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Note: This page contains sample records for the topic "disposition medical isotope" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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1

DOE/EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory (12/04)  

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

88 88 FINAL Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee December 2004 U. S. Department of Energy Oak Ridge Operations 04-049(doc)/120204 04-049(doc)/120204 SCIENCE APPLICATIONS INTERNATIONAL CORPORATION contributed to the preparation of this document and should not be considered an eligible contractor for its review. Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee Date Issued-December 2004 U. S. Department of Energy Oak Ridge Operations 04-049(doc)/120204 CONTENTS

2

EA-1488: Environmental Assessment for the U-233 Disposition, Medical  

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

488: Environmental Assessment for the U-233 Disposition, 488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee The purpose of the proposed action evaluated in this environmental assessment (EA) is the processing of uranium-233 (233U) stored at the Oak Ridge National Laboratory (ORNL) and other small quantities of similar material currently stored at other U. S. Department of Energy (DOE) sites in order to render it suitable for safe, long-term, economical storage. The 233U is stored within Bldg. 3019A, which is part of the Bldg. 3019

3

DOE/EA-1488: Finding of No Significant Impact U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory (12/10/04)  

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

FINDING OF NO SIGNIFICANT IMPACT FINDING OF NO SIGNIFICANT IMPACT U-233 DISPOSITION, MEDICAL ISOTOPE PRODUCTION, AND BUILDING 3019 COMPLEX SHUTDOWN AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U. S. Department of Energy ACTION: Finding of No Significant Impact. SUMMARY: The U. S. Department of Energy (DOE) has completed an Environmental Assessment (EA) [DOE/EA-1488] that evaluates the processing of uranium-233 ( 233 U) stored at the Oak Ridge National Laboratory (ORNL) and other small quantities of similar material currently stored at other DOE sites in order to render it suitable for safe, long-term, economical storage. The 233 U is stored within Bldg. 3019A, which is part of the Bldg. 3019 Complex. Additionally, the proposed action would increase the availability of medical

4

Uranium Downblending and Disposition Project Technology Readiness...  

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

Assessment EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory,...

5

AVLIS enrichment of medical isotopes  

SciTech Connect (OSTI)

Under the Sponsorship of the United states Enrichment Corporation (USEC), we are currently investigating the large scale separation of several isotopes of medical interest using atomic vapor isotope separation (AVLIS). This work includes analysis and experiments in the enrichment of thallium 203 as a precursor to the production of thallium 201 used in cardiac imaging following heart attacks, on the stripping of strontium 84 from natural strontium as precursor to the production of strontium 89, and on the stripping of lead 210 from lead used in integrated circuits to reduce the number of alpha particle induced logic errors.

Haynam, C.A.; Scheibner, K.F.; Stern, R.C.; Worden, E.F. [Lawrence Livermore National Laboratory, CA (United States)

1996-12-31T23:59:59.000Z

6

EA-1488: Environmental Assessment for the U-233 Disposition,...  

Office of Environmental Management (EM)

Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee...

7

EIS-0249: Medical Isotopes Production Project  

Broader source: Energy.gov [DOE]

This EIS evaluates the potential environmental impacts of a proposal to establish a production capability for molybdenum-99 (Mo-99) and related medical isotopes.

8

Expert Panel: Forecast Future Demand for Medical Isotopes  

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

Expert Panel: Expert Panel: Forecast Future Demand for Medical Isotopes March 1999 Expert Panel: Forecast Future Demand for Medical Isotopes September 25-26, 1998 Arlington, Virginia The Expert Panel ............................................................................................. Page 1 Charge To The Expert Panel........................................................................... Page 2 Executive Summary......................................................................................... Page 3 Introduction ...................................................................................................... Page 4 Rationale.......................................................................................................... Page 6 Economic Analysis...........................................................................................

9

Global Security, Medical Isotopes, and Nuclear Science  

SciTech Connect (OSTI)

Over the past century basic nuclear science research has led to the use of radioactive isotopes into a wide variety of applications that touch our lives everyday. Some are obvious, such as isotopes for medical diagnostics and treatment. Others are less so, such as National/Global security issues. And some we take for granted, like the small amount of 241Am that is in every smoke detector. At the beginning of this century, we are in a position where the prevalence and importance of some applications of nuclear science are pushing the basic nuclear science community for improved models and nuclear data. Yet, at the same time, the push by the basic nuclear science community to study nuclei that are farther and farther away from stability also offer new opportunities for many applications. This talk will look at several global security applications of nuclear science, summarizing current R&D and need for improved nuclear data It will also look at how applications of nuclear science, such as to medicine, will benefit from the push for more and more powerful radioactive ion beam facilities.

Ahle, L E

2007-09-17T23:59:59.000Z

10

Expert Panel: Forecast Future Demand for Medical Isotopes | Department of  

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

Expert Panel: Forecast Future Demand for Medical Isotopes Expert Panel: Forecast Future Demand for Medical Isotopes Expert Panel: Forecast Future Demand for Medical Isotopes The Expert Panel has concluded that the Department of Energy and National Institutes of Health must develop the capability to produce a diverse supply of radioisotopes for medical use in quantities sufficient to support research and clinical activities. Such a capability would prevent shortages of isotopes, reduce American dependence on foreign radionuclide sources and stimulate biomedical research. The expert panel recommends that the U.S. government build this capability around either a reactor, an accelerator or a combination of both technologies as long as isotopes for clinical and research applications can be supplied reliably, with diversity in adequate

11

Laser Isotope Enrichment for Medical and Industrial Applications  

SciTech Connect (OSTI)

Laser Isotope Enrichment for Medical and Industrial Applications by Jeff Eerkens (University of Missouri), Jay Kunze (Idaho State University), and Leonard Bond (Idaho National Laboratory) The principal isotope enrichment business in the world is the enrichment of uranium for commercial power reactor fuels. However, there are a number of other needs for separated isotopes. Some examples are: 1) Pure isotopic targets for irradiation to produce medical radioisotopes. 2) Pure isotopes for semiconductors. 3) Low neutron capture isotopes for various uses in nuclear reactors. 4) Isotopes for industrial tracer/identification applications. Examples of interest to medicine are targets to produce radio-isotopes such as S-33, Mo-98, Mo-100, W-186, Sn-112; while for MRI diagnostics, the non-radioactive Xe-129 isotope is wanted. For super-semiconductor applications some desired industrial isotopes are Si-28, Ga-69, Ge-74, Se-80, Te-128, etc. An example of a low cross section isotope for use in reactors is Zn-68 as a corrosion inhibitor material in nuclear reactor primary systems. Neutron activation of Ar isotopes is of interest in industrial tracer and diagnostic applications (e.g. oil-logging). . In the past few years there has been a sufficient supply of isotopes in common demand, because of huge Russian stockpiles produced with old electromagnetic and centrifuge separators previously used for uranium enrichment. Production of specialized isotopes in the USA has been largely accomplished using old ”calutrons” (electromagnetic separators) at Oak Ridge National Laboratory. These methods of separating isotopes are rather energy inefficient. Use of lasers for isotope separation has been considered for many decades. None of the proposed methods have attained sufficient proof of principal status to be economically attractive to pursue commercially. Some of the authors have succeeded in separating sulfur isotopes using a rather new and different method, known as condensation repression. In this scheme a gas, of the selected isotopes for enrichment, is irradiated with a laser at a particular wavelength that would excite only one of the isotopes. The entire gas is subject to low temperatures sufficient to cause condensation on a cold surface. Those molecules in the gas that the laser excited are not as likely to condense as are the unexcited molecules. Hence the gas drawn out of the system will be enriched in the isotope that was excited by the laser. We have evaluated the relative energy required in this process if applied on a commercial scale. We estimate the energy required for laser isotope enrichment is about 20% of that required in centrifuge separations, and 2% of that required by use of "calutrons".

Leonard Bond

2006-07-01T23:59:59.000Z

12

HEU Minimization and the Reliable Supply of Medical Isotopes Nuclear  

National Nuclear Security Administration (NNSA)

HEU Minimization and the Reliable Supply of Medical Isotopes Nuclear HEU Minimization and the Reliable Supply of Medical Isotopes Nuclear Security Summit: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > HEU Minimization and the Reliable Supply of ... Fact Sheet HEU Minimization and the Reliable Supply of Medical Isotopes Nuclear

13

Domestic production of medical isotope Mo-99 moves a step closer  

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

Domestic production of medical isotope Mo-99 Domestic production of medical isotope Mo-99 moves a step closer Irradiated uranium fuel has been recycled and reused for molybdenum-99...

14

Isotopic noble gas signatures released from medical isotope production facilities - Simulations and measurements  

SciTech Connect (OSTI)

Journal article on the role that radioxenon isotopes play in confirming whether or not an underground explosion was nuclear in nature. Radioxenon isotopes play a major role in confirming whether or not an underground explosion was nuclear in nature. It is then of key importance to understand the sources of environmental radioxenon to be able to distinguish civil sources from those of a nuclear explosion. Based on several years of measurements, combined with advanced atmospheric transport model results, it was recently shown that the main source of radioxenon observations are strong and regular batch releases from a very limited number of medical isotope production facilities. This paper reviews production processes in different medical isotope facilities during which radioxenon is produced. Radioxenon activity concentrations and isotopic compositions are calculated for six large facilities. The results are compared with calculated signals from nuclear explosions. Further, the outcome is compared and found to be consistent with radioxenon measurements recently performed in and around three of these facilities. Some anomalies in measurements in which {sup 131m}Xe was detected were found and a possible explanation is proposed. It was also calculated that the dose rate of the releases is well below regulatory values. Based on these results, it should be possible to better understand, interpret and verify signals measured in the noble gas measurement systems in the International Monitoring of the Comprehensive Nuclear-Test-Ban Treaty.

Saey, Paul R.; Bowyer, Ted W.; Ringbom, Anders

2010-09-09T23:59:59.000Z

15

PF-4 actinide disposition strategy  

SciTech Connect (OSTI)

The dwindling amount of Security Category I processing and storage space across the DOE Complex has driven the need for more effective storage of nuclear materials at LANL's Plutonium Facility's (PF-4's) vault. An effort was begun in 2009 to create a strategy, a roadmap, to identify all accountable nuclear material and determine their disposition paths, the PF-4 Actinide Disposition Strategy (PADS). Approximately seventy bins of nuclear materials with similar characteristics - in terms of isotope, chemical form, impurities, disposition location, etc. - were established in a database. The ultimate disposition paths include the material to remain at LANL, disposition to other DOE sites, and disposition to waste. If all the actions described in the document were taken, over half of the containers currently in the PF-4 vault would been eliminated. The actual amount of projected vault space will depend on budget and competing mission requirements, however, clearly a significant portion of the current LANL inventory can be either dispositioned or consolidated.

Marcevicius, Robert W [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

16

Methods for separating medical isotopes using ionic liquids  

SciTech Connect (OSTI)

A method for extracting a radioisotope from an aqueous solution, the method comprising: a) intimately mixing a non-chelating ionic liquid with the aqueous solution to transfer at least a portion of said radioisotope to said non-chelating ionic liquid; and b) separating the non-chelating ionic liquid from the aqueous solution. In preferred embodiments, the method achieves an extraction efficiency of at least 80%, or a separation factor of at least 1.times.10.sup.4 when more than one radioisotope is included in the aqueous solution. In particular embodiments, the method is applied to the separation of medical isotopes pairs, such as Th from Ac (Th-229/Ac-225, Ac-227/Th-227), or Ra from Ac (Ac-225 and Ra-225, Ac-227 and Ra-223), or Ra from Th (Th-227 and Ra-223, Th-229 and Ra-225).

Luo, Huimin; Boll, Rose Ann; Bell, Jason Richard; Dai, Sheng

2014-10-21T23:59:59.000Z

17

Feasibility study of medical isotope production at Sandia National Laboratories  

SciTech Connect (OSTI)

In late 1994, Sandia National Laboratories in Albuquerque, New Mexico, (SNL/NM), was instructed by the Department of Energy (DOE) Isotope Production and Distribution Program (IPDP) to examine the feasibility of producing medically useful radioisotopes using the Annular Core Research Reactor (ACRR) and the Hot Cell Facility (HCF). Los Alamos National Laboratory (LANL) would be expected to supply the targets to be irradiated in the ACRR. The intent of DOE would be to provide a capability to satisfy the North American health care system demand for {sup 99}Mo, the parent of {sup 99m}Tc, in the event of an interruption in the current Canadian supply. {sup 99m}Tc is used in 70 to 80% of all nuclear medicine procedures in the US. The goal of the SNL/NM study effort is to determine the physical plant capability, infrastructure, and staffing necessary to meet the North American need for {sup 99}Mo and to identify and examine all issues with potential for environmental impact.

Massey, C.D.; Miller, D.L.; Carson, S.D. [Sandia National Labs., Albuquerque, NM (United States). Environmental Regulatory Assessment Dept.] [and others

1995-12-01T23:59:59.000Z

18

Processing and Disposition of Special Actinide Target Materials - 13138  

SciTech Connect (OSTI)

The Department of Energy (DOE) manages an inventory of materials that contains a range of long-lived radioactive isotopes that were produced from the 1960's through the 1980's by irradiating targets in high-flux reactors at the Savannah River Site (SRS) to produce special heavy isotopes for DOE programmatic use, scientific research, and industrial and medical applications. Among the products were californium-252, heavy curium (including Cm-246 through Cm-248), and plutonium-242 and -244. Many of the isotopes are still in demand today, and they can be recovered from the remaining targets previously irradiated at SRS or produced from the recovered isotopes. Should the existing target materials be discarded, the plutonium (Pu) and curium (Cm) isotopes cannot be replaced readily with existing production sources. Some of these targets are stored at SRS, while other target material is stored at Oak Ridge National Laboratory (ORNL) at several stages of processing. The materials cannot be stored in their present form indefinitely. Their long-term management involves processing items for beneficial use and/or for disposition, using storage and process facilities at SRS and ORNL. Evaluations are under way for disposition options for these materials, and demonstrations of improved flow sheets to process the materials are being conducted at ORNL and the Savannah River National Laboratory (SRNL). The disposition options and a management evaluation process have been developed. Processing demonstrations and evaluations for these unique materials are under way. (authors)

Robinson, Sharon M.; Patton, Brad D. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)] [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States); Allender, Jeffrey S. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

2013-07-01T23:59:59.000Z

19

Reduce, reuse and recycle: A green solution to Canada's medical isotope shortage  

Science Journals Connector (OSTI)

Abstract Due to the unforeseen maintenance issues at the National Research Universal (NRU) reactor at Chalk River and coincidental shutdowns of other international reactors, a global shortage of medical isotopes (in particular technetium-99m, Tc-99m) occurred in 2009. The operation of these research reactors is expensive, their age creates concerns about their continued maintenance and the process results in a large amount of long-lived nuclear waste, whose storage cost has been subsidized by governments. While the NRU has since revived its operations, it is scheduled to cease isotope production in 2016. The Canadian government created the Non-reactor based medical Isotope Supply Program (NISP) to promote research into alternative methods for producing medical isotopes. The NRC was a member of a collaboration looking into the use of electron linear accelerators (LINAC) to produce molybdenum-99 (Mo-99), the parent isotope of Tc-99m. This paper outlines NRC’s involvement in every step of this process, from the production, chemical processing, recycling and preliminary animal studies to demonstrate the equivalence of LINAC Tc-99m with the existing supply. This process stems from reusing an old idea, reduces the nuclear waste to virtually zero and recycles material to create a green solution to Canada's medical isotope shortage.

R. Galea; C. Ross; R.G. Wells

2014-01-01T23:59:59.000Z

20

DESIGN OF A SUBCRITICAL AQUEOUS TARGET SYSTEM FOR MEDICAL ISOTOPE PRODUCTION  

E-Print Network [OSTI]

DESIGN OF A SUBCRITICAL AQUEOUS TARGET SYSTEM FOR MED- ICAL ISOTOPE PRODUCTION An Undergraduate Research Scholars Thesis by RICHARD VEGA Submitted to Honors and Undergraduate Research Texas A&M University in partial fulfillment... ..............................................................................................................................52 1 ABSTRACT Design of a Subcritical Aqueous Target System for Medical Isotope Production. (May 2014) Richard Vega Department of Nuclear Engineering Department of Physics Texas A&M University Research Advisor: Dr. Gamal...

Vega, Richard Manuel

2013-12-10T23:59:59.000Z

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


21

Domestic production of medical isotope Mo-99 moves a step closer  

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

Domestic production of medical isotope Mo-99 Domestic production of medical isotope Mo-99 Domestic production of medical isotope Mo-99 moves a step closer Irradiated uranium fuel has been recycled and reused for molybdenum-99 (Mo-99) production, with virtually no losses in Mo-99 yields or uranium recovery. May 13, 2013 From left, Los Alamos scientists Roy Copping, Sean Reilly, and Daniel Rios. Copping examines the Buchi Multivapor P-12 Evaporator, and Reilly and Rios are at the Agilent Technologies Cary 60 UV-Vis Spectrometer. From left, Los Alamos scientists Sean Reilly, Roy Copping, and Daniel Rios. Sean is looking at the Buchi Multivapor P-12 Evaporator, and Roy and Daniel are at the Agilent Technologies Cary 60 UV-Vis Spectrometer. Contact Nancy Ambrosiano Communications Office (505) 667-0471

22

DOE and NNSA labs work with CTBTO to reduce medical isotope emissions,  

National Nuclear Security Administration (NNSA)

and NNSA labs work with CTBTO to reduce medical isotope emissions, and NNSA labs work with CTBTO to reduce medical isotope emissions, enhance the effectiveness of nuclear explosion monitoring | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > DOE and NNSA labs work with CTBTO ... DOE and NNSA labs work with CTBTO to reduce medical isotope emissions,

23

Radioactive isotope production for medical applications using Kharkov electron driven subcritical assembly facility.  

SciTech Connect (OSTI)

Kharkov Institute of Physics and Technology (KIPT) of Ukraine has a plan to construct an accelerator driven subcritical assembly. The main functions of the subcritical assembly are the medical isotope production, neutron thereby, and the support of the Ukraine nuclear industry. Reactor physics experiments and material research will be carried out using the capabilities of this facility. The United States of America and Ukraine have started collaboration activity for developing a conceptual design for this facility with low enrichment uranium (LEU) fuel. Different conceptual designs are being developed based on the facility mission and the engineering requirements including nuclear physics, neutronics, heat transfer, thermal hydraulics, structure, and material issues. Different fuel designs with LEU and reflector materials are considered in the design process. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements and upgrades. This report is a part of the Argonne National Laboratory Activity within this collaboration for developing and characterizing the subcritical assembly conceptual design. In this study, the medical isotope production function of the Kharkov facility is defined. First, a review was carried out to identify the medical isotopes and its medical use. Then a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Finally, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and irradiation location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes were considered and all transmutation channels are used including (n,{gamma}), (n,2n), (n,p), and ({gamma},n). In the second part, the parent isotopes with high reaction rate were explicitly modeled in the calculations. For the nuclides with a very high capture microscopic cross section, such as iridium, rhenium, and samarium, their specific activities are reduced by a factor of 30 when the self-shielding effect is included. Four irradiation locations were considered in the analyses to maximize the medical isotope production rate. The results show the self-shield effect reduces the specific activity values and changes the irradiation location for obtaining the maximum possible specific activity. The axial and radial distributions of the specific activity were used to define the irradiation sample size for producing each isotope.

Talamo, A.; Gohar, Y.; Nuclear Engineering Division

2007-05-15T23:59:59.000Z

24

Maximum Reasonable Radioxenon Releases from Medical Isotope Production Facilities and Their Effect on Monitoring Nuclear Explosions  

SciTech Connect (OSTI)

Fission gases such as 133Xe are used extensively for monitoring the world for signs of nuclear testing in systems such as the International Monitoring System (IMS). These gases are also produced by nuclear reactors and by fission production of 99Mo for medical use. Recently, medical isotope production facilities have been identified as the major contributor to the background of radioactive xenon isotopes (radioxenon) in the atmosphere (Saey, et al., 2009). These releases pose a potential future problem for monitoring nuclear explosions if not addressed. As a starting point, a maximum acceptable daily xenon emission rate was calculated, that is both scientifically defendable as not adversely affecting the IMS, but also consistent with what is possible to achieve in an operational environment. This study concludes that an emission of 5×109 Bq/day from a medical isotope production facility would be both an acceptable upper limit from the perspective of minimal impact to monitoring stations, but also appears to be an achievable limit for large isotope producers.

Bowyer, Ted W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Kephart, Rosara F.; Eslinger, Paul W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Friese, Judah I. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Miley, Harry S. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Saey, Paul R. [Vienna University of Technology, Atomic Institute of the Austrian Universities, Vienna (Austria)

2013-01-01T23:59:59.000Z

25

Records Disposition  

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

To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its management and operating contractors. Cancels DOE O 1324.2 dated 5-28-80. Chg 1 dated 4-9-92. Canceled by DOE O 1324.2B dated 1-12-95.

1988-09-13T23:59:59.000Z

26

Records Disposition  

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

To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its operating and onsite service contractors. Cancels DOE O 1324.1 dated 7-10-78. Chg 1 dated 7-2-81. Chg 2 dated 11-9-82. Canceled by DOE O 1324.2A dated 9-13-88.

1980-05-28T23:59:59.000Z

27

Abatement of Xenon and Iodine Emissions from Medical Isotope Production Facilities  

SciTech Connect (OSTI)

The capability of the International Monitoring System (IMS) to detect xenon from underground nuclear explosions is dependent on the radioactive xenon background. Adding to the background, medical isotope production (MIP) by fission releases several important xenon isotopes including xenon-133 and iodine-133 that decays to xenon-133. The amount of xenon released from these facilities may be equivalent to or exceed that released from an underground nuclear explosion. Thus the release of gaseous fission products within days of irradiation makes it difficult to distinguish MIP emissions from a nuclear explosion. In addition, recent shortages in molybdenum-99 have created interest and investment opportunities to design and build new MIP facilities in the United States and throughout the world. Due to the potential increase in the number of MIP facilities, a discussion of abatement technologies provides insight into how the problem of emission control from MIP facilities can be tackled. A review of practices is provided to delineate methods useful for abatement of medical isotopes.

Doll, Charles G. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Sorensen, Christina M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Bowyer, Ted W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Friese, Judah I. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Hayes, James C. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Hoffman, Emma L. [Australian Nuclear Science and Technology Organisation, Menai (Australia); Kephart, Rosara F. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

2014-04-01T23:59:59.000Z

28

Estimates of Radioxenon Released from Southern Hemisphere Medical isotope Production Facilities Using Measured Air Concentrations and Atmospheric Transport Modeling  

SciTech Connect (OSTI)

Abstract The International Monitoring System (IMS) of the Comprehensive-Nuclear-Test-Ban-Treaty monitors the atmosphere for radioactive xenon leaking from underground nuclear explosions. Emissions from medical isotope production represent a challenging background signal when determining whether measured radioxenon in the atmosphere is associated with a nuclear explosion prohibited by the treaty. The Australian Nuclear Science and Technology Organisation (ANSTO) operates a reactor and medical isotope production facility in Lucas Heights, Australia. This study uses two years of release data from the ANSTO medical isotope production facility and Xe-133 data from three IMS sampling locations to estimate the annual releases of Xe-133 from medical isotope production facilities in Argentina, South Africa, and Indonesia. Atmospheric dilution factors derived from a global atmospheric transport model were used in an optimization scheme to estimate annual release values by facility. The annual releases of about 6.8×1014 Bq from the ANSTO medical isotope production facility are in good agreement with the sampled concentrations at these three IMS sampling locations. Annual release estimates for the facility in South Africa vary from 1.2×1016 to 2.5×1016 Bq and estimates for the facility in Indonesia vary from 6.1×1013 to 3.6×1014 Bq. Although some releases from the facility in Argentina may reach these IMS sampling locations, the solution to the objective function is insensitive to the magnitude of those releases.

Eslinger, Paul W.; Friese, Judah I.; Lowrey, Justin D.; McIntyre, Justin I.; Miley, Harry S.; Schrom, Brian T.

2014-04-06T23:59:59.000Z

29

Disposition Schedules | Department of Energy  

Office of Environmental Management (EM)

Disposition Schedules Disposition Schedules The DOE Records Disposition Schedules provide the authority for the transfer, or disposal of records created and maintained by the...

30

Request For Records Disposition | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Request For Records Disposition Southeastern Power Administration (SEPA) Request For Records Disposition More Documents & Publications Audit...

31

DOE Records Disposition Schedule Changes | Department of Energy  

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

Records Disposition Schedule Changes DOE Records Disposition Schedule Changes Disposition Schedule Changes DOE Records Disposition Schedule Changes More Documents & Publications...

32

Disposition of uranium-233  

SciTech Connect (OSTI)

The US is developing a strategy for the disposition of surplus weapons-usable uranium-233 ({sup 233}U). The strategy (1) identifies the requirements for the disposition of surplus {sup 233}U; (2) identifies potential disposition options, including key issues to be resolved with each option; and (3) defines a road map that identifies future key decisions and actions. The disposition of weapons-usable fissile materials is part of a US international arms-control program for reduction of the number of nuclear weapons and the quantities of nuclear-weapons-usable materials worldwide. The disposition options ultimately lead to waste forms requiring some type of geological disposal. Major options are described herein.

Tousley, D.R. [Dept. of Energy, Washington, DC (United States). Office of Fissile Materials Disposition; Forsberg, C.W.; Krichinsky, A.M. [Oak Ridge National Lab., TN (United States)

1997-10-16T23:59:59.000Z

33

disposition | OpenEI  

Open Energy Info (EERE)

disposition disposition Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 11, and contains only the reference case. The dataset uses million barrels per day. The data is broken down into crude oil, other petroleum supply, other non petroleum supply and liquid fuel consumption. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA liquid fuels Supply Data application/vnd.ms-excel icon AEO2011: Liquid Fuels Supply and Disposition- Reference Case (xls, 117 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035

34

Request For Records Disposition | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Request For Records Disposition Spent Nuclear Fuels Request For Records Disposition More Documents & Publications The Report To The President And...

35

Characterizing Surplus US Plutonium for Disposition - 13199  

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

36

Characterizing surplus US plutonium for disposition  

SciTech Connect (OSTI)

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

Allender, Jeffrey S.; Moore, Edwin N.

2013-02-26T23:59:59.000Z

37

WOSMIP II- Workshop on Signatures of Medical and Industrial Isotope Production  

SciTech Connect (OSTI)

Medical and industrial fadioisotopes are fundamental tools used in science, medicine and industry with an ever expanding usage in medical practice where their availability is vital. Very sensitive environmental radionuclide monitoring networks have been developed for nuclear-security-related monitoring [particularly Comprehensive Test-Ban-Treaty (CTBT) compliance verification] and are now operational.

