing Facility (DWPF) canister. These canisters will then be interred in the national repository at Yucca Mountain, New Mexico. The facility is divided into three distinct operating areas: Plutonium Conversion, First Stage Immobilization, and Second Stage Immobilization. This paper will discuss the first two operations

MaRIE; a proposed materials facility at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Bourke, M.A.M. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)

2009-06-15

This presentation will describe the current definition of a proposed new facility called MaRIE at Los Alamos National Laboratory. The concept is of decadal scope and is predicated on the collocation of a fourth-generation X-ray light source with a proton accelerator spallation neutron source and complementary synthesis and characterization capabilities. MaRIE is an acronym which stands for Matter-Radiation Interactions in Extremes. The facility has been conceived partly in response to the increasing role that control science is expected to play in materials research compared to observation science. If new materials are to be implemented in a timely fashion for the most aggressive conditions of proposed fission and fusion energy applications they will have to rely, at least in part, on models, simulations and scientific insight. Validation of these models will require measurements at spatial and temporal scales that have only recently become enabled by the latest generations of light sources. A hallmark of the MaRIE concept is an emphasis on in situ studies (under extreme neutron, photon and ion irradiation conditions) of the phenomena that lead to swelling, phase transformations, thermal properties and corrosion. Insights and data, relevant to atomistic and quantum mechanical models, are major goals, as well as the facilitation of rapid materials discovery. It is hoped that this presentation will solicit input on aspects of the facility definition that should be strengthened or diminished to meet the needs of the fission community. (authors)

Rough order of magnitude cost estimate for immobilization of 18.2 MT of plutonium sharing existing facilities at Hanford with MOX fuel fabrication facility: alternative 4B

International Nuclear Information System (INIS)

DiSabatino, A.

1998-01-01

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 MOX Fuel Fabrication Facility (MFFF), which is being costed in a separate report, will also be located in the FMEF in this co-location option

Liquid-waste management systems improvement programmes at Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Emelity, L.A.; Stanley, P.M.; Buchholz, J.R.

1981-01-01

Programmes at the Los Alamos Scientific Laboratory (LASL) are approximately 50% nuclear weapons related and 50% general energy research and development. Since its beginning in the 1940s, liquid industrial wastes have been contaminated with isotopes of plutonium, americium, uranium and various beta-gamma emitters, but management and treatment efforts were, owing to the proportions of the various isotopes, directed primarily at the alpha emitters. The evolution in management methods at LASL since the 1940s has been reported in previous papers. This treatise discusses the most recent three-phase effort to modernize the systems to the probable standards of the next twenty years. The first phase, provision of a double-encased, continuously monitored sewer system will soon be under construction. The second phase, modernization of the treatment facilities, has been funded and is in the final design stage. The third phase, not funded as of this date, will provide lined, monitored solar evaporation ponds for total management of the treated industrial wastes with no release of any liquid to the environment. (author)

Liquid waste management systems improvement programs at Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Emelity, L.A.; Stanley, P.M.; Buchholz, J.R.

1980-01-01

Programs at the Los Alamos Scientific Laboratory (LASL) are approximately 50% nuclear weapons related and 50% general energy research and development. Since its beginning in the 1940's liquid industrial wastes have been contaminated with isotopes of plutonium, americium, uranium and various beta-gamma emitters, but management and treatment efforts were, due to the proportions of the various isotopes, directed primarily at the alpha emitters. The evolution in management methods at LASL since the 40's has been reported in previous papers. This treatise discusses the most recent three-phase effort to modernize the systems to the probable standards of the next twenty years. The first phase, provision of double-encased, continuously monitored sewer system will soon be under construction. The second phase, modernization of the treatment facilities, has been funded and is in the final design stage. The third phase, not funded as of this date, will provide lined, monitored solar evaporation ponds for total management of the treated industrial wastes with no release of any liquid to the environment

Surplus plutonium disposition draft environmental impact statement. Volume 1, Part B

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. This volume has chapters on environmental consequences; environmental regulations, permits, and consultations; a glossary; list of preparers; distribution list

The plutonium fuel cycles

International Nuclear Information System (INIS)

Pigford, T.H.; Ang, K.P.

1975-01-01

The quantities of plutonium and other fuel actinides have been calculated for equilibrium fuel cycles for 1000-MW water reactors fueled with slightly enriched uranium, water reactors fueled with plutonium and natural uranium, fast-breder reactors, gas-cooled reactors fueled with thorium and highly enriched uranium, and gas-cooled reactors fueled with thorium, plutonium and recycled uranium. The radioactivity quantities of plutonium, americium and curium processed yearly in these fuel cycles are greatest for the water reactors fueled with natural uranium and recycled plutonium. The total amount of actinides processed is calculated for the predicted future growth of the U.S. nuclear power industry. For the same total installed nuclear power capacity, the introduction of the plutonium breeder has little effect upon the total amount of plutonium in this century. The estimated amount of plutonium in the low-level process wastes in the plutonium fuel cycles is comparable to the amount of plutonium in the high-level fission product wastes. The amount of plutonium processed in the nuclear fuel cycles can be considerably reduced by using gas-cooled reactors to consume plutonium produced in uranium-fueled water reactors. These, and other reactors dedicated for plutonium utilization, could be co-located with facilities for fuel reprocessing ad fuel fabrication to eliminate the off-site transport of separated plutonium. (author)

Improving aircraft accident forecasting for an integrated plutonium storage facility

International Nuclear Information System (INIS)

Rock, J.C.; Kiffe, J.; McNerney, M.T.; Turen, T.A.

1998-06-01

Aircraft accidents pose a quantifiable threat to facilities used to store and process surplus weapon-grade plutonium. The Department of Energy (DOE) recently published its first aircraft accident analysis guidelines: Accident Analysis for Aircraft Crash into Hazardous Facilities. This document establishes a hierarchy of procedures for estimating the small annual frequency for aircraft accidents that impact Pantex facilities and the even smaller frequency of hazardous material released to the environment. The standard establishes a screening threshold of 10 -6 impacts per year; if the initial estimate of impact frequency for a facility is below this level, no further analysis is required. The Pantex Site-Wide Environmental Impact Statement (SWEIS) calculates the aircraft impact frequency to be above this screening level. The DOE Standard encourages more detailed analyses in such cases. This report presents three refinements, namely, removing retired small military aircraft from the accident rate database, correcting the conversion factor from military accident rates (accidents per 100,000 hours) to the rates used in the DOE model (accidents per flight phase), and adjusting the conditional probability of impact for general aviation to more accurately reflect pilot training and local conditions. This report documents a halving of the predicted frequency of an aircraft impact at Pantex and points toward further reductions

Operational status and future plans for the Los Alamos Neutron Science Center

International Nuclear Information System (INIS)

Jones, Kevin W.; Schoenberg, Kurt F.

2008-01-01

The Los Alamos Neutron Science Center (LANSCE) continues to be a signature experimental science facility at Los Alamos National Laboratory (LANL). The 800 MeV linear proton accelerator provides multiplexed beams to five unique target stations to produce medical radioisotopes, ultra-cold neutrons, thermal and high energy neutrons for material and nuclear science, and to conduct proton radiography of dynamic events. Recent operating experience will be reviewed and the role of an enhanced LANSCE facility in LANL's new signature facility initiative, Matter and Radiation in Extremes (MaRIE) will be discussed.

Materials identification and surveillance project item evaluation: Items, impure plutonium oxide (ATL27960) and pure plutonium oxide (PEOR3258)

International Nuclear Information System (INIS)

Allen, T.; Appert, Q.; Davis, C.

1997-03-01

In this report, Los Alamos scientists characterize properties relevant to storage of an impure plutonium oxide (74 mass % plutonium) in accordance with the Department of Energy (DOE) standard DOE-STD-3013-96. This oxide is of interest because it is the first impure plutonium oxide sample to be evaluated and it is similar to other materials that must be stored. Methods used to characterize the oxide at certain points during calcination include surface-area analyses, mass loss-on-ignition (LOI) measurements, elemental analysis, moisture-adsorption measurements, and quantitative supercritical-CO 2 extraction of adsorbed water. Significant decreases in the LOI and surface area occurred as the oxide was calcined at progressively increasing temperatures. Studies indicate that supercritical-CO 2 extraction is an effective method for removing adsorbed water from oxides. We extracted the water from powdered oxides (high-purity ZrO 2 , pure PuO 2 , and impure plutonium oxide) using CO 2 at 3000 psi pressure and 75 degrees C, and we quantitatively determined it by using gravimetric and dew-point procedures. The effectiveness of the extraction method is demonstrated by good agreement between the amounts of water extracted from pure zirconium and plutonium dioxides and the mass changes obtained from LOI analyses. However, the amount of moisture (0.025 mass %) extracted from the impure plutonium oxide after it had been calcined at 950 degrees C and stored for a period of months is much less than the LOI value (0.97 mass %). These results imply that the impure plutonium oxide is free of adsorbed water after calcination at 950 degrees C, even though the sample does not satisfy the LOI requirement of <0.50 mass % for storage

Self-imposed self-assessment program at a DOE Nuclear Facility

International Nuclear Information System (INIS)

Geoffrion, R.R.; Loud, J.J.; Walter, E.C.

1996-01-01

The Nuclear Materials and Technology (NMT) Division at Los Alamos National Laboratory (LANL) has implemented a performance-based self-assessment program at the TA-55 plutonium facility. The program was conceptualized and developed by LANL's internal assessment group, AA-2. The management walkaround program fosters continuous improvement in NMT products and performance of its activities. The program, based on experience from the Institute of Nuclear Power Operations, is endorsed at the site by the U.S. Department of Energy (DOE) Environment, Safety, and Health (ES ampersand H) personnel and by the Defense Nuclear Facility Safety Board. The self-assessment program focuses on how work is actually performed rather than on paperwork or process compliance. Managers critically and continually assess ES ampersand H, conduct of operations, and other functional area requirements

International and institutional aspects of reprocessing and plutonium management

International Nuclear Information System (INIS)

1978-09-01

Various institutional alternatives applicable to reprocessing, plutonium management and recycle are considered, not as a definitive analysis but rather as a basis for identifying the institutional approaches and measures which the Working Group might wish to examine more thoroughly. Seven alternatives arrangements for reprocessing are presented. These range from suspending the operation of existing reprocessing plants through placing national facilities under safeguards to limiting reprocessing to a few large facilities subject to plutonium management, multinational or international control. Finally, the comprehensive alternative of an International Nuclear Fuel Authority with worldwide responsibility for reprocessing and plutonium management is considered. Plutonium management alternatives to complement the reprocessing options, are then outlined. These include national discretion on the separation and disposition of plutonium under safeguards, an agreed Code of Practice for plutonium management at national facilities and the international storage of plutonium. The advantages and disadvantages of the alternative are discussed tentatively. It is recognised that the alternatives are presented in a simplified form and that their elements can be combined or separated in many ways. Although strengthening the institutions relating to the peaceful uses of nuclear energy is imperative and can contribute to non-proliferation, such arrangements might open other proliferation risks through the spread of sensitive materials, facilities and technology. While there are risks with any fuel cycle, where plutonium in quantity is separated these risks are of a high order. Although these can be mitigated, they will have to be set against the energy and economic case for reprocessing and alternatives other than plutonium considered

LOS ALAMOS: Hadron future

International Nuclear Information System (INIS)

Ernst, David J.

1992-01-01

At a Workshop on the Future of Hadron Facilities, held on 15-16 August at Los Alamos National Laboratory, several speakers pointed out that the US physics community carrying out fixed target experiments with hadron beam had not been as successful with funding as it deserved. To rectify this, they said, the community should be better organized and present a more united front

LOS ALAMOS: Hadron future

Energy Technology Data Exchange (ETDEWEB)

Ernst, David J.

1992-11-15

At a Workshop on the Future of Hadron Facilities, held on 15-16 August at Los Alamos National Laboratory, several speakers pointed out that the US physics community carrying out fixed target experiments with hadron beam had not been as successful with funding as it deserved. To rectify this, they said, the community should be better organized and present a more united front.

Environmental Assessment for the High Explosives Wastewater Treatment Facility, Los Alamos National Laboratory, Los Alamos, New Mexico

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy (DOE) has identified a need to improve the management of wastewater resulting from high explosives (HE) research and development work at Los Alamos National Laboratory (LANL). LANL's current methods off managing HE-contaminated wastewater cannot ensure that discharged HE wastewater would consistently meet the Environmental Protection Agency's (EPA's) standards for wastewater discharge. The DOE needs to enhance He wastewater management to e able to meet both present and future regulatory standards for wastewater discharge. The DOE also proposes to incorporate major pollution prevention and waste reduction features into LANL's existing HE production facilities. Currently, wastewater from HE processing buildings at four Technical Areas (TAs) accumulates in sumps where particulate HE settles out and barium is precipitated. Wastewater is then released from the sumps to the environment at 15 permitted outfalls without treatment. The released water may contain suspended and dissolved contaminants, such as HE and solvents. This Environmental Assessment (EA) analyzes two alternatives, the Proposed Action and the Alternative Action, that would meet the purpose and need for agency action. Both alternatives would treat all HE process wastewater using sand filters to remove HE particulates and activated carbon to adsorb organic solvents and dissolved HE. Under either alternative, LANL would burn solvents and flash dried HE particulates and spent carbon following well-established procedures. Burning would produce secondary waste that would be stored, treated, and disposed of at TA-54, Area J. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact and Floodplain Statement of Findings for the High Explosives Wastewater Treatment Facility

Seismic engineering for an expanded tritium facility at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Volkman, D.E.; Olive, W.B.; Endebrocid, E.E.; Khan, P.K.; Rebillet, W.R.

1997-10-01

An existing complex of three single story concrete and masonry shear wall buildings will be integrated into an expanded tritium facility for neutron tube target loading. Known as the NTTL Project, the expanded plant is a major element of the Department of Energy's tritium program at the Los Alamos National Laboratory. This paper describes seismic evaluation and upgrade modifications for the 1950's concrete shear wall building; drift analyses of two 1980's CMU [concrete masonry unit] shear wall buildings; design of a new CMU shear wall building linking existing structures and providing personnel change room services; and design of a new steel frame building housing HVAC and electrical power and communication equipment for the complex. All buildings are closely adjacent and drift analysis to establish separation to prevent pounding is a major seismic engineering concern for the project

Gas generation over plutonium oxides in the 94-1 shelf-life surveillance program

International Nuclear Information System (INIS)

Berg, J.M.; Harradine, D.M.; Hill, D.D.; McFarlan, James T.; Padilla, D.D.; Prenger, F. Coyne; Veirs, D.K.; Worl, L.A.

2002-01-01

The Department of Energy (DOE) is embarking upon a program to store large quantities of plutonium-bearing materials for up to fifty years. The Los Alamos National Laboratory Shelf Life Project was established to bound the behavior of plutonium-bearing material meeting the DOE 3013 Standard. The shelf life study monitors temperature, pressure and gas composition over oxide materials in a limited number of large-scale 3013 inner containers and in many small-scale containers. For the large-scale study, baseline plutonium oxides, oxides exposed to high-humidity atmospheres, and oxides containing chloride salt impurities are planned. The first large-scale container represents a baseline and contains dry plutonium oxide prepared according to the 3013 Standard. This container has been observed for pressure, temperature and gas compositional changes for less than a year. Results indicate that no detectable changes in pressure and gas composition are observed.

Plutonium Finishing Plant safety evaluation report

International Nuclear Information System (INIS)

1995-01-01

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

Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

1991-10-01

This investigations of the Savannah River Site's Plutonium Fuel Form fabrication facility located in Building 235-F was initiated in April 1991. The purpose of the investigation was to determine whether, as has been alleged, operation of the facility's argon inert gas system was terminated with the knowledge that continued inoperability of the argon system would cause accelerated corrosion damage to the equipment in the plutonium 238 processing cells. The investigation quickly established that the decision to discontinue operation of the argon system, by not repairing it, was merely one of the measures, and not the most important one, which led to the current deteriorated state of the facility. As a result, the scope of the investigation was broadened to more identify and assess those factors which contributed to the facility's current condition. This document discusses the backgrounds, results, and recommendations of this investigation.

Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site

International Nuclear Information System (INIS)

1991-10-01

This investigations of the Savannah River Site's Plutonium Fuel Form fabrication facility located in Building 235-F was initiated in April 1991. The purpose of the investigation was to determine whether, as has been alleged, operation of the facility's argon inert gas system was terminated with the knowledge that continued inoperability of the argon system would cause accelerated corrosion damage to the equipment in the plutonium 238 processing cells. The investigation quickly established that the decision to discontinue operation of the argon system, by not repairing it, was merely one of the measures, and not the most important one, which led to the current deteriorated state of the facility. As a result, the scope of the investigation was broadened to more identify and assess those factors which contributed to the facility's current condition. This document discusses the backgrounds, results, and recommendations of this investigation

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

International Nuclear Information System (INIS)

DeMuth, S.

1997-01-01

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 Exchangeclose 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

Chemical and Radiochemical Composition of Thermally Stabilized Plutonium Oxide from the Plutonium Finishing Plant Considered as Alternate Feedstock for the Mixed Oxide Fuel Fabrication Facility

International Nuclear Information System (INIS)

Tingey, Joel M.; Jones, Susan A.