Matthews, Murray; Achim, Pascal; Auer, M.; Bell, Randy; Bowyer, Ted W.; Braekers, Damien; Bradley, Ed; Briyatmoko, Budi; Berglund, Helena; Camps, Johan; Carranza, Eduardo C.; Carty, Fitz; DeCaire, Richard; Deconninck, Benoit; DeGeer, Lars E.; Druce, Michael; Friese, Judah I.; Hague, Robert; Hoffman, Ian; Khrustalev, Kirill; Lucas, John C.; Mattassi, G.; Mattila, Aleski; Nava, Elisabetta; Nikkinin, Mika; Papastefanou, Constantin; Piefer, Gregory R.; Quintana, Eduardo; Ross, Ole; Rotty, Michel; Sabzian, Mohammad; Saey, Paul R.; Sameh, A. A.; Safari, M.; Schoppner, Michael; Siebert, Petra; Unger, Klaus K.; Vargas, Albert

2011-11-01T23:59:59.000Z

38

SRS - Programs - Liquid Waste Disposition  

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

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

39

Integrated Facilities Disposition Program  

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

Facilities Facilities Disposition Program Tank Waste Corporate Board Meeting at ORNL Sharon Robinson Dirk Van Hoesen Robert Jubin Brad Patton July 29, 2009 2 Managed by UT-Battelle for the U.S. Department of Energy The Integrated Facility Disposition Program (IFDP) addresses the remaining EM Scope at both ORNL and Y-12 Cost Range: $7 - $14B Schedule: 26 Years 3 Managed by UT-Battelle for the U.S. Department of Energy Scope of work * Treatment and disposition of legacy materials and waste * D&D 327 (1.5 M ft 2 ) excess facilities generating >2 M yd 3 debris * Soil and groundwater remedial actions generating >1 M yd 3 soils * Facilities surveillance and maintenance * Reconfiguration of waste management facilities * Ongoing waste management operations * Project management

40

RFNC-VNIIEF Capabilities to Production High Pure Isotopes for Scientific and Medical Applications  

SciTech Connect (OSTI)

In the technical paper there is presented the information on the basic equipment and more than thirty-year experience of RFNC-VNIIEF activities in the sphere of producing highly enriched isotopes of actinide elements--thorium, uranium, neptunium, plutonium, americium and curium--for scientific researches and practical applications. Electromagnetic separator and radiochemical methods provide obtaining of superpure isotope samples for nuclear-physical radiometric and mass-spectrometric equipment, and also as tracers when analyzing environmental contamination. There are presented the structure of the laboratory occupied with these isotopes electromagnetic separation as well as the nomenclature and characteristics of the specimens supplied. There are stated science and engineering elaborations of technologies aimed at producing alpha-ray radiating radionuclides--thorium-229, thorium-228, actinium-225, radium-224--for the purpose of anti-cancer therapy using bismuth-212 and bismuth-213 produced by the specially developed generators. There are presented the basic directions of cooperation with other Russian Institutes in developing this promising line of conversion.

Vesnovskii, S. P.

2002-02-26T23:59:59.000Z

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


41

Assistant Manager for Waste Disposition  

Broader source: Energy.gov [DOE]

The incumbent of this position is responsible for providing overall leadership and direction for oversight of assigned contractor and Federal programs and activities associated with the disposition...

42

Major Risk Factors Integrated Facility Disposition Project -...  

Office of Environmental Management (EM)

Integrated Facility Disposition Project - Oak Ridge Major Risk Factors Integrated Facility Disposition Project - Oak Ridge Full Document and Summary Versions are available for...

43

EM Waste and Materials Disposition & Transportation | Department...  

Office of Environmental Management (EM)

EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

44

Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has made significant progress with regard to disposition planning for 174 metric tons (MTU) of surplus Highly Enriched Uranium (HEU). Approximately 55 MTU of this 174 MTU are ''offspec'' HEU. (''Off-spec'' signifies that the isotopic or chemical content of the material does not meet the American Society for Testing and Materials standards for commercial nuclear reactor fuel.) Approximately 33 of the 55 MTU have been allocated to off-spec commercial reactor fuel per an Interagency Agreement between DOE and the Tennessee Valley Authority (1). To determine disposition plans for the remaining {approx}22 MTU, the DOE National Nuclear Security Administration (NNSA) Office of Fissile Materials Disposition (OFMD) and the DOE Office of Environmental Management (EM) co-sponsored this technical study. This paper represents a synopsis of the formal technical report (NNSA/NN-0014). The {approx} 22 MTU of off-spec HEU inventory in this study were divided into two main groupings: one grouping with plutonium (Pu) contamination and one grouping without plutonium. This study identified and evaluated 26 potential paths for the disposition of this HEU using proven decision analysis tools. This selection process resulted in recommended and alternative disposition paths for each group of HEU. The evaluation and selection of these paths considered criteria such as technical maturity, programmatic issues, cost, schedule, and environment, safety and health compliance. The primary recommendations from the analysis are comprised of 7 different disposition paths. The study recommendations will serve as a technical basis for subsequent programmatic decisions as disposition of this HEU moves into the implementation phase.

Bridges, D. N.; Boeke, S. G.; Tousley, D. R.; Bickford, W.; Goergen, C.; Williams, W.; Hassler, M.; Nelson, T.; Keck, R.; Arbital, J.

2002-02-27T23:59:59.000Z

45

unstable isotope  

Science Journals Connector (OSTI)

unstable isotope, radioisotope ? unstabiles Isotop n, nichtstabiles Isotop, radioaktives Isotop, Radioisotop

2014-08-01T23:59:59.000Z

46

Isotope production facility produces cancer-fighting actinium  

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

Cancer therapy gets a boost from new isotope Isotope production facility produces cancer-fighting actinium A new medical isotope project shows promise for rapidly producing major...

47

Disposition options for {sup 233}U  

SciTech Connect (OSTI)

The United States is implementing a program to dispose of excess nuclear-weapons-usable materials--including {sup 233}U. A series of studies have identified multiple {sup 233}U disposition options, and these options are described herein. Most of the options involve adding depleted uranium containing {sup 238}U to the {sup 233}U. Converting the {sup 233}U into a mixture of <12 wt % {sup 233}U in {sup 238}U converts the weapons-usable {sup 233}U into nonweapons-usable {sup 233}U. For {sup 233}U that is considered waste, further isotopic dilution to <0.66 wt % {sup 233}U in {sup 238}U minimizes potential long-term repository criticality concerns and in many cases minimizes final waste volumes.

Forsberg, C.W.; Icenhour, A.S.; Krichinsky, A.M.

1998-04-27T23:59:59.000Z

48

disposition. prices | OpenEI  

Open Energy Info (EERE)

disposition. prices disposition. prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is Table 15, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO coal coal supply disposition. prices EIA Data application/vnd.ms-excel icon AEO2011: Coal Supply, Disposition, and Prices- Reference Case (xls, 91.7 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

49

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

RS-Weapons X-Rays REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY...

50

Facility Disposition Safety Strategy RM | Department of Energy  

Office of Environmental Management (EM)

Facility Disposition Safety Strategy RM Facility Disposition Safety Strategy RM The Facility Disposition Safety Strategy (FDSS) Review Module is a tool that assists DOE federal...

51

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Request For Records Disposition Autnority Records Dispostion-Coal Distribution Data...

52

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

Request for Records Disposition Authority REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications Request For Records Disposition Authority Request For Records...

53

Request For Records Disposition Authority | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Authority Request For Records Disposition Authority National Archives Pacific Southwest Region Request For Records Disposition Authority More...

54

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

LEAVE BLANK (NARA use only) LEAVE BLANK (NARA use only) JOB NUMBER To: NATIONAL ARCHIVES & RECORDS ADMINISTRATION 8601 ADELPHI ROAD, COLLEGE PARK, MD 20740-6001 Date Received 1. FROM (Agency or establishment) NOTIFICATION TO AGENCY In accordance with the provisions of 44 U.S.C 3303a, the disposition request, including amendments is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. 2. MAJOR SUB DIVISION 3. MINOR SUBDIVISION 4. NAME OF PERSON WITH WHOM TO CONFER 5. TELEPHONE DATE ARCHIVIST OF THE UNITED STATES 6. AGENCY CERTIFICATION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposition of its records and that the records proposed for disposal on the attached______page(s) are not needed now for the business of this agency or will not be

55

Depleted uranium disposition study -- Supplement, Revision 1  

SciTech Connect (OSTI)

The Department of Energy Office of Weapons and Materials Planning has requested a supplemental study to update the recent Depleted Uranium Disposition report. This supplemental study addresses new disposition alternatives and changes in status.

Becker, G.W.

1993-11-01T23:59:59.000Z

56

Fissile Materials Disposition | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Fissile Materials Disposition | National Nuclear Security Administration Fissile Materials Disposition | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Fissile Materials Disposition Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition Fissile Materials Disposition Since the end of the Cold War, significant quantities of plutonium and

57

Plutonium Disposition Program | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

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

58

Facility Disposition Safety Strategy RM  

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

Facility Disposition Safety Strategy Review Module Facility Disposition Safety Strategy Review Module March 2010 CD-0 O 0 OFFICE OF Facilit C CD-1 F ENVIRO Standard R ty Dispos Rev Critical Decis CD-2 M ONMENTAL Review Plan sition Saf view Module sion (CD) Ap CD March 2010 L MANAGE n (SRP) fety Strat e pplicability D-3 EMENT tegy CD-4 Post Ope eration Standard Review Plan, 2 nd Edition, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of Environmental Management (EM) projects are identified early and addressed proactively. The internal EM project review process encompasses key milestones established by DOE O 413.3A, Change 1, Program and Project Management for the Acquisition of Capital Assets, DOE-STD-1189-2008,

59

Savannah River Site Waste Disposition Project  

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

Terrel J. Spears Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste Disposition Project 2 Waste Disposition Project - Mission Radioactive Liquid Waste - Tank Waste Stabilization and Disposition - Disposition 36 million gallons of radioactive liquid waste - Close 49 underground storage tanks in which the waste now resides 3 36.7 Million 33.7 Mgal (92%) 3.0 Mgal (8%) Saltcake Sludge Salt Supernate Volume Curies 397 Million Curies (MCi) 212 MCi (54%) 185 MCi (46%) Gallons (Mgal) 36.5 Million 33.5 Mgal (92%) 3.0 Mgal (8%) Liquid Waste Background Liquid Waste Background * 2 tanks closed * 49 tanks remaining to close - aging, carbon steel - 27 compliant, 22 non-compliant - 12 have known leak sites

60

Summary - Major Risk Factors Integrated Facility Disposition...  

Office of Environmental Management (EM)

& ORNL, Oak Ridge, TN EM Project: Integrated Facility Disposition Project (IFDP) ETR Report Date: August 2008 ETR-15 United States Department of Energy Office of Environmental...

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


61

Plutonium Disposition Program | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

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

62

Used Fuel Disposition Campaign Preliminary Quality Assurance...  

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

Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to...

63

Weapons Dismantlement and Disposition NNSS Capabilities  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has tasked the WDD working group to disposition the large inventory of legacy classified weapon components scattered across the complex.

Pat Arnold

2011-12-01T23:59:59.000Z

64

DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM...  

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

authorities which are under the moratorium on the destruction of health related records as of March 2008. DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM...

65

Storage and Disposition of Weapons-Usable Fissile Materials  

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

86 86 Federal Register / Vol. 63, No. 156 / Thursday, August 13, 1998 / Notices 1 SRS has been identified by DOE as the preferred site for the immobilization disposition facility. responsibilities are to (1) evaluate the standards of accreditation applied to applicant foreign medical schools; and (2) determine the comparability of those standards to standards for accreditation applied to United States medical schools. For Further Information Contact: Bonnie LeBold, Executive Director, National Committee on Foreign Medical Education and Accreditation, 7th and D Streets, S.W., Room 3082, ROB #3, Washington, D.C. 20202-7563. Telephone: (202) 260-3636. Beginning September 28, 1998, you may call to obtain the identity of the countries whose standards are to be evaluated during this

66

Request For Records Disposition Authority | Department of Energy  

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

Records Schedule Contractor Checks Request For Records Disposition Authority More Documents & Publications DOE-STD-4001-2000 DOE Records Disposition Schedule Changes Audit Letter...

67

Request For Records Disposition Authority | Department of Energy  

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

Fossil Energy Equity Re-determination Records Request For Records Disposition Authority More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Inspection Report:...

68

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

Pacific Northwest Lab: Richland Operations Office REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Request For...

69

PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES...  

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

PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) This document lists the...

70

Nuclear Materials Disposition | Department of Energy  

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

Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Spent Nuclear Fuel Spent nuclear fuel (SNF) is fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing. SNF may include: (1) intact, non-defective fuel assemblies or fuel rods; (2) failed fuel assemblies or fuel rods; (3) segments of fuel rods or pieces of fuel derived from spent fuel rods; and

71

I REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY LEAVE BL ...A (NARA use only1 JOB NUMBER TO: NATIONAL ARCHIVES & RECORDS ADMINISTRATION In accordance with the provisions of 44 U.S.C. 3303a, the Office of the Chief Information Officer disposition request, including amendments, is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. Records Management Division N1-434-02-2 Date received 860 1 ADELPHI ROAD COLLEGE PARK, MD 20740-600 1 1. FROM (Agency or establishment) Department of Energy , ( / I 4 30 -A&&& NOTIFICATION TO AGENCY 6. AGENCY CERTIFICATION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposition of its records and that the

72

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

1nstrlrcrlons on reverts) 1nstrlrcrlons on reverts) ' 0 NATIONAL ARCMVES and RECORDS AD~~INISTRAT~ON (NIR) WASHINGTON, DC 20408 1. FROM (Agency or estabi~shment) Department of Energy Washington, DC 20585 . '2. MAJOR SUBDIVISION fn lccordance w i l h the provirions o f 4 4 DOE~NEVADA OPERATIONS OFFICE U.S.C. 3 3 0 3 r the disposition r e q u c ~ t , including rmtndments, i s approvtd n c t p l 3. MINOR SUBOlVlStON lor ilemr that mky be mrrkcd 'dir wition not approved' o r withdmwn' in c&mn lo. '4. NAME O F PERSON WITH WHOM TO CONFER 5. TELEPHONE Mary Ann Wallace -301 903 4353 6. AGENCY CERTIFICATION I hereby certify that I am authorized to a d for this to th#disposit-ion of its records and that the records roposed for disposal on the P now needed for the business of this agency or wil not be needed after the concurrence f

73

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

m m - REQUEST FOR RECORDS DISPOSITION AUTHORITY (See Instructions on reverse) GENERAL SERVICES ADMINISTRATION N A T I O N A L ARCHIVES AND RECORDS SERVICE, WASHINGTON, DC 20408 1. F R O M ( A g e n c y o r e s t a b l i s h m e n t ) jepartment of Energy 2. MAJOR S U B D I V I S I O N Oak Ridse Operations Office 3. M I N O R S U B D I V I S I O N 4 . N A M E O F PERSON W I T H W H O M T O C O N F E R ( 5 . T E L E P H O N E E X T . L E A V E B L A N K - JOB N O . d/-d33P PO- ZJ - - - - p p D A T E R E C E I V E D p - NOTIFICATION TO AGENCY In accordance with the provisions of 44 U.S.C. 3303a the disposal request, including amendments, is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. If no records are proposed for disposal, the signature of the Archivist is not required. - DATE ARCHIVIST

74

EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement  

Broader source: Energy.gov [DOE]

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

75

Used Fuel Disposition Campaign Disposal  

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

Campaign Disposal Research and Development Roadmap Prepared for U.S. Department of Energy Used Fuel Disposition Campaign September 2012 FCR&D-USED-2011-000065 REV 1 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or

76

Waste Disposition Update by Christine Gelles  

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

Waste Disposition Update Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o Waste Stream Highlights o DOE Transportation Update o Greater Than Class C (GTCC) Low Level Waste Environmental Impact Statement o Blue Ribbon Commission on America's Nuclear Future o Nuclear Regulatory Commission's LLW Regulatory Initiatives Discussion Topics www.em.doe.gov 3 Waste Stream Highlights www.em.doe.gov 4 o Within current budget outlook, it is especially critical that EM ensures safe, reliable and cost effective disposition paths exist. o The program's refocused organization and the detailed

77

Excess plutonium disposition using ALWR technology  

SciTech Connect (OSTI)

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

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

1993-02-01T23:59:59.000Z

78

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

Instructions on reverse) Instructions on reverse) LEAVE BLANK - GENERAL SERVICES ADMINISTRATION NATIONAL ARCHIVES AND RECORDS SERVICE, WASHINGTON, DC 20408 I . F R O M (Agency or ertabluhmentJ D A T E RECEIVED NOTIF~CATION TO AGENCY Department of Energy 2. MAJ0.R S U B D I V I S I O N I 4 . N A M E O F PERSON W I T H W H O M T O CONFER 15. TELEPHONE E X T . \OATS l A R C H l V l S T O F T H E U N I T E D STATES In accordance with the provisions of 44 U.S.C. 3303 the dispoal request. including amendmentr, is approved . 3. M I N O R S U B D I V I S I O N except for items that may be marked "disposition not approved" or "withdrawn" in column 10. If no records are proposed for disposal, the signature of the Archivist is not required. I hereby certify that I am authorized to act for this agency in matters pertaining to the disposal of the agency's records;

79

Plutonium Disposition Program | National Nuclear Security Administration  

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

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

80

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

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

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

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


81

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

U. S. Atomic Energy Commision REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY DOE-HDBK-1109-97 DOE-HDBK-1109-97...

82

Surplus Highly Enriched Uranium Disposition Program plan  

SciTech Connect (OSTI)

The purpose of this document is to provide upper level guidance for the program that will downblend surplus highly enriched uranium for use as commercial nuclear reactor fuel or low-level radioactive waste. The intent of this document is to outline the overall mission and program objectives. The document is also intended to provide a general basis for integration of disposition efforts among all applicable sites. This plan provides background information, establishes the scope of disposition activities, provides an approach to the mission and objectives, identifies programmatic assumptions, defines major roles, provides summary level schedules and milestones, and addresses budget requirements.

NONE

1996-10-01T23:59:59.000Z

83

NorthStar Medical Technologies LLC  

National Nuclear Security Administration (NNSA)

Environmental Assessment for Environmental Assessment for NorthStar Medical Technologies LLC Commercial Domestic Production of the Medical Isotope Molybdenum-99 (DOE/EA-1929) Prepared for U.S. Department of Energy National Nuclear Security Administration Defense Nuclear Nonproliferation/ Global Threat Reduction Initiative August 2012 EA for NorthStar Medical Technologies LLC Commercial Domestic Production of the Medical Isotope Mo-99 i COVER SHEET ENVIRONMENTAL ASSESSMENT FOR NORTHSTAR MEDICAL TECHNOLOGIES LLC COMMERCIAL DOMESTIC PRODUCTION OF THE MEDICAL ISOTOPE MOLYBDENUM-99 Proposed Action: The Department of Energy (DOE) National Nuclear Security Administration (NNSA) proposes to provide funding to NorthStar to accelerate the establishment of the commercial production of

84

Disposition of Surplus Highly Enriched Uranium  

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

EIS-0240-S EIS-0240-S For Further Information Contact: U.S. Departmel>t of Energy Office of Fissile Materials Disposition, 1000 Independence Ave., SW, Washington, D.C. 20585 . This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices, Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: Office of Fissile Materials Disposition, MD-4 Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 @ Printed with soy ink on recycled paper. .__- -. @ .: Depafimmt of Energy . i i~t " Wastin@on, DC 20585 June 1996 Dear hterested

85

Disposition of Surplus Highly Enriched Uranium  

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

@ @ Printed with soy ink on recycled paper. ,, ,, This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors horn the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices, Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: Office of Fissile Materials Disposition, MD-4 ' Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 Department of Energy Washington, DC 20585 June 1996 Dear hterested Party: The Disposition of Surplus Highly Enriched Uranium Final Environmental Impact Statemnt is enclosed for your information. This document has been prepared in accordance

86

Disposition of Surplus Highly Enriched Uranium  

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

. . ------- .--- --. ---- DOE/EIS-0240 I United States Department of Energy I For Further Information Contact: U.S. Department of Energy Otice of Fissile Materials Disposition, 1000 Independence Ave., SW, Washington, D.C. 20585 1 I ---- I I . I I I I This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices. Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: I Office of Fissile Materials Disposition, MD-4 Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 , @ Printed with soy ink on recycled paper. -_. - COVERS~ET

87

The ultimate disposition of depleted uranium  

SciTech Connect (OSTI)

Depleted uranium (DU) is produced as a by-product of the uranium enrichment process. Over 340,000 MTU of DU in the form of UF{sub 6} have been accumulated at the US government gaseous diffusion plants and the stockpile continues to grow. An overview of issues and objectives associated with the inventory management and the ultimate disposition of this material is presented.

Lemons, T.R. [Uranium Enrichment Organization, Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

88

SRS - Programs - H Area Nuclear Materials Disposition  

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

H Area Nuclear Materials Disposition H Area Nuclear Materials Disposition The primary mission of the H-Canyon Complex is to dissolve, purify and blend-down surplus highly enriched uranium (HEU) and aluminum-clad foreign and domestic research reactor fuel to produce a low enriched uranium (LEU) solution suitable for conversion to commercial reactor fuel. A secondary mission for H-Canyon is to dissolve excess plutonium (Pu) not suitable for MOX and transfer it for vitrification in the Defense Waste Processing Facility at SRS. H Canyon was constructed in the early 1950s and began operations in 1955. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains the process vessels. It is approximately 1,000 feet long with several levels to accommodate the various stages of material stabilization, including control rooms to monitor overall equipment and operating processes, equipment and piping gallery for solution transport, storage, and disposition, and unique overhead bridge cranes to support overall process operations. All work is remotely controlled, and employees are further protected from radiation by thick concrete walls.

89

Update of the Used Fuel Disposition Campaign Implementation Plan |  

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

Update of the Used Fuel Disposition Campaign Implementation Plan Update of the Used Fuel Disposition Campaign Implementation Plan Update of the Used Fuel Disposition Campaign Implementation Plan The Used Fuel Disposition Campaign will identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign supports achievement of the overarching Fuel Cycle Research and Development Program mission and objectives. Activities will be sufficiently flexible to accommodate any of the potential fuel cycle options for used fuel management. Update of the Used Fuel Disposition Campaign Implementation Plan

90

Waste and Materials Disposition Information | Department of Energy  

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

Waste and Materials Disposition Waste and Materials Disposition Information Waste and Materials Disposition Information Waste and Materials Disposition Information As the Office of Environmental Management (EM) fulfills its mission, waste and materials disposition plays a vital role in the cleanup of radioactive waste and the environmental legacy of nuclear weapons production and nuclear energy research. Disposal of waste frequently falls on the critical path of cleanup projects. Significant planning resources are spent to identify alternatives and find a path that is cost-effective and in the best interest of the Federal government. In many instances, waste disposition, (processing, treatment and disposal) is part of cleanup agreements and is of interest to stakeholders and requires the oversight of regulators.

91

Request For Records Disposition Authority: Strategic Petroleum Reserve  

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

Request For Records Disposition Authority: Strategic Petroleum Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Paper case files pertaining to environmental permit applications, permits and related correspondence as well as NEPA correspondence within of the Strategic Petroleum Reserve Project Management Office (SPRPMO) Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office More Documents & Publications 2012 Annual Planning Summary for Fossil Energy, National Energy Technology Laboratory, RMOTC, and Strategic Petroleum Reserve Field Office CX-002673: Categorical Exclusion Determination CX-009794: Categorical Exclusion Determination

92

Request For Records Disposition Authority-Nuclear Weapons | Department...  

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

For Records Disposition Authority-Nuclear Weapons This document identifies the nuclear weapon records generated by the Department of Energy's (DOE) Nuclear Weapons Complex Request...

93

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

Nuclear Power Plant Docket Records REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications PIA - Savannah River Remediation Accreditation Boundary (SRR AB) REQUEST...

94

Request For Records Disposition Autnority | Department of Energy  

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

Autnority Request For Records Disposition Autnority Published Posters. Posters depicting Department of Energy facilities, research projects, security awareness themes, and related...

95

Used Fuel Disposition Campaign Phase I Ring Compression Testing...  

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

Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign Phase I Ring Compression Testing of High Burnup Cladding The purpose of ring compression...

96

Major Risk Factors to the Integrated Facility Disposition Project  

Broader source: Energy.gov [DOE]

The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks atthe Oak Ridge Reservation (ORO).

97

Consent Order, Uranium Disposition Services, LLC- NCO-2010-01  

Broader source: Energy.gov [DOE]

Issued to Uranium Disposition Services, LLC related to Construction Deficiencies at the DUF6 Conversion Buildings at the Portsmouth and Paducah Gaseous Diffusion Plants

98

Office of UNF Disposition International Program - Strategic Plan |  

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

UNF Disposition International Program - Strategic Plan UNF Disposition International Program - Strategic Plan Office of UNF Disposition International Program - Strategic Plan The Department of Energy's Office of Nuclear Energy, Used Nuclear Fuel Disposition Research and Development Office (UFD), performs the critical mission of addressing the need for an integrated strategy that combines safe storage of spent nuclear fuel with expeditious progress toward siting and licensing a disposal facility or facilities. The UFD International Program plays a key role in this effort. International collaboration provides a forum for exchanging strategies, expertise, and technologies with other nations that have also been investigating solutions to the problems of nuclear waste disposal-information that otherwise would have

99

Isotope Analysis  

Science Journals Connector (OSTI)

Naturally occurring oxygen includes three stable isotopes,16O,17O, and18O, with the relative abundances of 99.763%, 0.0375%, and 0.1995%, respectively. Isotopic analysis does not consider the absolute abundances ...

Tandong Yao; Wusheng Yu; Huabiao Zhao…

2014-08-01T23:59:59.000Z

100

Medical Radioisotope | Nuclear Science | ORNL  

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

Medical Medical Radioisotope SHARE Medical Radioisotope Staff members preparing Ac-225 in glove boxes for shipment to hospitals to support radiotherapy cancer clinical trials in multiple locations around the world. ORNL's Medical Radioisotope Program is focused on the development of improved reactor production and processing methods to provide medical radioisotopes, the development of new radionuclide generator systems, the design and evaluation of new radiopharmaceuticals for applications in nuclear medicine and oncology, and association with Medical Cooperative Programs throughout the world for further preclinical testing and clinical evaluation of agents developed at ORNL. The collective resources of ORNL, including access to the enriched stable isotope inventory, a High Flux

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


101

Online Catalog of Isotope Products from DOE's National Isotope Development Center  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

The National Isotope Development Center (NIDC) interfaces with the User Community and manages the coordination of isotope production across the facilities and business operations involved in the production, sale, and distribution of isotopes. A virtual center, the NIDC is funded by the Isotope Development and Production for Research and Applications (IDPRA) subprogram of the Office of Nuclear Physics in the U.S. Department of Energy Office of Science. The Isotope subprogram supports the production, and the development of production techniques of radioactive and stable isotopes that are in short supply for research and applications. Isotopes are high-priority commodities of strategic importance for the Nation and are essential for energy, medical, and national security applications and for basic research; a goal of the program is to make critical isotopes more readily available to meet domestic U.S. needs. This subprogram is steward of the Isotope Production Facility (IPF) at Los Alamos National Laboratory (LANL), the Brookhaven Linear Isotope Producer (BLIP) facility at BNL, and hot cell facilities for processing isotopes at ORNL, BNL and LANL. The subprogram also coordinates and supports isotope production at a suite of university, national laboratory, and commercial accelerator and reactor facilities throughout the Nation to promote a reliable supply of domestic isotopes. The National Isotope Development Center (NIDC) at ORNL coordinates isotope production across the many facilities and manages the business operations of the sale and distribution of isotopes.