2005-01-01

Eighteen plutonium oxide samples originating from the Plutonium Finishing Plant (PFP) on the Hanford Site were analyzed to provide additional data on the suitability of PFP thermally stabilized plutonium oxides and Rocky Flats oxides as alternate feedstock to the Mixed Oxide Fuel Fabrication Facility (MFFF). Radiochemical and chemical analyses were performed on fusions, acid leaches, and water leaches of these 18 samples. The results from these destructive analyses were compared with nondestructive analyses (NDA) performed at PFP and the acceptance criteria for the alternate feedstock. The plutonium oxide materials considered as alternate feedstock at Hanford originated from several different sources including Rocky Flats oxide, scrap from the Remote Mechanical C-Line (RMC) and the Plutonium Reclamation Facility (PRF), and materials from other plutonium conversion processes at Hanford. These materials were received at PFP as metals, oxides, and solutions. All of the material considered as alternate feedstock was converted to PuO2 and thermally stabilized by heating the PuO2 powder at 950 C in an oxidizing environment. The two samples from solutions were converted to PuO2 by precipitation with Mg(OH)2. The 18 plutonium oxide samples were grouped into four categories based on their origin. The Rocky Flats oxide was divided into two categories, low- and high-chloride Rocky Flats oxides. The other two categories were PRF/RMC scrap oxides, which included scrap from both process lines and oxides produced from solutions. The two solution samples came from samples that were being tested at Pacific Northwest National Laboratory because all of the plutonium oxide from solutions at PFP had already been processed and placed in 3013 containers. These samples originated at the PFP and are from plutonium nitrate product and double-pass filtrate solutions after they had been thermally stabilized. The other 16 samples originated from thermal stabilization batches before canning at

Los Alamos National Lab: National Security Science

Science.gov (United States)

SKIP TO PAGE CONTENT Los Alamos National Laboratory Delivering science and technology to protect Museum New Hires Publications Research Library Mission Science & Innovation Science & Innovation Facilities Science Pillars Research Library Science Briefs Science News Lab Organizations Science Programs

Calorimetry measurements in less than 20 minutes

International Nuclear Information System (INIS)

Perry, R.B.; Cremers, T.

1991-01-01

Argonne National Laboratory has developed a new series of 10 watt Bulk Plutonium Assay Calorimeters (BPAC10). The calorimeter measures bulk samples of plutonium bearing material in containers up to 5in. in diameter and 7in. high. The average measurement time is 19.7 minutes compared to 2--9 hours for the same sample measured in a water bath calorimeter. Measurement precision in the range of 1--10 watts is 1% to 0.1% and it is 0.010 watt for sample power less than 1 watt. BPAC10 series calorimeters are in use in two plutonium facilities at the EG ampersand G Rocky Flats Plant and at the Los Alamos National Laboratory TA55 Plutonium Facility. The paper presents a description of the calorimeter, discusses operating experience at Los Alamos, and presents a comparison of data on typical samples measured with both types of calorimeters. 5 refs., 5 figs., 1 tab

Role of non-destructive examinations in leak testing of glove boxes for industrial scale plutonium handling at nuclear fuel fabrication facility along with case study

International Nuclear Information System (INIS)

Aher, Sachin

2015-01-01

Non Destructive Examinations has the prominent role at Nuclear Fuel Fabrication Facilities. Specifically NDE has contributed at utmost stratum in Leak Testing of Glove Boxes and qualifying them as a Class-I confinement for safe Plutonium handling at industrial scale. Advanced Fuel Fabrication Facility, BARC, Tarapur is engaged in fabrication of Plutonium based MOX (PuO 2 , DDUO 2 ) fuel with different enrichments for first core of PFBR reactor. Alpha- Leak Tight Glove Boxes along with HEPA Filters and dynamic ventilation form the promising engineering system for safe and reliable handling of plutonium bearing materials considering the radiotoxicity and risk associated with handling of plutonium. Leak Testing of Glove Boxes which involves the leak detection, leak rectification and leak quantifications is major challenging task. To accomplish this challenge, various Non Destructive Testing methods have assisted in promising way to achieve the stringent leak rate criterion for commissioning of Glove Box facilities for plutonium handling. This paper highlights the Role of various NDE techniques like Soap Solution Test, Argon Sniffer Test, Pressure Drop/Rise Test etc. in Glove Box Leak Testing along with procedure and methodology for effective rectification of leakage points. A Flow Chart consisting of Glove Box leak testing procedure starting from preliminary stage up to qualification stage along with a case study and observations are discussed in this paper. (author)

Russian youth forum special session: Youth and the global political challenges of plutonium

International Nuclear Information System (INIS)

Browne, J.C.

1998-01-01

This paper, given by the director of the Los Alamos National Laboratory, briefly points out the unusual properties of plutonium, for example, its most unusual electronic structure, its sensitivity to changes in temperature, pressure, and chemical alloying, and its great propensity for oxygen and hydrogen. The combination of nuclear and electronic processes it undergoes complicate the behavior also

Evaluation of cancer incidence among employees at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

Acquavella, J.F.; Wilkinson, G.S.; Wiggs, L.D.; Tietjen, G.L.; Key, C.R.

1983-01-01

As part of the National Plutonium Workers Study, cancer incidence for 1969 to 1978 among employees of the Los Alamos National Laboratory was investigated. Incident cancers were identified by a computer match of the Los Alamos employed roster against New Mexico Tumor Registry files. The resulting numbers of total and site-specific cancers were compared to the numbers expected based on incidence rates for the State of New Mexico, specific for age, sex, ethnicity, and calendar period. For Anglo males, significantly fewer cancers than expected (SIR = 0.60, 95% CI 0.44 to 0.79) were found. This resulted from marked deficits of smoking-related cancers, particularly lung (2 observed, 19.4 expected) and oral (1 observed, 6.5 expected) cancer. Similarly, no smoking-related cancers were detected among Anglo females, though they had a slight nonsignificant excess of breast cancer (14 observed, 9.1 expected) and a suggestive excess of cancer of the uterine corpus (2 observed, 0.25 expected). The pattern of cancerincidence among Anglo employees is typical of high social class populations and not likely related to the Los Alamos working environment

Environmental Assessment for the High Explosives Wastewater Treatment Facility, Los Alamos National Laboratory, Los Alamos, New Mexico

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-03

The Department of Energy (DOE) has identified a need to improve the management of wastewater resulting from high explosives (HE) research and development work at Los Alamos National Laboratory (LANL). LANL`s current methods off managing HE-contaminated wastewater cannot ensure that discharged HE wastewater would consistently meet the Environmental Protection Agency`s (EPA`s) standards for wastewater discharge. The DOE needs to enhance He wastewater management to e able to meet both present and future regulatory standards for wastewater discharge. The DOE also proposes to incorporate major pollution prevention and waste reduction features into LANL`s existing HE production facilities. Currently, wastewater from HE processing buildings at four Technical Areas (TAs) accumulates in sumps where particulate HE settles out and barium is precipitated. Wastewater is then released from the sumps to the environment at 15 permitted outfalls without treatment. The released water may contain suspended and dissolved contaminants, such as HE and solvents. This Environmental Assessment (EA) analyzes two alternatives, the Proposed Action and the Alternative Action, that would meet the purpose and need for agency action. Both alternatives would treat all HE process wastewater using sand filters to remove HE particulates and activated carbon to adsorb organic solvents and dissolved HE. Under either alternative, LANL would burn solvents and flash dried HE particulates and spent carbon following well-established procedures. Burning would produce secondary waste that would be stored, treated, and disposed of at TA-54, Area J. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact and Floodplain Statement of Findings for the High Explosives Wastewater Treatment Facility.

Use of laboratory robots in the automation of a urine plutonium bioassay

International Nuclear Information System (INIS)

Gonzales, E.R.; Moss, W.D.; Rodriguez, R.; Martinez, G.M.

1986-01-01

Determination of plutonium in urine is a routine procedure performed at Los Alamos. Samples are taken from the many workers who handle plutonium in their day to day activities and from those individuals whose jobs may bring them into contact with this metal. The analytical procedure used is based on alkaline earth phosphate precipitation that coprecipitates the plutonium. This procedure gives excellent results but it involves many manipulative steps and the chances for human error are ever present. In order to eliminate potential human error and decrease analysis time this procedure was automated using a Zymark Corporation robotic workcell. The developmental work for the automation process was divided into two parts: robot programmatic needs - software and hardware, and chemical modifications of existing methods for utilization with the robotic system. The optimum integration of these developments are discussed in this paper

Overview of the Los Alamos National Laboratory Inertial Confinement Fusion Program

International Nuclear Information System (INIS)

Harris, D.B.

1991-01-01

The Los Alamos Inertial Confinement Fusion (ICF) Program is focused on preparing for a National Ignition Facility. Target physics research is addressing specific issues identified for the Ignition Facility target, and materials experts are developing target fabrication techniques necessary for the advanced targets. We are also working with Lawrence Livermore National Laboratory on the design of the National Ignition Facility target chamber. Los Alamos is also continuing to develop the KrF laser-fusion driver for ICF. We are modifying the Aurora laser to higher intensity and shorter pulses and are working with the Naval Research Laboratory on the development of the Nike KrF laser. 9 refs., 1 fig., 2 tabs

Plutonium Vulnerability Management Plan

International Nuclear Information System (INIS)

1995-03-01

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

Upgrading a 1944 plutonium-extraction plant to a modern decontamination facility

International Nuclear Information System (INIS)

Wills, C.E.; Millikin, R.M.; Cruz, E.A.

1993-10-01

The Hanford Site, located in south-central Washington State, is currently undergoing extensive modifications as its mission changes from defense material production to one of waste management and environmental restoration. Starting in World War II, Hanford's mission for over four decades was the production of plutonium for defense needs. With the removal of such defense requirements over the last several years, the Hanford Site has refocused its efforts on the issues of cleanup and safety. The T Plant Complex is the first of the existing facilities to begin conversion from the old mission to the new. This conversion process and associated problems are described

Survey of plutonium and uranium atom ratios and activity levels in Mortandad Canyon

Energy Technology Data Exchange (ETDEWEB)

Gallaher, B.M.; Benjamin, T.M.; Rokop, D.J.; Stoker, A.K.

1997-09-22

For more than three decades Mortandad Canyon has been the primary release area of treated liquid radioactive waste from the Los Alamos National Laboratory (Laboratory). In this survey, six water samples and seven stream sediment samples collected in Mortandad Canyon were analyzed by thermal ionization mass spectrometry (TIMS) to determine the plutonium and uranium activity levels and atom ratios. Be measuring the {sup 240}Pu/{sup 239}Pu atom ratios, the Laboratory plutonium component was evaluated relative to that from global fallout. Measurements of the relative abundance of {sup 235}U and {sup 236}U were also used to identify non-natural components. The survey results indicate the Laboratory plutonium and uranium concentrations in waters and sediments decrease relatively rapidly with distance downstream from the major industrial sources. Plutonium concentrations in shallow alluvial groundwater decrease by approximately 1000 fold along a 3000 ft distance. At the Laboratory downstream boundary, total plutonium and uranium concentrations were generally within regional background ranges previously reported. Laboratory derived plutonium is readily distinguished from global fallout in on-site waters and sediments. The isotopic ratio data indicates off-site migration of trace levels of Laboratory plutonium in stream sediments to distances approximately two miles downstream of the Laboratory boundary.

Survey of plutonium and uranium atom ratios and activity levels in Mortandad Canyon

Energy Technology Data Exchange (ETDEWEB)

Gallaher, B.M.; Efurd, D.W.; Rokop, D.J.; Benjamin, T.M. [Los Alamos National Lab., NM (United States); Stoker, A.K. [Science Applications, Inc., White Rock, NM (United States)

1997-10-01

For more than three decades, Mortandad Canyon has been the primary release area of treated liquid radioactive waste from the Los Alamos National Laboratory (Laboratory). In this survey, six water samples and seven stream sediment samples collected in Mortandad Canyon were analyzed by thermal ionization mass spectrometry to determine the plutonium and uranium activity levels and atom ratios. By measuring the {sup 240}Pu/{sup 239}Pu atom ratios, the Laboratory plutonium component was evaluated relative to that from global fallout. Measurements of the relative abundance of {sup 235}U and {sup 236}U were also used to identify non-natural components. The survey results indicate that the Laboratory plutonium and uranium concentrations in waters and sediments decrease relatively rapidly with distance downstream from the major industrial sources. Plutonium concentrations in shallow alluvial groundwater decrease by approximately 1,000-fold along a 3,000-ft distance. At the Laboratory downstream boundary, total plutonium and uranium concentrations were generally within regional background ranges previously reported. Laboratory-derived plutonium is readily distinguished from global fallout in on-site waters and sediments. The isotopic ratio data indicate off-site migration of trace levels of Laboratory plutonium in stream sediments to distances approximately two miles downstream of the Laboratory boundary.

Survey of plutonium and uranium atom ratios and activity levels in Mortandad Canyon

International Nuclear Information System (INIS)

Gallaher, B.M.; Efurd, D.W.; Rokop, D.J.; Benjamin, T.M.; Stoker, A.K.

1997-10-01

For more than three decades, Mortandad Canyon has been the primary release area of treated liquid radioactive waste from the Los Alamos National Laboratory (Laboratory). In this survey, six water samples and seven stream sediment samples collected in Mortandad Canyon were analyzed by thermal ionization mass spectrometry to determine the plutonium and uranium activity levels and atom ratios. By measuring the 240 Pu/ 239 Pu atom ratios, the Laboratory plutonium component was evaluated relative to that from global fallout. Measurements of the relative abundance of 235 U and 236 U were also used to identify non-natural components. The survey results indicate that the Laboratory plutonium and uranium concentrations in waters and sediments decrease relatively rapidly with distance downstream from the major industrial sources. Plutonium concentrations in shallow alluvial groundwater decrease by approximately 1,000-fold along a 3,000-ft distance. At the Laboratory downstream boundary, total plutonium and uranium concentrations were generally within regional background ranges previously reported. Laboratory-derived plutonium is readily distinguished from global fallout in on-site waters and sediments. The isotopic ratio data indicate off-site migration of trace levels of Laboratory plutonium in stream sediments to distances approximately two miles downstream of the Laboratory boundary

Survey of plutonium and uranium atom ratios and activity levels in Mortandad Canyon

International Nuclear Information System (INIS)

Gallaher, B.M.; Benjamin, T.M.; Rokop, D.J.; Stoker, A.K.

1997-01-01

For more than three decades Mortandad Canyon has been the primary release area of treated liquid radioactive waste from the Los Alamos National Laboratory (Laboratory). In this survey, six water samples and seven stream sediment samples collected in Mortandad Canyon were analyzed by thermal ionization mass spectrometry (TIMS) to determine the plutonium and uranium activity levels and atom ratios. Be measuring the 240 Pu/ 239 Pu atom ratios, the Laboratory plutonium component was evaluated relative to that from global fallout. Measurements of the relative abundance of 235 U and 236 U were also used to identify non-natural components. The survey results indicate the Laboratory plutonium and uranium concentrations in waters and sediments decrease relatively rapidly with distance downstream from the major industrial sources. Plutonium concentrations in shallow alluvial groundwater decrease by approximately 1000 fold along a 3000 ft distance. At the Laboratory downstream boundary, total plutonium and uranium concentrations were generally within regional background ranges previously reported. Laboratory derived plutonium is readily distinguished from global fallout in on-site waters and sediments. The isotopic ratio data indicates off-site migration of trace levels of Laboratory plutonium in stream sediments to distances approximately two miles downstream of the Laboratory boundary

A recent source modification for noble gases at the Los Alamos on-line mass analysis facility

International Nuclear Information System (INIS)

Balestrini, S.J.; Forman, L.

1976-01-01

The Los Alamos on-line mass analysis experiment at the Godiva-IV burst reactor facility has been modified to determine independent fission yields of noble gases. The gases are released from a stearate target and ionization by electron bombardment. The distance traveled by the gases from the target to the ionization chamber is 20 cm. The efficiency of the electron bombardment source is lower than that of the surface ionization source that was employed to measure the yields of Rb and Cs. But this effect is compensated by the larger quantity of target metal that is possible when using a stearate target. (Auth.)

The use of safeguards data for process monitoring in the Advanced Test Line for Actinide Separations

International Nuclear Information System (INIS)

Barnes, J.W.; Yarbro, S.L.

1987-01-01

Los Alamos is constructing an integrated process monitoring/materials control and accounting (PM/MC and A) system in the Advanced Testing Line for Actinide Separations (ATLAS) at the Los Alamos Plutonium Facility. The ATLAS will test and demonstrate new methods for aqueous processing of plutonium. The ATLAS will also develop, test, and demonstrate the concepts for integrated process monitoring/materials control and accounting. We describe how this integrated PM/MC and A system will function and provide benefits to both process research and materials accounting personnel

Current segmented gamma-ray scanner technology

International Nuclear Information System (INIS)

Bjork, C.W.

1987-01-01

A new generation of segmented gamma-ray scanners has been developed at Los Alamos for scrap and waste measurements at the Savannah River Plant and the Los Alamos Plutonium Facility. The new designs are highly automated and exhibit special features such as good segmentation and thorough shielding to improve performance

Plutonium safe handling

International Nuclear Information System (INIS)

Tvehlov, Yu.

2000-01-01

The abstract, prepared on the basis of materials of the IAEA new leadership on the plutonium safe handling and its storage (the publication no. 9 in the Safety Reports Series), aimed at presenting internationally acknowledged criteria on the radiation danger evaluation and summarizing the experience in the safe management of great quantities of plutonium, accumulated in the nuclear states, is presented. The data on the weapon-class and civil plutonium, the degree of its danger, the measures for provision of its safety, including the data on accident radiation consequences with the fission number 10 18 , are presented. The recommendations, making it possible to eliminate the super- criticality danger, as well as ignition and explosion, to maintain the tightness of the facility, aimed at excluding the radioactive contamination and the possibility of internal irradiation, to provide for the plutonium security, physical protection and to reduce irradiation are given [ru

Availability of environmental radioactivity to honey bee colonies at Los Alamos

International Nuclear Information System (INIS)

Hakonson, T.E.; Bostick, K.V.

1976-01-01

Data are presented on the availability of tritium, cesium 137, and plutonium to honey bee colonies foraging in the environment surrounding the Los Alamos Scientific Laboratory. Sources of these radionuclides in the laboratory environs include liquid and atmospheric effluents and buried solid waste. Honey bee colonies were placed in three canyon liquid waste disposal areas and were sampled frequently, along with honey, surface water, and surrounding vegetation, to qualitatively determine the availability of these radionuclides to bees (Apis mellifera) and to identify potential food chain sources of the elements. Tritium concentrations in bee and honey samples from the canyons increased rapidly from initial values of 137 Cs in the environs. The existence of at least three radionuclide sources in the Los Alamos Scientific Laboratory (LASL) environs complicates the interpretation of the data. However, it is apparent that honey bees can acquire 3 H, 137 Cs, and Pu from multiple sources in the environs

Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility

International Nuclear Information System (INIS)

1997-01-01

The deactivated 233-S Plutonium Concentration Facility (233-S Facility) is located in the 200 Area. The facility has undergone severe degradation due to exposure to extreme weather conditions. A rapid freeze and thaw cycle occurred at the Hanford Site during February 1996, which caused cracking to occur on portions of the building's roof. This has resulted in significantly infiltration of water into the facility, which provides a pathway for potential release of radioactive material into the environment (air and/or ground). The weather caused several existing cracks in the concrete portions of the structure to lengthen, increasing the potential for failed confinement of the radioactive material in the building. Differential settlement has also occurred, causing portions of the facility to separate from the main building structure thus creating a potential for release of radioactive material t the environment. An expedited removal action is proposed to ensure that a release from the 233-S Facility does not occur. The US Department of Energy (DOE), Richland Operations Office (RL), in cooperation with the EPA, has prepared this Engineering Evaluation/Cost Analysis (EE/CA) pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health and/or the environment, and that an expedited removal action is warranted. The purpose of the EE/CA is to provide the framework for the evaluation and selection of a technology from a viable set of alternatives for a removal action

Rough order of magnitude cost estimate for immobilization of 18.2 MT of plutonium using existing facilities at Hanford: alternatives 4A/8/10

International Nuclear Information System (INIS)

DiSabatino, A.

1998-01-01

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, the Fuels and Materials Examination Facility (FMEF), at Hanford

Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2016

Energy Technology Data Exchange (ETDEWEB)

Birdsell, Kay Hanson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Atchley, Adam Lee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Elizabeth D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chu, Shaoping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-03-24

As a condition to the disposal authorization statement issued to Los Alamos National Laboratory (LANL or the Laboratory) on March 17, 2010, a comprehensive performance assessment and composite analysis (PA/CA) maintenance program must be implemented for the Technical Area 54, Area G disposal facility. Annual determinations of the adequacy of the PA/CA are to be conducted under the maintenance program to ensure that the conclusions reached by those analyses continue to be valid. This report summarizes the results of the fiscal year (FY) 2016 annual review for Area G.

Study of uranium-plutonium alloys containing from 0 to 20 peri cent of plutonium (1963); Etude des alliages uranium-plutonium aux concentrations comprises entre 0 et 20 pour cent de plutonium (1963)

Energy Technology Data Exchange (ETDEWEB)

Paruz, H [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1963-05-15

The work is carried out on U-Pu alloys in the region of the solid solution uranium alpha and in the two-phase region uranium alpha + the zeta phase. The results obtained concern mainly the influence of the addition of plutonium on the physical properties of the uranium (changes in the crystalline parameters, the density, the hardness) in the region of solid solution uranium alpha. In view of the discrepancies between various published results as far as the equilibrium diagram for the system U-Pu is concerned, an attempt was made to verify the extent of the different regions of the phase diagram, in particular the two phased-region. Examinations carried out on samples after various thermal treatments (in particular quenching from the epsilon phase and prolonged annealings, as well as a slow cooling from the epsilon phase) confirm the results obtained at Los Alamos and Harwell. (author) [French] L'etude porte sur des alliages U-Pu du domaine de la solution solide uranium alpha et du domaine biphase uranium + phase zeta. Les resultats obtenus concernent en premier lieu l'influence de l'addition de plutonium sur les proprietes physiques de l'uranium (changement des parametres cristallins, densite, durete) dans le domaine de la solution solide uranium alpha. Compte tenu des divergences entre les differents resultats publies en ce qui concerne le diagramme d'equilibre du systeme U-Pu, on a essaye ensuite de verifier l'etendue des differents domaines du diagramme des phases, en particulier du domaine biphase zeta + uranium alpha. Les examens par micrographie et par diffraction des rayons X des echantillons apres differents traitements thermiques (notamment trempe a partir de la phase epsilon et recuits prolonges, ainsi qu'un refroidissement lent etage a partir de la phase epsilon) confirment les resultats obtenus a Los Alamos et a Harwell. (auteur)

The WNR facility - a pulsed spallation neutron source at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Russell, G.J.; Lisowski, P.W.; King, N.S.P.

1978-01-01

The Weapons Neutron Research facility (WNR) at the Los Alamos Scientific Laboratory is the first operating example of a new class of pulsed neutron sources using the X(p,n)Y spallation reaction. At present, up to 10 microamperes of 800-MeV protons from the Clinton P. Anderson Meson Physics Facility (LAMPF) linear accelerator bombard a Ta target to produce an intense white-neutron spectrum from about 800 MeV to 100 keV. The Ta target can be coupled with CH 2 and H 2 O moderators to produce neutrons of lower energy. The time structure of the WNR proton beam may be varied to optimize neutron time-of-flight (TOF) measurements covering the energy range from several hundred MeV to a few meV. The neutronics of the WNR target and target/moderator configurations have been calculated from 800 MeV to 0.5 eV. About 11 neutrons per proton are predicted for the existing Ta target. Some initial neutron TOF data are presented and compared with calculations

A performance indicator for reduction in vulnerability through stabilization of plutonium

International Nuclear Information System (INIS)

Marchese, A.R.; Neogy, P.; Azarm, M.A.

1997-01-01

The US Department of Energy (DOE) is currently storing several metric tons of plutonium in various forms in a variety of facilities throughout the DOE complex. Since the cessation of weapons production in 1990, many of these facilities with plutonium in storage have not operated. Since the shutdown was regarded as temporary, little attempt was made at that time to empty the process lines of plutonium, or to place the plutonium in containers or packages that would provide safe storage for extended periods of time. As a result, the packages and containers providing interim storage are vulnerable to failure through leakage, rupture and other modes, and pose potential hazards to facility workers, the public and the environment. Here, an approach to measuring and tracking the reduction in vulnerabilities resulting from stabilizing and repackaging plutonium is developed and presented. The approach utilizes results obtained by the DOE Working Group on the vulnerabilities associated with plutonium storage

Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

International Nuclear Information System (INIS)

Reneau, S.L.; Raymond, R. Jr.

1995-12-01

This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau

Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Reneau, S.L.; Raymond, R. Jr. [eds.

1995-12-01

This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau.

The Los Alamos National Laboratory Chemistry and Metallurgy Research Facility upgrades project - A model for waste minimization

International Nuclear Information System (INIS)

Burns, M.L.; Durrer, R.E.; Kennicott, M.A.

1996-07-01

The Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Facility, constructed in 1952, is currently undergoing a major, multi-year construction project. Many of the operations required under this project (i.e., design, demolition, decontamination, construction, and waste management) mimic the processes required of a large scale decontamination and decommissioning (D ampersand D) job and are identical to the requirements of any of several upgrades projects anticipated for LANL and other Department of Energy (DOE) sites. For these reasons the CMR Upgrades Project is seen as an ideal model facility - to test the application, and measure the success of - waste minimization techniques which could be brought to bear on any of the similar projects. The purpose of this paper will be to discuss the past, present, and anticipated waste minimization applications at the facility and will focus on the development and execution of the project's open-quotes Waste Minimization/Pollution Prevention Strategic Plan.close quotes

CFD analysis and experimental investigation associated with the design of the Los Alamos nuclear materials storage facility

International Nuclear Information System (INIS)

Bernardin, J.D.; Hopkins, S.; Gregory, W.S.; Martin, R.A.

1997-01-01

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory is being renovated for long-term storage of canisters designed to hold heat-generating nuclear materials, such as powders, ingots, and other components. The continual heat generation within the canisters necessitates a reliable cooling scheme of sufficient magnitude which maintains the stored material temperatures within acceptable limits. The primary goal of this study was to develop both an experimental facility and a computational fluid dynamics (CFD) model of a subsection of the NMSF which could be used to observe general performance trends of a proposed passive cooling scheme and serve as a design tool for canister holding fixtures. Comparisons of numerical temperature and velocity predictions with empirical data indicate that the CFD model provides an accurate representation of the NMSF experimental facility. Minor modifications in the model geometry and boundary conditions are needed to enhance its accuracy, however, the various fluid and thermal models correctly capture the basic physics

The development of the atomic bomb, Los Alamos

Energy Technology Data Exchange (ETDEWEB)

Seidel, R.W.

1993-11-01

The historical presentation begins with details of the selection of Los Alamos as the site of the Army installation. Wartime efforts of the Army Corps of Engineers, and scientists to include the leader of Los Alamos, Robert Oppenheimer are presented. The layout and construction of the facilities are discussed. The monumental design requirements of the bombs are discussed, including but not limited to the utilization of the second choice implosion method of detonation, and the production of bomb-grade nuclear explosives. The paper ends with a philosophical discussion on the use of nuclear weapons.

Plutonium Finishing Plant (PFP) Final Safety Analysis Report (FSAR) [SEC 1 THRU 11

Energy Technology Data Exchange (ETDEWEB)

ULLAH, M K

2001-02-26

The Plutonium Finishing Plant (PFP) is located on the US Department of Energy (DOE) Hanford Site in south central Washington State. The DOE Richland Operations (DOE-RL) Project Hanford Management Contract (PHMC) is with Fluor Hanford Inc. (FH). Westinghouse Safety Management Systems (WSMS) provides management support to the PFP facility. Since 1991, the mission of the PFP has changed from plutonium material processing to preparation for decontamination and decommissioning (D and D). The PFP is in transition between its previous mission and the proposed D and D mission. The objective of the transition is to place the facility into a stable state for long-term storage of plutonium materials before final disposition of the facility. Accordingly, this update of the Final Safety Analysis Report (FSAR) reflects the current status of the buildings, equipment, and operations during this transition. The primary product of the PFP was plutonium metal in the form of 2.2-kg, cylindrical ingots called buttoms. Plutonium nitrate was one of several chemical compounds containing plutonium that were produced as an intermediate processing product. Plutonium recovery was performed at the Plutonium Reclamation Facility (PRF) and plutonium conversion (from a nitrate form to a metal form) was performed at the Remote Mechanical C (RMC) Line as the primary processes. Plutonium oxide was also produced at the Remote Mechanical A (RMA) Line. Plutonium processed at the PFP contained both weapons-grade and fuels-grade plutonium materials. The capability existed to process both weapons-grade and fuels-grade material through the PRF and only weapons-grade material through the RMC Line although fuels-grade material was processed through the line before 1984. Amounts of these materials exist in storage throughout the facility in various residual forms left from previous years of operations.

Technological alternatives for plutonium transport

International Nuclear Information System (INIS)

1978-12-01

This paper considers alternative transport modes (air, sea, road, rail) for moving (1) plutonium from a reprocessing plant to a store or a fuel fabrication facility, and (2) MOX fuel from the latter to a reactor. These transport modes and differing forms of plutonium are considered in terms of: their proliferation resistance and safeguards; environmental and safety aspects; and economic aspects. It is tentatively proposed that the transport of plutonium could continue by air or sea where long distances are involved and by road or rail over shorter distances; this would be acceptable from the non-proliferation, environmental impact and economic aspects - there may be advantages in protection if plutonium is transported in the form of mixed oxide

Decommissioning three nuclear reactors at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Montoya, G.M.; Salazar, M.

1992-01-01

Three nuclear reactors, including the historic water boiler reactor, were decommissioned at Los Alamos National Laboratory (LANL). The decommissioning of the facilities involved removing the reactors and their associated components. Planning for the decommissioning operation included characterizing the facilities, estimating the costs of decommissioning operations, preparing environmental documentation, establishing systems to track costs and work progress, and preplanning to correct health and safety concerns in each facility

Automation of plutonium spectrophotometry

International Nuclear Information System (INIS)

Perez, J.J.; Boisde, G.; Goujon de Beauvivier, M.; Chevalier, G.; Isaac, M.

1980-01-01

Instrumentation was designed and constructed for automatic control of plutonium by molecular absorption spectrophotometry, on behalf of the reprocessing facilities, to meet two objectives: on-line measurement, of the valency state of plutonium, on by-pass, with the measured concentration covering the process concentration range up to a few mg.l -1 ; laboratory measurement of plutonium adjusted to valency VI, with operation carried out using a preparative system meeting the required containment specifications. For this two objectives, the photometer, optical cell connections are made by optical fibers resistant to β, γ radiation. Except this characteristic the devices are different according to the quality required for result [fr

THE DEACTIVATION, DECONTAMINATION AND DECOMMISSIONING OF THE PLUTONIUM FINISHING PLANT, A FORMER PLUTONIUM PROCESSING FACILITY AT DOE'S HANFORD SITE

International Nuclear Information System (INIS)

CHARBONEAU, S.L.

2006-01-01

The Plutonium Finishing Plant (PFP) was constructed as part of the Manhattan Project during World War II. The Manhattan Project was developed to usher in the use of nuclear weapons to end the war. The primary mission of the PFP was to provide plutonium used as special nuclear material (SNM) for fabrication of nuclear devices for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race and later the processing of fuel grade mixed plutonium-uranium oxide to support DOE's breeder reactor program. In October 1990, at the close of the production mission for PFP, a shutdown order was prepared by the Department of Energy (DOE) in Washington,; DC--and issued to the Richland DOE field office. Subsequent to the shutdown order, a team from the Defense Nuclear Facilities Safety Board (DNFSB) analyzed the hazards at PFP associated with the continued storage of certain forms of plutonium solutions and solids. The assessment identified many discrete actions that were required to stabilize the different plutonium forms into stable form and repackage the material in high integrity containers. These actions were technically complicated and completed as part of the PFP nuclear material stabilization project between 1995 and early 2005. The completion of the stabilization project was a necessary first step in deactivating PFP. During stabilization, DOE entered into negotiations with the U.S. Environmental Protection Agency (EPA) and the State of Washington and established milestones for the Deactivation and Decommissioning (DandD) of the PFP. The DOE and its contractor, Fluor Hanford (Fluor), have made great progress in deactivating, decontaminating and decommissioning the PFP at the Hanford Site as detailed in this paper. Background information covering the PFP DandD effort includes descriptions of negotiations with the State of Washington concerning consent

Direct oxide reduction (DOR) solvent salt recycle in pyrochemical plutonium recovery operations

International Nuclear Information System (INIS)

Fife, K.W.; Bowersox, D.F.; Davis, C.C.; McCormick, E.D.

1987-02-01

One method used at Los Alamos for producing plutonium metal is to reduce the oxide with calcium metal in molten CaCl 2 at 850 0 C. The solvent CaCl 2 from this reduction step is currently discarded as low-level radioactive waste because it is saturated with the reaction by-product, CaO. We have developed and demonstrated a molten salt technique for rechlorinating the CaO, thereby regenerating the CaCl 2 and incorporating solvent recycle into the batch PuO 2 reduction process. We discuss results from the process development experiments and present our plans for incorporating the technique into an advanced design for semicontinuous plutonium metal production

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

International Nuclear Information System (INIS)

DiSabatino, A.

1998-01-01

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)

A proposal for a long-pulse spallation source at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Pynn, R.; Weinacht, D.

1995-01-01

Los Alamos National Laboratory is proposing a new spallation neutron source that will provide the US with an internationally competitive facility for neutron science and technology that can be built in approximately three years for less than $100 million. The establishment of a 1-MW, long-pulse spallation source (LPSS) at the Los Alamos Neutron Science Center (LANSCE) will meet many of the present needs of scientists in the neutron scattering community and provide a significant boost to neutron research in the US. The new facility will support the development of a future, more intense spallation neutron source, that is planned by DOE's Office of Energy Research. Together with the existing short pulse spallation source (SPSS) at the Manual Lujan, Jr. Neutron Scattering Center (MLNSC) at Los Alamos, the new LPSS will provide US scientists with a complementary pair of high-performance neutron sources to rival the world's leading facilities in Europe

A proposal for a long-pulse spallation source at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Pynn, R; Weinacht, D [Los Alamos National Lab., NM (United States)

1995-11-01

Los Alamos National Laboratory is proposing a new spallation neutron source that will provide the U.S. with an internationally competitive facility for neutron science and technology that can be built in approximately three years for less than $100 million. The establishment of a 1-MW long-pulse spallation source (LPSS) at the Los Alamos Neutron Science Center (LANSCE) will meet many of the present needs of scientists in the neutron scattering community and provide a significant boost to neutron research in the U.S. The new facility will support the development of a future, more intense spallation neutron source, that is planned by DOE`s Office of Energy Research. Together with the existing short pulse spallation source (SPSS) at the Manual Lujan, Jr. Neutron Scattering Center (MLNSC) at Los Alamos, the new LPSS will provide U.S. scientists with a complementary pair of high-performance neutron sources to rival the world`s leading facilities in Europe. (author) 1 ref.

A proposal for a long-pulse spallation source at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Pynn, R.; Weinacht, D.

1995-01-01

Los Alamos National Laboratory is proposing a new spallation neutron source that will provide the U.S. with an internationally competitive facility for neutron science and technology that can be built in approximately three years for less than $100 million. The establishment of a 1-MW long-pulse spallation source (LPSS) at the Los Alamos Neutron Science Center (LANSCE) will meet many of the present needs of scientists in the neutron scattering community and provide a significant boost to neutron research in the U.S. The new facility will support the development of a future, more intense spallation neutron source, that is planned by DOE's Office of Energy Research. Together with the existing short pulse spallation source (SPSS) at the Manual Lujan, Jr. Neutron Scattering Center (MLNSC) at Los Alamos, the new LPSS will provide U.S. scientists with a complementary pair of high-performance neutron sources to rival the world's leading facilities in Europe. (author) 1 ref

Plutonium contaminated solid waste programs at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Johson, L.J.; Jordan, H.S.