102

EM Waste and Materials Disposition & Transportation  

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

On Closure Success On Closure Success 1 EM Waste and Materials Disposition & Transportation National Transportation Stakeholders Forum Chicago, Illinois May 26, 2010 Frank Marcinowski Acting Chief Technical Officer and Deputy Assistant Secretary for Technical and Regulatory Support Office of Environmental Management DOE's Radioactive Waste Management Priorities * Continue to manage waste inventories in a safe and compliant manner * Address high risk waste in a cost- ff ti effective manner * Maintain and optimize current disposal capability for future generations * Develop future disposal capacity in a complex environment * Promote the development of treatment and disposal alternatives in the 2 and disposal alternatives in the

103

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final...  

Office of Environmental Management (EM)

: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition...

104

GENERATION OF RADIOXENON ISOTOPES  

SciTech Connect (OSTI)

With the continued population of the International Monitoring System (IMS) network and the certification of radioxenon laboratory systems it has become necessary to calibrate and test these systems using as many of the radioxenon isotopes as possible. Several very promising techniques have been explored recently that allow for convenient production of Xe-133, Xe-131m, the short-lived isotope Xe-135, and even the difficult to obtain Xe-133m. IMS national and international laboratories have traditionally obtained Xe-133 from medical isotope suppliers. The activity of these medical dose samples is extremely high (~ 740 MBq) and requires very careful fume hood work to dilute down to appropriate levels (~ 10 Bq). By waiting for 10 or more half-lives it is possible to reduce the handling regimen considerably, while also obtaining a strong Xe-131m signature due to its longer half-life (11.9 days). The short-lived isotope Xe-135 (9.14 hrs) and the longer lived parent nuclide Xe-133m (2.2 day half-life) are never present in these samples. To obtain these isotopes another source or technique is required. This paper will discuss the two techniques developed and implemented at Pacific Northwest National Lab (PNNL) and show the results obtained from each technique. The first is an in-house method that allows for on demand production of two of these isotopes, Xe-133 and Xe-135, using HEU and a modest flux neutron source. The second method uses a research reactor at the Pullman campus of Washington State University to produce Xe-133, Xe-133m and Xe-135.

McIntyre, Justin I.; Pratt, Sharon L.; Bowyer, Ted W.; Cooper, Matthew W.; Hayes, James C.; Heimbigner, Tom R.; Hubbard, Charles W.; Miley, Harry S.; Ripplinger, Mike D.

2008-09-23T23:59:59.000Z

105

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

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

Assessment of the Integrated Facility Disposition Project at Oak Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

106

EIS-0327: Disposition of Scrap Metals Programmatic EIS | Department of  

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

27: Disposition of Scrap Metals Programmatic EIS 27: Disposition of Scrap Metals Programmatic EIS EIS-0327: Disposition of Scrap Metals Programmatic EIS Summary This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download December 19, 2011 EA-1919: Notice of Revision to Clearance Policy Recycle of Scrap Metals Originating from Radiological Areas (December 2011) July 12, 2001 EIS-0327: Notice of Intent to Prepare a Programmatic Environmental Impact Statement and Announcement of Public Scoping Meetings Disposition of Scrap Metals

107

Properties and Dispositions: Some Metaphysical Remarks on Quantum Ontology  

Science Journals Connector (OSTI)

After some suggestions about how to clarify the confused metaphysical distinctions between dispositional and non?dispositional or categorical properties I review some of the main interpretations of QM in order to show that — with the relevant exception of Bohm’s minimalist interpretation — quantum ontology is irreducibly dispositional. Such an irreducible character of dispositions must be explained differently in different interpretations but the reducibility of the contextual properties in the case of Bohmian mechanics is guaranteed by the fact that the positions of particles play the role of the categorical basis a role that in other interpretations cannot be filled by anything else. In Bohr’s and Everett?type interpretations dispositionalism is instrumentalism in disguise.

Mauro Dorato

2006-01-01T23:59:59.000Z

108

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

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

the Integrated Facility Disposition Project at Oak the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

109

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

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

Used Fuel Disposition Campaign Preliminary Quality Assurance Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to accommodate the UFDC. The FCT QAPD provides a sound and useable foundation for the implementation of QA for UFDC R&D activities, including the application of QA in a graded approach. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan More Documents & Publications

110

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental  

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

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

111

Hight-Level Waste & Facilities Disposition  

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

High-Level Waste (HLW) and Facilities Disposition Final High-Level Waste (HLW) and Facilities Disposition Final Environmental Impact Statement You are here: DOE-ID Home > Environmental Management > Idaho High-Level Waste (HLW) Table of Contents Documents are in the Adobe® PDF format and require the Adobe® Reader to access them. If you do not currently have the Acrobat Reader, you can download the Free Adobe Reader at http://get.adobe.com/reader/ Icon link to Free Adobe Acrobat Reader software * Large chapters broken down into sections Summary* Cover [ Adobe Acrobat File Size 1.48 MB] Section, 1.0 [ Adobe Acrobat File Size 612 KB] Section, 2.0 [ Adobe Acrobat File Size 251 KB] Sections, 3.0 - 3.2.1a [ Adobe Acrobat File Size 1.4 MB] Section, 3.2.1b [ Adobe Acrobat File Size 2.0 MB] Sections, 3.2.2 - 4.0 [ Adobe Acrobat File Size 1.4 MB]

112

Carbon Isotopes  

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

Atmospheric Trace Gases » Carbon Isotopes Atmospheric Trace Gases » Carbon Isotopes Carbon Isotopes Gateway Pages to Isotopes Data Modern Records of Carbon and Oxygen Isotopes in Atmospheric Carbon Dioxide and Carbon-13 in Methane 800,000 Deuterium Record and Shorter Records of Various Isotopic Species from Ice Cores Carbon-13 13C in CO Measurements from Niwot Ridge, Colorado and Montana de Oro, California (Tyler) 13C in CO2 NOAA/CMDL Flask Network (White and Vaughn) CSIRO GASLAB Flask Network (Allison, Francey, and Krummel) CSIRO in situ measurements at Cape Grim, Tasmania (Francey and Allison) Scripps Institution of Oceanography (Keeling et al.) 13C in CH4 NOAA/CMDL Flask Network (Miller and White) Northern & Southern Hemisphere Sites (Quay and Stutsman) Northern & Southern Hemisphere Sites (Stevens)

113

HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY  

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

- - HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY (See ~nstructions on reverse) / GENERAL SERVICES ADMINISTRATION NATIONAL ARCHIVES AND RECORDS SERVICE, WASHINGTON, D C 20408 1 . F R O M (Agency orestablishment) U.S. Department of Energy 2 . MAJOR SUBDIVISION Oak Ridge Operations Office 3. M I N O R SUBDIVISION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposal of the agency's records; that the records proposed for disposal in this Request of 4 page(s) are not now needed for the business of this agency or will not be needed after the retention periods specified; and that written concurrence from the General Accounting Office, if required under the provisions of Title 8 of the GAO Manual for Guidance of Federal Agencies, is

114

REQUEST FOR RECORDS DISPOSITION AUTHORITY S  

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

S S e e Instructions o n reverse) NATIONAL ARCHIVES and RECORDS ADMINISTRATION (NIR) WASHINGTON. DC 20408 , - - 1. FROM (Agency or establishment) Department of Energy 2. MAJOR SUBDIVISION Assistant Secretary For Fossil Energy (FE-1) I 3. MINOR SUBDIVISION Office of Naval Petroleum and Shale Oil 4 . NAME OF PERSON WITH WHOM TO CON I 1 Jerry Hinkle (FE 47) 1(202)586-43 80 I I / 6. AGENCY CERTIFICATION I NOTIFICATION TO AGENCY i I In accordance with the provisions of 44 U.S.C. 3303a the disposition request, including amendments, is ap roved except for items that may be marke! "dis osition not approved" or "withdrawn" in c o L n 10. I hereby certify that I am authorized to act for this agency in yatters pertaining to of its records and that the records roposed for disposal on the attached

115

Neutron Assay System for Confinement Vessel Disposition  

SciTech Connect (OSTI)

Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the CVs. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of special nuclear material (SNM) in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le}100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-13T23:59:59.000Z

116

The ultimate disposition of depleted uranium  

SciTech Connect (OSTI)

Significant amounts of the depleted uranium (DU) created by past uranium enrichment activities have been sold, disposed of commercially, or utilized by defense programs. In recent years, however, the demand for DU has become quite small compared to quantities available, and within the US Department of Energy (DOE) there is concern for any risks and/or cost liabilities that might be associated with the ever-growing inventory of this material. As a result, Martin Marietta Energy Systems, Inc. (Energy Systems), was asked to review options and to develop a comprehensive plan for inventory management and the ultimate disposition of DU accumulated at the gaseous diffusion plants (GDPs). An Energy Systems task team, under the chairmanship of T. R. Lemons, was formed in late 1989 to provide advice and guidance for this task. This report reviews options and recommends actions and objectives in the management of working inventories of partially depleted feed (PDF) materials and for the ultimate disposition of fully depleted uranium (FDU). Actions that should be considered are as follows. (1) Inspect UF{sub 6} cylinders on a semiannual basis. (2) Upgrade cylinder maintenance and storage yards. (3) Convert FDU to U{sub 3}O{sub 8} for long-term storage or disposal. This will include provisions for partial recovery of costs to offset those associated with DU inventory management and the ultimate disposal of FDU. Another recommendation is to drop the term tails'' in favor of depleted uranium'' or DU'' because the tails'' label implies that it is waste.'' 13 refs.

Not Available

1990-12-01T23:59:59.000Z

117

Niowave Develops Production Route for Medical Radioisotopes with...  

Office of Science (SC) Website

lack of a domestic supply and current use of techniques requiring weapons grade uranium led Congress to pass the American Medical Isotope Production Act in 2013. The Act...

118

Major Risk Factors to the Integrated Facility Disposition Project  

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

Oak Ridge Reservation Tennessee Major Risk Factors to the Integrated Facility Disposition Project (IFDP) Challenge The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). These include: environmental remediation, regulatory compliance, deactivation and decommissioning (D&D) activities, and disposition of legacy materials and waste, along with the ongoing modernization, reindustrialization, and reconfiguration initiatives at the Oak Ridge National Laboratory and at the Y-12 National Security Complex. The balancing of the broad nature of these activities and issues at ORO are a key challenge for the IFDP especially since their interrelationship is not always obvious.

119

Plutonium stabilization and disposition focus area, FY 1999 and FY 2000 multi-year program plan  

SciTech Connect (OSTI)

Consistent with the Environmental Management`s (EM`s) plan titled, ``Accelerating Cleanup: Paths to Closure``, and ongoing efforts within the Executive Branch and Congress, this Multi-Year Program Plan (MYPP) for the Plutonium Focus Area was written to ensure that technical gap projects are effectively managed and measured. The Plutonium Focus Area (PFA) defines and manages technology development programs that contribute to the effective stabilization of nuclear materials and their subsequent safe storage and final disposition. The scope of PFA activities includes the complete spectrum of plutonium materials, special isotopes, and other fissile materials. The PFA enables solutions to site-specific and complex-wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. The report describes the current technical activities, namely: Plutonium stabilization (9 studies); Highly enriched uranium stabilization (2 studies); Russian collaboration program (2 studies); Packaging and storage technologies (6 studies); and PFA management work package/product line (3 studies). Budget information for FY 1999 and FY 2000 is provided.

NONE

1998-03-01T23:59:59.000Z

120

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

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

DOE Seeks Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy March 23, 2012 - 12:00pm Addthis WASHINGTON, D.C. - The Energy Department's prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel. The EOI requests technical, financial, and product market information to review the feasibility of technologies capable of decontaminating the nickel to a level indistinguishable from what is commercially available, such that it could be safely recycled and reused. The EOI scope is for 6,400 tons of nickel to be recovered from the uranium enrichment process

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


121

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

122

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

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

Preliminary Quality Assurance Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to accommodate the UFDC. The FCT QAPD provides a sound and useable foundation for the implementation of QA for UFDC R&D activities, including the application of QA in a graded approach. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan More Documents & Publications Used Fuel Disposition Campaign International Activities Implementation Plan

123

AEO2011: Liquid Fuels Supply and Disposition | OpenEI  

Open Energy Info (EERE)

Liquid Fuels Supply and Disposition Liquid Fuels Supply and Disposition Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 11, and contains only the reference case. The dataset uses million barrels per day. The data is broken down into crude oil, other petroleum supply, other non petroleum supply and liquid fuel consumption. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA liquid fuels Supply Data application/vnd.ms-excel icon AEO2011: Liquid Fuels Supply and Disposition- Reference Case (xls, 117 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually

124

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

125

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

126

Low Level Waste Disposition - Quantity and Inventory | Department of  

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

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

127

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

128

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

Used Fuel Disposition Campaign Disposal Research and Development Used Fuel Disposition Campaign Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

129

Low Level Waste Disposition - Quantity and Inventory | Department of  

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

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

130

Integrated Tool Development for Used Fuel Disposition Natural System  

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

Integrated Tool Development for Used Fuel Disposition Natural Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions. Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report More Documents & Publications Natural System Evaluation and Tool Development FY11 Progress Report

131

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

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

Industry Input on Nickel Disposition Strategy Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy March 23, 2012 - 12:00pm Addthis WASHINGTON, D.C. - The Energy Department's prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel. The EOI requests technical, financial, and product market information to review the feasibility of technologies capable of decontaminating the nickel to a level indistinguishable from what is commercially available, such that it could be safely recycled and reused. The EOI scope is for 6,400 tons of nickel to be recovered from the uranium enrichment process

132

Integrated Tool Development for Used Fuel Disposition Natural System  

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

Integrated Tool Development for Used Fuel Disposition Natural Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions. Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report More Documents & Publications Natural System Evaluation and Tool Development FY11 Progress Report

133

AEO2011: Coal Supply, Disposition, and Prices | OpenEI  

Open Energy Info (EERE)

Supply, Disposition, and Prices Supply, Disposition, and Prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is Table 15, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO coal coal supply disposition. prices EIA Data application/vnd.ms-excel icon AEO2011: Coal Supply, Disposition, and Prices- Reference Case (xls, 91.7 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

134

EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing...  

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

Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing U.S.-Origin...

135

Americium/Curium Disposition Life Cycle Planning Study  

SciTech Connect (OSTI)

At the request of the Department of Energy Savannah River Office (DOE- SR), Westinghouse Savannah River Company (WSRC) evaluated concepts to complete disposition of Americium and Curium (Am/Cm) bearing materials currently located at the Savannah River Site (SRS).

Jackson, W.N. [Westinghouse Savannah River Company, AIKEN, SC (United States); Krupa, J.; Stutts, P.; Nester, S.; Raimesch, R.

1998-04-30T23:59:59.000Z

136

EIS-0327: Disposition of Scrap Metals Programmatic EIS  

Broader source: Energy.gov [DOE]

This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS.

137

A Study of Cattle Disposition: Exploring QTL Associated with Temperament  

E-Print Network [OSTI]

In any production setting, cattle disposition (temperament) has a great impact on handling and performance. Thus, behavior can be economically important, yielding the rationale for study. Wegenhoft (2005) previously identified several quantitative...

Boldt, Clayton Ryan

2008-05-16T23:59:59.000Z

138

DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS  

SciTech Connect (OSTI)

The Kaiser-Hill Company, LLC has the responsibility for closure activities at the Rocky Flats Environmental Technology Site (RFETS). One of the challenges faced for closure is the disposition of radiologically contaminated gloveboxes. Evaluation of the disposition options for gloveboxes included a detailed analysis of available treatment capabilities, disposal facilities, and lifecycle costs. The Kaiser-Hill Company, LLC followed several processes in determining how the gloveboxes would be managed for disposition. Currently, multiple disposition paths have been chosen to accommodate the needs of the varying styles and conditions of the gloveboxes, meet the needs of the decommissioning team, and to best manage lifecycle costs. Several challenges associated with developing a disposition path that addresses both the radiological and RCRA concerns as well as offering the most cost-effective solution were encountered. These challenges included meeting the radiological waste acceptance criteria of available disposal facilities, making a RCRA determination, evaluating treatment options and costs, addressing void requirements associated with disposal, and identifying packaging and transportation options. The varying disposal facility requirements affected disposition choices. Facility conditions that impacted decisions included radiological and chemical waste acceptance criteria, physical requirements, and measurement for payment options. The facility requirements also impacted onsite activities including management strategies, decontamination activities, and life-cycle cost.

Lobdell, D.; Geimer, R.; Larsen, P.; Loveland, K.

2003-02-27T23:59:59.000Z

139

Medical Ethics  

Science Journals Connector (OSTI)

Medical ethics is a discipline that evaluates the risks and merits of medical activities such as medical research and the delivery of medical services with regard to the protection of the interests of the pati...

2008-01-01T23:59:59.000Z

140

TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION  

SciTech Connect (OSTI)

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

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

2013-07-16T23:59:59.000Z

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


141

from Isotope Production Facility  

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

Cancer-fighting treatment gets boost from Isotope Production Facility April 13, 2012 Isotope Production Facility produces cancer-fighting actinium 2:32 Isotope cancer treatment...

142

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect (OSTI)

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S. (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated. (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass. (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Carter, J.

2011-01-03T23:59:59.000Z

143

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect (OSTI)

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S; (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass; and (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Jones, R.; Carter, J.

2010-10-13T23:59:59.000Z

144

Isotope studies in photosynthesis  

Science Journals Connector (OSTI)

Isotope studies in photosynthesis ... Examines the use of isotopic oxygen, hydrogen, carbon, and phosphorus in the study of photosynthesis. ...

J. A. Bassham; A. A. Benson; Melvin Calvin

1953-01-01T23:59:59.000Z

145

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

146

EA-1290: Disposition of Russian Federation Titled Natural Uranium |  

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

290: Disposition of Russian Federation Titled Natural Uranium 290: Disposition of Russian Federation Titled Natural Uranium EA-1290: Disposition of Russian Federation Titled Natural Uranium SUMMARY This EA evaluates the potential environmental impacts of a proposal to transport up to an average of 9,000 metric tons per year of natural uranium as uranium hexafluoride (UF6) from the United States to the Russian Federation. This amount of uranium is equivalent to 13,3000 metric tons of UF6. The EA also examines the impacts of this action on the global commons. Transfer of natural UF6 to the Russian Federation is part of a joint U.S./Russian program to dispose of highly enriched uranium (HEU) from dismantled Russian nuclear weapons. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD

147

EA-1599: Disposition of Radioactively Contaminated Nickel Located at the  

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

99: Disposition of Radioactively Contaminated Nickel Located 99: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications Summary This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold. Public Comment Opportunities No public comment opportunities at this time.

148

Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 |  

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

Savannah River Site Achieves Transuranic Waste Disposition Goal in Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 December 24, 2013 - 12:00pm Addthis Workers gather behind a “Safety and Security begins with Me” banner at the Savannah River Site. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. SRR employees Glenn Kelly and Fred Merriweather pour the final amount of grout into Tank 6. SRR employees Glenn Kelly and Fred Merriweather pour the final amount of grout into Tank 6. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site.

149

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

150

Used Fuel Disposition Research & Development | Department of Energy  

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

Used Fuel Disposition Used Fuel Disposition Research & Development Used Fuel Disposition Research & Development A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. In order to assure the development of a sustainable nuclear fuel cycle for the nation's energy future, to provide a sound technical basis for implementation of a new national policy for managing the back end of the nuclear fuel cycle, and to better understand, assess, and communicate the

151

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and  

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

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium The U.S. Department of Energy (DOE) owns and manages an inventory of depleted uranium (DU), natural uranium (NU), and low-enriched uranium (LEU) that is currently stored in large cylinders as depleted uranium hexafluoride (DUF6), natural uranium hexafluoride (NUF6), and low-enriched uranium hexafluoride (LEUF6) at the DOE Paducah site in western Kentucky (DOE Paducah) and the DOE Portsmouth site near Piketon in south-central Ohio (DOE Portsmouth)1. This inventory exceeds DOE's current and projected energy and defense program needs. On March 11, 2008, the Secretary of Energy issued a policy statement (the

152

Paducah Demolition Debris Shipped for Disposition | Department of Energy  

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

Demolition Debris Shipped for Disposition Demolition Debris Shipped for Disposition Paducah Demolition Debris Shipped for Disposition August 27, 2013 - 12:00pm Addthis The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow. The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow.

153

Fissile material disposition program final immobilization form assessment and recommendation  

SciTech Connect (OSTI)

Lawrence Livermore National Laboratory (LLNL), in its role as the lead laboratory for the development of plutonium immobilization technologies for the Department of Energy`s Office of Fissile Materials Disposition (MD), has been requested by MD to recommend an immobilization technology for the disposition of surplus weapons- usable plutonium. The recommendation and supporting documentation was requested to be provided by September 1, 1997. This report addresses the choice between glass and ceramic technologies for immobilizing plutonium using the can-in-canister approach. Its purpose is to provide a comparative evaluation of the two candidate technologies and to recommend a form based on technical considerations.

Cochran, S.G.; Dunlop, W.H.; Edmunds, T.A.; MacLean, L.M.; Gould, T.H. [Westinghouse Savannah River Co., Aiken, SC (United States)

1997-10-03T23:59:59.000Z

154

DOE-STD-3028-2000 | Department of Energy  

Office of Environmental Management (EM)

Assessment EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory,...

155

NEPA Cases Filed in 2010 2010 NEPA Case Dispositions  

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

Filed in 2010 2010 NEPA Case Dispositions Filed in 2010 2010 NEPA Case Dispositions Lead Defendant Cases Filed Injunctions - Remands Judgment for defendant 46 ARMY-USACE 6 3 Dismissal w/o settlement 11 DHS-USCG 0 0 Settlement 8 DOD 1 0 Adverse dispositions: 17 DOE-Energy 0 0 TRO 0 DOE-FERC 0 0 Preliminary Injunction 5 DOE-NNSA 1 0 Permanent Injunction 4 DOI-BIA 1 0 Remand 8 DOI-BLM 17 5 DOI-BOEM 5 0 Basis for 2010 NEPA Dispositions DOI-BOR 0 0 Jurisdictional - P prevailed 0 DOI-FWS 6 1 Jurisdictional - D prevailed 12 DOI-OSM 0 1 NEPA - Not required 1 DOI-NPS 2 2 NEPA - Is required 2 DOJ 0 0 CE - Adequate 4 DOS 0 0 CE - Not Adequate 1 DOT-FAA 3 0 EA - Adequate* 11 DOT-FHWA 10 1 EA - Not Adequate* 5 DOT-FTA 2 0 EIS - Adequate* 17 EPA 1 0 EIS - Not Adequate* 5

156

MINIMIZING WASTE AND COST IN DISPOSITION OF LEGACY RESIDUES  

SciTech Connect (OSTI)

Research is being conducted at the Los Alamos National Laboratory (LANL) which is directed toward development of a quantitative basis for disposition of actinide-bearing process residues (both legacy residues and residues generated from ongoing programmatic operations). This research is focused in two directions: (1) identifying minimum negative consequence (waste, dose, cost) dispositions working within regulatory safeguards termination criteria, and (2) evaluating logistics/consequences of across-the-board residue discards such as authorized at Rocky Flats under a safeguards termination variance. The first approach emphasizes Laboratory commitments to environmental stewardship, worker safety, and fiscal responsibility. This approach has been described as the Plutonium Disposition Methodology (PDM) in deference to direction provided by DOE Albuquerque. The second approach is born of the need to expedite removal of residues from storage for programmatic and reasons and residue storage safety concerns. Any disposition path selected must preserve the legal distinction between residues as Special Nuclear Material (SNM) and discardable materials as waste in order to insure the continuing viability of Laboratory plutonium processing facilities for national security operations.

J. BALKEY; M. ROBINSON

2001-05-01T23:59:59.000Z

157

EA-1929: NorthStar Medical Technologies LLC, Commercial Domestic Production  

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

9: NorthStar Medical Technologies LLC, Commercial Domestic 9: NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99 EA-1929: NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99 SUMMARY This EA evaluates the potential environmental impacts of a proposal to use federal funds to support and accelerate Northstar Medical Radioisotopes' project to develop domestic, commercial production capability for the medical isotope Molybdenum-99 without the use of highly enriched uranium. PUBLIC COMMENT OPPORTUNITIES None available this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 24, 2012 EA-1929: Finding of No Significant Impact NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99

158

EA-1929: NorthStar Medical Technologies LLC, Commercial Domestic Production  

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

29: NorthStar Medical Technologies LLC, Commercial Domestic 29: NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99 EA-1929: NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99 SUMMARY This EA evaluates the potential environmental impacts of a proposal to use federal funds to support and accelerate Northstar Medical Radioisotopes' project to develop domestic, commercial production capability for the medical isotope Molybdenum-99 without the use of highly enriched uranium. PUBLIC COMMENT OPPORTUNITIES None available this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 24, 2012 EA-1929: Finding of No Significant Impact NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99

159

Medical Data  

Science Journals Connector (OSTI)

Medical data describes the state of health of a ... and contains no personally identifiable information. Medical data are stored under a pseudonym, which is ... prevents unauthorized association of this inform...

2008-01-01T23:59:59.000Z

160

lead-isotope dating  

Science Journals Connector (OSTI)

lead-isotope dating, lead-lead dating, lead-isotope age measurement, lead-lead age measurement ? Blei-Isotopen(-Alters)bestimmung, f, Blei-Isotopen-Datierung

2014-08-01T23:59:59.000Z

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


161

isotopic ratio | EMSL  

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

isotopic ratio isotopic ratio Leads No leads are available at this time. Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. Abstract: As a candidate...

162

Used Fuel Disposition Campaign Disposal Research and Development Roadmap  

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

Disposal Research and Development Disposal Research and Development Roadmap Rev. 01 Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01 The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW) generated by existing and future nuclear fuel cycles. The disposal of SNF and HLW in a range of geologic media has been investigated internationally. Considerable progress has been made in the U.S and other nations, but gaps in knowledge still exist. This document provides an evaluation and prioritization of R&D opportunities

163

Used Fuel Disposition Campaign International Activities Implementation Plan  

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

International Activities International Activities Implementation Plan Used Fuel Disposition Campaign International Activities Implementation Plan The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through

164

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

Disposal Research and Development Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

165

Microsoft PowerPoint - REVWaste_Disposition_Update.061411.pptx  

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

Materials and Disposition Update Materials and Disposition Update Environmental Management Site-Specific www.em.doe.gov 1 Environmental Management Site-Specific Advisory Board Chairs' Meeting June 15, 2011 Shirley J. Olinger EM Associate Principal Deputy for Corporate Operations DOE's Waste Management Priorities Continue to manage waste inventories in a safe and compliant manner. Address high risk waste in a cost- effective manner. Maintain and optimize current disposal capability for future generations. www.em.doe.gov 2 Develop future disposal capacity in a complex environment. Promote the development of treatment and disposal alternatives in the commercial sector. Review current policies and directives and provide needed oversight. Completed Legacy TRU Sites Teledyne-Brown ARCO Energy Technology Engineering Center

166

Update of the Used Fuel Disposition Campaign Implementation Plan  

SciTech Connect (OSTI)

This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign (UFDC) supports achievement of the overarching mission and objectives of the Department of Energy Office of Nuclear Energy Fuel Cycle Technologies Program The implementation plan begins with the assumption of target dates that are set out in the January 2013 DOE Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-level-radioactive-waste). These target dates and goals are summarized in section III. This implementation plan will be maintained as a living document and will be updated as needed in response to progress in the Used Fuel Disposition Campaign and the Fuel Cycle Technologies Program.