1975-01-01

Development of handling and storage criteria for plutonium contaminated solid waste materials is discussed. Data from corrosion and radiolytic attack studies are reviewed. Instrumentation systems developed for solid waste management applications at the 10nCi Pu/g waste material level is described and their sensitivity and operational limitations reviewed. Current programs for the environmental risk analysis of past waste disposal areas and for development of technology for the volume reduction and chemical stabilization of transuranic contaminated solid waste is outlined

Validation of the method for determination of plutonium isotopes in urine samples and its application in a nuclear facility at Otwock

Directory of Open Access Journals (Sweden)

Rzemek Katarzyna

2015-03-01

Full Text Available The studies aimed at determining low activities of alpha radioactive elements are widely recognized as essential for the human health, because of their high radiotoxicity in case of internal contamination. Some groups of workers of nuclear facility at Otwock are potentially exposed to contamination with plutonium isotopes. For this reason, the method for determination of plutonium isotopes has been introduced and validated in Radiation Protection Measurements Laboratory (LPD of the National Centre for Nuclear Research (NCBJ. In this method the plutonium is isolated from a sample by coprecipitation with phosphates and separated on a AG 1-X2 Resin. After electrodeposition, the sample is measured by alpha spectrometry. Validation was performed in order to assess parameters such as: selectivity, accuracy (trueness and precision and linearity of the method. The results of plutonium determination in urine samples of persons potentially exposed to internal contamination are presented in this work.

Experience in the cleanup of plutonium-contaminated land

International Nuclear Information System (INIS)

Smith, W.J. II; Fowler, E.B.; Stafford, R.G.

1977-03-01

During the summer of 1974, two accidental releases from a radioactive liquid-waste line at the Los Alamos Scientific Laboratory (LASL) resulted in plutonium contamination of a small area of land, a portion of a Laboratory parking lot, and a strip along an adjacent street. This report documents the immediate control actions and radiation surveys made in response to these leaks, and the subsequent exhumation and decontamination processes, including the physical operations, operational health physics, and soil sample analyses. The cost and results of the decontamination and restoration are also covered

Water bath and air bath calorimeter qualification for measuring 3013 containers of plutonium oxide at the Hanford Plutonium Finishing Plant (PFP)

International Nuclear Information System (INIS)

WELSH, T.L.

2003-01-01

The purpose of this paper is to present qualification data generated from water and air-bath calorimeters measuring radioactive decay heat from plutonium oxide in DOE STD-3013-2000 (3013) containers at the Hanford Plutonium Finishing Plant (PFP). Published data concerning air and water bath calorimeters and especially 3013-qualified calorimeters is minimal at best. This paper will address the data from the measurement/qualification test plan, the heat standards used, and the calorimeter precision and accuracy results. The 3013 package is physically larger than earlier plutonium oxide storage containers, thereby necessitating a larger measurement chamber. To accommodate the measurements of the 3013 containers at PFP, Los Alamos National Laboratory (LANL) supplied a water bath dual-chambered unit and the Savannah River Technology Center (SRTC) provided two air-bath calorimeters. Both types of Calorimeters were installed in the analytical laboratory at PFP. The larger 3013 containers presented a new set of potential measurement problems: longer counting times, heat conductivity through a much larger container mass and wall thickness, and larger amounts of copper shot to assist sample thermal conductivity. These potential problems were addressed and included in the measurement/qualification test plan

Migration of Sr-20, Cs-137, and Pu-239/240 in Canyon below Los Alamos outfall

International Nuclear Information System (INIS)

Murphy, J.M.; Mason, C.F.V.; Boak, J.M.; Longmire, P.A.

1996-01-01

Technical Area-21 (TA-21) of Los Alamos National Laboratory (LANL) is on a mesa bordered by two canyons DP Canyon and Los Alamos (LA) Canyon. DP Canyon is a small semiarid watershed with a well defined channel system where the stream flow is ephemeral. TA-21 has had a complex history of waste disposal as research to determine the chemical and metallurgical properties of nuclear materials occurred here from 1945-1978. Due to these operations, the TA-21 mesa top and bordering canyons have been monitored and characterized by the LANL Environmental Restoration Program. Results identify radionuclide values at outfall. 21-011 (k) which exceed Screening Action Levels, and points along DP Canyon which exceed regional background levels. The radiocontaminants considered in this study are strontium-90, cesium-137, and plutonium-239. This research examines sediment transport and speciation of radionuclide contaminant migration from a source term named SWMU 21-011 (k) down DP Canyon. Three dimensional surface plots of data from 1977-1994 are used to portray the transport and redistribution of radioactive contaminants in an alluvial stream channel. An overall decrease in contamination concentration since 1983 has been observed which could be due to more stringent laboratory controls and also to the removal of main plutonium processing laboratories to another site

Migration of Sr-20, Cs-137, and Pu-239/240 in Canyon below Los Alamos outfall

Energy Technology Data Exchange (ETDEWEB)

Murphy, J.M.; Mason, C.F.V.; Boak, J.M.; Longmire, P.A.

1996-04-01

Technical Area-21 (TA-21) of Los Alamos National Laboratory (LANL) is on a mesa bordered by two canyons DP Canyon and Los Alamos (LA) Canyon. DP Canyon is a small semiarid watershed with a well defined channel system where the stream flow is ephemeral. TA-21 has had a complex history of waste disposal as research to determine the chemical and metallurgical properties of nuclear materials occurred here from 1945-1978. Due to these operations, the TA-21 mesa top and bordering canyons have been monitored and characterized by the LANL Environmental Restoration Program. Results identify radionuclide values at outfall. 21-011 (k) which exceed Screening Action Levels, and points along DP Canyon which exceed regional background levels. The radiocontaminants considered in this study are strontium-90, cesium-137, and plutonium-239. This research examines sediment transport and speciation of radionuclide contaminant migration from a source term named SWMU 21-011 (k) down DP Canyon. Three dimensional surface plots of data from 1977-1994 are used to portray the transport and redistribution of radioactive contaminants in an alluvial stream channel. An overall decrease in contamination concentration since 1983 has been observed which could be due to more stringent laboratory controls and also to the removal of main plutonium processing laboratories to another site.

Rough order of magnitude cost estimate for immobilization of 50 MT of plutonium using existing facilities at the Savannah River site: alternative 12B

International Nuclear Information System (INIS)

DiSabatino, A.

1998-01-01

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 an existing facility (221-F) at an Savannah River Site (SRS)

Technical considerations and policy requirements for plutonium management

International Nuclear Information System (INIS)

Christensen, D.C.; Dinehart, S.M.; Yarbro, S.L.

1995-01-01

The goals for plutonium management have changed dramatically over the past few years. Today, the challenge is focused on isolating plutonium from the environment and preparing it for permanent disposition. In parallel, the requirements for managing plutonium are rapidly changing. For example, there is a significant increase in public awareness on how facilities operate, increased attention to environmental safety and health (ES and H) concerns, greater interest in minimizing waste, more emphasis on protecting material from theft, providing materials for international inspection, and a resurgence of interest in using plutonium as an energy source. Of highest concern, in the immediate future, is protecting plutonium from theft or diversion, while the national policy on disposition is debated. These expanded requirements are causing a broadening of responsibilities within the Department of Energy (DOE) to include at least seven organizations. An unavoidable consequence is the divergence in approach and short-term goals for managing similar materials within each organization. The technology base does exist, properly, safely, and cost effectively to extract plutonium from excess weapons, residues, waste, and contaminated equipment and facilities, and to properly stabilize it. Extracting the plutonium enables it to be easily inventoried, packaged, and managed to minimize the risk of theft and diversion. Discarding excess plutonium does not sufficiently reduce the risk of diversion, and as a result, long-term containment of plutonium from the environment may not be able to be proven to the satisfaction of the public

Technical considerations and policy requirements for plutonium management

International Nuclear Information System (INIS)

Christensen, D.C.; Dinehart, S.M.; Yarbro, S.L.

1996-01-01

The goals for plutonium management have changed dramatically over the past few years. Today, the challenge is focused on isolating plutonium from the environment and preparing it for permanent disposition. In parallel, the requirements for managing plutonium are rapidly changing. For example, there is a significant increase in public awareness on how facilities operate, increased attention to environmental safety and health (ES and H) concerns, greater interest in minimizing waste, more emphasis on protecting material from theft, providing materials for international inspection, and a resurgence of interest in using plutonium as an energy source. Of highest concern, in the immediate future, is protecting plutonium from theft or diversion, while the national policy on disposition is debated. These expanded requirements are causing a broadening of responsibilities within the Department of Energy (DOE) to include at least seven organizations. An unavoidable consequence is the divergence in approach and short-term goals for managing similar materials within each organization. The technology base does exist, properly, safely, and cost effectively to extract plutonium from excess weapons, residues, waste, and contaminated equipment and facilities, and to properly stabilize it. Extracting the plutonium enables it to be easily inventoried, packaged, and managed to minimize the risk of theft and diversion. Discarding excess plutonium does not sufficient reduce the risk of diversion, and as a result, long-term containment of plutonium from the environment may not be able to be proven to the satisfaction of the public

Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility – Fiscal Year 2015

Energy Technology Data Exchange (ETDEWEB)

French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Birdsell, Kay H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-02-29

As a condition to the disposal authorization statement issued to Los Alamos National Laboratory (LANL or the Laboratory) on March 17, 2010, a comprehensive performance assessment and composite analysis maintenance program must be implemented for the Technical Area 54, Area G disposal facility. Annual determinations of the adequacy of the performance assessment and composite analysis (PA/CA) are to be conducted under the maintenance program to ensure that the conclusions reached by those analyses continue to be valid. This report summarizes the results of the fiscal year (FY) 2015 annual review for Area G.

Confinement facilities for handling plutonium

International Nuclear Information System (INIS)

Maraman, W.J.; McNeese, W.D.; Stafford, R.G.

1975-01-01

Plutonium handling on a multigram scale began in 1944. Early criteria, equipment, and techniques for confining contamination have been superseded by more stringent criteria and vastly improved equipment and techniques for in-process contamination control, effluent air cleaning and treatment of liquid wastes. This paper describes the evolution of equipment and practices to minimize exposure of workers and escape of contamination into work areas and into the environment. Early and current contamination controls are compared. (author)

Stabilization of Rocky Flats combustible residues contaminated with plutonium metal and organic solvents

International Nuclear Information System (INIS)

Bowen, S.M.; Cisneros, M.R.; Jacobson, L.L.; Schroeder, N.C.; Ames, R.L.

1998-01-01

This report describes tests on a proposed flowsheet designed to stabilize combustible residues that were generated at the Rocky Flats Environmental Technology Site (RFETS) during the machining of plutonium metal. Combustible residues are essentially laboratory trash contaminated with halogenated organic solvents and plutonium metal. The proposed flowsheet, designed by RFETS, follows a glovebox procedure that includes (1) the sorting and shredding of materials, (2) a low temperature thermal desorption of solvents from the combustible materials, (3) an oxidation of plutonium metal with steam, and (4) packaging of the stabilized residues. The role of Los Alamos National Laboratory (LANL) in this study was to determine parameters for the low temperature thermal desorption and steam oxidation steps. Thermal desorption of carbon tetrachloride (CCl 4 ) was examined using a heated air stream on a Rocky Flats combustible residue surrogate contaminated with CCl 4 . Three types of plutonium metal were oxidized with steam in a LANL glovebox to determine the effectiveness of this procedure for residue stabilization. The results from these LANL experiments are used to recommend parameters for the proposed RFETS stabilization flowsheet

Safeguarding the Plutonium Fuel Cycle

International Nuclear Information System (INIS)

Johnson, S.J.; Lockwood, D.

2013-01-01

In developing a Safeguards Approach for a plutonium process facility, two general diversion and misuse scenarios must be addressed: 1) Unreported batches of undeclared nuclear material being processed through the plant and bypassing the accountancy measurement points, and 2) The operator removing plutonium at a rate that cannot be detected with confidence due to measurement uncertainties. This paper will look at the implementation of international safeguards at plutonium fuel cycle facilities in light of past lessons learned and current safeguards approaches. It will then discuss technical areas which are currently being addressed as future tools to improve on the efficiency of safeguards implementation, while maintaining its effectiveness. The discussion of new improvements will include: safeguards by design (SBD), process monitoring (PM), measurement and monitoring equipment, and data management. The paper is illustrated with the implementation of international safeguards at the Rokkasho Reprocessing Plant in Japan and its accountancy structure is detailed. The paper is followed by the slides of the presentation

Precautions for preventing criticality at plutonium fuel treatment facilities

International Nuclear Information System (INIS)

Deworm, J.P.; Fieuw, G.; Cank, H. de

1976-01-01

Four criticality accidents took place between 1958 and 1964 at fuel processing plants using wet methods. So far accident of this type has taken place at production units where fissionable material is used. The prevention of criticality is one of the major concerns of the officials in charge of the plutonium fuel research laboratories operated at the Mol Nuclear Energy Study Centre by the SCK/CEN-Belgonucleaire Association. The means of preventing such an accident are of three types: introducing different types of treatment in well-defined work units; thorough analysis of planned experiments or fabrication programmes to determine the sub-criticality factors; application of technical and administrative procedures which ensure that the facilities are always sub-critical during the treatment and storage of fissionable materials. The installation includes a detection and warning system and provision is made for the immediate evacuation of staff should a crticality incident occur. The effects of a critical excursion on the building have been assessed. (author)

HB-Line Plutonium Oxide Data Collection Strategy

Energy Technology Data Exchange (ETDEWEB)

Watkins, R. [Savannah River Nuclear Solutions; Varble, J. [Savannah River Nuclear Solutions; Jordan, J. [Savannah River Nuclear Solutions

2015-05-26

HB-Line and H-Canyon will handle and process plutonium material to produce plutonium oxide for feed to the Mixed Oxide Fuel Fabrication Facility (MFFF). However, the plutonium oxide product will not be transferred to the MFFF directly from HB-Line until it is packaged into a qualified DOE-STD-3013-2012 container. In the interim, HB-Line will load plutonium oxide into an inner, filtered can. The inner can will be placed in a filtered bag, which will be loaded into a filtered outer can. The outer can will be loaded into a certified 9975 with getter assembly in compliance with onsite transportation requirement, for subsequent storage and transfer to the K-Area Complex (KAC). After DOE-STD-3013-2012 container packaging capabilities are established, the product will be returned to HB-Line to be packaged into a qualified DOE-STD-3013-2012 container. To support the transfer of plutonium oxide to KAC and then eventually to MFFF, various material and packaging data will have to be collected and retained. In addition, data from initial HB-Line processing operations will be needed to support future DOE-STD-3013-2012 qualification as amended by the HB-Line DOE Standard equivalency. As production increases, the volume of data to collect will increase. The HB-Line data collected will be in the form of paper copies and electronic media. Paper copy data will, at a minimum, consist of facility procedures, nonconformance reports (NCRs), and DCS print outs. Electronic data will be in the form of Adobe portable document formats (PDFs). Collecting all the required data for each plutonium oxide can will be no small effort for HB-Line, and will become more challenging once the maximum annual oxide production throughput is achieved due to the sheer volume of data to be collected. The majority of the data collected will be in the form of facility procedures, DCS print outs, and laboratory results. To facilitate complete collection of this data, a traveler form will be developed which

Linear induction accelerators at the Los Alamos National Laboratory DARHT facility

International Nuclear Information System (INIS)

Nath, Subrata

2010-01-01

The Dual-Axis Radiographic Hydrodynamic Test Facility (DARHT) at Los Alamos National Laboratory consists of two linear induction accelerators at right angles to each other. The First Axis, operating since 1999, produces a nominal 20-MeV, 2-kA single beam-pulse with 60-nsec width. In contrast, the DARHT Second Axis, operating since 2008, produces up to four pulses in a variable pulse format by slicing micro-pulses out of a longer ∼1.6-microseconds (flat-top) pulse of nominal beam-energy and -current of 17 MeV and 2 kA respectively. Bremsstrahlung x-rays, shining on a hydro-dynamical experimental device, are produced by focusing the electron beam-pulses onto a high-Z target. Variable pulse-formats allow for adjustment of the pulse-to-pulse doses to record a time sequence of x-ray images of the explosively driven imploding mock device. Herein, we present a sampling of the numerous physics and engineering aspects along with the current status of the fully operational dual axes capability. First successful simultaneous use of both the axes for a hydrodynamic experiment was achieved in 2009.

Results of Active Test of Uranium-Plutonium Co-denitration Facility at Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Numao, Teruhiko; Nakayashiki, Hiroshi; Arai, Nobuyuki; Miura, Susumu; Takahashi, Yoshiharu; Nakamura, Hironobu; Tanaka, Izumi

2007-01-01

In the U-Pu co-denitration facility at Rokkasho Reprocessing Plant (RRP), Active Test which composes of 5 steps was performed by using uranium-plutonium nitrate solution that was extracted from spent fuels. During Active Test, two kinds of tests were performed in parallel. One was denitration performance test in denitration ovens, and expected results were successfully obtained. The other was validation and calibration of non-destructive assay (NDA) systems, and expected performances were obtained and their effectiveness as material accountancy and safeguards system was validated. (authors)

DYMAC - The first stab at large safeguards systems

International Nuclear Information System (INIS)

Augustson, R.H.

1987-01-01

This article discussed the evolution of the Los Alamos Safeguards Program that led to the concept of dynamic materials accountability and control (DYMAC). A plant specific DYMAC system was installed at the Los Alamos Plutonium Facility, TA-55, in 1978. This system was turned over to the plant management and is still operational today. Systems like DYMAC/TA-55 provide necessary and realistic data on the workability of near-real-time accountability in nuclear material processing facilities

International shipment of plutonium by air

International Nuclear Information System (INIS)

Mercado, J.E.; McGrogan, J.P.

1995-05-01

In support of the United States (US) Government's decision to place excess plutonium oxide at the US Department of Energy's (DOE) Hanford Site under International Atomic Energy Agency (IAEA) safeguards, the Department of State notified the Congress that a plutonium storage vault at the Plutonium Finishing Plant at the Hanford Site would be added to the eligible facilities list. As part of the preparations to transfer the plutonium oxide under IAEA safeguards, samples of the powder were taken from the inventory to be shipped to the IAEA headquarters in Vienna, Austria, for laboratory analysis. The analysis of these samples was of high priority, and the IAEA requested that the material be shipped by aircraft, the most expeditious method

Cleanup of a Department of Energy Nonreactor Nuclear Facility: Experience at the Los Alamos National Laboratory High Pressure Tritium Laboratory

International Nuclear Information System (INIS)

Horak, H.L.

1995-01-01

On October 25, 1990, Los Alamos National Laboratory (LANL) ceased programmatic operations at the High Pressure Tritium Laboratory (HPTL). Since that time, LANL has been preparing the facility for transfer into the Department of Energy's (DOE's) Decontamination and Decommissioning Program. LANL staff now has considerable operational experience with the cleanup of a 40-year-old facility used exclusively to conduct experiments in the use of tritium, the radioactive isotope of hydrogen. Tritium and its compounds have permeated the HPTL structure and equipment, have affected operations and procedures, and now dominate efforts at cleanup and disposal. At the time of shutdown, the HPTL still had a tritium inventory of over 100 grams in a variety of forms and containers

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

International Nuclear Information System (INIS)

DiSabatino, A.

1998-01-01

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

Studies on health risks to persons exposed to plutonium

International Nuclear Information System (INIS)

Voelz, G.L.; Stebbings, J.H. Jr.; Healy, J.W.; Hempelmann, L.H.

1979-01-01

Two studies on Los Alamos workers exposed to plutonium have shown no increase in cancers of the lung, bone, and liver, three principal cancers of interest following plutonium deposition. A clinical study of 26 workers exposed 32 years ago shows no cases of cancer other than two skin cancers that were excised successfully. A mortality study of 224 workers, all persons with estimated deposition of 10 nCi or moe in 1974, showed no excess of mortality due to any cause. No bone or liver cancers were present, while one death due to lung cancer was observed as compared to an expected three cases. These negative findings on such small groups are not able to prove or disprove the validity of commonly used risk estimates as recommended in the 1972 BEIR and 1977 UNSCEAR reports, but the data do indicate that much higher risk estimates are not warranted

Studies on health risks to persons exposed to plutonium

Energy Technology Data Exchange (ETDEWEB)

Voelz, G.L.; Stebbings, J.H. Jr.; Healy, J.W.; Hempelmann, L.H.

1979-01-01

Two studies on Los Alamos workers exposed to plutonium have shown no increase in cancers of the lung, bone, and liver, three principal cancers of interest following plutonium deposition. A clinical study of 26 workers exposed 32 years ago shows no cases of cancer other than two skin cancers that were excised successfully. A mortality study of 224 workers, all persons with estimated deposition of 10 nCi or moe in 1974, showed no excess of mortality due to any cause. No bone or liver cancers were present, while one death due to lung cancer was observed as compared to an expected three cases. These negative findings on such small groups are not able to prove or disprove the validity of commonly used risk estimates as recommended in the 1972 BEIR and 1977 UNSCEAR reports, but the data do indicate that much higher risk estimates are not warranted.

GrayQb^TM Single-Faced Version 2 (SF2) Hanford Plutonium Reclamation Facility (PRF) deployment report

Energy Technology Data Exchange (ETDEWEB)

Plummer, J. R. [Savannah River Site (SRS), Aiken, SC (United States); Immel, D. M. [Savannah River Site (SRS), Aiken, SC (United States); Serrato, M. G. [Savannah River Site (SRS), Aiken, SC (United States); Dalmaso, M. J. [Savannah River Site (SRS), Aiken, SC (United States); Shull, D. J. [Savannah River Site (SRS), Aiken, SC (United States)

2015-11-18

The Savannah River National Laboratory (SRNL) in partnership with CH2M Plateau Remediation Company (CHPRC) deployed the GrayQb^TM SF2 radiation imaging device at the Hanford Plutonium Reclamation Facility (PRF) to assist in the radiological characterization of the canyon. The deployment goal was to locate radiological contamination hot spots in the PRF canyon, where pencil tanks were removed and decontamination/debris removal operations are on-going, to support the CHPRC facility decontamination and decommissioning (D&D) effort. The PRF canyon D&D effort supports completion of the CHPRC Plutonium Finishing Plant Decommissioning Project. The GrayQb^TM SF2 (Single Faced Version 2) is a non-destructive examination device developed by SRNL to generate radiation contour maps showing source locations and relative radiological levels present in the area under examination. The Hanford PRF GrayQbTM Deployment was sponsored by CH2M Plateau Remediation Company (CHPRC) through the DOE Richland Operations Office, Inter-Entity Work Order (IEWO), DOE-RL IEWO- M0SR900210.

Plutonium Immobilization Can Loading Concepts

International Nuclear Information System (INIS)

Kriikku, E.; Ward, C.; Stokes, M.; Randall, B.; Steed, J.; Jones, R.; Hamilton, L.; Rogers, L.; Fiscus, J.; Dyches, G.

1998-05-01

The Plutonium Immobilization Facility will encapsulate plutonium in ceramic pucks and seal the pucks inside welded cans. Remote equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. This report discusses five can loading conceptual designs and the lists the advantages and disadvantages for each concept. This report identifies loading pucks into cans and backfilling cans with helium as the top priority can loading development areas. The can loading welder and cutter are very similar to the existing Savannah River Site (SRS) FB-Line bagless transfer welder and cutter and thus they are a low priority development item

LLNL Site plan for a MOX fuel lead assembly mission in support of surplus plutonium disposition

Energy Technology Data Exchange (ETDEWEB)

Bronson, M.C.

1997-10-01

The principal facilities that LLNL would use to support a MOX Fuel Lead Assembly Mission are Building 332 and Building 334. Both of these buildings are within the security boundary known as the LLNL Superblock. Building 332 is the LLNL Plutonium Facility. As an operational plutonium facility, it has all the infrastructure and support services required for plutonium operations. The LLNL Plutonium Facility routinely handles kilogram quantities of plutonium and uranium. Currently, the building is limited to a plutonium inventory of 700 kilograms and a uranium inventory of 300 kilograms. Process rooms (excluding the vaults) are limited to an inventory of 20 kilograms per room. Ongoing operations include: receiving SSTS, material receipt, storage, metal machining and casting, welding, metal-to-oxide conversion, purification, molten salt operations, chlorination, oxide calcination, cold pressing and sintering, vitrification, encapsulation, chemical analysis, metallography and microprobe analysis, waste material processing, material accountability measurements, packaging, and material shipping. Building 334 is the Hardened Engineering Test Building. This building supports environmental and radiation measurements on encapsulated plutonium and uranium components. Other existing facilities that would be used to support a MOX Fuel Lead Assembly Mission include Building 335 for hardware receiving and storage and TRU and LLW waste storage and shipping facilities, and Building 331 or Building 241 for storage of depleted uranium.

LLNL Site plan for a MOX fuel lead assembly mission in support of surplus plutonium disposition

International Nuclear Information System (INIS)

Bronson, M.C.

1997-01-01

The principal facilities that LLNL would use to support a MOX Fuel Lead Assembly Mission are Building 332 and Building 334. Both of these buildings are within the security boundary known as the LLNL Superblock. Building 332 is the LLNL Plutonium Facility. As an operational plutonium facility, it has all the infrastructure and support services required for plutonium operations. The LLNL Plutonium Facility routinely handles kilogram quantities of plutonium and uranium. Currently, the building is limited to a plutonium inventory of 700 kilograms and a uranium inventory of 300 kilograms. Process rooms (excluding the vaults) are limited to an inventory of 20 kilograms per room. Ongoing operations include: receiving SSTS, material receipt, storage, metal machining and casting, welding, metal-to-oxide conversion, purification, molten salt operations, chlorination, oxide calcination, cold pressing and sintering, vitrification, encapsulation, chemical analysis, metallography and microprobe analysis, waste material processing, material accountability measurements, packaging, and material shipping. Building 334 is the Hardened Engineering Test Building. This building supports environmental and radiation measurements on encapsulated plutonium and uranium components. Other existing facilities that would be used to support a MOX Fuel Lead Assembly Mission include Building 335 for hardware receiving and storage and TRU and LLW waste storage and shipping facilities, and Building 331 or Building 241 for storage of depleted uranium

Impact of receipt of coprocessed uranium/plutonium on advanced accountability concepts and fabrication facilities. Addendum 1 to application of advanced accountability concepts in mixed oxide fabrication

International Nuclear Information System (INIS)

Bastin, J.J.; Jump, M.J.; Lange, R.A.; Randall, C.C.

1977-11-01

The Phase I study of the application of advanced accountability methods (DYMAC) in a uranium/plutonium mixed oxide facility was extended to assess the effect of coprocessed UO 2 --PuO 2 feed on the observations made in the original Phase I effort and on the proposed Phase II program. The retention of plutonium mixed with uranium throughout the process was also considered. This addendum reports that coprocessed feed would have minimal effect on the DYMAC program, except in the areas of material specifications, starting material delivery schedule, and labor requirements. Each of these areas is addressed, as are the impact of coprocessed feed at a large fuel fabrication facility and the changes needed in the dirty scrap recovery process to maintain the lower plutonium levels which may be required by future nonproliferation philosophy. An amended schedule for Phase II is included

Smart unattended systems for plutonium safeguards

International Nuclear Information System (INIS)

Menlove, H.O.; Abhold, M.; Eccleston, G.; Puckett, J.M.

1996-01-01

During the past decade, IAEA inspectors, national inspectors, and facility operators have used neutron coincidence counters and gamma-ray isotopics measurements extensively to measure the plutonium content of various forms of nuclear materials in the fuel cycle. Large automated facilities for fabricating plutonium fuel present both difficulties and challenges for improved accounting of nuclear materials. The traditional methods of sample measurements, requiring the transfer of the sample from the production line to the assay measurement station, are not possible in automated facilities. A bilateral safeguards agreement between the US Department of Energy (DOE) and Power Reactor and Nuclear Fuel Development Corporation (PNC) in Japan was signed to develop and implement nondestructive assay (NDA) systems to provide continuous safeguards measurements for material accountancy in the robot-automated Plutonium Fuel Fabrication Facility (PFFF). The PFFF assay systems were required to operate in unattended mode with a size and fuel mass capability to match the robotics fuel manipulators. Unattended assay systems reduce the requirement for inspector''s oversight of measurement operations, reduce the inspector''s workload, and improve inspection efficiencies. In addition, unattended measurements become essential when facility constraints limit the access of inspectors to the operations area during material processing. Authentication techniques were incorporated into the NDA systems so that data obtained form unattended assays could be used by independent inspectors such as the IAEA. The standardized containers and robot-controlled fuel movements in automated facilities enable more accurate nondestructive assay (NDA) measurements than are possible in conventional nonautomated facilities. The NDA instrumentation can be custom designed and optimized for the particular measurement goal in the automated facility

Hazardous Waste Treatment Facility and skid-mounted treatment systems at Los Alamos

International Nuclear Information System (INIS)

Lussiez, G.W.; Zygmunt, S.J.

1994-01-01

To centralize treatment, storage, and areas for hazardous wastes, Los Alamos National Laboratory has designed a 1115 m2 hazardous waste treatment facility. The facility will house a treatment room for each of four kinds of wastes: nonradioactive characteristic wastes, nonradioactive listed wastes, radioactive characteristic wastes, and radioactive listed wastes. The facility will be used for repacking labpacks; bulking small organic waste volumes; processing scintillation vials; treating reactives such as lithium hydride and pyrophoric uranium; treating contaminated solids such as barium sand; treating plating wastes and other solutions with heavy metals and oxidizing organics: Separate treatment rooms will allow workers to avoid mixing waste types and prevent cross-contamination. The ventilation air from the treatment areas may contain hazardous or radioactive dust. Gas may also leak from process equipment. The gas treatment process includes separating solids and gases and neutralization or adsorption of the hazardous gases. The ventilation air from each room will first be filtered before being scrubbed in a common gas caustic scrubber on an outside pad. There are two levels of exhaust in each treatment room, one for heavy gases and another for light gases. Several features help mitigate or eliminate hazards due to spills and releases: each treatment room is sealed and under slight negative pressure; each room has its own HEPA filtration; to avoid mixing of incompatible wastes and reagents, portable individual spill-containment trays are used for skids, to limit the danger of spills, the waste is directly transferred from outside storage to the treatment room; to mitigate the consequences of a gas release in the room, mobile hoods are connected to the exhaust-air treatment system; the floor, walls, ceilings, fixtures, ducts, and piping are made of acid-resistant material or are coated

Inertial confinement fusion at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

Lindman, E.; Baker, D.; Barnes, C.; Bauer, B.; Beck, J.B.

1997-01-01

The Los Alamos National Laboratory is contributing to the resolution of key issues in the US Inertial-Confinement-Fusion Program and plans to play a strong role in the experimental program at the National Ignition Facility when it is completed

Evaluation of the seismic integrity of a plutonium-handling facility

International Nuclear Information System (INIS)

Coats, D.W.

1981-01-01

Many studies have been made by and for the Lawrence Livermore National Laboratory (LLNL) to ensure the seismic safety of its Plutonium Facility (Building 332). These studies have included seismological and geologic field investigations to define the actual seismic hazard existing at the Laboratory site as well as structural studies of the Facility itself. Because the basic seismic design criteria has undergone changes over the years, numerous structural studies and upgrades have been completed. The seismic criteria in use at the LLNL site is reviewed on a continuing basis as new information on the seismicity and geology of the Livermore Valley is obtained. At present, the Laboratory's Earth Sciences Division is conducting a multi-million dollar program to identify and characterize the geologic hazards at the Livermore site, with the primary emphasis on earthquake hazards in the Livermore Valley. This effort is undergoing an independent review by Woodward-Clyde Associates. Additionally, because of increased concerns over the seismic safety of Building 332, the Laboratory has initiated an independent structural review. This review effort will be monitored by the California Seismic Safety Commission to ensure its independence. Both of these studiies are in their early stages and results are not yet available

Collector for recovering gallium from weapons plutonium

International Nuclear Information System (INIS)

Philip, C.V.; Anthony, R.G.; Chokkaram, S.

1998-09-01

Currently, the separation of gallium from weapons plutonium involves the use of aqueous processing using either solvent extraction of ion exchange. However, this process generates significant quantities of liquid radioactive wastes. A Thermally Induced Gallium Removal process, or TIGR, developed by researchers at Los Alamos National Laboratories, is a simpler alternative to aqueous processing. This research examined this process, and the behavior of gallium suboxide, a vapor that is swept away by passing hydrogen/argon over gallium trioxide/plutonium oxide heated at 1100 C during the TIGR process. Through experimental procedures, efforts were made to prevent the deposition of corrosive gallium onto furnace and vent surfaces. Experimental procedures included three options for gallium removal and collection: (1) collection of gallium suboxide through use of a cold finger; (2) collection by in situ air oxidation; and (3) collection of gallium on copper. Results conclude all three collection mechanisms are feasible. In addition, gallium trioxide exists in three crystalline forms, and each form was encountered during each experiment, and that each form will have a different reactivity

Comments on a paper entitled: Toxicity and carcinogenicity of plutonium-239

International Nuclear Information System (INIS)

Stocum, W.E.; Pigg, C.J.

1978-06-01

Studies on carcinogenic effects of Pu-239 on animals have been reviewed often in the literature. A summary of these studies, which were done primarily with dogs or rats, shows that the inhalation of Pu-239 results in plutonium being retained in highest concentrations in bone, liver, lung, and lymph nodes. This may result in the induction of specific kinds of cancer, primarily lung and bone carcinomas, and to a lesser extent, bile duct tumors. These animal studies have been extremely useful in the analysis of the limited number of studies available on humans exposed to plutonium and in the prediction of plutonium cancer risk to man. One of the most significant and relevant studies on human exposures to Pu-239 is that of the 1944-45 exposure at Los Alamos Scientific Laboratory. Twenty-five men associated with the Manhattan Project were identified as having had significant plutonium exposures; total initial lung burden across the group was approximately 10 μCi. These individuals have been monitored clinically and in laboratory studies for the past 30 years. None of the individuals has shown cancer incidence and none shows medical findings attributable to internally deposited plutonium. There has been no recorded instance of cancer in man resulting from the internal deposition of any plutonium isotope in the more than three decades in which plutonium has been used. This excellent record illustrates the effectiveness of control measures and safety standards imposed on the handling of radioactive materials. These facts lead to a high level of confidence that the transportation of radioactive materials to and around the WIPP would not have a markedly different record

Nondestructive analysis of plutonium contaminated soil

International Nuclear Information System (INIS)

Smith, H.E.; Taylor, L.H.

1977-01-01

Plutonium contaminated soil is currently being removed from a covered liquid waste disposal trench near the Pu Processing facility on the Hanford Project. This soil with the plutonium is being mined using remote techniques and equipment. The mined soil is being packaged for placement into retrievable storage, pending possible recovery. To meet the requirements of criticality safety and materials accountability, a nondestructive analysis program has been developed to determine the quantity of plutonium in each packing-storage container. This paper describes the total measurement program: equipment systems, calibration techniques, matrix assumption, instrument control program and a review of laboratory operating experience

Safety analysis of the Los Alamos Critical Experiments Facility. Volume II

International Nuclear Information System (INIS)

Paxton, H.C.

1976-04-01

The Los Alamos critical assembly layout is designed to facilitate personnel protection by means of remote operation and stringent procedural controls during nonoperating periods. Public protection is straightforward because of the small fission-product inventory, essentially ambient pressures, and moderate temperatures

Best available technology for the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility

International Nuclear Information System (INIS)

Midkiff, W.S.; Romero, R.L.; Suazo, I.L.; Garcia, R.; Parsons, R.M.