Jens Birkholzer; Robert MacKinnon; Kevin McMahon; Sylvia Saltzstein; Ken Sorenson; Peter Swift

2014-09-01T23:59:59.000Z

167

Preliminary siting characterization Salt Disposition Facility - Site B  

SciTech Connect (OSTI)

A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ``Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data.

Wyatt, D.

2000-01-04T23:59:59.000Z

168

Accelerating the disposition of transuranic waste from LANL - 9495  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) was established during World War II with a single mission -- to design and build an atomic bomb. In the 65 years since, nuclear weapons physics, design and engineering have been the Laboratory's primary and sustaining mission. Experimental and process operations -- and associated cleanout and upgrade activities -- have generated a significant inventory of transuranic (TRU) waste that is stored at LANL's Technical Area 54, Material Disposal Area G (MDA G). When the Waste Isolation Pilot Plant (WIPP) opened its doors in 1999, LANL's TRU inventory totaled about 10,200 m{sup 3}, with a plutonium 239-equivalent curie (PE Ci) content of approximately 250,000 curies. By December 2008, a total of about 2,300 m3 (61,000 PE Ci) had been shipped to WIPP from LANL. This has resulted in a net reduction of about 1,000 m{sup 3} of TRU inventory over that time frame. This paper presents progress in dispositioning legacy and newly-generated transuranic waste (TRU) from ongoing missions at the LANL. The plans for, and lessons learned, in dispositioning several hundred high-activity TRU waste drums are reviewed. This waste population was one of the highest risks at LANL. Technical challenges in disposition of the high-activity drums are presented. These provide a preview of challenges to be addressed in dispositioning the remaining 6,800 m{sup 3} of TRU stored above ground and 2,400 m{sup 3} of TRU waste that is 'retrievably' stored below-grade. LANL is using subcontractors for much of this work and has formed a strong partnership with WIPP and its contractor to address this cleanup challenge.

Shepard, Mark D [Los Alamos National Laboratory; Stiger, Susan G [Los Alamos National Laboratory; Blankenhorn, James A [Los Alamos National Laboratory; Rael, George J [Los Alamos National Laboratory; Moody, David C [U.S DOE

2009-01-01T23:59:59.000Z

169

Management of Heavy Isotope in the DOE Complex  

SciTech Connect (OSTI)

Currently each Department Of Energy (DOE) Program office manages its own nuclear materials through activities such as production, processing, storage, transportation, and disposition. However, recognizing the need to strengthen its strategic approach to the integrated life-cycle management of nuclear materials, DOE established the Nuclear Materials Management Stewardship Initiative (NMMSI) in January 2000. The NMMSI's first visible product was the Integrated Nuclear Material Management Plan in which it was generally recommended that DOE take a cross-cutting look at managing its nuclear materials, and specifically recommended that four Nuclear Material Management Groups (NMMGs) be formed. These groups were established to facilitate management of nuclear materials for which DOE has or may have responsibility, including many presently not in DOE's direct control. One of these NMMGs, the Heavy Isotope Management Group (HIMG) was established at Oak Ridge National Laboratory in Dec ember 2000, to facilitate management of (a) actinide and their decay products (except sealed sources) and (b) isotopically enriched stable and radioactive isotopes except uranium and lithium, but excluding thorium, uranium, spent fuel, and weapons or reactor grade plutonium which are addressed by other NMMGs. Despite its short duration and relatively limited funding, the HIMG has facilitated the disposition of heavy isotopes from Lawrence Berkeley National Laboratory (LBNL), Rocky Flats Environmental Technology Site (RFETS), Pacific Northwest National Laboratory (PNNL), Oak Ridge National Laboratory (ORNL), Lawrence Livermore National Laboratory (LLNL), and Idaho National Engineering and Environmental Laboratory (INEEL). The primary disposition options have been to facilitate reuse of valuable heavy isotopes by matching custodians of unwanted materials with other users that seek such materials for new applications. This approach has the dual advantages of avoiding custodian disposal costs plus cost to the user of obtaining newly produced material. The HIMG has also prepared issue papers on neptunium and americium/curium that identify the resources, potential uses, and disposal pathways for the materials across the DOE Complex. In the future the HIMG expects to comprehensively identify the status of the U.S. heavy isotope inventory, prepare additional issue papers and plans charting the future of this inventory, and to facilitate execution of the plan.

Canon, R.; Croff, A.; Boyd, L.

2002-02-27T23:59:59.000Z

170

Isotope Science and Production  

E-Print Network [OSTI]

of Energy National Isotope Program http://www.nuclear.energy.gov/isotopes/nelsotopes2a.html Isotopes for Environmental Science Isotopes produced at Los Alamos National Laboratory are used as environmental tracers change and its effects. Los Alamos National Laboratory can produce Si-32 needed for oceanographic tracing

171

Stable isotope studies  

SciTech Connect (OSTI)

The research has been in four general areas: (1) correlation of isotope effects with molecular forces and molecular structures, (2) correlation of zero-point energy and its isotope effects with molecular structure and molecular forces, (3) vapor pressure isotope effects, and (4) fractionation of stable isotopes. 73 refs, 38 figs, 29 tabs.

Ishida, T.

1992-01-01T23:59:59.000Z

172

Cancer-fighting treatment gets boost from Isotope Production Facility  

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

Cancer-fighting treatment gets boost from Isotope Production Cancer-fighting treatment gets boost from Isotope Production Facility Cancer-fighting treatment gets boost from Isotope Production Facility New capability expands existing program, creates treatment product in quantity. April 13, 2012 Medical Isotope Work Moves Cancer Treatment Agent Forward Medical Isotope Work Moves Cancer Treatment Agent Forward - Los Alamos scientist Meiring Nortier holds a thorium foil test target for the proof-of-concept production experiments. Research indicates that it will be possible to match current annual, worldwide production of Ac-225 in just two to five days of operations using the accelerator at Los Alamos and analogous facilities at Brookhaven. Alpha particles are energetic enough to destroy cancer cells but are unlikely to move beyond a tightly controlled target region and destroy

173

Update to the Fissile Materials Disposition program SST/SGT transportation estimation  

SciTech Connect (OSTI)

This report is an update to ``Fissile Materials Disposition Program SST/SGT Transportation Estimation,'' SAND98-8244, June 1998. The Department of Energy Office of Fissile Materials Disposition requested this update as a basis for providing the public with an updated estimation of the number of transportation loads, load miles, and costs associated with the preferred alternative in the Surplus Plutonium Disposition Final Environmental Impact Statement (EIS).

John Didlake

1999-11-15T23:59:59.000Z

174

Microsoft Word - CX-MountainAvenueDispositionFY12_WEB.doc  

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

1, 2012 REPLY TO ATTN OF: KEPR-4 SUBJECT: Environmental Clearance Memorandum Joan Kendall Realty Specialist - TERR-3 Proposed Action: Disposition of Mountain Avenue Substation and...

175

EA-0942: Return of Isotope Capsules to the Waste Encapsulation and Storage  

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

42: Return of Isotope Capsules to the Waste Encapsulation and 42: Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington EA-0942: Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington SUMMARY This EA evaluates the environmental impacts of the proposal for the return of all leased cesium-137 and strontium-90 leased capsules to the U.S. Department of Energy's Waste Encapsulation and Storage Facility on the Hanford Site, to ensure safe management and storage, pending final disposition. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD May 11, 1994 EA-0942: Finding of No Significant Impact Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington

176

Isotopically pumped isotopic CF4 laser  

Science Journals Connector (OSTI)

Single-mode optical pumping of CF4 to generate 16-µm frequencies has been extended to include the isotopic species 12CF4,...

Eckhardt, Roger; Telle, John; Haynes, Larry

1982-01-01T23:59:59.000Z

177

Disposition of excess highly enriched uranium status and update  

SciTech Connect (OSTI)

This paper presents the status of the US DOE program charged with the disposition of excess highly enriched uranium (HEU). Approximately 174 metric tonnes of HEU, with varying assays above 20 percent, has been declared excess from US nuclear weapons. A progress report on the identification and characterization of specific batches of excess HEU is provided, and plans for processing it into commercial nuclear fuel or low-level radioactive waste are described. The resultant quantities of low enriched fuel material expected from processing are given, as well as the estimated schedule for introducing the material into the commercial reactor fuel market. 2 figs., 3 tabs.

Williams, C.K. III; Arbital, J.G.

1997-09-01T23:59:59.000Z

178

Sound propagation in urban areas: A periodic disposition of buildings  

Science Journals Connector (OSTI)

A numerical simulation of background noise propagation is performed for a network of hexagonal buildings. The obtained results suggest that the prediction of background noise in urban spaces is possible by means of a modified diffusion equation using two parameters: the diffusion coefficient that expresses the spreading out of noise resulting from diffuse scattering and multiple reflections by buildings, and an attenuation term accounting for the wall absorption, atmospheric attenuation, and absorption by the open top. The dependence of the diffusion coefficient with geometrical shapes and the diffusive nature of the buildings are investigated in the case of a periodic disposition of hexagonal buildings.

J. Picaut; J. Hardy; L. Simon

1999-10-01T23:59:59.000Z

179

Abstract 4241: Preclinical studies of brain/brain tumor disposition and antitumor efficacy of the aromatase inhibitor letrozole  

Science Journals Connector (OSTI)

...San Diego, CA Abstract 4241: Preclinical studies of brain/brain tumor disposition and antitumor efficacy of the aromatase...target for the treatment of CNS malignancies, as well as brain disposition and anti-tumor efficacy of letrozole, an...

Nimita Dave; Pankaj B. Desai; Gary A. Gudelsky; Kathleen LaSance; Lionel M.L. Chow; Xiaoyang Qi

2014-10-01T23:59:59.000Z

180

Implementation Guide for Surveillance and Maintenance during Facility Transition and Disposition  

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

As DOE facilities complete mission operations and are declared excess, they pass into a transition phase that ultimately prepares them for disposition. The disposition phase of a facility's life cycle usually includes deactivation, decommissioning, and surveillance and maintenance (S&M) activities.

1999-09-29T23:59:59.000Z

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


181

Fisetin disposition and metabolism in mice: Identification of geraldol as an active metabolite  

E-Print Network [OSTI]

1 Fisetin disposition and metabolism in mice: Identification of geraldol as an active metabolite title: Fisetin disposition and metabolism in mice ** Corresponding author: Dr. Guy G. Chabot, Chemical-yl)-3,5-diphenyltetrazolium; PBS, phosphate buffered saline. Keywords: flavonoid, fisetin

Paris-Sud XI, Université de

182

Isotope Geothermometry | Open Energy Information  

Open Energy Info (EERE)

Isotope Geothermometry Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Isotope Geothermometry Details Activities (0) Areas (0) Regions (0)...

183

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final  

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

Idaho High-Level Waste and Facilities Disposition Final Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, DOE/EIS-0287 (September 2002)

184

EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials |  

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

29: Storage and Disposition of Weapons-Usable Fissile 29: Storage and Disposition of Weapons-Usable Fissile Materials EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials Summary The EIS will evaluate the reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. Public Comment Opportunities None available at this time. Documents Available For Download September 5, 2007 EIS-0229: Supplement Analysis (September 2007) Storage of Surplus Plutonium Materials at the Savannah River Site November 14, 2003 EIS-0229: Record of Decision (November 2003) Storage and Disposition of Weapons-Usable Fissile Materials November 7, 2003 EIS-0229-SA-03: Supplement Analysis Fabrication of Mixed Oxide Fuel Lead Assemblies in Europe

185

EIS-0287: Idaho High-Level Waste & Facilities Disposition | Department of  

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

7: Idaho High-Level Waste & Facilities Disposition 7: Idaho High-Level Waste & Facilities Disposition EIS-0287: Idaho High-Level Waste & Facilities Disposition SUMMARY This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD January 12, 2010 EIS-0287: Amended Record of Decision Idaho High-Level Waste and Facilities Disposition January 4, 2010

186

Consent Order, Uranium Disposition Services, LLC - NCO-2010-01 | Department  

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

Uranium Disposition Services, LLC - NCO-2010-01 Uranium Disposition Services, LLC - NCO-2010-01 Consent Order, Uranium Disposition Services, LLC - NCO-2010-01 March 26, 2010 Consent Order issued to Uranium Disposition Services, LLC related to Construction Deficiencies at the DUF6 Conversion Buildings at the Portsmouth and Paducah Gaseous Diffusion Plants The Office of Health, Safety and Security's Office of Enforcement has completed its investigation into the facts and circumstances associated with construction deficiencies at the DUF6 Conversion Buildings located at the Portsmouth and Paducah Gaseous Diffusion Plants. The investigation reports, dated January 22, 2009, and April 23, 2009, were provided to Uranium Disposition Services, LLC (DDS), and addressed specific areas of potential noncompliance with DOE nuclear safety requirements established in

187

THE ISOTOPES OF AMERICIUM  

E-Print Network [OSTI]

spectrographic analysis of the americium samples. It is a48 J'---_I" THE ISOTOPES OF AMERICIUM K. Street, Jr. , A.Elements THE ISOTOPES OF AMERICIUM K. Street, Jr. , A.

Street, K.; Ghiroso, A.; Seaborg, G.T.

2008-01-01T23:59:59.000Z

188

U.S. Natural Gas Monthly Supply and Disposition Balance  

U.S. Energy Information Administration (EIA) Indexed Site

Monthly Supply and Disposition Balance Monthly Supply and Disposition Balance (Billion Cubic Feet) Period: Monthly Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Data Series Apr-13 May-13 Jun-13 Jul-13 Aug-13 Sep-13 View History Gross Withdrawals 2,473 2,541 2,444 2,550 2,540 2,465 1973-2013 Marketed Production 2,086 2,166 2,097 2,188 2,188 2,105 1973-2013 NGPL Production, Gaseous Equivalent 107 110 107 113 117 116 1973-2013 Dry Production 1,979 2,056 1,990 2,076 2,071 1,989 1973-2013 Supplemental Gaseous Fuels 5 5 3 3 5 5 1973-2013 Net Imports 95 92 103 108 106 123 1973-2013 Net Storage Withdrawals -136 -418 -372 -275 -270 -355 1973-2013 Balancing Item 14 12 9 7 6 -5 2001-2013

189

Draft Environmental Assessment on the Remote-handled Waste Disposition  

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

Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment The U.S. Department of Energy invites the public to review and comment on a draft environmental assessment that the Department issued today, for a proposal to process approximately 327 cubic meters of remote-handled waste currently stored at the Idaho National Laboratory. An additional five cubic meters of waste stored at the Hanford Site near Richland, Washington is also evaluated since it is reasonably foreseeable that a decision may be made in the future to send that waste to Idaho for treatment. The project is necessary to prepare the waste for legally-required disposal. Under the Department�s preferred alternative, workers would use sealed rooms called hot cells at the Idaho Nuclear Technology and Engineering Center (INTEC) to process the waste, treat it as necessary and repackage it so that it is ready for disposal. The document describes the modifications necessary to hot cells to perform the work.

190

Innovative Resin Transfer and Disposition at Indian Point Unit 1  

SciTech Connect (OSTI)

A number of sites have both operating and shuttered nuclear facilities. Reducing dose to the caretakers can have beneficial effects for other site personnel who may work or pass near the shuttered facility. Furthermore, disposition of waste can have a positive effect on NRC required regular reporting of, and plans for the disposition of on-site wastes. Entergy's Indian Point Energy Center recently reduced the on-site curie load by working with RWE NUKEM and WMG, Inc. to innovatively free and ship nearly 1,000 cubic feet and nearly 600 curies of 30 year old resin and sludge from Unit 1. Old drawings, operations logs, were consulted and transfer lines were remotely checked. The tank selection sequence was primarily based on dose rates. System modifications to facilitate resin transfer were made on the lowest dose tanks first to gain current operating experience. Resin transfers were performed in accordance with the procedures developed, into waiting cask with appropriate waste containers. Decomposed resin of varying consistency could clog discharge lines and operational changes were made to mitigate against flow interruptions. Hydrogen buildup in the tanks was carefully addressed while solidified resin remains a challenge to be overcome. (authors)

Posivak, E.J.; Freitag, A.A.; Miller, R.J. [WMG, Inc., Peekskill, NY (United States)

2007-07-01T23:59:59.000Z

191

Major Risk Factors Integrated Facility Disposition Project - Oak Ridge  

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

O O O f f f f i i c c e e o o f f E E n n v v i i r r o o n n m m e e n n t t a a l l M M a a n n a a g g e e m m e e n n t t ( ( E E M M ) ) E E n n g g i i n n e e e e r r i i n n g g a a n n d d T T e e c c h h n n o o l l o o g g y y External Technical Review (ETR) Report Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN AUGUST 1, 2008 Acknowledgement The External Technical Review of the Integrated Facility Disposition Project was conducted simultaneous to other assessments and visits. The ETR Team wishes to note the outstanding support received from all parties involved in the review, including the DOE Oak Ridge Office, the National Nuclear Security Administration Y-12 Site Office, UT-Battelle, B&W Y-12, and the Professional Project Services, Inc. (Pro2Serve). The ETR Team feels compelled to note, and

192

Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!  

E-Print Network [OSTI]

! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW Waste (MSW) Generation and Disposition in the U.S., in collaboration with Ms. Nora Goldstein of Bio in 2012 and in 2013 EEC and BioCycle agreed that the 2013 Survey of Waste Generation and Disposition

193

Electrochemical Isotope Effect and Lithium Isotope Separation  

Science Journals Connector (OSTI)

In a series of papers Kavner et al. (2005, 2008)(2, 3) derive an equation predicting isotopic fractionation due to an electrochemical isotope effect (?EIE), defined by the ratio of electron transfer rates (k?/k) for isotopically substituted species (prime for heavy isotopologues): where v, ?G, kB, T, m, ?eq, QP/QR, z, e, and ? denote collision frequency, activation free energy, Boltzmann’s constant, temperature, mass in motion, equilibrium fractionation factor, partition function ratio of abundant isotopologues of product (P) and reactant (R), number of electrons, charge of electron, and Marcus reorganization energy, respectively. ... fractional isotope evolution of Zn isotopes during an electroplating process which stepwise removes most of the Zn from the aq. ...

Jay R. Black; Grant Umeda; Bruce Dunn; William F. McDonough; Abby Kavner

2009-07-06T23:59:59.000Z

194

Perchlorate Isotope Forensics  

Science Journals Connector (OSTI)

In this study, comprehensive stable isotope analyses (37Cl/35Cl and 18O/17O/16O) of perchlorate from known synthetic and natural sources reveal systematic differences in isotopic characteristics that are related to the formation mechanisms. ... ?37Cl and ?18O are measures of mass-dependent fractionation of Cl and O isotopes by normal physical, chemical, or biological processes. ...

John Karl Böhlke; Neil C. Sturchio; Baohua Gu; Juske Horita; Gilbert M. Brown; W. Andrew Jackson; Jacimaria Batista; Paul B. Hatzinger

2005-11-04T23:59:59.000Z

195

Isotope Effect in Adhesion  

Science Journals Connector (OSTI)

Isotope Effect in Adhesion ... We report the first observation of an isotope effect in adhesion. ... The results are presented in Figure 3. Clearly, the isotope effect is very significant, substantiating the proposed H-bonding interactions between the PDMS and Si?OH(D) surfaces. ...

Gun Young Choi; Abraham Ulman; Yitzhak Shnidman; Walter Zurawsky; Cathy Fleischer

2000-05-25T23:59:59.000Z

196

DOE - Office of Legacy Management -- Cornell University Medical College -  

Office of Legacy Management (LM)

Cornell University Medical College Cornell University Medical College - NY 28 FUSRAP Considered Sites Site: CORNELL UNIVERSITY MEDICAL COLLEGE (NY.28 ) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: Cornell University and Medical College NY.28-1 Location: New York , New York NY.28-1 Evaluation Year: 1987 NY.28-1 Site Operations: Research activities involving small quantities of radioactive materials in a controlled environment. NY.28-1 Site Disposition: Eliminated - Potential for contamination considered remote - Only research quantities of material used NY.28-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Not Specified NY.28-1 Radiological Survey(s): None Indicated Site Status: Eliminated from further consideration under FUSRAP

197

DOE - Office of Legacy Management -- University of Utah Medical Research  

Office of Legacy Management (LM)

Utah Medical Research Utah Medical Research Center - UT 02 FUSRAP Considered Sites Site: UNIVERSITY OF UTAH, MEDICAL RESEARCH CENTER (UT.02) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Salt Lake City , Utah UT.02-2 Evaluation Year: 1987 UT.02-1 Site Operations: Research and development on animal inhalation of uranium dust during the 1950s. UT.02-2 Site Disposition: Eliminated - Radiation levels below criteria UT.02-1 UT.02-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium UT.02-2 Radiological Survey(s): Yes UT.02-2 Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to UNIVERSITY OF UTAH, MEDICAL RESEARCH CENTER UT.02-1 - DOE Letter; Fiore to Schiager; Subject: Elimination of

198

DOE - Office of Legacy Management -- University of Rochester Medical Lab -  

Office of Legacy Management (LM)

Rochester Medical Lab Rochester Medical Lab - NY 20 FUSRAP Considered Sites Site: UNIVERSITY OF ROCHESTER MEDICAL LAB. (NY.20) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Rochester , New York NY.20-1 Evaluation Year: 1987 NY.20-1 Site Operations: Research activities involving small quantities of radioactive materials in a controlled environment. NY.20-1 Site Disposition: Eliminated - Potential for contamination remote NY.20-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Not Specified NY.20-1 Radiological Survey(s): None Indicated Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to UNIVERSITY OF ROCHESTER MEDICAL LAB. NY.20-1 - Aerospace Corporation Letter; C. Young to A. Wallo;

199

ARM - Measurement - Isotope ratio  

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

govMeasurementsIsotope ratio govMeasurementsIsotope ratio ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Measurement : Isotope ratio Ratio of stable isotope concentrations. Categories Atmospheric Carbon, Atmospheric State Instruments The above measurement is considered scientifically relevant for the following instruments. Refer to the datastream (netcdf) file headers of each instrument for a list of all available measurements, including those recorded for diagnostic or quality assurance purposes. ARM Instruments FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes Field Campaign Instruments FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes Datastreams FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes

200

Isotope Program Transportation | Department of Energy  

Office of Environmental Management (EM)

Isotope Program Transportation Isotope Program Transportation Isotope Program Transportation More Documents & Publications Nuclear Fuel Storage and Transportation Planning Project...

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


201

Microsoft Word - BingenSwitchDisposition_CXMemo.doc  

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

7, 2012 7, 2012 REPLY TO ATTN OF: KEC-4 SUBJECT: Environmental Clearance Memorandum Joan Kendall Realty Specialist - TERR-3 Proposed Action: Bingen Substation Sectionalizing Switches Disposition Categorical Exclusion Applied (from Subpart D, 10 C.F.R. Part 1021): B1.24 Property Transfers Location: Klickitat County, Washington Proposed by: Bonneville Power Administration (BPA) Description of the Proposed Action: BPA proposes to sell two sectionalizing switches owned by BPA but located on PacifiCorp's Condit-Powerdale 69-kilovolt (kV) line in and adjacent to the Bingen Substation. BPA sold the Bingen substation to Klickitat County PUD in 1997 but retained ownership rights to inspect, maintain, repair, and replace its remaining revenue meters,

202

Microsoft Word - DOE Records Disposition Schedule Changes3.doc  

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

6 6 Changes-to-Schedules REV 3 DOE Administrative Records Schedules Changes Last revised: 12/14/2009 Date DOE Admin Schedule Item(s) Change Authorizing Document 3/02/07 1 10b, 24, 27, 42a-c Added items for Form I-9 (GRS 1, Item 10b), reasonable accommodation records (GRS 1, Item 24), alternative dispute resolution records (GRS 1, item 27), and alternative worksite records (GRS 1, Item 42). Added item numbers for N1 citations. GRS Transmittal No. 11, 12/31/03; GRS Transmittal No. 12, 7/14/04; GRS 1 Item 42 6/14/07 1 11 Second sentence in NOTE deleted. 6/14/07 1 12 Moved the NOTE for 12a to the series title. GRS 1, item 12 6/14/07 1 21 Inserted the "see note" and the disposition authority for the series title. N1-343-98-4, item 21 and GRS

203

Topic Index to the DOE Administrative Records Disposition Schedules  

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

5/21/07 TOPICINDEXTODOEADMINSCHEDULES 5/21/07 TOPICINDEXTODOEADMINSCHEDULES Topic Index to the DOE Administrative Records Disposition Schedules (excluding the GRS Schedules) Topic Schedule Item [A] [B] [C] [D] [E] [F] [G] [H] [I] [J] [K] [L] [M] [N] [O] [P] [Q] [R] [S] [T] [U] [V] [W] [X] [Y] [Z] A Academic/Outreach Program 1 44 Access Request Files 18 6 Accountable Officers' Files 6 1 Accounting Administrative Files 6 5 Administrative Claims Files 6 10 Administrative Training Records 1 29.2 Administrative Issuances 16 1 Administrative - All Other copies of Administrative Issuances 16 1.6 Administrative Grievance, Disciplinary, and Adverse Action Files 1 30 Americans with Disabilities Act 1 42 Apprenticeship Program Files 1 45 Architectural Models 17 7

204

ABSTRACT REQUESTER CONTRACT SCOPE OF WORK RATIONAL FOR DECISION DISPOSITION  

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

WAIVER ACTION - WAIVER ACTION - ABSTRACT REQUESTER CONTRACT SCOPE OF WORK RATIONAL FOR DECISION DISPOSITION General Motors Conduct research, development and Cost Sharing 20 percent Recommended Corporation testing of 30 KW proton-exchange- membrane (PEM) fuel cell propulsion systems 0 STATEMENT OF CONSIDERATIONS REQUEST BY GENERAL MOTORS CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS UNDER CONTRACT NO. DE-AC02-90CH10435, W(A)-90- 056, CH-0663 The Allison Gas Turbine Division of the General Motors Corporation (hereafter GM), a large business, has petitioned for an advance waiver of patent rights under DOE Contract No. DE-AC02- 90CH10435. The contract, yet to be definitized, resulted from an RFP issued in January 1990. As set out in the attached waiver petition, GM has requested that domestic and foreign title to

205

Master EM Project Definition Rating Index - Facility Disposition Definitions  

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

43 43 Master EM Project Definition Rating Index - Facility Disposition Definitions The following definitions describe the criteria required to achieve a maximum rating or maturity value of 5. It should be assumed that maturity values of 1-5 represent a subjective assessment of the quality of definition and/or the degree to which the end-state or maximum criteria have been met, or the product has been completed in accordance with the definition of maturity values. Rating Element Criteria for Maximum Rating COST A1 Cost Estimate A cost estimate has been developed and formally approved by DOE and is the basis for the cost baselines. The cost estimate is a reasonable approximation of Total Project Costs, and covers all phases of the project. The estimate is prepared in

206

Radiation Damage Effects in Candidate Titanates for Pu Disposition: Zirconolite  

SciTech Connect (OSTI)

Specimens of titanate ceramics containing approximately 10 mass% 238Pu were tested to determine the long-term effects of radiation-induced damage from the ? decay of 239Pu that would have been disposed of in the nuclear-waste repository at Yucca Mountain. These tests provided information on the changes in bulk properties such as dimensions, densities, and chemical durability. Although these materials become amorphous at low doses, the specimens remained physically strong. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, in combination with results reported previously on similar materials, the material remains a physically viable material for the disposition of surplus weapons-grade Pu.

Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

2008-01-15T23:59:59.000Z

207

Status of nuclear weapons material disposition in Russia  

SciTech Connect (OSTI)

The security of nuclear weapons and fissile material in Russia, the disposition of weapons-usable fissile material in Russia, the Clinton administration`s policies and programs for assisting Russia in improving its security over nuclear weapons and fissile material, and the disposal of Russian weapons-usable fissile materials are discussed in this paper. There are {approximately}30,000 nuclear warheads in the former Soviet Union, {approximately}1000 t of weapon-usable high-enriched uranium (HEU), {approximately} 160 t of separated plutonium in weapons or available for weapons, and {approximately}30 t of separated civil plutonium stored in Russia. Most, if not all, of these inventories are stored under inadequate conditions of physical security and of material control and accounting.

Cochran, T.B.

1994-12-31T23:59:59.000Z

208

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

SciTech Connect (OSTI)

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

Greene, S.R.

1999-07-17T23:59:59.000Z

209

Radiation Damage Effects in Candidate Titanates for Pu Disposition: Zirconolite  

SciTech Connect (OSTI)

This is the second of two papers on the results of radiation-induced damage accumulation in titanate ceramics that potentially could be used for weapons grade plutonium disposition. In the first paper we discussed the results from pyrochlore (betafite) based ceramics. In this paper, we discuss the effects of radiation-induced damage on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics from the alpha decay of 238Pu. Macro (bulk) and micro (X-ray diffraction) swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. It took approximately 740 days (2.6?1018 ?/g) for the specimens to become X-ray amorphous—longer for the swelling to saturate. Unlike what we observed for the pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)?10-3 g/(m2?d). Very little pH dependence was observed for zirconolite specimens and, like we observed for the pyrochlore-bearing ceramics in this study, there was no dependence on the amount of radiation-induced damage. As with the pyrochlore, these materials did not become substantially friable with increasing radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.

Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

2008-01-15T23:59:59.000Z

210

,"U.S. Natural Gas Monthly Supply and Disposition Balance"  

U.S. Energy Information Administration (EIA) Indexed Site

Monthly Supply and Disposition Balance" Monthly Supply and Disposition Balance" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Natural Gas Monthly Supply and Disposition Balance",9,"Monthly","9/2013","1/15/1973" ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","ng_sum_sndm_s1_m.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/ng/ng_sum_sndm_s1_m.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.gov"

211

,"U.S. Natural Gas Annual Supply and Disposition Balance"  

U.S. Energy Information Administration (EIA) Indexed Site

Annual Supply and Disposition Balance" Annual Supply and Disposition Balance" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Supply",5,"Annual",2012,"6/30/1930" ,"Data 2","Disposition",5,"Annual",2012,"6/30/1930" ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","ng_sum_snd_dcu_nus_a.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/ng/ng_sum_snd_dcu_nus_a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.gov"

212

Mass-Independent Isotope Effects  

Science Journals Connector (OSTI)

Scientific interests: ESR and NMR spectroscopies, molecular magnets, mechanisms of chemical and biochemical reactions, spin physics and chemistry, isotopes and isotope effects in chemistry and biochemistry. ... Another mass-independent isotope effect was detected in 1983 as a deviation of isotopic distribution in reaction products from that which would be expected from the mass-dependent isotope effect. ... Later, Nomura et al.(92) have found isotopic 233U anomaly in the U4+–U6+ exchange reaction; they noted that the isotope effect was correlated with isotope shifts in the atomic spectra of uranium isotopes. ...

Anatoly L. Buchachenko

2013-01-09T23:59:59.000Z

213

Hybrid isotope separation scheme  

DOE Patents [OSTI]

A method is described for yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which a scavenger, radiating the gas with a wave length or frequency characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photochemical reaction between the scavenger, and collecting the specific isotope-containing chemical by using a recombination surface or by a scooping apparatus. 2 figures.

Maya, J.

1991-06-18T23:59:59.000Z

214

Hybrid isotope separation scheme  

DOE Patents [OSTI]

A method of yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which a scavenger, radiating the gas with a wave length or frequency characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photochemical reaction between the scavenger, and collecting the specific isotope-containing chemical by using a recombination surface or by a scooping apparatus.

Maya, Jakob (Brookline, MA)

1991-01-01T23:59:59.000Z

215

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

3 of 5 3 of 5 Volume II Final Environmental Impact Statement November 1999 DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Volume II United States Department of Energy Office of Fissile Materials Disposition November 1999 Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition

216

Used Fuel Disposition R&D Documents | Department of Energy  

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

Used Fuel Disposition Used Fuel Disposition Research & Development » Used Fuel Disposition R&D Documents Used Fuel Disposition R&D Documents December 4, 2013 Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) This report documents the first phase of a multi-year project to understand the technical feasibility and logistical implications of direct disposal of spent nuclear fuel in existing dual-purpose canisters (DPCs) and other types of storage casks. October 25, 2013 Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs Deep borehole disposal is one alternative for the disposal of spent nuclear fuel and other radioactive waste forms; identifying a site or areas with favorable geological, hydrogeological, and geochemical conditions is one of

217

AEO2011:Total Energy Supply, Disposition, and Price Summary | OpenEI  

Open Energy Info (EERE)

Total Energy Supply, Disposition, and Price Summary Total Energy Supply, Disposition, and Price Summary Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 1, and contains only the reference case. The dataset uses quadrillion Btu and the U.S. Dollar. The data is broken down into production, imports, exports, consumption and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO consumption disposition energy exports imports Supply Data application/vnd.ms-excel icon AEO2011:Total Energy Supply, Disposition, and Price Summary- Reference Case (xls, 112.8 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage

218

EIS-0475: Disposition of the Bannister Federal Complex, Kansas City, MO |  

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

EIS-0475: Disposition of the Bannister Federal Complex, Kansas EIS-0475: Disposition of the Bannister Federal Complex, Kansas City, MO EIS-0475: Disposition of the Bannister Federal Complex, Kansas City, MO Summary NNSA/DOE announces its intent to prepare an EIS for the disposition of the Bannister Federal Complex, Kansas City, MO. NNSA previously decided in a separate NEPA review (EA-1592) to relocate its operations from the Bannister Federal Complex to a newly constructed industrial campus eight miles from the current location. NOTE: On November 30, 2012, DOE announced the cancellation of this EIS and its intent to prepare an Environmental Assessment (EA-1947). Public Comment Opportunities None available at this time. Documents Available for Download November 30, 2012 EA-1947: Notice of Intent to Prepare an Environmental Assessment and

219

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 | Department of  

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

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 The United States currently utilizes a once-through fuel cycle where used nuclear fuel is stored onsite in either wet pools or in dry storage systems with ultimate disposal envisioned in a deep mined geologic repository. This report provides an estimate of potential waste inventory and waste form characteristics for the DOE used nuclear fuel and high-level radioactive waste and a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. Fuel Cycle Potential Waste Inventory for Disposition R5a.docx More Documents & Publications Repository Reference Disposal Concepts and Thermal Load Management Analysis

220

EA-1410: Proposed Disposition of the Omega West Facility at Los Alamos  

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

10: Proposed Disposition of the Omega West Facility at Los 10: Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico EA-1410: Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico SUMMARY This EA evaluates the environmental impacts for the proposal to remove the Omega West Facility and the remaining support structures from Los Alamos Canyon at the U.S. Department of Energy Los Alamos National Laboratory in Los Alamos, New Mexico. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD March 28, 2002 EA-1410: Finding of No Significant Impact Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico March 28, 2002 EA-1410: Final Environmental Assessment

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


221

On Solar Energy Disposition:A Perspective from Observation and Modeling  

Science Journals Connector (OSTI)

Solar energy disposition (SED) concerns the amount of solar radiation reflected to space, absorbed in the atmosphere, and absorbed at the surface. The state of knowledge on SED is examined by comparing eight datasets from surface and satellite ...

Zhanqing Li; Louis Moreau; Albert Arking

1997-01-01T23:59:59.000Z

222

AEO2011: Natural Gas Supply, Disposition, and Prices | OpenEI  

Open Energy Info (EERE)

Supply, Disposition, and Prices Supply, Disposition, and Prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 13, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA natural gas supply prices Data application/vnd.ms-excel icon AEO2011: Natural Gas Supply, Disposition, and Prices - Reference Case (xls, 91.8 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

223

Stable isotope enrichment  

SciTech Connect (OSTI)

Brian Egle is working to increase the nation's capacity to produce stable isotopes for use including medicine, industry and national security.

Egle, Brian

2014-07-14T23:59:59.000Z

224

EMSL - isotopic ratio  

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

isotopic-ratio en Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. http:www.emsl.pnl.govemslwebpublicationsmagnesium-behavior-and-structural-def...

225

Environmental Assessment Addendum Disposition of Additional Waste at the Paducah Site  

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

9-A 9-A Environmental Assessment Addendum Disposition of Additional Waste at the Paducah Site December 2003 U. S. Department of Energy Oak Ridge Operations Oak Ridge, Tennessee DOE/EA-1339-A Disposition of Additional Waste at the Paducah Site Environmental Assessment Addendum December 2003 U. S. Department of Energy Oak Ridge Operations U.S. Department of Energy Paducah Site DOE/EA-1339A Table of Contents Table of Contents............................................................................................................................ v Acronyms.......................................................................................................................................

226

US weapons-useable plutonium disposition policy: implementation of the MOX fuel option  

E-Print Network [OSTI]

US WEAPONS-USEABLE PLUTONIUM DISPOSITION POLICY: IMPLEMENTATION OF THE MOX FUEL OPTION A Thesis by VANESSA L. GONZALEZ Submitted to the Office of Graduate Studies of Texas ARM University in partial fulfillment of the requirements... for the degree of MASTER OF ARTS August 1998 Major Subject: Political Science US WEAPONS-USEABLE PLUTONIUM DISPOSITION POLICY: IMPLEMENTATION OF THE MOX FUEL OPTION A Thesis by VANESSA L. GONZALEZ Submitted to Texas ARM University in partial fulfillment...

Gonzalez, Vanessa L

2012-06-07T23:59:59.000Z

227

Celebrating The Isotope  

Science Journals Connector (OSTI)

Celebrating The Isotope ... The notion of isotopes and the rest of Soddy’s lifetime body of work on radioactivity, the group displacement laws, the social responsibility of scientists, and the environment have had a profound effect on science and society. ...

GEORGE B. KAUFFMAN

2013-12-02T23:59:59.000Z

228

Isotope - based Quantum Information  

E-Print Network [OSTI]

This paper is brief review of three aspects of the isotope - based quantum information: computation, teleportation and cryptography. Our results demonstrate not only that entanglement exists in elementary excitation of isotope - mixed solids but also it can be used for quantum information processing.

Vladimir G. Plekhanov

2009-09-04T23:59:59.000Z

229

U.S. Crude Oil Supply & Disposition  

U.S. Energy Information Administration (EIA) Indexed Site

2007 2008 2009 2010 2011 2012 View 2007 2008 2009 2010 2011 2012 View History Supply Field Production (Commercial) 1,853,122 1,829,897 1,954,021 1,996,787 2,063,138 2,374,842 1859-2012 Alaskan 263,595 249,874 235,491 218,904 204,829 192,368 1981-2012 Lower 48 States 1,589,527 1,580,024 1,718,529 1,777,883 1,858,309 2,182,474 1993-2012 Imports 3,661,404 3,580,694 3,289,675 3,362,856 3,261,422 3,120,755 1910-2012 Commercial 3,658,701 3,573,581 3,269,307 3,362,856 3,261,422 3,120,755 2001-2012 Strategic Petroleum Reserve (SPR) 2,703 7,113 20,368 1977-2009 Adjustments (Commercial) 9,742 5,777 29,077 37,829 63,600 52,746 1981-2012 Disposition Stock Change -17,835 44,617 24,132 8,180 -33,345 34,134 1983-2012 Commercial -26,171 39,735 -661 8,251 -2,751 34,817 1993-2012

230

Radiation damage effects in candidate titanates for Pu disposition: Zirconolite  

Science Journals Connector (OSTI)

Results from studies of radiation-induced damage from the alpha decay of 238Pu on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics are discussed. Macro and micro swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. Approximately 2.6 × 1018 ?/g were needed to render the specimens X-ray amorphous– more to saturate the swelling. Unlike pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4) × 10?3 g/(m2 d) with very little pH dependence and no dependence on the amount of radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.

D.M. Strachan; R.D. Scheele; E.C. Buck; A.E. Kozelisky; R.L. Sell; R.J. Elovich; W.C. Buchmiller

2008-01-01T23:59:59.000Z

231

DOE/EIS-0240-SA-1: Supplement Analysis for the Disposition of Surplus Highly Enriched Uranium (October 2007)  

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

0-SA1 0-SA1 SUPPLEMENT ANALYSIS DISPOSITION OF SURPLUS HIGHLY ENRICHED URANIUM October 2007 U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. i TABLE OF CONTENTS 1.0 Introduction and Purpose .................................................................................................................1 2.0 Background......................................................................................................................................1 2.1 Scope of the HEU EIS............................................................................................................ 2 2.2 Status of Surplus HEU Disposition Activities .......................................................................

232

Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium  

SciTech Connect (OSTI)

Approximately 750,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms are stored at several Department of Energy (DOE) sites throughout the United States. Most of the DU is in the form of DU hexafluoride (DUF6) that resulted from uranium enrichment operations over the last several decades. DOE plans to convert the DUF6 to ''a more stable form'' that could be any one or combination of DU tetrafluoride (DUF4 or green salt), DU oxide (DUO3, DUO2, or DU3O8), or metal depending on the final disposition chosen for any given quantity. Barriers to final disposition of this material have existed historically and some continue today. Currently, the barriers are more related to finding uses for this material versus disposing as waste. Even though actions are beginning to convert the DUF6, ''final'' disposition of the converted material has yet to be decided. Unless beneficial uses can be implemented, DOE plans to dispose of this material as waste. This expresses the main barrier to DU disposition; DOE's strategy is to dispose unless uses can be found while the strategy should be only dispose as a last resort and make every effort to find uses. To date, only minimal research programs are underway to attempt to develop non-fuel uses for this material. Other issues requiring resolution before these inventories can reach final disposition (uses or disposal) include characterization, disposal of large quantities, storage (current and future), and treatment options. Until final disposition is accomplished, these inventories must be managed in a safe and environmentally sound manner; however, this is becoming more difficult as materials and facilities age. The most noteworthy final disposition technical issues include the development of reuse and treatment options.

Gillas, D. L.; Chambers, B. K.

2002-02-26T23:59:59.000Z

233

lead-isotope age  

Science Journals Connector (OSTI)

lead-isotope age, lead-lead age [An age in years calculated from the ratio of lead-207 to lead-206, a by-product of the uranium-thorium-lead age method] ? Blei-Isotopen-Alter n

2014-08-01T23:59:59.000Z

234

ISOTOPES IN WATER  

Science Journals Connector (OSTI)

The study of isotopic prosies ha two different though related basic aims: an understanding of the way in which the water cycle in linked to alterations in climate, and how the carbon cycle has responded to the...

W. GEORGE DARLING; ADRIAN H. BATH…

2006-01-01T23:59:59.000Z

235

Nuclear isotope thermometry  

Science Journals Connector (OSTI)

We discuss different aspects which might influence temperatures deduced from experimental isotopic yields in the multifragmentation process. It is shown that fluctuations due to the finite size of the system and distortions due to the decay of hot primary fragments conspire to blur the temperature determination in multifragmentation reactions. These facts suggest that caloric curves obtained through isotope thermometers, which were taken as evidence for a first-order phase transition in nuclear matter, should be investigated very carefully.

S. R. Souza, W. P. Tan, R. Donangelo, C. K. Gelbke, W. G. Lynch, and M. B. Tsang

2000-11-10T23:59:59.000Z

236

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

SciTech Connect (OSTI)

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

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

237

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

2 of 5 2 of 5 Volume I - Part B Final Environmental Impact Statement November 1999 DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Volume I - Part B United States Department of Energy Office of Fissile Materials Disposition November 1999 Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director

238

AEO2011: Total Energy Supply, Disposition, and Price Summary | OpenEI  

Open Energy Info (EERE)

Total Energy Supply, Disposition, and Price Summary Total Energy Supply, Disposition, and Price Summary Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 1, and contains only the reference case. The dataset uses quadrillion BTUs, and quantifies the energy prices using U.S. dollars. The data is broken down into total production, imports, exports, consumption, and prices for energy types. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO consumption EIA export import production reference case total energy Data application/vnd.ms-excel icon AEO2011: Total Energy Supply, Disposition, and Price Summary - Reference Case (xls, 112.8 KiB) Quality Metrics

239

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced  

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

Chooses Idaho Treatment Group, LLC to Disposition Waste at the Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site May 27, 2011 - 12:00pm Addthis Media Contact Brad Bugger (208) 526-0833 Idaho Falls - In order to further meet the U.S. Department of Energy's commitments to the citizens of the state of Idaho, the DOE today announced that it has selected Idaho Treatment Group, LLC (ITG) to perform waste processing at the Advanced Mixed Waste Treatment Project (AMWTP) at DOE's Idaho Site near Idaho Falls. The contract is estimated at approximately

240

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

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

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

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


241

DOE 2010 Safety and Security Reform Project - HSS Directives Disposition and Status (December 4, 2012)  

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

10 Safety and Security Reform Project - HSS Directives Disposition and Status (December 4, 2012) 10 Safety and Security Reform Project - HSS Directives Disposition and Status (December 4, 2012) Page 1 of 3 2010 HSS Directives Disposition Status Secretary of Energy Notice SEN-35-91, Nuclear Safety Policy Revise Complete - see Policy 420.1. Order 5400.5, Radiation Protection of the Public and the Environment Revise Complete - see Order 458.1. Order 5480.19, Conduct of Operations Requirements for DOE Facilities Revise Complete - see Order 422.1. Order 5480.20A, Personnel Selection, Training, Qualification, and Certification Requirements Revise Complete - see Order 426.2. Order 5480.30, Nuclear Reactor Design Criteria Re-certify Complete - re-certified. Manual 140.1-1B, Interface with the Defense Nuclear Facilities Safety Board Re-certify Complete - re-certified.

242

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

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

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

243

Used Fuel Disposition R&D Documents | Department of Energy  

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

March 31, 2011 March 31, 2011 Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is March 30, 2011 Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study including variations on the design of the repository, the engineered barrier, and the waste. Salt, clay/shale, and

244

Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407  

SciTech Connect (OSTI)

This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

Walker, Stuart [U.S. Environmental Protection Agency (United States)] [U.S. Environmental Protection Agency (United States)

2013-07-01T23:59:59.000Z

245

The impact of personal dispositions on information sensitivity, privacy concern and trust in disclosing health information online  

Science Journals Connector (OSTI)

Reluctance to provide personal health information could impede the success of web-based healthcare services. This paper focuses on the role of personal dispositions in disclosing health information online. The conceptual model argues that individuals' ... Keywords: Health status, Information privacy concern, Information sensitivity, Intrinsic and extrinsic perspectives of trust, Intrinsic factors, Personal dispositions, Personality, Trust, Utility Theory

Gaurav Bansal; Fatemeh "Mariam" Zahedi; David Gefen

2010-05-01T23:59:59.000Z

246

Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!  

E-Print Network [OSTI]

! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW on Municipal Solid Waste (MSW) Generation and Disposition in the U.S., in collaboration with Ms. Nora Goldstein was not carried out in 2012 and in 2013 EEC and BioCycle agreed that the 2013 Survey of Waste Generation

Columbia University

247

Preliminary Technology Readiness Assessment (TRA) for the Calcine Disposition Project Volume 1 (CDP)  

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

TECHNOLOGY READINESS ASSESSMENT TECHNOLOGY READINESS ASSESSMENT OF THE CALCINE DISPOSITION PROJECT VOLUME ONE Anthony F. Kluk Hoyt C. Johnson Clyde Phillip McGinnis Michael Rinker Steven L. Ross Herbert G. Sutter John Vienna February 2011 Prepared by the U.S. Department of Energy Washington, DC February 2011 ii This page intentionally left blank. Review of Calcine Disposition Project Self-Assessment of Technology Maturation iii SIGNATURES ____________________________________ ____________________________________ Anthony F. Kluk, Team Lead Date ____________________________________ ____________________________________ Hoyt C. Johnson Date ____________________________________ ____________________________________ Clyde Phillip McGinnis Date ____________________________________ ____________________________________

248

Fuel qualification issues and strategies for reactor-based surplus plutonium disposition  

SciTech Connect (OSTI)

The Department of Energy (DOE) has proposed irradiation of mixed-oxide (MOX) fuel in existing commercial reactors as a disposition method for surplus plutonium from the weapons program. The burning of MOX fuel in reactors is supported by an extensive technology base; however, the infrastructure required to implement reactor-based plutonium disposition does not exist domestically. This report identifies and examines the actions required to qualify and license weapons-grade (WG) plutonium-based MOX fuels for use in domestic commercial light-water reactors (LWRs).

Cowell, B.S.; Copeland, G.L.; Moses, D.L.

1997-08-01T23:59:59.000Z

249

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

Summary Final Environmental Impact Statement November 1999 Summary DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Summary United States Department of Energy Office of Fissile Materials Disposition November 1999 Summary i Table of Contents S.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-1 Purpose of and Need for the Proposed Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-3 Issues Identified During the Scoping Period . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-4 Issues Already Intended for Inclusion in the SPD EIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-4 Additional Issues That Need to Be Addressed in the SPD EIS . . . . . . . . . . . . . . . . . . . . . . . . S-5 Issues That Need to Be or Are Already Addressed Elsewhere . . . . . . . . . . . . . . . .

250

Medical (Visual) Information Retrieval  

Science Journals Connector (OSTI)

This text gives a broad overview of the domain of visual medical information retrieval and medical information analysis/search in general. The goal is to describe the specifics of medical information analysis ...

Henning Müller

2013-01-01T23:59:59.000Z

251

Atomic Spectroscopy and Separated Isotopes  

Science Journals Connector (OSTI)

The advantages in the use of separated isotopes in atomic spectroscopy for the determination of nuclear momentsI ? Q and for studies of the isotope-shift phenomena are discussed. Illustrations of spectra are given for mercury uranium and samarium. In addition a summary is given of twenty-two so-called problem nuclei i.e. those naturally occurring isotopes for which the nuclear moments are completely uncertain. Concluding remarks are made on such problems as the evaluation of the absolute magnitude of isotope shifts the role of “forbidden transitions” in isotope spectra and the potential future value of spectro-isotopic assay techniques.

J. R. McNally Jr.

1952-01-01T23:59:59.000Z

252

Radiation Damage Effects in Candidate Titanates for Pu Disposition: Pyrochlore  

SciTech Connect (OSTI)

Laboratory experiments on titanate ceramics were performed to verify whether certain assumptions are valid regarding the swelling, chemical durability, and microcracking that might occur as 239Pu decays. Titanate ceramics are the material of choice for the immobilization of surplus weapons-grade Pu. The short-lived isotope, 238Pu, was incorporated into the ceramic formulation to accelerate the effects of radiation induced damage. We report on the effects of this damage on the density (volumetric swelling <6%), crystal structure of pyrochlore-bearing specimens (amorphous after about 2?1018 ?/g), and dissolution (no change from fully the crystalline specimen). Even though the specimens became amorphous during the tests, there was no evidence for microcracking in the photomicrographs from the scanning electron microscope. Thus, although pyrochlore is susceptible to radiation-induced damage, the material remains chemically and physically viable as a material for immobilizing surplus weapons-grade Pu.

Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Icenhower, Jonathan P.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

2005-10-15T23:59:59.000Z

253

Radiation Damange Effects in Candidate Titanates for Plutonium Disposition: Pyrochlore.  

SciTech Connect (OSTI)

Laboratory experiments were conducted to verify certain assumptions as to the swelling, chemical durability, and microcracking that might occur in a waste-form ceramic as 239Pu decays. To study to effects of 239Pu decay, 238Pu, a short-lived isotope, was incorporated into a pyrochlore-rich baseline titanate – one that is formulated for pyrochlore as the dominant phase. The self-irradiation with 238Pu provided information on damage to the crystal structures of the phases in the ceramic as well as changes in dimensions, densities, and chemical durability. Overall, the pyrochlore baseline material appears to be a viable material for the immobilization of weapons-ready Pu. The physical and chemical properties of this material are not adversely affected by the material becoming amorphous from radiation-induced damage.

Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

2005-10-15T23:59:59.000Z

254

Radioactive Kr Isotopes  

Science Journals Connector (OSTI)

A radioactive isotope of 1.1-hour half-life has been produced in krypton by alpha-particle bombardment of Se74, enriched electromagnetically from 0.9 percent to 14.1 percent. Assignment of the isotope is made to Kr77. Aluminum absorption measurements indicate a positron end point of 1.7 Mev. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se74(?,n) reaction is computed as 2.6. The krypton 1.42-day isotope has been produced by an ?,n reaction on electromagnetically enriched Se76. The isotope is located as Kr79 and its half-life confirmed. A positron end point of 1.0 Mev is determined by aluminum absorption measurements. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se76(?,n) reaction is computed to be 50. The cross-section ratio for formation of Kr77 compared to Kr79 by alpha-particle bombardment of selenium is computed as 1.4. The 4.6-hour Kr85 isotope has been produced by a Se(?,n) reaction.

L. L. Woodward; D. A. Mccown; M. L. Pool

1948-10-01T23:59:59.000Z

255

Medical Aspects of Reliability  

SciTech Connect (OSTI)

This presentation covers the medical evaluation as part of a human reliability program, particularly the various medical qualifications and potential disqualifiers.

Atencio, Julian J.