1993-01-01

The existing Los Alamos National Laboratory TA-50 liquid radioactive waste treatment plant RLWP has been in service for over thirty years, during this period many technical, regulatory, and processing changes have occurred. The existing facility can no longer comply with the demands and requirements for continued operation, and would not be able to comply with anticipated stringent future contaminant discharge limitations. Either a major upgrading or replacement of the existing facility is required. In order to assess the most appropriate means of providing an adequate facility to comply with predicted requirements for Ta-50, this Best Available Technology (BAT) Study was conducted to compare feasible technical and economic alternatives in order to define the most favorable technology configuration. This report consists of eleven sections. Section 1 provides a general introduction and background of the TA-50 operations and the basis for this study. Section 2 provides a technical discussion of the unit processes at TA-50 and several other comparable operations at other DOE sites. Section 3 addresses the evaluation and selection of appropriate treatment processes. Section 4 provides an analysis of environmental issues and concerns. Section 5 presents the rationale for the selection of preferred process configurations. Section 6 is the evaluation of operational issues. Section 7 addresses energy and resource use topics. Section 8 provides an economic analysis, and Section 9 summarizes the evaluation and the identification of the BAT. These sections are augmented by appendices. The report identifies the construction of a new radioactive liquid waste treatment facility as the BAT. Based on the information analyzed for this study, this option appears to provide the best combination of environmental compliance, operability, and economic value

Plutonium production in a remote cell

International Nuclear Information System (INIS)

Maddux, E.P.; Purcell, J.A.

1987-01-01

Production of 239 Pu metal has traditionally been carried out in glovebox enclosures for protection of operating personnel and the environment. With the advent of more stringent federal regulations for protecting personnel, the environment, and security of special nuclear materials, it is proposed that plutonium be processed in a totally remote environment using automated work stations and robotic materials transfer and equipment maintenance. At the Savannah River Plant, the existing plutonium production facility is a batch-type glovebox operation built in the 1950s. A viable alternative to restoration of the existing glovebox operation is to provide a facility that uses remote cell operation

Regulatory issues for deep borehole plutonium disposition

International Nuclear Information System (INIS)

Halsey, W.G.

1995-03-01

As a result of recent changes throughout the world, a substantial inventory of excess separated plutonium is expected to result from dismantlement of US nuclear weapons. The safe and secure management and eventual disposition of this plutonium, and of a similar inventory in Russia, is a high priority. A variety of options (both interim and permanent) are under consideration to manage this material. The permanent solutions can be categorized into two broad groups: direct disposal and utilization. The deep borehole disposition concept involves placing excess plutonium deep into old stable rock formations with little free water present. Issues of concern include the regulatory, statutory and policy status of such a facility, the availability of sites with desirable characteristics and the technologies required for drilling deep holes, characterizing them, emplacing excess plutonium and sealing the holes. This white paper discusses the regulatory issues. Regulatory issues concerning construction, operation and decommissioning of the surface facility do not appear to be controversial, with existing regulations providing adequate coverage. It is in the areas of siting, licensing and long term environmental protection that current regulations may be inappropriate. This is because many current regulations are by intent or by default specific to waste forms, facilities or missions significantly different from deep borehole disposition of excess weapons usable fissile material. It is expected that custom regulations can be evolved in the context of this mission

A Long-Pulse Spallation Source at Los Alamos: Facility description and preliminary neutronic performance for cold neutrons

International Nuclear Information System (INIS)

Russell, G.J.; Weinacht, D.J.; Pitcher, E.J.; Ferguson, P.D.

1998-03-01

The Los Alamos National Laboratory has discussed installing a new 1-MW spallation neutron target station in an existing building at the end of its 800-MeV proton linear accelerator. Because the accelerator provides pulses of protons each about 1 msec in duration, the new source would be a Long Pulse Spallation Source (LPSS). The facility would employ vertical extraction of moderators and reflectors, and horizontal extraction of the spallation target. An LPSS uses coupled moderators rather than decoupled ones. There are potential gains of about a factor of 6 to 7 in the time-averaged neutron brightness for cold-neutron production from a coupled liquid H 2 moderator compared to a decoupled one. However, these gains come at the expense of putting ''tails'' on the neutron pulses. The particulars of the neutron pulses from a moderator (e.g., energy-dependent rise times, peak intensities, pulse widths, and decay constant(s) of the tails) are crucial parameters for designing instruments and estimating their performance at an LPSS. Tungsten is the reference target material. Inconel 718 is the reference target canister and proton beam window material, with Al-6061 being the choice for the liquid H 2 moderator canister and vacuum container. A 1-MW LPSS would have world-class neutronic performance. The authors describe the proposed Los Alamos LPSS facility, and show that, for cold neutrons, the calculated time-averaged neutronic performance of a liquid H 2 moderator at the 1-MW LPSS is equivalent to about 1/4th the calculated neutronic performance of the best liquid D 2 moderator at the Institute Laue-Langevin reactor. They show that the time-averaged moderator neutronic brightness increases as the size of the moderator gets smaller

Treatment of plutonium contaminated ashes by electrogenerated Ag(II): a new, simple and efficient process

International Nuclear Information System (INIS)

Madic, C.; Saulze, J.L.; Bourges, J.; Lecomte, M.; Koehly, G.

1990-01-01

Incineration is a very attractive technique for managing plutonium contaminated solid wastes, allowing for large volume and mass reduction factors. After waste incineration, the plutonium is concentrated in the ashes and an efficient method must be designed for its recovery. To achieve this goal, a process based on the dissolution of plutonium in nitric solution under the agressive action of electrogenerated Ag(II) was developed. This process is very simple, requiring very few steps. Plutonium recovery yields up to 98% can be obtained and, in addition, the plutonium bearing solutions generated by the treatment can be processed by the PUREX technique for plutonium recovery. This process constitutes the basis for the development of industrial facilities: 1) a pilot facility is being built in MARCOULE (COGEMA, UP1 plant), to treat active ash in 1990; 2) an industrial facility will be built in the MELOX plant under construction at MARCOULE (COGEMA plant)

Preliminary evaluation of the electrapette for possible use in the glovebox for pipetting plutonium solutions

Energy Technology Data Exchange (ETDEWEB)

Hansbury, E.; Ortiz, B.; Roybal, C.

1990-12-01

At the Los Alamos Laboratory Plutonium Facility, Solution Assay Instruments (SAIs) are used to provide real-time information on the plutonium (Pu) content of the process stream at various stages in the process. Much of the solution analysis must be carried and as a glovebox to protect the operator from radiation. In order to overcome some of the difficulties usually encountered when working in a glovebox, an electronic solution-volume measuring device called an Electrapette was ordered from Matrix Technologies Corporation. It is said to be highly accurate, simple to use, and can handle the 25 ml of solution required for SAI analyses. It is microprocessor-controlled and comes in two components connected by a detachable cable so that the electronic part can be installed outside the box, while the nosepiece is inside. The two pieces are connected through a plug-in on the glovebox wall. The Electrapette was tested in three sets of experiments: a cold'' lab set, a set run is a hood in a production building, and a third set run in a glovebox using a process solution whose density had been predetermined. The accuracy of the determination could not be determined because the samples had been mixed with other feed before being sent for analysis by the Electrapette. 2 refs., 5 tabs.

ZPR-9 airborne plutonium monitoring system

International Nuclear Information System (INIS)

Rusch, G.K.; McDowell, W.P.; Knapp, W.G.

1975-01-01

An airborne plutonium monitoring system which is installed in the ZPR-9 (Zero Power Reactor No. 9) facility at Argonne National Laboratory is described. The design and operational experience are discussed. This monitoring system utilizes particle size and density discrimination, alpha particle energy discrimination, and a background-subtraction techique operating in cascade to separate airborne-plutonium activity from other, naturally occurring, airborne activity. Relatively high sensitivity and reliability are achieved

Neutron Scattering Activity at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Bourke, M.A.M.

2015-01-01

The nondestructive and bulk penetrating aspects of neutron scattering techniques make them well suited to the study of materials from the nuclear energy sector (particularly those which are radioactive). This report provides a summary of the facility, LANSCE, which is used at Los Alamos National laboratory for these studies. It also provides a brief description of activities related to line broadening studies of radiation damage and recent imaging and offers observations about the outlook for future activity. The work alluded to below was performed during the period of the CRP by researchers that included but were not limited to; Sven Vogel and Don Brown of Los Alamos National Laboratory; and Anton Tremsin of the University of California, Berkeley. (author)

Plutonium fires; Incendies de plutonium

Energy Technology Data Exchange (ETDEWEB)

Mestre, E.

1959-06-23

The author reports an information survey on accidents which occurred when handling plutonium. He first addresses accidents reported in documents. He indicates the circumstances and consequences of these accidents (explosion in glove boxes, fires of plutonium chips, plutonium fire followed by filter destruction, explosion during plutonium chip dissolution followed by chip fire). He describes hazards associated with plutonium fires: atmosphere and surface contamination, criticality. The author gives some advices to avoid plutonium fires. These advices concern electric installations, the use of flammable solvents, general cautions associated with plutonium handling, venting and filtration. He finally describes how to fight plutonium fires, and measures to be taken after the fire (staff contamination control, atmosphere control)

Low-level radioactive waste disposal operations at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Stanford, A.R.

1997-01-01

Los Alamos National Laboratory (LANL) generates Low-Level Radioactive Waste (LLW) from various activities: research and development, sampling and storage of TRU wastes, decommissioning and decontamination of facilities, and from LANL's major role in stockpile stewardship. The Laboratory has its own active LLW disposal facility located at Technical Area 54, Area G. This paper will identify the current operations of the facility and the issues pertaining to operating a disposal facility in today's compliance and cost-effective environment

Plutonium immobilization program - Cold pour Phase 1 test results

International Nuclear Information System (INIS)

Hamilton, L.

2000-01-01

The Plutonium Immobilization Project will disposition excess weapons grade plutonium. It uses the can-in-canister approach that involves placing plutonium-ceramic pucks in sealed cans that are then placed into Defense Waste Processing Facility canisters. These canisters are subsequently filled with high-level radioactive waste glass. This process puts the plutonium in a stable form and makes it unattractive for reuse. A cold (non-radioactive) glass pour program was performed to develop and verify the baseline design for the canister and internal hardware. This paper describes the Phase 1 scoping test results

Plutonium Immobilization Program - Cold pour Phase 1 test results

International Nuclear Information System (INIS)

Hamilton, L.

2000-01-01

The Plutonium Immobilization Project will disposition excess weapons grade plutonium. It uses the can-in-canister approach that involves placing plutonium-ceramic pucks in sealed cans that are then placed into Defense Waste Processing Facility canisters. These canisters are subsequently filled with high-level radioactive waste glass. This process puts the plutonium in a stable form and makes it unattractive for reuse. A cold (non-radioactive) glass pour program was performed to develop and verify the baseline design for the canister and internal hardware. This paper describes the Phase 1 scoping test results

Stop plutonium; Stop plutonium

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-02-01

This press document aims to inform the public on the hazards bound to the plutonium exploitation in France and especially the plutonium transport. The first part is a technical presentation of the plutonium and the MOX (Mixed Oxide Fuel). The second part presents the installation of the plutonium industry in France. The third part is devoted to the plutonium convoys safety. The highlight is done on the problem of the leak of ''secret'' of such transports. (A.L.B.)

Preliminary volcanic hazards evaluation for Los Alamos National Laboratory Facilities and Operations : current state of knowledge and proposed path forward

Energy Technology Data Exchange (ETDEWEB)

Keating, Gordon N.; Schultz-Fellenz, Emily S.; Miller, Elizabeth D.

2010-09-01

The integration of available information on the volcanic history of the region surrounding Los Alamos National Laboratory indicates that the Laboratory is at risk from volcanic hazards. Volcanism in the vicinity of the Laboratory is unlikely within the lifetime of the facility (ca. 50–100 years) but cannot be ruled out. This evaluation provides a preliminary estimate of recurrence rates for volcanic activity. If further assessment of the hazard is deemed beneficial to reduce risk uncertainty, the next step would be to convene a formal probabilistic volcanic hazards assessment.

Fundamental symmetry studies at Los Alamos using epithermal neutrons

International Nuclear Information System (INIS)

Bowman, C.D.; Bowman, J.D.; Yuan, V.W.

1988-01-01

Fundamental symmetry studies using intense polarized beams of epithermal neutrons are underway at the LANSCE facility of the Los Alamos National Laboratory. Three classes of symmetry experiments can be explored: parity violation, and time reversal invariance violation for both parity-violating and parity-conserved observables. The experimental apparatus is described and performance illustrated with examples of recent measurements. Possible improvements in the facilities and prospective experiments are discussed. 15 refs., 10 figs

Final characterization report for the non-process areas of the 233-S Plutonium Concentration Facility

International Nuclear Information System (INIS)

Encke, D.B.; Harris, R.A.

1997-04-01

This report addresses the 233-S Plutonium Concentration Facility characterization survey data collected from January 21, 1997 through February 3, 1997. The characterization activities evaluated the radiological status and identified the hazardous materials locations. The scope of this report is limited to the nonprocess areas in the facility, which include the special work permit (SWP) change room, toilet, equipment room, electrical cubicle, control room, and pipe gallery. A portion of the roof (excluding the roof over the process hood and viewing room) was also included. Information in this report will be used to identify waste streams, provide specific chemical and radiological data to aid in planning decontamination and demolition activities, and allow proper disposal of the demolition debris, as required by the Comprehensive Environmental Response, Compensation, and Liability Act of 1980

Smart unattended systems for plutonium safeguards

International Nuclear Information System (INIS)

Menlove, H.O.; Abhold, M.; Eccleston, G.; Puckett, J.M.

1996-01-01

Large automated facilities for fabricating plutonium fuel present both difficulties and challenges for improved accounting of nuclear materials. The traditional methods of sample measurements, requiring the transfer of the sample from the production line to the assay measurement station, are not possible in automated facilities. The robotics used for automation require special containers for nuclear material that cannot be easily removed from the production line. Safety and radiation protection considerations also require that the assay instrumentation be installed in the fuel production lines because, in general, personnel cannot be in the fuel-handling area with nuclear material during operations. Such operational constraints are common in many of the modern facilities that have been designed for fabricating and processing plutonium fuel. A bilateral safeguards agreement between the US Department of Energy (DOE) and Power Reactor and Nuclear Fuel Development Corporation (PNC) in Japan was signed to develop and implement nondestructive assay (NDA) systems to provide continuous safeguards measurements for material accountancy in the robot-automated Plutonium Fuel Fabrication Facility (PFFF). The PFFF assay systems were required to operate in unattended mode with a size and fuel mass capability to match the robotics fuel manipulators. Unattended assay systems reduce the requirement for inspector's oversight of measurement operations, reduce the inspector's workload, and improve inspection efficiencies. In addition, unattended measurements become essential when facility constraints limit the access of inspectors to the operations area during material processing. Authentication techniques were incorporated into the NDA systems so that data obtained from unattended assays could be used by independent inspectors such as the IAEA

Benchmark assemblies of the Los Alamos critical assemblies facility

International Nuclear Information System (INIS)

Dowdy, E.J.

1986-01-01

Several critical assemblies of precisely known materials composition and easily calculated and reproducible geometries have been constructed at the Los Alamos National Laboratory. Some of these machines, notably Jezebel, Flattop, Big Ten, and Godiva, have been used as benchmark assemblies for the comparison of the results of experimental measurements and computation of certain nuclear reaction parameters. These experiments are used to validate both the input nuclear data and the computational methods. The machines and the applications of these machines for integral nuclear data checks are described. (author)

Benchmark assemblies of the Los Alamos Critical Assemblies Facility

International Nuclear Information System (INIS)

Dowdy, E.J.

1985-01-01

Several critical assemblies of precisely known materials composition and easily calculated and reproducible geometries have been constructed at the Los Alamos National Laboratory. Some of these machines, notably Jezebel, Flattop, Big Ten, and Godiva, have been used as benchmark assemblies for the comparison of the results of experimental measurements and computation of certain nuclear reaction parameters. These experiments are used to validate both the input nuclear data and the computational methods. The machines and the applications of these machines for integral nuclear data checks are described

Benchmark assemblies of the Los Alamos critical assemblies facility

International Nuclear Information System (INIS)

Dowdy, E.J.

1985-01-01

Several critical assemblies of precisely known materials composition and easily calculated and reproducible geometries have been constructed at the Los Alamos National Laboratory. Some of these machines, notably Jezebel, Flattop, Big Ten, and Godiva, have been used as benchmark assemblies for the comparison of the results of experimental measurements and computation of certain nuclear reaction parameters. These experiments are used to validate both the input nuclear data and the computational methods. The machines and the applications of these machines for integral nuclear data checks are described

High-Precision Plutonium Isotopic Compositions Measured on Los Alamos National Laboratory’s General’s Tanks Samples: Bearing on Model Ages, Reactor Modelling, and Sources of Material. Further Discussion of Chronometry

Energy Technology Data Exchange (ETDEWEB)

Spencer, Khalil J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rim, Jung Ho [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Porterfield, Donivan R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Roback, Robert Clifford [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Boukhalfa, Hakim [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stanley, Floyd E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-06-29

In this study, we re-analyzed late-1940’s, Manhattan Project era Plutonium-rich sludge samples recovered from the ''General’s Tanks'' located within the nation’s oldest Plutonium processing facility, Technical Area 21. These samples were initially characterized by lower accuracy, and lower precision mass spectrometric techniques. We report here information that was previously not discernable: the two tanks contain isotopically distinct Pu not only for the major (i.e., ²⁴⁰Pu, ²³⁹Pu) but trace (²³⁸Pu ,²⁴¹Pu, ²⁴²Pu) isotopes. Revised isotopics slightly changed the calculated ²⁴¹Am-²⁴¹Pu model ages and interpretations.

The Los Alamos accelerator-driven transmutation of nuclear waste (ATW) concept development of the ATW target/blanket system

International Nuclear Information System (INIS)

Venneri, F.; Williamson, M.A.; Ning, L.

1997-01-01

In the past several years, the Los Alamos ADTT program has conducted studies of an innovative technology for solving the nuclear waste problem and building a new generation of safer and non-proliferant nuclear power plants. The ATW concept destroys higher actinides, plutonium and selected fission products in a liquid-fuel subcritical assembly. In this paper special attention is given to the basic design of the ATW Molten Salt concept and the safety perspective. 40 refs., 11 figs

Plutonium inventories for stabilization and stabilized materials

Energy Technology Data Exchange (ETDEWEB)

Williams, A.K.