2014-05-05T23:59:59.000Z

256

Oak Ridge Isotope Products and Services - Current and Expected Supply and Demand  

SciTech Connect (OSTI)

Oak Ridge National Laboratory (ORNL) has been a major center of isotope production research, development, and distribution for over 50 years. Currently, the major isotope production activities include (1) the production of transuranium element radioisotopes, including 252 Cf; (2) the production of medical and industrial radioisotopes; (3) maintenance and expansion of the capabilities for production of enriched stable isotopes; and, (4) preparation of a wide range of custom-order chemical and physical forms of isotope products, particularly in accelerator physics research. The recent supply of and demand for isotope products and services in these areas, research and development (R&D), and the capabilities for future supply are described in more detail below. The keys to continuing the supply of these important products and services are the maintenance, improvement, and potential expansion of specialized facilities, including (1) the High Flux Isotope Reactor (HFIR), (2) the Radiochemical Engineering Development Center (REDC) and Radiochemical Development Laboratory (RDL) hot cell facilities, (3) the electromagnetic calutron mass separators and the plasma separation process equipment for isotope enrichment, and (4) the Isotope Research Materials Laboratory (IRML) equipment for preparation of specialized chemical and physical forms of isotope products. The status and plans for these ORNL isotope production facilities are also described below.

Aaron, W.S.; Alexander, C.W.; Cline, R.L.; Collins, E.D.; Klein, J.A.; Knauer, J.B., Jr.; Mirzadeh, S.

1999-08-29T23:59:59.000Z

257

Isotope separation apparatus  

DOE Patents [OSTI]

Isotope separation apparatus consisting of a plurality of cells disposed adjacent to each other in an evacuated container. A common magnetic field is established extending through all of the cells. A source of energetic electrons at one end of the container generates electrons which pass through the cells along the magnetic field lines. Each cell includes an array of collector plates arranged in parallel or in tandem within a common magnetic field. Sets of collector plates are disposed adjacent to each other in each cell. Means are provided for differentially energizing ions of a desired isotope by applying energy at the cyclotron resonant frequency of the desired isotope. As a result, the energized desired ions are preferentially collected by the collector plates.

Arnush, Donald (Rancho Palos Verdes, CA); MacKenzie, Kenneth R. (Pacific Palisades, CA); Wuerker, Ralph F. (Palos Verdes Estates, CA)

1980-01-01T23:59:59.000Z

258

Development of a Techno-Economic Model to Optimize DOE Spent Nuclear Fuel Disposition  

SciTech Connect (OSTI)

The National Spent Nuclear Fuel (NSNF) Program is evaluating final disposition of spent nuclear fuel (SNE) in the Department of Energy (DOE) complex. Final disposition of SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the EMT process for fuels at several locations. The set of questions addresses all issues associated with design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs can be applied to determine the life cycle cost of each option. This technique can also be applied to other treatment techniques for treating SNF.

Ramer, R. J.; Plum, M. M.; Adams, J. P.; Dahl, C. A.

1998-02-01T23:59:59.000Z

259

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement  

Broader source: Energy.gov [DOE]

This EIS analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives. The original EIS is available at http://energy.gov/nepa/downloads/eis-0283-final-environmental-impact-sta....

260

Plutonium-bearing materials feed report for the DOE Fissile Materials Disposition Program alternatives  

SciTech Connect (OSTI)

This report has identified all plutonium currently excess to DOE Defense Programs under current planning assumptions. A number of material categories win clearly fan within the scope of the MD (Materials Disposition) program, but the fate of the other categories are unknown at the present time. MD planning requires that estimates be made of those materials likely to be considered for disposition actions so that bounding cases for the PEIS (Programmatic Environmental Impact Statement) can be determined and so that processing which may be required can be identified in considering the various alternatives. A systematic analysis of the various alternatives in reachmg the preferred alternative requires an understanding of the possible range of values which may be taken by the various categories of feed materials. One table identifies the current total inventories excess to Defense Program planning needs and represents the bounding total of Pu which may become part of the MD disposition effort for all materials, except site return weapons. The other categories, principally irradiated fuel, rich scrap, and lean scrap, are discussed. Another table summarizes the ranges and expected quantities of Pu which could become the responsibility of the MD program. These values are to be used for assessing the impact of the various alternatives and for scaling operations to assess PEIS impact. Determination of the actual materials to be included in the disposition program will be done later.

Brough, W.G. [Lawrence Livermore National Lab., CA (United States); Boerigter, S.T. [Los Alamos National Lab., NM (United States)

1995-04-06T23:59:59.000Z

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


261

Coherence and Conservatism in the Dynamics of Belief II: Iterated Belief Change without Dispositional Coherence  

Science Journals Connector (OSTI)

......University Press 2003 Original Article Coherence and Conservatism in the Dynamics of Belief...Iterated Belief Change without Dispositional Coherence Hans Rott 1 1 Department of Philosophy...based on the conclusions of Rott, Coherence and Conservatism in the Dynamics of Belief......

Hans Rott

2003-02-01T23:59:59.000Z

262

IDENTIFYING IMPURITIES IN SURPLUS NON PIT PLUTONIUM FEEDS FOR MOX OR ALTERNATIVE DISPOSITION  

SciTech Connect (OSTI)

This report provides a technical basis for estimating the level of corrosion products in materials stored in DOE-STD-3013 containers based on extrapolating available chemical sample results. The primary focus is to estimate the levels of nickel, iron, and chromium impurities in plutonium-bearing materials identified for disposition in the United States Mixed Oxide fuel process.

Allender, J; Moore, E

2010-07-14T23:59:59.000Z

263

Used fuel disposition campaign international activities implementation plan.  

SciTech Connect (OSTI)

The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through information exchange and a broader participation of experts in the field. U.S. participation in international UNF and HLW exchanges leads to safe management of nuclear materials, increased security through global oversight, and protection of the environment worldwide. Such interactions offer the opportunity to develop consensus on policy, scientific, and technical approaches. Dialogue to address common technical issues helps develop an internationally recognized foundation of sound science, benefiting the U.S. and participating countries. The UNF and HLW management programs in nuclear countries are at different levels of maturity. All countries utilizing nuclear power must store UNF, mostly in wet storage, and HLW for those countries that reprocess UNF. Several countries either utilize or plan to utilize dry storage systems for UNF, perhaps for long periods of time (several decades). Geologic disposal programs are at various different states, ranging from essentially 'no progress' to selected sites and pending license applications to regulators. The table below summarizes the status of UNF and HLW management programs in several countriesa. Thus, the opportunity exists to collaborate at different levels ranging from providing expertise to those countries 'behind' the U.S. to obtaining access to information and expertise from those countries with more mature programs. The U.S. fuel cycle is a once through fuel cycle involving the direct disposal of UNF, as spent nuclear fuel, in a geologic repository (previously identified at Yucca Mountain, Nevada), following at most a few decades of storage (wet and dry). The geology at Yucca Mountain, unsaturated tuff, is unique among all countries investigating the disposal of UNF and HLW. The decision by the U.S. Department of Energy to no longer pursue the disposal of UNF at Yucca Mountain and possibly utilize very long term storage (approaching 100 years or more) while evaluating future fuel cycle alternatives for managing UNF, presents a different UNF and HLW management R&D portfolio that has been pursued in the U.S. In addition, the research and development activities managed by OCRWM have been transferred to DOE-NE. This requires a reconsideration of how the UFDC will engage in cooperative and collaborative activities with other countries. This report presents the UFDC implementation plan for international activities. The DOE Office of Civilian Radioactive Waste Management (OCRWM) has cooperated and collaborated with other countries in many different 'arenas' including the Nuclear Energy Agency (NEA) within the Organization for Economic Co-operation and Development (OECD), the International Atomic Energy Agency (IAEA), and through bilateral agreements with other countries. These international activities benefited OCRWM through the acquisition and exchange of information, database development, and peer reviews by experts from other countries. DOE-NE cooperates and collaborates with other countries in similar 'arenas' with similar objectives and realizing similar benefits. However the DOE-NE focus has not typically been in the area of UNF and HLW management. This report will first summarize these recent cooperative and collaborative activities. The manner that the UFDC will cooperate and collaborate in the future is expected to change as R&D is conducted regarding long-term storage and the potential disposal of UNF and HLW in different geolo

Nutt, W. M. (Nuclear Engineering Division)

2011-06-29T23:59:59.000Z

264

Isotope Effect of Mercury Diffusion in Air  

Science Journals Connector (OSTI)

Isotope fractionation describes the separation of a reservoir with one isotope composition into “fractions” with different isotope compositions due to small isotopic differences in equilibrium partitioning, rates of mass transfer, or rates of transformation. ... (29) ?202Hg is the value most frequently used to examine mass dependent fractionation of mercury isotopes as 202Hg is the heaviest mercury isotope without significant isobaric interferences. ...

Paul G. Koster van Groos; Bradley K. Esser; Ross W. Williams; James R. Hunt

2013-12-23T23:59:59.000Z

265

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

SciTech Connect (OSTI)

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

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

1998-08-01T23:59:59.000Z

266

Final Demolition and Disposition of 209-E Critical Mass Laboratory - 12267  

SciTech Connect (OSTI)

The 209-E Critical Mass Laboratory was constructed in 1960 to provide a heavy shielded reactor room where quantities of plutonium or uranium in solution could be brought to near-critical configurations under carefully controlled and monitored conditions. In the late 1980's, the responsible contractor, Pacific Northwest National Laboratory (PNNL), was directed by the Department of Energy (DOE) to prepare the facility for unoccupied status. The facility was demolished under a Removal Action Work Plan pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The funding for this project was provided by the American Recovery and Reinvestment Act (ARRA). The primary rooms of concern with regards to contamination in 209-E facility, which is over 9,000 square feet, are the criticality assembly room (CAR), the mix room, and the change room. The CAR contained two reactor hoods (HO-140 and HO-170), which each had a high efficiency particulate air (HEPA) filter system. The CAR contained 13 tanks ranging from 38 L (10 gal) to 401 L (106 gal). Tanks TK-109 and TK-110 are below grade, and were removed as part of this demolition and disposition remedy. Nonradiological and radiological hazardous substances were removed, decontaminated, or fixed in place, prior to demolition. Except for the removal of below grade tanks TK-109 and TK-110, the facility was demolished to slab-on-grade. PNNL performed stabilization and deactivation activities that included removal of bulk fissile material and chemicals, flushing tanks, stabilizing contamination within gloveboxes and hoods, and packaging and removing waste. The removal of the contaminated plutonium equipment and materials from the 209E facility presented a number of challenges similar in nature to those associated with the inventory reduction and cleanup activities at the Plutonium Finishing Plant. Although there were no bulk fissile materials or chemicals within the facility, there were residual radiological materials (isotopes of plutonium and americium) in the tanks and hoods. The complexity of the remedy was present because of the various configurations of the tanks and hoods, combined with the residual contaminants. Because of the weight and dimensional configuration, size reduction of the slab tanks, as well as removal and disposal of the different material used for moderation and absorption, were two examples of challenges that were resolved to complete the remedy. One of the key methods developed and implemented at the facility was the design and construction of a shroud to allow the cutting of the Pu contaminated tanks. The shroud design, development and implementation at the 209E Project was an example of enhanced work planning and task hazards analysis with worker involvement. This paper will present the lessons learned from the 209E facility inventory reduction activities including the shroud and other methodologies used. The initial Lessons Learned discussion for this project was scheduled for late January 2012. This facility is the first open-air demolition of a highly contaminated plutonium-contaminated facility accomplished by CH2M Hill under the Plateau Remediation Contract. The demolition was completed without spread of contamination to the workers and the surrounding area. As with any project of this complexity, there are significant accomplishments, as well as experience that can be applied to future demolition of plutonium-contaminated facilities on the Hanford Site. These experiences will be documented at a later date. (authors)

Woolery, Wade [US Department of Energy, Richland WA (United States); Dodd, Edwin III [CH2M Hill Plateau Remediation Company, Richland WA (United States)

2012-07-01T23:59:59.000Z

267

Medical Applications of Non-Medical Research  

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

Applications Applications Medical Applications of Non of Non - - Medical Research Medical Research Applications Derived from Applications Derived from BES BES - - Supported Research Supported Research and Research at BES Facilities and Research at BES Facilities Office of Basic Energy Sciences Office of Energy Research * U.S. Department of Energy July 1998 i Table of Contents The Office of Basic Energy Sciences ..............................................................................................1 1. DISEASE DIAGNOSIS.............................................................................................................1 Thin-Film Lithium Batteries for Biomedical Applications (ORNL)......................................1 Positron Emission Tomography (BNL)

268

Used fuel disposition research and development roadmap - FY10 status.  

SciTech Connect (OSTI)

Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R&D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R&D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been made in the U.S. and other nations in understanding disposal concepts in different geologic media, but gaps in knowledge still exist. A principal aspect of concern to the UFDC as it considers the broad issues of siting a repository in different geologic media are the marked differences in the regulatory bases for assessing suitability and safety of a repository between the U.S. and other nations. Because the probability based - risked informed nature of the current U.S. regulations for high-level radioactive waste and spent nuclear fuel is sufficiently different from other regulations, information gained in previous studies, while useful, likely need to be supplemented to enable more convincing communication with the public, better defense of the numerical models, and stronger safety cases. Thus, it was recognized when the UFDC was established that there were readily identified disposal-related R&D opportunities to address knowledge gaps. An effort to document these research opportunities was a key component of Fiscal Year (FY) 2010 engineered system, natural system, and system-level modeling activities for a range of disposal environments. A principal contribution to identifying these gaps was a workshop held to gather perspectives from experts both within and external to the UFDC regarding R&D opportunities. In the planning for FY2010 it was expected that these activities would culminate with a UFDC research and development roadmap that would identify the knowledge gaps, discuss the R&D needed to fill these gaps, and prioritize the proposed R&D over both the near- and long-term. A number of knowledge gaps and needed R&D were identified and are discussed in this report. However, these preliminary R&D topics have not been evaluated in detail nor have they been prioritized to support future planning efforts. This will be completed in FY11 and the final UFDC Research and Development Roadmap will be completed. This report discusses proposed R&D topics in three areas related to repository siting, design, and performance: natural systems

Nutt, W. M. (Nuclear Engineering Division)

2010-10-01T23:59:59.000Z

269

Record of Decision for the Medical Isotopes Production Project: Molybdenum-99 and Related Isotopes  

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

21 21 Federal Register / Vol. 61, No. 181 / Tuesday, September 17, 1996 / Notices property at Fort Ord, California. The FSEIS also analyzes impacts on a range of potential reuse alternatives. Copies of the FSEIS have been forwarded to various federal, state and local agencies, and predetermined interested organizations and individuals. DATES: This FSEIS will be available to the public for 30 days, after which the Army will prepare a Record of Decision for the Army action. ADDRESSES: Copies of the Final Supplemental Environmental Impact Statement can be obtained by writing or calling Mr. Bob Verkade, Sacramento District, U.S. Army Corps of Engineers, 1325 J Street, Sacramento, California 95814-2922, telephone (916) 557-7423, fax (916) 557-5307. Raymond J. Fatz, Deputy Assistant Secretary of the Army

270

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

SciTech Connect (OSTI)

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

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

271

Neutron Assay System for Con?nement Vessel Disposition  

SciTech Connect (OSTI)

Waste will be removed from confinement vessels remaining from 1970s-era experiments. Los Alamos has 9+ spherical confinement vessels remaining from experiments. Each vessel contains {approx} 500 lbs of radioactive debris such as actinide metals and oxides, metals, powdered silica, graphite, and wires and hardware. In order to dispose of the vessels, debris and contamination must be removed. Neutron assay system was designed to assay vessels before and after cleanout. System requirements are: (1) Modular and moveable; (2) Capable of detecting {approx}100g {sup 239}Pu equivalent in a 2-inch thick steel sphere with 6 foot diameter; and (3) Capable of safeguards-quality assays. Initial design parameters arethe use of 4-atm {sup 3}He tubes with length of 6 feet, and {sup 3}He tubes embedded in polyethelene for moderation. This paper describes the calibration of the Confinement Vessel Assay System (CVAS) and quantification of its uncertainties. Assay uncertainty depends on five factors: (1) Statistical uncertainty in the assay measurement; (2) Statistical uncertainty in the background measurement; (3) Statistical uncertainty in the isotopics determination - This should be much smaller than the other uncertainties; (4) Systematic uncertainty due to position bias; and (5) Systematic uncertainty due to fluctuations in cosmic ray spallation. This one can be virtually eliminated by performing the background measurement with an empty vessel - but that may not be possible. We used modeling and experiments to quantify the systematic uncertainties. The calibration assumes a uniform distribution of material, but reality will be different. MCNPX modeling was used to quantify the positional bias. The model was benchmarked to build confidence in its results. Material at top of vessel is 44% greater than amount assayed, according to singles. Material near 19-tube detector is 38% less than amount assayed, according to singles. Cosmic ray spallation contributes significantly to the background. Comparing rates with and without a vessel showed that spallation adds an average of 27.27 singles/s and 5.45 doubles/s to background. Errors in the background rates were estimated at 20%.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-13T23:59:59.000Z

272

Developing the Sandia National Laboratories transportation infrastructure for isotope products and wastes  

SciTech Connect (OSTI)

The US Department of Energy (DOE) plans to establish a medical isotope project that would ensure a reliable domestic supply of molybdenum-99 ({sup 99}Mo) and related medical isotopes (Iodine-125, Iodine-131, and Xenon-133). The Department`s plan for production will modify the Annular Core Research Reactor (ACRR) and associated hot cell facility at Sandia National Laboratories (SNL)/New Mexico and the Chemistry and Metallurgy Research facility at Los Alamos National Laboratory (LANL). Transportation activities associated with such production is discussed.

Trennel, A.J.

1997-11-01T23:59:59.000Z

273

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update  

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

EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 November 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates * Disposition Maps - Current Tools Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of TRU with 89 percent of shipments departed from TRU waste sites as planned * Los Alamos: Met Framework Agreement goal for FY 13 ahead of schedule, disposing of over 1,800 cubic meters of legacy managed TRU waste * Oak Ridge: Partnered with regulators to develop strategy for

274

Preliminary Technology Readiness Assessment (TRA) for the Calcine Disposition Project Volume 2 (CDP)  

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

PRELIMINARY TECHNOLOGY PRELIMINARY TECHNOLOGY OF THE CALCINE Prepared by the U.S. Department of Energy ECHNOLOGY READINESS ASSESSMENT ALCINE DISPOSITION PROJECT VOLUME TWO Anthony F. Kluk Hoyt C. Johnson Clyde Phillip McGinnis Michael Rinker Steven L. Ross Herbert G. Sutter John Vienna February 2011 Prepared by the U.S. Department of Energy Washington, DC SSESSMENT ROJECT 412.09 (06/03/2009 - Rev. 11) CALCINE DISPOSITION PROJECT TECHNOLOGY MATURATION PLAN Identifier: Revision*: Page: PLN-1482 2 C-1 of C-317 Appendix C Appendix C Checklists for Critical Technology Elements and Technology Readiness Levels This appendix provides the CTE and TRL checklists for the CTEs. For the TRL questions that receive a "Y" (yes) response, the supporting documentation is provided with a complete reference at the

275

Portugal Egypt Figure 2. Natural gas supply and disposition in the United States, 2012  

U.S. Energy Information Administration (EIA) Indexed Site

Portugal Egypt Figure 2. Natural gas supply and disposition in the United States, 2012 (trillion cubic feet) Natural Gas Plant Liquids Production Gross Withdrawals From Gas and Oil Wells Nonhydrocarbon Gases Removed Vented/Flared Reservoir Repressuring Production Dry Gas Imports Canada Trinidad/Tobago Natural Gas Storage Facilities Exports Japan Canada Mexico Additions Withdrawals Gas Industry Use Residential Commercial Industrial Vehicle Fuel Electric Power 29.5 0.8 0.2 3.3 2.963 0.112 0.620 0.971 0.014 24.1 1.3 2.9 2.8 2.5 2.9 7.2 0.03 9.1 0.003 Sources: Energy Information Administration (EIA), Form EIA-176, "Annual Report of Natural and Supplemental Gas Supply and Disposition"; Form EIA-895, "Annual Quantity and

276

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

5 of 5 5 of 5 Final Environmental Impact Statement November 1999 Comment Response Document Volume III - Part B Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition Office of NEPA Policy and Assistance U.S. Department of Energy Office of Environment, Safety and Health

277

Environmental Assessment Addendum Disposition of Additional Waste at the Paducah Site  

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

FINDING OF NO SIGNIFICANT IMPACT FINDING OF NO SIGNIFICANT IMPACT WASTE DISPOSITION ACTIVITIES AT THE PADUCAH SITE PADUCAH, KENTUCKY AGENCY: U.S. DEPARTMENT OF ENERGY ACTION: FINDING OF NO SIGNIFICANT IMPACT SUMMARY: The U.S. Department of Energy (DOE) has completed an environmental assessment addendum (DOE/EA-1339-A), which is incorporated herein by reference, for proposed disposition of 17,600 m 3 of waste from the Paducah Site in Paducah, Kentucky. It is anticipated that most of the waste would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is not a major federal action that would significantly affect the quality of the human environment within the context of the

278

EIS-0283DS Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement, April 1999  

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

Sheet Sheet Responsible Agency: United States Department of Energy (DOE) Title: Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement (Supplement) (DOE/EIS-0283-DS) Locations of Candidate Sites: Idaho, North Carolina, South Carolina, Texas, Virginia, and Washington Contacts: For further information on the Supplement contact: For further information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Office of Fissile Materials Disposition U.S. Department of Energy P.O. Box 23786 Washington, DC 20026-3786 Voice: (202) 586-5368 Ms. Carol Borgstrom, Director Office of NEPA Policy and Assistance Office of Environment, Safety and Health U.S. Department of Energy 1000 Independence Ave., SW

279

Final Environmental Assessment for Waste Disposition Activities at the Paducah Site Paducah, Kentucky  

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

0-347(doc)/093002 0-347(doc)/093002 1 FINDING OF NO SIGNIFICANT IMPACT WASTE DISPOSITION ACTIVITIES AT THE PADUCAH SITE PADUCAH, KENTUCKY AGENCY: U.S. DEPARTMENT OF ENERGY ACTION: FINDING OF NO SIGNIFICANT IMPACT SUMMARY: The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1339), which is incorporated herein by reference, for proposed disposition of polychlorinated biphenyl (PCB) wastes, low-level radioactive waste (LLW), mixed low- level radioactive waste (MLLW), and transuranic (TRU) waste from the Paducah Gaseous Diffusion Plant Site (Paducah Site) in Paducah, Kentucky. All of the wastes would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is

280

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

4 of 5 4 of 5 Final Environmental Impact Statement November 1999 Comment Response Document Volume III - Part A Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition Office of NEPA Policy and Assistance U.S. Department of Energy Office of Environment, Safety and Health

Note: This page contains sample records for the topic "disposition medical isotope" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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281

U.S. weapons-usable plutonium disposition policy: Implementation of the MOX fuel option  

SciTech Connect (OSTI)

A comprehensive case study was conducted on the policy problem of disposing of US weapons-grade plutonium, which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to US plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective.

Woods, A.L. [ed.] [Amarillo National Resource Center for Plutonium, TX (United States); Gonzalez, V.L. [Texas A and M Univ., College Station, TX (United States). Dept. of Political Science

1998-10-01T23:59:59.000Z

282

Biomedical Ethics & Medical Humanities  

E-Print Network [OSTI]

List Sample Elective Courses Arts & Humanities Medical Scholars: Student Projects #12;2 What is BEMHBEMH Biomedical Ethics & Medical Humanities Scholarly Concentration Stanford University School? The Biomedical Ethics and Medical Humanities Scholarly Concentration is part of the new initiative at Stanford

Ford, James

283

Low-level Waste Safely Dispositioned Under Runoff Cover at SRS | Department  

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

Low-level Waste Safely Dispositioned Under Runoff Cover at SRS Low-level Waste Safely Dispositioned Under Runoff Cover at SRS Low-level Waste Safely Dispositioned Under Runoff Cover at SRS April 26, 2011 - 12:00pm Addthis The liner installer heat-welds a sand anchor closed. The sand anchors are installed under the liner and across the length of the slit trench to keep the liner in place and minimize the effects of wind lift. The liner installer heat-welds a sand anchor closed. The sand anchors are installed under the liner and across the length of the slit trench to keep the liner in place and minimize the effects of wind lift. A view of the Slit Trenches 1-4 operational cover in E Area. A view of the Slit Trenches 1-4 operational cover in E Area. The liner installer heat-welds a sand anchor closed. The sand anchors are installed under the liner and across the length of the slit trench to keep the liner in place and minimize the effects of wind lift.

284

Microsoft PowerPoint - FY09_11 Disposition Plan_090804  

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

to 2011 FIMS Disposition to 2011 FIMS Disposition Plan Phil Dalby, P.E., LEED AP Facilities Engineer Office of Engineering and Construction Management U. S. Department of Energy August 4, 2009 2 FY 2009 to FY 2011 Disposition Plan RPV # Of Assets GSF RPV # Of Assets Gross Sq Feet FY 02 N/A N/A N/A $322,545,118 379 1,533,715 - $2,914,059 $322,545,118 FY 03 N/A N/A N/A $313,800,817 420 1,140,524 - $2,166,996 $636,345,935 FY 04 N/A N/A N/A $678,724,838 536 2,878,328 - $5,468,823 $1,315,070,773 FY 05 $1,029,311,442 473 4,111,764 $1,047,538,247 488 4,101,396 102% $7,792,652 $2,362,609,020 FY 06 $788,456,532 270 1,773,232 $1,352,580,138 625 2,800,679 172% $5,321,290 $3,715,189,158 FY 07 $550,347,778 208 1,414,961 $595,332,143 243 1,568,969 108% $2,981,041 $4,310,521,301 FY 08 $312,272,791 114 782,388 $1,029,579,616 219 1,418,007 330%

285

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

SciTech Connect (OSTI)

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

Williams, K.A.

1999-10-01T23:59:59.000Z

286

Transportation requirements for the disposition of excess weapon plutonium by burning in fission reactors  

SciTech Connect (OSTI)

Both the US and Russia are planning to dispose of about 50 Mg of excess weapon plutonium over a 25-year period. One option is to transfer the plutonium to Advanced Light Water (power) Reactors (ALWRs) for use as fuel. Subsequent disposal would then be considered commercial spent fuel. This disposition option, like others, involves the transportation of plutonium in various material forms as it proceeds through various points in the recovery operation. This paper examines both the disposition option and the issues surrounding the transportation of 50 Mg of excess plutonium within the US under current regulatory and infrastructure constraints. Transportation issues include criticality control, shielding, and containment of the contents. Allowable limits on each of these issues are specified by the applicable (or selected) regulation. The composition and form of the radioactive materials to be transported will determine, in part, the applicable portions of the regulations as well as the packaging design. The regulations and the packaging design, along with safeguard and security issues, will determine the quantity of plutonium or fuel assemblies per package as well as the number of packages per shipment and the type of highway carrier. For the disposition of 50 Mg of weapon plutonium using ALWRs in a 25-year campaign, the annual shipment rates are determined for the various types of carriers.

Hovingh, J.; Walter, C.E.

1996-01-01T23:59:59.000Z

287

Study of plutonium disposition using existing GE advanced Boiling Water Reactors  

SciTech Connect (OSTI)

The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the US to dispose of 50 to 100 metric tons of excess of plutonium in a safe and proliferation resistant manner. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing permanent conversion and long-term diversion resistance to this material. The NAS study ``Management and Disposition of Excess Weapons Plutonium identified Light Water Reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a US disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a typical 1155 MWe GE Boiling Water Reactor (BWR) is utilized to convert the plutonium to spent fuel. A companion study of the Advanced BWR has recently been submitted. The MOX core design work that was conducted for the ABWR enabled GE to apply comparable fuel design concepts and consequently achieve full MOX core loading which optimize plutonium throughput for existing BWRs.

Not Available

1994-06-01T23:59:59.000Z

288

Development of a techno-economic model to optimization DOE spent nuclear fuel disposition  

SciTech Connect (OSTI)

The purpose of the National Spent Nuclear Fuel (NSNF) Program conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL) is to evaluate what to do with the spent nuclear fuel (SNF) in the Department of Energy (DOE) complex. Final disposition of the SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on the fuel type and the current locations of the fuel. One of the first steps associated with selecting one or more sites for treating the SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the electrometallurgical treatment process for fuels at several locations. The set of questions addresses all issues associated with the design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs will be applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment techniques for treating spent nuclear fuel.

Ramer, R.J.; Plum, M.M.; Adams, J.P.; Dahl, C.A.

1997-11-01T23:59:59.000Z

289

Comparisons between stable isotope tr  

Science Journals Connector (OSTI)

Nitrogen spiraling in streams: Comparisons between stable isotope tracer and nutrient addition experiments. Abstract—A common method to quantify stream.

2007-05-31T23:59:59.000Z

290

Medical Radioisotopes & Applications| U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

Isotope Isotope Related Reports » Medical Radioisotopes & Applications Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Funding Opportunities Nuclear Science Advisory Committee (NSAC) News & Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: sc.np@science.doe.gov More Information » Isotope Related Reports Medical Radioisotopes & Applications Print Text Size: A A A RSS Feeds FeedbackShare Page ISOTOPE HALF- LIFE APPLICATIONS Ac-225 10.0d Monoclonal antibody attachment used for cancer treatment (RIT), also parent of Bi-213. Ac-227 21.8y Parent of Ra-223 (Monoclonal antibody attachment used for cancer treatment (RIT).

291

RADIOCHEMICAL STUDIES OF NEUTRON DEFICIENT ACTINIDE ISOTOPES  

E-Print Network [OSTI]

Isotope Targets and Foils, AERE-R 5097, Paper 10 (1965). V.Isotope Targets and Foils, AERE-R 5097 Paper 12 (1965). K.M.Isotope Targets and Foils, AERE-R-5097 Paper 11 (1965). M.

Williams, Kimberly Eve

2011-01-01T23:59:59.000Z

292

Advanced isotope separation  

SciTech Connect (OSTI)

The Study Group briefly reviewed the technical status of the three Advanced Isotope Separation (AIS) processes. It also reviewed the evaluation work that has been carried out by DOE's Process Evaluation Board (PEB) and the Union Carbide Corporation-Nuclear Division (UCCND). The Study Group briefly reviewed a recent draft assessment made for DOE staff of the nonproliferation implications of the AIS technologies. The staff also very briefly summarized the status of GCEP and Advanced Centrifuge development. The Study Group concluded that: (1) there has not been sufficient progress to provide a firm scientific, technical or economic basis on which to select one of the three competing AIS processes for full-scale engineering development at this time; and (2) however, should budgetary restraints or other factors force such a selection, we believe that the evaluation process that is being carried out by the PEB provides the best basis available for making a decision. The Study Group recommended that: (1) any decisions on AIS processes should include a comparison with gas centrifuge processes, and should not be made independently from the plutonium isotope program; (2) in evaluating the various enrichment processes, all applicable costs (including R and D and sales overhead) and an appropriate discounting approach should be included in order to make comparisons on a private industry basis; (3) if the three AIS programs continue with limited resources, the work should be reoriented to focus only on the most pressing technical problems; and (4) if a decision is made to develop the Atomic Vapor Laser Isotope Separation process, the solid collector option should be pursued in parallel to alleviate the potential program impact of liquid collector thermal control problems.

Not Available

1982-05-04T23:59:59.000Z

293

Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM  

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

Integrated Facilities Disposition Project Integrated Facilities Disposition Project Technical Assistance Page 1 of 2 Oak Ridge National Laboratory Y-12 National Security Complex Tennessee Tennessee Assessment of the Integrated Facility Disposition Project at ORNL & Y-12 for Transfer of Facilities & Materials to EM Challenge In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). In parallel with the EM-1 initiative, the Oak Ridge Reservation was conducting a Critical

294

Isotopic Analysis- Fluid | Open Energy Information  

Open Energy Info (EERE)

Isotopic Analysis- Fluid Isotopic Analysis- Fluid Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Isotopic Analysis- Fluid Details Activities (61) Areas (32) Regions (6) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: Fluid Lab Analysis Parent Exploration Technique: Fluid Lab Analysis Information Provided by Technique Lithology: Water rock interaction Stratigraphic/Structural: Hydrological: Origin of hydrothermal fluids; Mixing of hydrothermal fluids Thermal: Isotopic ratios can be used to characterize and locate subsurface thermal anomalies. Dictionary.png Isotopic Analysis- Fluid: Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in

295

Isotope Development & Production | Nuclear Science | ORNL  

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

of the "Calutrons" (electromagnetic enrichment devices) were converted by ORNL to the separation and enrichment of stable isotopes and some actinide isotopes. Until 1998 when...

296

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

SciTech Connect (OSTI)

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

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

1997-08-01T23:59:59.000Z

297

ISOTOPE FRACTIONATION Isotopes are atoms whose nuclei contain the same number of protons but a different number of neutrons. The  

E-Print Network [OSTI]

the most abundant isotope appears in the denominator: b R = b E / a E (stable boron isotopes = , [ ] [ ] [ ] [ ]OOCOOC2 OOCOOC2 O 16181616 16181818 CO 18 2 + + = . The isotopic composition, , of a sample, determined____________________________ ISOTOPE FRACTIONATION ____________________________ Isotopes are atoms

Zeebe, Richard E.

298

Plan and schedule for disposition and regulatory compliance for miscellaneous streams. Revision 1  

SciTech Connect (OSTI)

On December 23, 1991, the U.S. Department of Energy, Richland Operations Office (RL) and the Washington State Department of Ecology (Ecology) agreed to adhere to the provisions of Department of Ecology Consent Order No. DE 91NM-177 (Consent Order). The Consent Order lists regulatory milestones for liquid effluent streams at the Hanford Site to comply with the permitting requirements of Washington Administrative Code (WAC) 173-216 (State Waste Discharge Permit Program) or WAC 173-218 (Washington Underground Injection Control Program) where applicable. Hanford Site liquid effluent streams discharging to the soil column have been categorized in the Consent Order as follows: Phase I Streams Phase II Streams Miscellaneous Streams. Phase I and Phase II Streams are addressed in two RL reports: {open_quotes}Plan and Schedule to Discontinue Disposal of Contaminated Liquids into the Soil Column at the Hanford Site{close_quotes} (DOE-RL 1987), and {open_quotes}Annual Status of the Report of the Plan and Schedule to Discontinue Disposal of Contaminated Liquids into the Soil Column at the Hanford Site{close_quotes}. Miscellaneous Streams are those liquid effluent streams discharged to the ground that are not categorized as Phase I or Phase II Streams. Miscellaneous Streams discharging to the soil column at the Hanford Site are subject to the requirements of several milestones identified in the Consent Order. This document provides a plan and schedule for the disposition of Miscellaneous Streams. The disposition process for the Miscellaneous Streams is facilitated using a decision tree format. The decision tree and corresponding analysis for determining appropriate disposition of these streams is presented in this document.

NONE

1994-12-01T23:59:59.000Z

299

Disposition of toxic PCB congeners in snapping turtle eggs: expressed as toxic equivalents of TCDD  

SciTech Connect (OSTI)

Studies of snapping turtles, taken from the region of the Upper Hudson River, in New York State, revealed exceedingly high levels of PCBs in the adipose tissue. There is evidence to suggest that large reserves of fat provide protection against chlorinated hydrocarbon toxicity. Such storage may protect snapping turtle eggs from disposition of toxic PCB congeners and account for the apparent absence of reports regarding detrimental effects on the hatchability of eggs from turtles living in the vicinity of the upper Hudson River. The present study was undertaken to determine if indeed these eggs are protected against disposition of toxic PCB congeners by the presence of large reserves of fat. Although tissue volumes play an important role in determining the initial site of disposition, the major factor controlling the elimination of these compounds involves metabolism. For simple halogenated benzenes as well as for more complex halogenated biphenyls, oxidative metabolism catalyzed by P-448, occurs primarily at the site of two adjacent unsubstituted carbon atoms via arene oxide formation leading to the formation of water soluble metabolites. Toxicological studies have demonstrated that the most toxic PCB congeners, isosteriomers of tetrachlorodibenzo-p-dioxin (TCDD), require no metabolic activation. These compounds have chlorine atoms in the meta and para positions of both rings. It may be concluded that the structures of PCB congeners and isomers which favor induction of cytochrome P-448 are also those which are toxic and resist metabolism. It is the objective of the present study to determine if the heavy fat bodies of the female turtle provide a sufficiently large sink to retain the toxic congeners and prevent their incorporation into the eggs.

Bryan, A.M.; Stone, W.B.; Olafsson, P.G.

1987-11-01T23:59:59.000Z

300

Bases, Assumptions, and Results of the Flowsheet Calculations for the Decision Phase Salt Disposition Alternatives  

SciTech Connect (OSTI)

The High Level Waste (HLW) Salt Disposition Systems Engineering Team was formed on March 13, 1998, and chartered to identify options, evaluate alternatives, and recommend a selected alternative(s) for processing HLW salt to a permitted wasteform. This requirement arises because the existing In-Tank Precipitation process at the Savannah River Site, as currently configured, cannot simultaneously meet the HLW production and Authorization Basis safety requirements. This engineering study was performed in four phases. This document provides the technical bases, assumptions, and results of this engineering study.

Dimenna, R.A.; Jacobs, R.A.; Taylor, G.A.; Durate, O.E.; Paul, P.K.; Elder, H.H.; Pike, J.A.; Fowler, J.R.; Rutland, P.L.; Gregory, M.V.; Smith III, F.G.; Hang, T.; Subosits, S.G.; Campbell, S.G.

2001-03-26T23:59:59.000Z

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


301

DOE plutonium disposition study: Pu consumption in ALWRs. Volume 2, Final report  

SciTech Connect (OSTI)

The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document Volume 2, provides a discussion of: Plutonium Fuel Cycle; Technology Needs; Regulatory Considerations; Cost and Schedule Estimates; and Deployment Strategy.

Not Available

1993-05-15T23:59:59.000Z

302

Apparatus and process for separating hydrogen isotopes  

DOE Patents [OSTI]

The apparatus and process for separating hydrogen isotopes is provided using dual columns, each column having an opposite hydrogen isotopic effect such that when a hydrogen isotope mixture feedstock is cycled between the two respective columns, two different hydrogen isotopes are separated from the feedstock.

Heung, Leung K; Sessions, Henry T; Xiao, Xin

2013-06-25T23:59:59.000Z

303

Medical Robots Surgical Assistants  

E-Print Network [OSTI]

1 Medical Robots Surgical Assistants · Efficacy of Procedure ­ Accuracy ­ Longevity ­ Invasiveness · Augment human capabilities ­ Enabling new procedures ­ Time under anaesthetic #12;2 Surgical Robots) ­ Sensei (Hansen Medical) Autonomous Surgical Robots Robodoc.com #12;3 Guided Surgical Robots Makosurgical

Pulfrey, David L.

304

New Program: NIH Medical  

E-Print Network [OSTI]

at a medical, dental, or veterinary school in the U.S. · Not currently enrolled in a combined professional In good standing at a medical, dental, or veterinary school Not currently enrolled in a combined://www.med.upenn.edu/apps/faculty/index.php/g20000320/p6071, for further information. Joint Initiative ­ Interventional Radiology · Joint initiative

Bushman, Frederic

305

Isotopic Analysis- Rock | Open Energy Information  

Open Energy Info (EERE)

Isotopic Analysis- Rock Isotopic Analysis- Rock Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Isotopic Analysis- Rock Details Activities (13) Areas (11) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: Rock Lab Analysis Parent Exploration Technique: Rock Lab Analysis Information Provided by Technique Lithology: Water rock interaction Stratigraphic/Structural: Hydrological: Thermal: Dictionary.png Isotopic Analysis- Rock: Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in a given system, while the conditions which increase/decrease the number of neutrons are well understood and measurable.

306

DOE/EIS-0283-SA1: Supplement Analysis and Amended Record of Decision for Changes Needed To the Surplus Plutonium Disposition Program (4/24/03)  

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

3-SA1 3-SA1 April 2003 Changes Needed To The Surplus Plutonium Disposition Program SUPPLEMENT ANALYSIS AND AMENDED RECORD OF DECISION U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. Table of Contents i Table of Contents List of Figures ................................................................................................................................. ii List of Tables .................................................................................................................................. ii List of Acronyms ...........................................................................................................................

307

Novel hybrid isotope separation scheme and apparatus  

DOE Patents [OSTI]

A method is described for yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which the specific isotope is to be isolated, radiating the gas with frequencies characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photoionization reaction of the desired isotope, and collecting the specific isotope ion by suitable ion collection means. 3 figures.

Maya, J.

1991-06-18T23:59:59.000Z

308

Novel hybrid isotope separation scheme and apparatus  

DOE Patents [OSTI]

A method of yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which the specific isotope is to be isolated, radiating the gas with frequencies characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photoionization reaction of the desired isotope, and collecting the specific isotope ion by suitable ion collection means.

Maya, Jakob (Brookline, MA)

1991-01-01T23:59:59.000Z

309

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

SciTech Connect (OSTI)

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

NONE

1996-09-01T23:59:59.000Z

310

A comparative assessment of the economics of plutonium disposition including comparison with other nuclear fuel cycles  

SciTech Connect (OSTI)

DOE has been evaluating three technologies for the disposition of approximately 50 metric tons of surplus plutonium from defense-related programs: reactors, immobilization, and deep boreholes. As part of the process supporting an early CY 1997 Record of Decision (ROD), a comprehensive assessment of technical viability, cost, and schedule has been conducted. Oak Ridge National Laboratory has managed and coordinated the life-cycle cost (LCC) assessment effort for this program. This paper discusses the economic analysis methodology and the results prior to ROD. Other objectives of the paper are to discuss major technical and economic issues that impact plutonium disposition cost and schedule. Also to compare the economics of a once-through weapons-derived MOX nuclear fuel cycle to other fuel cycles, such as those utilizing spent fuel reprocessing. To evaluate the economics of these technologies on an equitable basis, a set of cost estimating guidelines and a common cost-estimating format were utilized by all three technology teams. This paper also includes the major economic analysis assumptions and the comparative constant-dollar and discounted-dollar LCCs.

Williams, K.A.; Miller, J.W.; Reid, R.L.

1997-05-01T23:59:59.000Z

311

SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 4 TANK 21H QUALIFICATION SAMPLES  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H to qualify them for use in the Integrated Salt Disposition Program (ISDP) Batch 4 processing. All sample results agree with expectations based on prior analyses where available. No issues with the projected Salt Batch 4 strategy are identified. This revision includes additional data points that were not available in the original issue of the document, such as additional plutonium results, the results of the monosodium titanate (MST) sorption test and the extraction, scrub strip (ESS) test. This report covers the revision to the Tank 21H qualification sample results for Macrobatch (Salt Batch) 4 of the Integrated Salt Disposition Program (ISDP). A previous document covers initial characterization which includes results for a number of non-radiological analytes. These results were used to perform aluminum solubility modeling to determine the hydroxide needs for Salt Batch 4 to prevent the precipitation of solids. Sodium hydroxide was then added to Tank 21 and additional samples were pulled for the analyses discussed in this report. This work was specified by Task Technical Request and by Task Technical and Quality Assurance Plan (TTQAP).

Peters, T.; Fink, S.

2011-06-22T23:59:59.000Z

312

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons  

SciTech Connect (OSTI)

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the Fission Options'' provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium.

Omberg, R.P. (Westinghouse Hanford Co., Richland, WA (United States)); Walter, C.E. (Lawrence Livermore National Lab., CA (United States))

1993-02-05T23:59:59.000Z

313

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons  

SciTech Connect (OSTI)

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the ``Fission Options`` provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium.

Omberg, R.P. [Westinghouse Hanford Co., Richland, WA (United States); Walter, C.E. [Lawrence Livermore National Lab., CA (United States)

1993-02-05T23:59:59.000Z

314

Disposition of fuel elements from the Aberdeen and Sandia pulse reactor (SPR-II) assemblies  

SciTech Connect (OSTI)

We describe the disposition of fuel from the Aberdeen (APR) and the Sandia Pulse Reactors (SPR-II) which were used to provide intense neutron bursts for radiation effects testing. The enriched Uranium - 10% Molybdenum fuel from these reactors was shipped to the Los Alamos National Laboratory (LANL) for size reduction prior to shipment to the Savannah River Site (SRS) for final disposition in the H Canyon facility. The Shipper/Receiver Agreements (SRA), intra-DOE interfaces, criticality safety evaluations, safety and quality requirements and key materials management issues required for the successful completion of this project will be presented. This work is in support of the DOE Consolidation and Disposition program. Sandia National Laboratories (SNL) has operated pulse nuclear reactor research facilities for the Department of Energy since 1961. The Sandia Pulse Reactor (SPR-II) was a bare metal Godiva-type reactor. The reactor facilities have been used for research and development of nuclear and non-nuclear weapon systems, advanced nuclear reactors, reactor safety, simulation sources and energy related programs. The SPR-II was a fast burst reactor, designed and constructed by SNL that became operational in 1967. The SPR-ll core was a solid-metal fuel enriched to 93% {sup 235}U. The uranium was alloyed with 10 weight percent molybdenum to ensure the phase stabilization of the fuel. The core consisted of six fuel plates divided into two assemblies of three plates each. Figure 1 shows a cutaway diagram of the SPR-II Reactor with its decoupling shroud. NNSA charged Sandia with removing its category 1 and 2 special nuclear material by the end of 2008. The main impetus for this activity was based on NNSA Administrator Tom D'Agostino's six focus areas to reenergize NNSA's nuclear material consolidation and disposition efforts. For example, the removal of SPR-II from SNL to DAF was part of this undertaking. This project was in support of NNSA's efforts to consolidate the locations of special nuclear material (SNM) to reduce the cost of securing many SNM facilities. The removal of SPR-II from SNL was a significant accomplishment in SNL's de-inventory efforts and played a key role in reducing the number of locations requiring the expensive security measures required for category 1 and 2 SNM facilities. A similar pulse reactor was fabricated at the Y-12 National Security Complex beginning in the late 1960's. This Aberdeen Pulse Reactor (APR) was operated at the Army Pulse Radiation Facility (APRF) located at the Aberdeen Test Center (ATC) in Maryland. When the APRF was shut down in 2003, a portion of the DOE-owned Special Nuclear Material (SNM) was shipped to an interim facility for storage. Subsequently, the DOE determined that the material from both the SPR-II and the APR would be processed in the H-Canyon at the Savannah River Site (SRS). Because of the SRS receipt requirements some of the material was sent to the Los Alamos National Laboratory (LANL) for size-reduction prior to shipment to the SRS for final disposition.

Mckerley, Bill [Los Alamos National Laboratory; Bustamante, Jacqueline M [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Drypolcher, Anthony F [Los Alamos National Laboratory; Hickey, Joseph [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

315

Data Sharing Report Characterization of Isotope Row Facilities Oak Ridge National Laboratory Oak Ridge TN  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Oak Ridge Office of Environmental Management (EM-OR) requested that Oak Ridge Associated Universities (ORAU), working under the Oak Ridge Institute for Science and Education (ORISE) contract, provide technical and independent waste management planning support using funds provided by the American Recovery and Reinvestment Act (ARRA). Specifically, DOE EM-OR requested ORAU to plan and implement a survey approach, focused on characterizing the Isotope Row Facilities located at the Oak Ridge National Laboratory (ORNL) for future determination of an appropriate disposition pathway for building debris and systems, should the buildings be demolished. The characterization effort was designed to identify and quantify radiological and chemical contamination associated with building structures and process systems. The Isotope Row Facilities discussed in this report include Bldgs. 3030, 3031, 3032, 3033, 3033A, 3034, 3036, 3093, and 3118, and are located in the northeast quadrant of the main ORNL campus area, between Hillside and Central Avenues. Construction of the isotope production facilities was initiated in the late 1940s, with the exception of Bldgs. 3033A and 3118, which were enclosed in the early 1960s. The Isotope Row facilities were intended for the purpose of light industrial use for the processing, assemblage, and storage of radionuclides used for a variety of applications (ORNL 1952 and ORAU 2013). The Isotope Row Facilities provided laboratory and support services as part of the Isotopes Production and Distribution Program until 1989 when DOE mandated their shutdown (ORNL 1990). These facilities performed diverse research and developmental experiments in support of isotopes production. As a result of the many years of operations, various projects, and final cessation of operations, production was followed by inclusion into the surveillance and maintenance (S&M) project for eventual decontamination and decommissioning (D&D). The process for D&D and final dismantlement of facilities requires that the known contaminants of concern (COCs) be evaluated and quantified and to identify and quantify any additional contaminants in order to satisfy the waste acceptance criteria requirements for the desired disposal pathway. Known facility contaminants include, but are not limited to, asbestos-containing material (ACM), radiological contaminants, and chemical contaminants including polychlorinated biphenyls (PCBs) and metals.

Weaver, Phyllis C

2013-12-12T23:59:59.000Z

316

Quick-release medical tape  

E-Print Network [OSTI]

Medical tape that provides secure fixation of life-sustaining and -monitoring devices with quick, easy, damage-free removal represents a longstanding unmet medical need in neonatal care. During removal of current medical ...

Laulicht, Bryan E.

317

December 2009 ARMY MEDICAL LOGISTICS  

E-Print Network [OSTI]

FM 4-02.1 December 2009 ARMY MEDICAL LOGISTICS DISTRIBUTION RESTRICTION: Approved for public Medical Logistics Contents Page PREFACE...................................................................................................ix Chapter 1 OVERVIEW OF ARMY MEDICAL LOGISTICS................................................. 1-1 Section

US Army Corps of Engineers

318

Automated data extraction from in situ protein stable isotope...  

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

data extraction from in situ protein stable isotope probing studies. Automated data extraction from in situ protein stable isotope probing studies. Abstract: Protein stable isotope...

319

Copper isotope fractionation in acid mine drainage. | EMSL  

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

Copper isotope fractionation in acid mine drainage. Copper isotope fractionation in acid mine drainage. Abstract: We surveyed the Cu isotopic composition of primary minerals and...

320

Definition: Isotopic Analysis- Fluid | Open Energy Information  

Open Energy Info (EERE)

Definition Definition Edit with form History Facebook icon Twitter icon » Definition: Isotopic Analysis- Fluid Jump to: navigation, search Dictionary.png Isotopic Analysis- Fluid Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in a given system, while the conditions which increase/decrease the number of neutrons are well understood and measurable. Fluid isotopes are used to characterize a fluids origin, age, and/or interaction with rocks or other fluids based on unique isotopic ratios or concentrations.[1] View on Wikipedia Wikipedia Definition Isotope geochemistry is an aspect of geology based upon study of the relative and absolute concentrations of the elements and their isotopes in

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


321

Definition: Isotopic Analysis | Open Energy Information  

Open Energy Info (EERE)

Analysis Analysis Jump to: navigation, search Dictionary.png Isotopic Analysis Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in a given system, while the conditions which increase/decrease the number of neutrons are well understood and measurable.[1] View on Wikipedia Wikipedia Definition Isotope analysis is the identification of isotopic signature, the distribution of certain stable isotopes and chemical elements within chemical compounds. This can be applied to a food web to make it possible to draw direct inferences regarding diet, trophic level, and subsistence. Isotope ratios are measured using mass spectrometry, which separates the different isotopes of an element on the basis of their mass-to-charge

322

End of FY10 report - used fuel disposition technical bases and lessons learned : legal and regulatory framework for high-level waste disposition in the United States.  

SciTech Connect (OSTI)

This report examines the current policy, legal, and regulatory framework pertaining to used nuclear fuel and high level waste management in the United States. The goal is to identify potential changes that if made could add flexibility and possibly improve the chances of successfully implementing technical aspects of a nuclear waste policy. Experience suggests that the regulatory framework should be established prior to initiating future repository development. Concerning specifics of the regulatory framework, reasonable expectation as the standard of proof was successfully implemented and could be retained in the future; yet, the current classification system for radioactive waste, including hazardous constituents, warrants reexamination. Whether or not consideration of multiple sites are considered simultaneously in the future, inclusion of mechanisms such as deliberate use of performance assessment to manage site characterization would be wise. Because of experience gained here and abroad, diversity of geologic media is not particularly necessary as a criterion in site selection guidelines for multiple sites. Stepwise development of the repository program that includes flexibility also warrants serious consideration. Furthermore, integration of the waste management system from storage, transportation, and disposition, should be examined and would be facilitated by integration of the legal and regulatory framework. Finally, in order to enhance acceptability of future repository development, the national policy should be cognizant of those policy and technical attributes that enhance initial acceptance, and those policy and technical attributes that maintain and broaden credibility.

Weiner, Ruth F.; Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Rechard, Robert Paul; Perry, Frank (Los Alamos National Laboratory, Los Alamos, NM); Jenkins-Smith, Hank C. (University of Oklahoma, Norman, OK); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Nutt, Mark (Argonne National Laboratory, Argonne, IL); Cotton, Tom (Complex Systems Group, Washington DC)

2010-09-01T23:59:59.000Z

323

Review of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project, September 2011  

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

Facility Centered Assessment of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project September 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Introduction ............................................................................................................................ 1 2.0 Background ............................................................................................................................ 1 3.0 Results .................................................................................................................................... 2 4.0 Conclusions ............................................................................................................................ 7

324

Review of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project, September 2011  

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

Facility Centered Assessment of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project September 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Introduction ............................................................................................................................ 1 2.0 Background ............................................................................................................................ 1 3.0 Results .................................................................................................................................... 2 4.0 Conclusions ............................................................................................................................ 7

325

Sample results from the integrated salt disposition program macrobatch 6 tank 21H qualifications MST solids sample  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 6 processing. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake. The results of these analyses are reported and are within historical precedent.

Peters, T. B.

2013-02-26T23:59:59.000Z

326

Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky  

E-Print Network [OSTI]

Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky 16 September 2014 ABSTRACT: Green River Locks and Dams 3 through 6 and Barren River Lock and Dam 1 were. The Green River Locks and Dams 5 and 6 ceased operations in 1951 due to a marked decline in navigation

US Army Corps of Engineers

327

Process Guide for the Identification and Disposition of S/CI or Defective Items at Department of Energy Facilities  

Broader source: Energy.gov [DOE]

The Process Guide for the Identification and Disposition of S/CI or Defective Items was developed to help DOE facilities to collect, screen, communicate information, and dispose of S/CI or defective items that could potentially impact operations at DOE facilities.