1996-05-01

The objective of the breakout session was to identify characteristics of materials containing plutonium, the need to stabilize these materials for storage, and plans to accomplish the stabilization activities. All current stabilization activities are driven by the Defense Nuclear Facilities Safety Board Recommendation 94-1 (May 26, 1994) and by the recently completed Plutonium ES&H Vulnerability Assessment (DOE-EH-0415). The Implementation Plan for accomplishing stabilization of plutonium-bearing residues in response to the Recommendation and the Assessment was published by DOE on February 28, 1995. This Implementation Plan (IP) commits to stabilizing problem materials within 3 years, and stabilizing all other materials within 8 years. The IP identifies approximately 20 metric tons of plutonium requiring stabilization and/or repackaging. A further breakdown shows this material to consist of 8.5 metric tons of plutonium metal and alloys, 5.5 metric tons of plutonium as oxide, and 6 metric tons of plutonium as residues. Stabilization of the metal and oxide categories containing greater than 50 weight percent plutonium is covered by DOE Standard {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides{close_quotes} December, 1994 (DOE-STD-3013-94). This standard establishes criteria for safe storage of stabilized plutonium metals and oxides for up to 50 years. Each of the DOE sites and contractors with large plutonium inventories has either started or is preparing to start stabilization activities to meet these criteria.

Proton Radiography at Los Alamos

Energy Technology Data Exchange (ETDEWEB)

Saunders, Alexander [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-28

The proton radiography (pRad) facility at Los Alamos National Lab uses high energy protons to acquire multiple frame flash radiographic sequences at megahertz speeds: that is, it can make movies of the inside of explosions as they happen. The facility is primarily used to study the damage to and failure of metals subjected to the shock forces of high explosives as well as to study the detonation of the explosives themselves. Applications include improving our understanding of the underlying physical processes that drive the performance of the nuclear weapons in the United States stockpile and developing novel armor technologies in collaboration with the Army Research Lab. The principle and techniques of pRad will be described, and examples of some recent results will be shown.

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

Energy Technology Data Exchange (ETDEWEB)

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

1996-01-15

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.

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

International Nuclear Information System (INIS)

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

1996-01-01

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

Compositions of airborne plutonium-bearing particles from a plutonium finishing operation

International Nuclear Information System (INIS)

Sanders, S.M. Jr.

1976-11-01

The elemental composition of 111 plutonium-bearing particles was determined (using an electron microprobe) as part of a program to investigate the origin and behavior of the long-lived transuranic radionuclides released from fuel reprocessing facilities at the Savannah River Plant. These particles, collected from wet-cabinet and room-air exhausts from the plutonium finishing operation (JB-Line), were between 0.4 and 36 μm in diameter. Ninety-nine of the particles were found to be aggregates of various minerals and metals, six were quartz, and six were small (less than 2-μm-diameter) pieces of iron oxide. Collectively, these particles contained less minerals and more metals than natural dusts contain. The metallic constituents included elements normally not found in dusts, e.g., chromium, nickel, copper, and zinc. Concentrations of aluminum and iron exceeded those normally found in minerals. Elemental concentrations in individual particles covered a wide range: one 2-μm-diameter particle contained 97 percent NiO, a 9-μm-diameter particle contained 72 percent Cr 2 O 3 . Although the particles were selected because they produced plutonium fission tracks, the plutonium concentration was too low to be estimated by microprobe analysis in all but a 1-μm-diameter particle. This plutonium-bearing particle contained 73 percent PuO 2 by weight in combination with Fe 2 O 3 and mica; its activity was estimated at 0.17 pCi of 239 Pu

Remote handling in the Plutonium Immobilization Project: Puck handling

International Nuclear Information System (INIS)

Brault, J.R.

2000-01-01

Since the break up of the Soviet Union at the end of the Cold War, the US and Russia have been negotiating ways to reduce their nuclear stockpiles. Economics is one of the reasons behind this, but another important reason is safeguarding these materials from unstable organizations and countries. With the downsizing of the nuclear stockpiles, large quantities of plutonium are being declared excess and must be safely disposed of. The Savannah River Site (SRS) has been selected as the site where the immobilization facility will be located. Conceptual design and process development commenced in 1998. SRS will immobilize excess plutonium in a ceramic waste form and encapsulate it in vitrified high level waste in the Defense Waste Processing Facility (DWPF) canister. These canisters will then be interred in the national repository at Yucca Mountain, New Mexico. The facility is divided into three distinct operating areas: Plutonium Conversion, First Stage Immobilization, and Second Stage Immobilization. This paper will discuss the first two operations

Summary of the last step of active test at separation facility and purification facility in Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Kuroishi, Yuuki; Iseki, Tadahiro; Mitani, Akira; Takahashi, Naoki; Tsujimura, Akino; Sato, Nobuharu; Inaba, Makoto; Itagaki, Takashi

2008-01-01

During the last step of Active Test (AT) at Rokkasho Reprocessing Plant (RRP), the performance of the Separation Facility, mainly for pulsed columns and mixer-settlers were tested; Diluent washing efficiency, Plutonium extraction and stripping efficiency, Decontamination factors of fission products and Uranium and plutonium losses into wastes. Also, those of the Plutonium purification unit in the Purification Facility have been checked; Diluent washing efficiency, Plutonium extraction and stripping efficiency and Plutonium losses into wastes. Test results were equivalent to or better than expected values. (author)

Plutonium in depleted uranium penetrators

International Nuclear Information System (INIS)

McLaughlin, J.P.; Leon-Vintro, L.; Smith, K.; Mitchell, P.I.; Zunic, Z.S.

2002-01-01

Depleted Uranium (DU) penetrators used in the recent Balkan conflicts have been found to be contaminated with trace amounts of transuranic materials such as plutonium. This contamination is usually a consequence of DU fabrication being carried out in facilities also using uranium recycled from spent military and civilian nuclear reactor fuel. Specific activities of 239+240 Plutonium generally in the range 1 to 12 Bq/kg have been found to be present in DU penetrators recovered from the attack sites of the 1999 NATO bombardment of Kosovo. A DU penetrator recovered from a May 1999 attack site at Bratoselce in southern Serbia and analysed by University College Dublin was found to contain 43.7 +/- 1.9 Bq/kg of 239+240 Plutonium. This analysis is described. An account is also given of the general population radiation dose implications arising from both the DU itself and from the presence of plutonium in the penetrators. According to current dosimetric models, in all scenarios considered likely ,the dose from the plutonium is estimated to be much smaller than that due to the uranium isotopes present in the penetrators. (author)

Penetrating radiation: applications at Los Alamos National Laboratory

Science.gov (United States)

Watson, Scott; Hunter, James; Morris, Christopher

2013-09-01

Los Alamos has used penetrating radiography extensively throughout its history dating back to the Manhattan Project where imaging dense, imploding objects was the subject of intense interest. This interest continues today as major facilities like DARHT1 have become the mainstay of the US Stockpile Stewardship Program2 and the cornerstone of nuclear weapons certification. Meanwhile, emerging threats to national security from cargo containers and improvised explosive devices (IEDs) have invigorated inspection efforts using muon tomography, and compact x-ray radiography. Additionally, unusual environmental threats, like those from underwater oil spills and nuclear power plant accidents, have caused renewed interest in fielding radiography in severe operating conditions. We review the history of penetrating radiography at Los Alamos and survey technologies as presently applied to these important problems.

Applicability of molten salt oxidation to the destruction of actinide-contaminated wastes

International Nuclear Information System (INIS)

West, M.H.; Garcia, E.; Griego, W.J.; Court, D.B.; Rodriguez, L.

1992-01-01

A 1989 ban on incineration in the state of New Mexico caused cessation of actinide-contaminated cheesecloth, paper, and wood incineration within the Plutonium Facility (TA-55) at Los Alamos National Laboratory. Subsequently, plastic wipes were substituted for cheesecloth in the cleaning of glovebox interiors. However, waste minimization is not achieved by these measures since the wipes are discarded as Waste Isolation Pilot Plant certifiable wastes. After the ban was instituted, thermal decomposition of cheesecloth under argon at elevated temperature was examined and found satisfactory although scale of operation and speed were inferior to incineration. In 1991, the ban on incineration was lifted in New Mexico but Alamos has not chosen to pursue renewal of incineration at the Plutonium Facility. This paper reports that Los Alamos is looking from alternatives to incineration and thermal decomposition which are compatible with molten salt processing technology, historically a strength in actinide research at the Laboratory. Also, the technology must significantly reduce the volume of the waste upon treatment, i.e. waste minimization. Molten salt oxidation (MSO) has the promise of such a technology

The future of plutonium - an overview

International Nuclear Information System (INIS)

Larson, C.E.

1975-01-01

Plutonium is the underpinning of the nuclear industry. Without it it is estimated that the fuel will run out not long after the turn of the century. With plutonium in fast breeders nuclear reactors can be operated for tens of thousands of years and the depleted uranium now available can be utilized The fuel cycle contemplated is similar to that of the light water reactor with some important differences at least partially related to the greater radioactivity of the resulting mixture of plutonium isotopes. The regulatory program does recognize the problems, including those of toxicity, safeguards and transportation. The concept of an integrated fuel cycle facility at a single location must be seriously considered. (author)

Validation of KENO, ANISN and Hansen-Roach cross-section set on plutonium oxide and metal fuel system

International Nuclear Information System (INIS)

Matsumoto, Tadakuni; Yumoto, Ryozo; Nakano, Koh.

1980-01-01

In the previous report, the authors discussed the validity of KENO, ANISN and Hansen-Roach 16 group cross-section set on the critical plutonium nitrate solution systems with various geometries, absorbers and neutron interactions. The purpose of the present report is to examine the validity of the same calculation systems on the homogeneous plutonium oxide and plutonium-uranium mixed oxide fuels with various density values. Eleven experiments adopted for validation are summarized. First six experiments were performed at Pacific Northwest Laboratory of Battelle Memorial Institute, and the remaining five at Los Alamos Scientific Laboratory. The characteristics of core fuel are given, and the isotopic composition of plutonium, the relation between H/(Pu + U) atomic ratio and fuel density as compared with the atomic ratios of PuO 2 and mixed oxides in powder storage and pellet fabrication processes, and critical core dimensions and reflector conditions are shown. The effective multiplication factors were calculated with the KENO code. In case of the metal fuels with simple sphere geometry, additional calculations with the ANISN code were performed. The criticality calculation system composed of KENO, ANISN and Hansen-Roach cross-section set was found to be valid for calculating the criticality on plutonium oxide, plutonium-uranium mixed oxide, plutonium metal and uranium metal fuel systems as well as on plutonium solution systems with various geometries, absorbers and neutron interactions. There seems to remain some problems in the method for evaluating experimental correction. Some discussions foloow. (Wakatsuki, Y.)

Shielding calculational system for plutonium

International Nuclear Information System (INIS)

Zimmerman, M.G.; Thomsen, D.H.

1975-08-01

A computer calculational system has been developed and assembled specifically for calculating dose rates in AEC plutonium fabrication facilities. The system consists of two computer codes and all nuclear data necessary for calculation of neutron and gamma dose rates from plutonium. The codes include the multigroup version of the Battelle Monte Carlo code for solution of general neutron and gamma shielding problems and the PUSHLD code for solution of shielding problems where low energy gamma and x-rays are important. The nuclear data consists of built in neutron and gamma yields and spectra for various plutonium compounds, an automatic calculation of age effects and all cross-sections commonly used. Experimental correlations have been performed to verify portions of the calculational system. (23 tables, 7 figs, 16 refs) (U.S.)

Capabilities required to conduct the LLNL plutonium mission

International Nuclear Information System (INIS)

Kass, J.; Bish, W.; Copeland, A.; West, J.; Sack, S.; Myers, B.

1991-01-01

This report outlines the LLNL plutonium related mission anticipated over the next decade and defines the capabilities required to meet that mission wherever the Plutonium Facility is located. If plutonium work is relocated to a place where the facility is shared, then some capabilities can be commonly used by the sharing parties. However, it is essential that LLNL independently control about 20000 sq ft of net lab space, filled with LLNL controlled equipment, and staffed by LLNL employees. It is estimated that the cost to construct this facility should range from $140M to $200M. Purchase and installation of equipment to replace that already in Bldg 332 along with additional equipment identified as being needed to meet the mission for the next ten to fifteen years, is estimated to cost $118M. About $29M of the equipment could be shared. The Hardened Engineering Test Building (HETB) with its additional 8000 sq ft of unique test capability must also be replaced. The fully equipped replacement cost is estimated to be about $10M. About 40000 sq ft of setup and support space are needed along with office and related facilities for a 130 person resident staff. The setup space is estimated to cost $8M. The annual cost of a 130 person resident staff (100 programmatic and 30 facility operation) is estimated to be $20M

Long-term plutonium storage: Design concepts

International Nuclear Information System (INIS)

Wilkey, D.D.; Wood, W.T.; Guenther, C.D.

1994-01-01

An important part of the Department of Energy (DOE) Weapons Complex Reconfiguration (WCR) Program is the development of facilities for long-term storage of plutonium. The WCR design goals are to provide storage for metals, oxides, pits, and fuel-grade plutonium, including material being held as part of the Strategic Reserve and excess material. Major activities associated with plutonium storage are sorting the plutonium inventory, material handling and storage support, shipping and receiving, and surveillance of material in storage for both safety evaluations and safeguards and security. A variety of methods for plutonium storage have been used, both within the DOE weapons complex and by external organizations. This paper discusses the advantages and disadvantages of proposed storage concepts based upon functional criteria. The concepts discussed include floor wells, vertical and horizontal sleeves, warehouse storage on vertical racks, and modular storage units. Issues/factors considered in determining a preferred design include operational efficiency, maintenance and repair, environmental impact, radiation and criticality safety, safeguards and security, heat removal, waste minimization, international inspection requirements, and construction and operational costs

Upgrades and Enclosure of Building 15 at Technical Area 40: Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Plimpton, Kathryn D [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Garcia, Kari L. M [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brunette, Jeremy Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McGehee, Ellen D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-09-15

The U.S. Department of Energy, National Nuclear Security Administration, Los Alamos Field Office (Field Office) proposes to upgrade and enclose Building 15 at Technical Area (TA) 40, Los Alamos National Laboratory. Building TA-40-15, a Cold War-era firing site, was determined eligible for listing in the National Register of Historic Places (Register) in DX Division’s Facility Strategic Plan: Consolidation and Revitalization at Technical Areas 6, 8, 9, 14, 15, 22, 36, 39, 40, 60, and 69 (McGehee et al. 2005). Building TA-40-15 was constructed in 1950 to support detonator testing. The firing site will be enclosed by a steel building to create a new indoor facility that will allow for year-round mission capability. Enclosing TA-40-15 will adversely affect the building by altering the characteristics that make it eligible for the Register. In compliance with Section 106 of the National Historic Preservation Act of 1966, as amended, the Field Office is initiating consultation for this proposed undertaking. The Field Office is also requesting concurrence with the use of standard practices to resolve adverse effects as defined in the Programmatic Agreement among the U.S. Department of Energy, National Nuclear Security Administration, Los Alamos Field Office, the New Mexico State Historic Preservation Office and the Advisory Council on Historic Preservation Concerning Management of the Historic Properties at Los Alamos National Laboratory, Los Alamos, New Mexico.

International plutonium policy

International Nuclear Information System (INIS)

1978-12-01

The need to distinguish between diversion by sub-national groups and by governments is clearly stated. The paper identifies the international safeguards measures which already exist for the handling of plutonium. It proposes that the implementation of Article XII A5 of the IAEA statute concerning the international storage of plutonium could be an important additional measure. The paper also mentions the concept of using confinement as a complimentary safeguards measure and identifies the PIPEX concept. In addition, greater use is proposed of containment and surveillance procedures. The multiplication of small reprocessing plants spread over many countries is perceived as a proliferation risk. Other means such as co-location of reprocessing and fuel fabrication facilities are relevant to diversion by sub-national groups

The Plutonium Temperature Effect Experimental Program

Energy Technology Data Exchange (ETDEWEB)

Haeck, Wim; Leclaire, Nicolas; Letang, Eric [IRSN, Fontenay-aux-Roses (France); Girault, Emmanuel; Fouillaud, Patrick [CEA, VALDUC (France)

2008-07-01

Various theoretical studies have shown that highly diluted plutonium solutions could have a positive temperature effect but (up to now) no experimental program has confirmed this effect. The main goal of the French Plutonium Temperature Effect Experimental Program (or PU+ in short) is to effectively show that such a positive temperature effect exists for diluted plutonium solutions. The experiments were conducted in the 'Apparatus B' facility at the CEA Valduc research centre in France and involved several sub-critical approach type of experiments using plutonium nitrate solutions with concentrations of 14.3, 15 and 20 g/l at temperatures ranging from 20 to 40 deg. C. A total number of 14 phase I experiments (consisting of independent subcritical approaches) have been performed (5 at 20 g/l, 4 at 15 g/l and 5 at 14.3 g/l) between 2006 and 2007. The impact of the uncertainties on the solution acidity and the plutonium concentration makes it difficult to clearly demonstrate the positive temperature effect, requiring an additional phase II experiment (in which the use of the same plutonium solution was ensured) from 22 to 28 deg. C performed in July 2007. This experiment has shown the existence of a positive temperature effect approx +2 pcm/deg. C (from 22 to 28 deg. C for a plutonium concentration of 14.3 g/l). (authors)

Appraisal of BWR plutonium burners for energy centers

International Nuclear Information System (INIS)

Williamson, H.E.

1976-01-01

The design of BWR cores with plutonium loadings beyond the self-generation recycle (SGR) level is investigated with regard to their possible role as plutonium burners in a nuclear energy center. Alternative plutonium burner approaches are also examined including the substitution of thorium for uranium as fertile material in the BWR and the use of a high-temperature gas reactor (HTGR) as a plutonium burner. Effects on core design, fuel cycle facility requirements, economics, and actinide residues are considered. Differences in net fissile material consumption among the various plutonium-burning systems examined were small in comparison to uncertainties in HTGR, thorium cycle, and high plutonium-loaded LWR technology. Variation in the actinide content of high-level wastes is not likely to be a significant factor in determining the feasibility of alternate systems of plutonium utilization. It was found that after 10,000 years the toxicity of actinide high-level wastes from the plutonium-burning fuel cycles was less than would have existed if the processed natural ores had not been used for nuclear fuel. The implications of plutonium burning and possible future fuel cycle options on uranium resource conservation are examined in the framework of current ERDA estimates of minable uranium resources

Performance assessment of refractory samples in the Los Alamos Controlled Air Incinerator

International Nuclear Information System (INIS)

Hutchins, D.A.; Borduin, L.C.; Koenig, R.A.; Vavruska, J.S.; Warner, C.L.

1986-01-01

A refractory evaluation project was initiated in 1979 to study the performance of six selected refractory materials within the Los Alamos Controlled Air Incinerator (CAI). Determining refractory resistance to thermal shock, chemical attack, and plutonium uptake was of particular interest. The experimental refractories were subjected to a variety of waste materials, including transuranic (TRU) contaminated wastes, highly chlorinated compounds and alkaline metal salts of perchlorate, chlorate, nitrate and oxylate, over the six year period of this study. Results of this study to date indicate that the use of high alumina, and possibly specialty plastic refractories, is advisable for the lining of incinerators used for the thermal destruction of diverse chemical compounds. 12 refs., 4 tabs

Repository and deep borehole disposition of plutonium

International Nuclear Information System (INIS)

Halsey, W.G.

1996-02-01

Control and disposition of excess weapons plutonium is a growing issue as both the US and Russia retire a large number of nuclear weapons> A variety of options are under consideration to ultimately dispose of this material. Permanent disposition includes tow broad categories: direct Pu disposal where the material is considered waste and disposed of, and Pu utilization, where the potential energy content of the material is exploited via fissioning. The primary alternative to a high-level radioactive waste repository for the ultimate disposal of plutonium is development of a custom geologic facility. A variety of geologic facility types have been considered, but the concept currently being assessed is the deep borehole

Treatment of plutonium process residues by molten salt oxidation

Energy Technology Data Exchange (ETDEWEB)

Stimmel, J.; Wishau, R.; Ramsey, K.B.; Montoya, A.; Brock, J. [Los Alamos National Lab., NM (United States); Heslop, M. [Naval Surface Warfare Center (United States). Indian Head Div.; Wernly, K. [Molten Salt Oxidation Corp. (United States)

1999-04-01

Molten Salt Oxidation (MSO) is a thermal process that can remove more than 99.999% of the organic matrix from combustible {sup 238}Pu material. Plutonium processing residues are injected into a molten salt bed with an excess of air. The salt (sodium carbonate) functions as a catalyst for the conversion of the organic material to carbon dioxide and water. Reactive species such as fluorine, chlorine, bromine, iodine, sulfur, phosphorous and arsenic in the organic waste react with the molten salt to form the corresponding neutralized salts, NaF, NaCl, NaBr, NaI, Na{sub 2}SO{sub 4}, Na{sub 3}PO{sub 4} and NaAsO{sub 2} or Na{sub 3}AsO4. Plutonium and other metals react with the molten salt and air to form metal salts or oxides. Saturated salt will be recycled and aqueous chemical separation will be used to recover the {sup 238}Pu. The Los Alamos National Laboratory system, which is currently in the conceptual design stage, will be scaled down from current systems for use inside a glovebox.

Treatment of plutonium process residues by molten salt oxidation

International Nuclear Information System (INIS)

Stimmel, J.; Wishau, R.; Ramsey, K.B.; Montoya, A.; Brock, J.; Heslop, M.

1999-01-01

Molten Salt Oxidation (MSO) is a thermal process that can remove more than 99.999% of the organic matrix from combustible 238 Pu material. Plutonium processing residues are injected into a molten salt bed with an excess of air. The salt (sodium carbonate) functions as a catalyst for the conversion of the organic material to carbon dioxide and water. Reactive species such as fluorine, chlorine, bromine, iodine, sulfur, phosphorous and arsenic in the organic waste react with the molten salt to form the corresponding neutralized salts, NaF, NaCl, NaBr, NaI, Na 2 SO 4 , Na 3 PO 4 and NaAsO 2 or Na 3 AsO4. Plutonium and other metals react with the molten salt and air to form metal salts or oxides. Saturated salt will be recycled and aqueous chemical separation will be used to recover the 238 Pu. The Los Alamos National Laboratory system, which is currently in the conceptual design stage, will be scaled down from current systems for use inside a glovebox

Mercury: The Los Alamos ICF KrF laser system

International Nuclear Information System (INIS)

Czuchlewski, S.J.; York, G.W.; Bigio, I.J.; Brucker, J.; Hanson, D.; Honig, E.M.; Kurnit, N.; Leland, W.; McCown, A.W.; McLeod, J.; Rose, E.; Thomas, S.; Thompson, D.

1993-01-01

The Mercury KrF laser facility at Los Alamos is being built with the benefit of lessons learned from the Aurora system. An increased understanding of KrF laser engineering, and the designed implementation of system flexibility, will permit Mercury to serve as a tested for a variety of advanced KrF technology concepts

Enhancement of the basic seismic assessment of the Los Alamos National Laboratory facilities and buildings

International Nuclear Information System (INIS)

Fritz-de la Orta, G.O.

1995-01-01

This paper presents the results of a comparison of values obtained for the seismic security of 479 buildings and facilities at Los Alamos National Laboratory following the methodology adapted from Dr. Otto Frit's original System, and the requirements contained both in FEMA-154 ''Rapid Visual Screening of Buildings for Potential Hazards: A Handbook'' and FEMA-187 ''NEHRP Handbook for the Seismic Evaluation of Existing Buildings.'' These comparisons were made from five buildings chosen randomly illustrating a wide variety of construction types and building configurations. Each building is divided into sectors, defined as portions of it that are attached additions to the original building, or portions separated by an expansion joint between the structural systems. The five buildings studied contain a total of sixteen sectors. The paper is divided into the following sections: Introduction; Basic Concepts of the LANL Methodology; Basic Concepts of FEMA-178; Highlights of the Comparison; Comments on the Results; and Final Words

Present and future neutrino physics research at the Los Alamos Meson Physics Facility

International Nuclear Information System (INIS)

Sanders, G.H.

1988-01-01

The Los Alamos Meson Physics Facility is currently the site of two neutrino experiments. A measurement of elastic scattering of electron-neutrinos on electrons is providing confirmation of the destructive interference between the weak neutral and charged currents predicted in the standard electroweak theory. A search for the appearance of /bar/ν//sub e/ is being carried out at the LAMPF beam stop, as well. The status of this experiment is described. A major new initiative is being undertaken to measure neutrino-electron scattering in a large water Cerenkov detector. This meaurement will be precise enough to provide, in combination with the meaurements to be performed at the new generation of high-energy electron-positron colliers, the first experimental study of the standard electrowak theory at the level of one-loop radiative corrections. The detector will also be a vehicle for neutrino-oscillation searches, measurement of neutrinos from supernovae, and other fundamental physics. The apparatus will consist of a neutrino production target and shield surrounded by a water Cerenkov detector. The fiducial volume of water will be approximately 7000 tons, viewed by approximately 13000 20 cm diameter photomultiplier tubes. 11 refs., 6 figs

Mortality among plutonium and other workers at a nuclear facility

International Nuclear Information System (INIS)

Wilkinson, G.S.; Voelz, G.L.; Acquavella, J.F.; Tietjen, G.L.; Reyes, M.; Brackbill, R.; Wiggs, L.

1983-01-01

Mortality among plutonium and other nuclear workers has been investigated to assess the effects of exposures to low levels of internal and external radiation. Standarized mortality ratios (SMRs) for white male workers employed at least two years from 1951 through 1977 were significantly lower than expected for all causes, all cancers, cancers of the respiratory system, and lung cancer. Benign neoplasms, all of which were intracranial tumors, were significantly elevated. No bone cancers were discovered and other radiogenic cancers did not differ significantly from expectation. Duration of employment and latency did not affect these results. SMRs for a subcohort of plutonium exposed workers were significantly low for all causes of deaths and all cancers. Estimates of relative risk for workers exposed to 2 or more nCi compared to unexposed workers were not significantly higher or lower than unity. These findings do not support the hypothesis of increased mortality among plutonium and other nuclear workers. The excess for benign and unspecified intracranial tumors is not consistent with previous studies on radiation induced brain tumors in terms of latency and exposure levels

Fast-neutron coincidence-counter manual

International Nuclear Information System (INIS)

Ensslin, N.; Atwell, T.L.; Lee, D.M.; Erkkila, B.; Marshall, R.S.; Morgan, A.; Shonrock, C.; Tippens, B.; Van Lyssel, T.

1982-03-01

The fast neutron counter (FNC) described in this report is a computer-based assay system employing fast-pulse counting instrumentation. It is installed below a glove box in the metal electrorefining area of the Los Alamos National Laboratory Plutonium Processing Facility. The instrument was designed to assay plutonium salts and residues from this process and to verify the mass of electrorefined metal. Los Alamos National Laboratory Groups Q-1, Q-3, and CMB-11 carried out a joint test and evaluation plan of this instrument between May 1978 and May 1979. The results of that evaluation, a description of the FNC, and operating instructions for further use are given in this report

Excess Weapons Plutonium Immobilization in Russia

International Nuclear Information System (INIS)

Jardine, L.; Borisov, G.B.

2000-01-01

The joint goal of the Russian work is to establish a full-scale plutonium immobilization facility at a Russian industrial site by 2005. To achieve this requires that the necessary engineering and technical basis be developed in these Russian projects and the needed Russian approvals be obtained to conduct industrial-scale immobilization of plutonium-containing materials at a Russian industrial site by the 2005 date. This meeting and future work will provide the basis for joint decisions. Supporting R and D projects are being carried out at Russian Institutes that directly support the technical needs of Russian industrial sites to immobilize plutonium-containing materials. Special R and D on plutonium materials is also being carried out to support excess weapons disposition in Russia and the US, including nonproliferation studies of plutonium recovery from immobilization forms and accelerated radiation damage studies of the US-specified plutonium ceramic for immobilizing plutonium. This intriguing and extraordinary cooperation on certain aspects of the weapons plutonium problem is now progressing well and much work with plutonium has been completed in the past two years. Because much excellent and unique scientific and engineering technical work has now been completed in Russia in many aspects of plutonium immobilization, this meeting in St. Petersburg was both timely and necessary to summarize, review, and discuss these efforts among those who performed the actual work. The results of this meeting will help the US and Russia jointly define the future direction of the Russian plutonium immobilization program, and make it an even stronger and more integrated Russian program. The two objectives for the meeting were to: (1) Bring together the Russian organizations, experts, and managers performing the work into one place for four days to review and discuss their work with each other; and (2) Publish a meeting summary and a proceedings to compile reports of all the

CONVERSION OF PLUTONIUM TRIFLUORIDE TO PLUTONIUM TETRAFLUORIDE

Science.gov (United States)

Fried, S.; Davidson, N.R.

1957-09-10

A large proportion of the trifluoride of plutonium can be converted, in the absence of hydrogen fluoride, to the tetrafiuoride of plutonium. This is done by heating plutonium trifluoride with oxygen at temperatures between 250 and 900 deg C. The trifiuoride of plutonium reacts with oxygen to form plutonium tetrafluoride and plutonium oxide, in a ratio of about 3 to 1. In the presence of moisture, plutonium tetrafluoride tends to hydrolyze at elevated temperatures and therefore it is desirable to have the process take place under anhydrous conditions.

Program management assessment of Federal Facility Compliance Agreement regarding CAA-40 C.F.R. Part 61, Subpart H at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

1997-01-01

An assessment of Los Alamos National Laboratory's management system related to facility compliance with an element of the Clean Air Act was performed under contract by a team from Northern Arizona University. More specifically, a Federal Facilities Compliance Agreement (FFCA) was established in 1996 to bring the Laboratory into compliance with emissions standards of radionuclides, commonly referred to as Rad/NESHAP. In the fall of 1996, the four-person team of experienced environmental managers evaluated the adequacy of relevant management systems to implement the FFCA provisions. The assessment process utilized multiple procedures including document review, personnel interviews and re-interviews, and facility observations. The management system assessment was completed with a meeting among team members, Laboratory officials and others on November 1, 1996 and preparation of an assessment report

DYMAC system: status and experience

International Nuclear Information System (INIS)

Malanify, J.J.

1980-01-01

The Dynamic Materials Accountability (DYMAC) system has been in operation at the Plutonium Processing Facility at the Los Alamos Scientific Laboratory since January 1978. The current status of this development and demonstration program, as well as the achieved operational experience, is reported

Characterizing Surplus US Plutonium for Disposition - 13199

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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)

Decommissioning of surplus facilities at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Stout, D.S.

1995-01-01

Decommissioning Buildings 3 and 4 South at Technical Area 21, Los Alamos National Laboratory, involves the decontamination, dismantlement, and demolition of two enriched-uranium processing buildings containing process equipment and ductwork holdup. The Laboratory has adopted two successful management strategies to implement this project: Rather than characterize an entire site, upfront, investigators use the ''observational approach,'' in which they collect only enough data to begin decommissioning activities and then determine appropriate procedures for further characterization as the work progresses. Project leaders augment work packages with task hazard analyses to fully define specific tasks and inform workers of hazards; all daily work activities are governed by specific work procedures and hazard analyses

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

International Nuclear Information System (INIS)

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

1982-02-01

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 μCi/m 2 . The deposition values following the 110-mph and the 130-mph tornadoes are below the EPA proposed guideline

Plutonium use - Present status and prospects

International Nuclear Information System (INIS)

Dievoet, J. van; Fossoul, E.; Jonckheere, E.; Bemden, E. van den

1977-01-01

The use of plutonium in thermal and fast reactors is a demonstrated, if not proven, technology. Moreover, plutonium is being produced in increasing quantities. Evaluation of this production on a world scale shows that it would be theoretically possible to construct numerous breeders and thus to make the best use of plutonium, while considerably reducing uranium consumption. This source of plutonium is nevertheless dependent on the reprocessing of irradiated fuel. Long delays in installing and adequate world reprocessing capacity are weakening the prospects for introducing breeders. Furthermore, the critical situation regarding reprocessing may delay the development of complementary reprocessing methods for fuels with a high plutonium content and high burnup. The recycling of plutonium is now a well-known technique and any objections to it hardly bear analysis. Utilization of plutonium offers an appreciable saving in terms of uranium and separative work units; and it can also be shown that immediate reprocessing of the recycling fuel is not essential for the economics of the concept. Temporary storage of recycled fuel is a particularly safe form of concentrating plutonium, namely in irradiated plutonium-bearing fuel assemblies. Finally, recycling offers such flexibility that it represents no obstacle to fuel management at power plants with light-water reactors. These strategic considerations imply that the technology of using plutonium for fabricating thermal or fast reactor fuels is both technically reliable and economically viable. The methods used in industrial facilities are fully reassuring in this respect. Although various unsolved problems exist, none seems likely to impede current developments, while the industrial experience gained has enabled the economics and reliability of the methods to be improved appreciably. Apart from the techno-economic aspects, the plutonium industry must face extremely important problems in connection with the safety of personnel

Natural hazards that may trigger a radiological release from a plutonium processing facility

Energy Technology Data Exchange (ETDEWEB)

Selvidge, J. E.

1977-04-28

Calculations show the probability of a tornado striking a plutonium area at Rocky Flats is 2.2 x 10/sup -4/ per year. The source term (expected value of plutonium release) should such an event occur is calculated at 3.3 x 10/sup -7/ grams. The source term for high-velocity, downslope winds is higher--2.2 x 10/sup -3/ grams. The probability of a meteorite that weighs one or more pounds (453 grams) striking a plutonium area is estimated at 8.88 x 10/sup -7/ per year. Because of this small probability and the remote chance that a plutonium release would occur even if a meteorite hit occurred, the hazard from meteorite impact is considered negligible. Conservative assumptions result in all calculated frequencies being almost certainly too high. Empirical observations have indicated lower frequencies than those calculated.

Natural hazards that may trigger a radiological release from a plutonium processing facility

International Nuclear Information System (INIS)

Selvidge, J.E.

1977-01-01

Calculations show the probability of a tornado striking a plutonium area at Rocky Flats is 2.2 x 10 -4 per year. The source term (expected value of plutonium release) should such an event occur is calculated at 3.3 x 10 -7 grams. The source term for high-velocity, downslope winds is higher--2.2 x 10 -3 grams. The probability of a meteorite that weighs one or more pounds (453 grams) striking a plutonium area is estimated at 8.88 x 10 -7 per year. Because of this small probability and the remote chance that a plutonium release would occur even if a meteorite hit occurred, the hazard from meteorite impact is considered negligible. Conservative assumptions result in all calculated frequencies being almost certainly too high. Empirical observations have indicated lower frequencies than those calculated

Acid-digestion treatment of plutonium-containing waste

International Nuclear Information System (INIS)

Wieczorek, H.; Kemmler, G.; Krause, H.

1981-01-01

The Radioactive Acid-Digestion Test Unit (RADTU) has been constructed at Hanford to demonstrate the application of the acid-digestion process for treating combustible transuranic wastes and scrap materials. The RADTU, with its original tray digestion vessel, has recently completed a six-month campaign processing potentially contaminated non-glovebox wastes from a Hanford plutonium facility. During this campaign, it processed 2100 kg largely cellulosic wastes at an average sustained processing rate of 3 kg/h as limited by the acid-waste contact and the water boil-off rate from the acid feeds. The on-line operating efficiency was nearly 50% on a twelve-hour day, five-day week basis. Following this campaign, a new annular high-rate digester has been installed for testing. In preliminary tests with simulated wastes, the new digester demonstrated a sustained capacity of 10 kg/h with greatly improved intimacy of contact between the digestion acid and the waste. The new design also doubles the heat-transfer surface, which is expected to provide at least twice the water boil-off rate of the previous tray digester design. Following shakedown testing with simulated and low-level wastes, the new unit will be used to process combustible plutonium scrap and waste from Hanford plutonium facilities for the purposes of volume reduction, plutonium recovery, and stabilization of the final waste form. (author)