328

A Roadmap and Discussion of Issues for Physics Analyses Required to Support Plutonium Disposition in VVER-1000 Reactors  

SciTech Connect (OSTI)

The purpose of this report is to document the physics analyses that must be performed to successfully disposition weapons-usable plutonium in VVER-1000 reactors in the Russian Federation. The report is a document to support programmatic and financial planning. It does not include documentation of the technical procedures by which physics analyses are performed, nor are the results of any analyses included.

Primm, R.T.; Drischler, J.D.; Pavlovichev, A.M. Styrine, Y.A.

2000-06-01T23:59:59.000Z

329

BioMedical Sciences BioMedical Sciences  

E-Print Network [OSTI]

BioMedical Sciences BioMedical Sciences As a professional working in the field of biomedical science, you'll perform essential tests that are vital to the well-being of our society. The BioMedical/Medical Laboratory Science, Cytotechnology, Biomedical Sciences and Public Health Microbiology. The Diagnostic

Saldin, Dilano

330

Medical Education: Assessment in Medical Education  

Science Journals Connector (OSTI)

...Ideally, the assessment of competence (what the student or physician is able to do) should provide insight into actual performance (what he or she does habitually when not observed), as well as the capacity to adapt to change, find and generate new knowledge, and improve overall performance. Competence... This article in the Medical Education series provides a conceptual framework for and a brief update on commonly used and emerging methods of assessment, discusses the strengths and limitations of each method, and identifies several major challenges in assessing professional competence and performance.

Epstein R.M.

2007-01-25T23:59:59.000Z

331

A strategy for intensive production of molybdenum-99 isotopes for nuclear medicine using CANDU reactors  

Science Journals Connector (OSTI)

Technetium-99m is an important medical isotope utilized worldwide in nuclear medicine and is produced from the decay of its parent isotope, molybdenum-99. The online fueling capability and compact fuel of the CANDU®11CANDU is a trademark of Atomic Energy of Canada Limited. reactor allows for the potential production of large quantities of 99Mo. This paper proposes 99Mo production strategies using modified target fuel bundles loaded into CANDU fuel channels. Using a small group of channels a yield of 89–113% of the weekly world demand for 99Mo can be obtained.

A.C. Morreale; D.R. Novog; J.C. Luxat

2012-01-01T23:59:59.000Z

332

Analysis and section of processes for the disposition of excess fissile material from nuclear weapon dismantlement in the United States  

SciTech Connect (OSTI)

The end of the cold war and the acceleration of nuclear disarmament efforts by the United States (US) and Russia are generating large quantities of surplus fissile nuclear materials that are no longer needed for military purposes. The safe and secure disposition of this surplus material to prevent theft or reuse in weapons has become a high priority for the US Department of Energy (USDOE). Many options exist for storage and disposition (use or disposal) of these surplus materials. The criteria, which have been developed from the basis for a preliminary ``screening`` of options, to eliminate from further consideration those options that do not meet minimal requirements. Factors, or attributes, contained in the screening and selection criteria include: (1) resistance to theft and diversion by unauthorized parties, (2) resistance to retrieval, extraction, and reuse by the host nation, (3) technical viability, (4) environmental, safety, and health impacts, (5) cost effectiveness, (6) timeliness, (7) fostering of progress and cooperation with Russia and others, (8) public and institutional acceptance, and (9) additional benefits. The evaluation of environmental impacts, in accordance with the US National Environmental Policy Ac (NEPA) process, is an integral part of the overall evaluation process. Because of the variety of physical and chemical forms of the nuclear material inventory, and because of the large number of possible disposition technologies and final forms, several hundred possible pathways to disposition have been defined and have undergone a systematic selection process. Also, because nuclear material disposition will have far ranging impacts, extensive public, in the form of public and stakeholder, input was integral to the selection process.

Myers, B.R.; Armantrout, G.A. [Lawrence Livermore National Lab., CA (United States); Erickson, R. [Los Alamos National Lab., NM (United States)

1995-02-01T23:59:59.000Z

333

DOE-STD-1120-2005; Integration of Environment Safety and Health into Facility Disposition Activities  

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

20-2005 20-2005 Volume 1 of 2 April 2005 DOE STANDARD INTEGRATION OF ENVIRONMENT, SAFETY, AND HEALTH INTO FACILITY DISPOSITION ACTIVITIES Volume 1 of 2: Documented Safety Analysis for Decommissioning and Environmental Restoration Projects U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE TS i This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (423) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000.

334

DOE/EA-1607 FINAL ENVIRONMENTAL ASSESSMENT DISPOSITION OF DOE EXCESS  

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

µCi/cc microcuries per cubic centimeter µCi/cc microcuries per cubic centimeter MAP mitigation action plan MEI maximally exposed individual mg/kg milligrams per kilogram mrem millirem mSv millisievert MT metric ton MTCA Model Toxics Control Act MTU metric tons of uranium N/A not applicable Final Environmental Assessment: Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium vi NAAQS National Ambient Air Quality Standards NEF National Enrichment Facility NEPA National Environmental Policy Act NRC U.S. Nuclear Regulatory Commission NU natural uranium NUF 6 natural uranium hexafluoride pCi/g picocuries per gram PEIS programmatic environmental impact statement PM 2.5 particulate matter with a diameter of 2.5 microns or less PM 10 particulate matter with a diameter of 10 microns or less

335

Microsoft Word - Fuel Cycle Potential Waste Inventory for Disposition R5a.docx  

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

Fuel Cycle Potential Fuel Cycle Potential Waste Inventory for Disposition Prepared for U.S. Department of Energy Used Nuclear Fuel Joe T. Carter, SRNL Alan J. Luptak, INL Jason Gastelum, PNNL Christine Stockman, SNL Andrew Miller, SNL July 2012 FCR&D-USED-2010-000031 Rev 5 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial

336

Used Fuel Disposition Campaign Phase I Ring Compression Testing of High  

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

Phase I Ring Compression Testing of Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign Phase I Ring Compression Testing of High Burnup Cladding The purpose of ring compression testing is to generate data to support the development of the technical basis for extended storage and transportation of high-burnup fuel. This report highlights the results of completed Phase I testing of high-burnup M5® cladding and the revised three-year test plan. The goal of the ring compression testing is to identify process conditions that would minimize radial-hydride formation and the corresponding DBTT of high-burnup fuel cladding and to generate data and models to support the development of the technical basis for extended storage and transportation of high-burnup fuel.

337

Microsoft PowerPoint - S08-05_Leishear_Salt Disposition Initiative.ppt  

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

Blending in Nuclear Waste Tanks Blending in Nuclear Waste Tanks Bob Leishear Savannah River Remediation Salt Disposition Engineering November 17, 2010 Print Close 2 Blending in Nuclear Waste Tanks Volume 37.1 Million Gallons (Mgal) Curies 183 MCi (52%) 169 MCi (48%) 352 Million Curies (MCi) 171 MCi (49%) Sludge 34.2 Mgal (92%) 2.9 Mgal (8%) 18.4 Mgal (49%) Salt Supernate 12 MCi (3%) Saltcake 15.8 Mgal (43%) Print Close 3 Blending in Nuclear Waste Tanks Sample of Vitrified Radioactive Glass Print Close 4 Blending in Nuclear Waste Tanks SDU 3 SDU 3 SDU 2 SDU 2 SDU (Vault) 4 SDU (Vault) 4 SDU (Vault) 1 SDU (Vault) 1 Cell A Cell B Saltstone Production Facility Saltstone Production Facility Print Close 5 Blending in Nuclear Waste Tanks Print Close 6 Blending in Nuclear Waste Tanks Sludge Salt Feed Solutions Print Close 7 Experimental Strategy Scale-

338

Record of decision for the Storage and Disposition of Weapons- Usable  

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

14 14 Federal Register / Vol. 62, No. 13 / Tuesday, January 21, 1997 / Notices Responses: 18,620 Burden Hours: 64,310. Abstract: The LESCP is being conducted in response to the legislative requirement in P.L. 103-382, Section 1501 to assess the implementation of Title I and related education reforms. The information will be used to examine changes-over a 3-year period-that are occurring in schools and classrooms. Teachers and teacher aides will complete a mail survey, and district Title I administrators, principals, school-based staff, and parents will be interviewed during on- site field work. [FR Doc. 97-1307 Filed 1-17-97; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF ENERGY Record of decision for the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic

339

May Also Be Used U.S. DEPARTMENT OF ENERGY REQUEST FOR RECORDS DISPOSITION AUTHORIZATION  

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

5 5 (06-93) 05-90 Edition May Also Be Used U.S. DEPARTMENT OF ENERGY REQUEST FOR RECORDS DISPOSITION AUTHORIZATION OMB Control No. 1910-1700 OMB Burden Disclosure Statement on Back 1. Control Number 2a. Organizational Unit and Routing Symbol 2b. Departmental Organization Contractor Organization 3a. Volume On Hand (Cu. Ft.) 3b. Volume Accumulated Annually (Estimate Cu. Ft.) 4. Record Dates (From/To) 5. Identification of Filing Unit (Include type of record, function performed, security classification (or other restrictions), and other descriptive facts) 6. Appraisal (Include justification for retention period. Indicate relationship of filing unit to any other related filing unit in the same or other organizations. Also, indicate retention period in U.S. Department of Energy (DOE), if subsequent transfer to National Archives

340

GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE FRIT B COMPOSITION FOR PLUTONIUM DISPOSITION  

SciTech Connect (OSTI)

The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) to disposition excess weapons-usable plutonium. A plutonium glass waste form is a leading candidate for immobilization of the plutonium for subsequent disposition in a geologic repository. A reference glass composition (Lanthanide Borosilicate (LaBS) Frit B) was developed during the Plutonium Immobilization Program (PIP) to immobilize plutonium. A limited amount of performance testing was performed on this baseline composition before efforts to further pursue Pu disposition via a glass waste form ceased. Therefore, the objectives of this present task were to fabricate plutonium loaded LaBS Frit B glass and perform additional testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the Yucca Mountain Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit B composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL) and for additional performance testing at Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL). The glass was characterized using x-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. A series of PCTs were conducted at SRNL with varying exposed surface area and test durations. The leachates from these tests were analyzed to determine the dissolved concentrations of key elements. Acid stripping of leach vessels was performed to determine the concentration of the glass constituents that may have sorbed on the vessels during leach testing. Additionally, the leachate solutions were ultrafiltered to quantify colloid formation. The leached solids from select PCTs were examined in an attempt to evaluate the Pu and neutron absorber release behavior from the glass and to identify the formation of alteration phases on the glass surface. Characterization of the glass prior to testing revealed that some undissolved plutonium oxide was present in the glass. The undissolved particles had a disk-like morphology and likely formed via coarsening of particles in areas compositionally enriched in plutonium. Similar disk-like PuO{sub 2} phases were observed in previous LaBS glass testing at PNNL. In that work, researchers concluded that plutonium formed with this morphology as a result of the leaching process. It was more likely that the presence of the plutonium oxide crystals in the PNNL testing was a result of glass fabrication. A series of PCTs were conducted at 90 C in ASTM Type 1 water. The PCT-Method A (PCT-A) was conducted to compare the Pu LaBS Frit B glass durability to current requirements for High Level Waste (HLW) glass in a geologic repository. The PCT-A test has a strict protocol and is designed to specifically be used to evaluate whether the chemical durability and elemental release characteristics of a nuclear waste glass have been consistently controlled during production and, thus, meet the repository acceptance requirements. The PCT-A results on the Pu containing LaBS Frit B glass showed that the glass was very durable with a normalized elemental release value for boron of approximately 0.02 g/L. This boron release value was better than two orders of magnitude better from a boron release standpoint than the current Environmental Assessment (EA) glass used for repository acceptance. The boron release value for EA glass is 16.7 g/L.

Marra, J

2006-01-19T23:59:59.000Z

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


341

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

SciTech Connect (OSTI)

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

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

1998-08-01T23:59:59.000Z

342

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

SciTech Connect (OSTI)

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

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

1998-08-01T23:59:59.000Z

343

Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes  

SciTech Connect (OSTI)

The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

Not Available

1984-01-01T23:59:59.000Z

344

Medical applications of evolutionary computation  

Science Journals Connector (OSTI)

Keywords: cartesian genetic programming, evolutionary computation, genetic programming, mammography, medical applications, neurodegenerative diseases, parkinson's disease

Stephen L. Smith

2014-07-01T23:59:59.000Z

345

Medical Technology for Superior Patient  

E-Print Network [OSTI]

of electromagnetic interference, hazardous vapors, electrical power, and acoustic noise · Medical device integration

Hayden, Nancy J.

346

Progress in the Use of Isotopes: The Atomic Triad - Reactors, Radioisotopes and Radiation  

DOE R&D Accomplishments [OSTI]

Recent years have seen a substantial growth in the use of isotopes in medicine, agriculture, and industry: up to the minute information on the production and use of isotopes in the U.S. is presented. The application of radioisotopes to industrial processes and manufacturing operations has expanded more rapidly than any one except its most ardent advocates expected. New uses and new users are numerous. The adoption by industry of low level counting techniques which make possible the use of carbon-14 and tritium in the control of industrial processes and in certain exploratory and research problems is perhaps most promising of current developments. The latest information on savings to industry will be presented. The medical application of isotopes has continued to develop at a rapid pace. The current trend appears to be in the direction of improvements in technique and the substitution of more effective isotopes for those presently in use. Potential and actual benefits accruing from the use of isotopes in agriculture are reviewed. The various methods of production of radioisotopes are discussed. Not only the present methods but also interesting new possibilities are covered. Although isotopes are but one of the many peaceful uses of the atom, it is the first to pay its way. (auth)

Libby, W. F.

1958-08-04T23:59:59.000Z

347

DOE/EA-1651: Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee (January 2010)  

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

51 51 Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee U. S. Department of Energy Oak Ridge Office Oak Ridge, Tennessee January 2010 FINDING OF NO SIGNIFICANT IMPACT URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U.S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has completed the Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory [DOE/EA-1651]. This environmental assessment (EA) evaluates the impacts of planned activities to modify selected

348

Identification of isotopically primitive interplanetary dust particles: A NanoSIMS isotopic imaging study  

E-Print Network [OSTI]

Identification of isotopically primitive interplanetary dust particles: A NanoSIMS isotopic imaging contain larger regions with more modest enrichments in 15 N, leading to average bulk N isotopic of those IDPs that have anomalous bulk N isotopic compositions. These particles typically also contain

349

Spinelolivine magnesium isotope thermometry in the mantle and implications for the Mg isotopic composition of Earth  

E-Print Network [OSTI]

Spinel­olivine magnesium isotope thermometry in the mantle and implications for the Mg isotopic: magnesium isotopes mantle geochemistry meteorites MC-ICPMS The magnesium isotopic composition of Earth., 2004; Poitrasson et al., 2005; Georg et al., 2007; Poitrasson, 2007; Weyer et al., 2007). Magnesium

Manning, Craig

350

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

SciTech Connect (OSTI)

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

Not Available

1994-06-01T23:59:59.000Z

351

Respiration, photosynthesis, and oxygen isotope fractionation in ...  

Science Journals Connector (OSTI)

Jan 25, 1971 ... Respiration, photosynthesis, and oxygen isotope fractionation in oceanic surface water1. Peter M. Kroopnick. Department of Oceanography,.

2000-01-04T23:59:59.000Z

352

Magnesium Isotope Effects in Enzymatic Phosphorylation  

Science Journals Connector (OSTI)

So far as magnesium isotope effect in phosphorylation is an unexpected and unusual phenomenon, it is worthy to shortly describe materials and technologies used in isotopic biochemical experiments. ... Isotope-containing MgCl2 samples were obtained using treatment of magnesium oxides 24MgO, 25MgO, 26MgO, and *MgO with analytically pure HCl (*Mg means magnesium with natural abundance of the three isotopes; see Table 1). ...

Anatoly L. Buchachenko; Dmitry A. Kouznetsov; Natalia N. Breslavskaya; Marina A. Orlova

2008-02-05T23:59:59.000Z

353

Magnetic Isotope Effect in the Photolysis of Organotin Compounds  

Science Journals Connector (OSTI)

Fractionation of isotopes in chemical and biochemical reactions is induced by two isotope effects; their origin and physical nature are shown in Figure 1. ... The classical isotope effect (CIE) sorts isotopic nuclei on their masses; the magnetic isotope effect (MIE) demonstrates nuclear spin selectivity of reactions and separates isotopic nuclei according to their magnetic moments.1 ...

Anatoly L. Buchachenko; Vladimir L. Ivanov; Vitaly A. Roznyatovsky; Yuri A. Ustynyuk

2006-03-02T23:59:59.000Z

354

Photo-oxidation of Water by Molecular Oxygen: Isotope Exchange and Isotope Effects  

Science Journals Connector (OSTI)

In order to detect the reaction, we used water highly enriched with isotopes 17O and 18O, controlling the isotope composition of molecular oxygen before and after reaction. ... stability of heavy-isotope clumps'; slower kinetics of reactions requiring the breakage of bonds between heavy isotopes; the mass dependence of diffusive and thermo-gravitational fractionations; mixing between components that differ from one another in bulk isotopic compn.; biochem. ... Study of oxygen three-isotope behavior during thermal decompn. of naturally occurring carbonates of calcium and magnesium in vacuo revealed that, surprisingly, anomalous isotopic compns. ...

Anatoly L. Buchachenko; Elena O. Dubinina

2011-03-30T23:59:59.000Z

355

Medical Professionalism in Society  

Science Journals Connector (OSTI)

...-dollar industry and those who seek greater government regulation. Physicians, feeling trapped between these camps, are turning to unionization and other tactics. In the first half of this century, medical professionalism was generally understood according to the structural–functional approach of Talcott... Today, at the dawn of a new century, genuine medical professionalism is in peril. Increasing-ly, physicians encounter perverse financial incentives, fierce market competition, and the erosion of patients' trust,1–7 yet most physicians are ill equipped to ...

Wynia M.K.Latham S.R.Kao A.C.Berg J.W.Emanuel L.L.

1999-11-18T23:59:59.000Z

356

Handbook of Medical Psychiatry  

Science Journals Connector (OSTI)

The title of this book is something of a misnomer. At nearly 1000 pages, with 130 contributors, this is not the kind of "handbook" that will fit into the side pocket of one's laboratory coat. Moreover, the term "medical psychiatry," as used here, appears to delineate content that most cognoscenti would... The title of this book is something of a misnomer. At nearly 1000 pages, with 130 contributors, this is not the kind of “handbook” that will fit into the side pocket of one's laboratory coat. Moreover, the term “medical psychiatry,” as used here, appears ...

Price L.H.

2004-02-19T23:59:59.000Z

357

NUCLEAR ISOTOPIC DILUTION OF HIGHLY ENRICHED URANIUM BY DRY BLENDING VIA THE RM-2 MILL TECHNOLOGY  

SciTech Connect (OSTI)

DOE has initiated numerous activities to focus on identifying material management strategies to disposition various excess fissile materials. In particular the INEEL has stored 1,700 Kg of offspec HEU at INTEC in CPP-651 vault facility. Currently, the proposed strategies for dispositioning are (a) aqueous dissolution and down blending to LEU via facilities at SRS followed by shipment of the liquid LEU to NFS for fabrication into LWR fuel for the TVA reactors and (b) dilution of the HEU to 0.9% for discard as a waste stream that would no longer have a criticality or proliferation risk without being processed through some type of enrichment system. Dispositioning this inventory as a waste stream via aqueous processing at SRS has been determined to be too costly. Thus, dry blending is the only proposed disposal process for the uranium oxide materials in the CPP-651 vault. Isotopic dilution of HEU to typically less than 20% by dry blending is the key to solving the dispositioning issue (i.e., proliferation) posed by HEU stored at INEEL. RM-2 mill is a technology developed and successfully tested for producing ultra-fine particles by dry grinding. Grinding action in RM-2 mill produces a two million-fold increase in the number of particles being blended in a centrifugal field. In a previous study, the concept of achieving complete and adequate blending and mixing (i.e., no methods were identified to easily separate and concentrate one titanium compound from the other) in remarkably short processing times was successfully tested with surrogate materials (titanium dioxide and titanium mono-oxide) with different particle sizes, hardness and densities. In the current project, the RM-2 milling technology was thoroughly tested with mixtures of natural uranium oxide (NU) and depleted uranium oxide (DU) stock to prove its performance. The effects of mill operating and design variables on the blending of NU/DU oxides were evaluated. First, NU and DU both made of the same oxide, UO{sub 3}, was used in the testing. Next, NU made up of UO{sub 3} and DU made up of UO{sub 2} was used in the test work. In every test, the blend achieved was characterized by spatial sampling of the ground product and analyzing for {sup 235}U concentration. The test work proved that these uranium oxide materials can be blended successfully. The spatial concentration was found to be uniform. Next, sintered thorium oxide pellets were used as surrogate for light water breeder reactor pellets (LWBR). To simulate LWBR pellet dispositioning, the thorium oxide pellets were first ground to a powder form and then the powder was blended with NU. In these tests also the concentration of {sup 235}U and {sup 232}Th in blended products fell within established limits proving the success of RM-2 milling technology. RM-2 milling technology is applicable to any dry radioactive waste, especially brittle solids that can be ground up and mixed with the non-radioactive stock.

Raj K. Rajamani; Sanjeeva Latchireddi; Vikas Devrani; Harappan Sethi; Roger Henry; Nate Chipman

2003-08-01T23:59:59.000Z

358

Medical Editors' Dilemma  

Science Journals Connector (OSTI)

...an exhaustive survey of all literature published on the subject between...tables to provide a ready review of infor-mation useful in...writing in Science ("Medical literature: The campus with-out tumult...responsible for the generation of bioenergy in plant and animal cells...

Frederick Silber

1970-10-23T23:59:59.000Z

359

MEDICAL SCIENCE SYLLABUS 2014  

E-Print Network [OSTI]

Neurology 63 Medical Oncology/Hematology 64 Hematology 65 Internal Related Radiology 66 Radiation Oncology;Pediatrics 71 General Pediatrics 72 Dermatology 73 Phychiatry 74 Laboratory Medicine 75 Metabolomics Research Breast Surgery 84 Cardiovascular Surgery 85 Thoracic Surgery 86 Pediatric Surgery 87 Surgery Related

Banbara, Mutsunori

360

Medical imaging systems  

DOE Patents [OSTI]

A medical imaging system provides simultaneous rendering of visible light and diagnostic or functional images. The system may be portable, and may include adapters for connecting various light sources and cameras in open surgical environments or laparascopic or endoscopic environments. A user interface provides control over the functionality of the integrated imaging system. In one embodiment, the system provides a tool for surgical pathology.

Frangioni, John V

2013-06-25T23:59:59.000Z

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


361

Isotope Evidence for Ozone Formation on Surfaces  

Science Journals Connector (OSTI)

Remarkably, the gas-phase recombination or association reaction of ozone has an unusually large (?10%) isotope effect and shows almost equal enrichments of the ozone molecules containing two different oxygen isotopes. ... For a better understanding of the pressure and temperature dependence of ozone isotopic composition in oxygen discharges, we developed a relatively simple isotope kinetic model that accounts for the processes of (i) heterogeneous ozone formation at the reactor walls, (ii) isotope exchange of oxygen atoms with O2 molecules, and (iii) ozone formation in the gas phase. ...

Christof Janssen; Béla Tuzson

2010-05-06T23:59:59.000Z

362

Magnesium-Isotope Fractionation During Plant Growth  

Science Journals Connector (OSTI)

With three stable isotopes naturally abundant (24Mg, 78.992%; 25Mg, 10.003%; 26Mg, 11.005%), magnesium stable isotope fractionation may provide insights into these cycles. ... Measurements of the magnesium isotopic composition of chlorophylls, seeds, shoots, roots, leaves, exudates, and the limiting nutrient solution over time show that the plant appears to establish an isotopic equilibrium with the nutrient available to it and that the plant (in particular, the seeds and exudates) becomes enriched in the heavy isotopes of magnesium in a mass-dependent relationship as the plant reaches maturity. ...

Jay R. Black; Emanuel Epstein; William D. Rains; Qing-zhu Yin; William H. Casey

2008-10-01T23:59:59.000Z

363

Slow Neutron Scattering by the Titanium Isotopes  

Science Journals Connector (OSTI)

Neutron diffraction studies are reported on isotopically enriched samples of TiO2 from which are evaluated the coherent scattering amplitudes of the titanium isotopes. Scattering amplitudes of +0.48, +0.33, -0.58, +0.08, and +0.55×10-12 cm were established for the titanium isotopes of mass 46, 47, 48, 49, and 50, respectively. The major isotope Ti48 is thus responsible for the anomalous scattering amplitude, -0.34×10-12 cm, characteristic of the normal element. Pronounced nuclear scattering resonance effects on the observed neutron scattering are suggested to occur for most of the isotopes.

C. G. Shull; M. K. Wilkinson; M. H. Mueller

1960-05-01T23:59:59.000Z

364

Isotope Effects in Isotope-Exchange Reactions:? Evidence for a Large 12C/13C Kinetic Isotope Effect in the Gas Phase  

Science Journals Connector (OSTI)

Isotope effects are key to understanding reaction mechanisms because isotopic substitution affects reaction rates and equilibrium constants. ... These values are considered in relation to the vapor pressures of isotopic compds., the geologic abundance of C and O isotopes, the relative abundance of O isotopes in air and H2O, and variations in the at. ...

Giulia de Petris; Anna Troiani

2008-03-05T23:59:59.000Z

365

Definition: Isotopic Analysis- Rock | Open Energy Information  

Open Energy Info (EERE)

Isotopic Analysis- Rock Isotopic Analysis- Rock Jump to: navigation, search Dictionary.png Isotopic Analysis- Rock Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in a given system, while the conditions which increase/decrease the number of neutrons are well understood and measurable.[1] View on Wikipedia Wikipedia Definition References ↑ http://wwwrcamnl.wr.usgs.gov/isoig/isopubs/itchch2.html Ret LikeLike UnlikeLike You like this.Sign Up to see what your friends like. rieved from "http://en.openei.org/w/index.php?title=Definition:Isotopic_Analysis-_Rock&oldid=687702" Category: Definitions What links here Related changes Special pages Printable version Permanent link Browse properties

366

Metabolism and disposition of 1-bromopropane in rats and mice following inhalation or intravenous administration  

Science Journals Connector (OSTI)

Workplace exposure to 1-bromopropane (1-BrP) can potentially occur during its use in spray adhesives, fats, waxes, and resins. 1-BrP may be used to replace ozone depleting solvents, resulting in an increase in its annual production in the US, which currently exceeds 1 million pounds. The potential for human exposure to 1-BrP and the reports of adverse effects associated with potential occupational exposure to high levels of 1-BrP have increased the need for the development of biomarkers of exposure and an improved understanding of 1-BrP metabolism and disposition. In this study, the factors influencing the disposition and biotransformation of 1-BrP were examined in male F344 rats and B6C3F1 mice following inhalation exposure (800 ppm) or intravenous administration (5, 20, and 100 mg/kg). [1,2,3-13C]1-BrP and [1-14C]1-BrP were administered to enable characterization of urinary metabolites using NMR spectroscopy, LC–MS/MS, and HPLC coupled radiochromatography. Exhaled breath volatile organic chemicals (VOC), exhaled CO2, urine, feces, and tissues were collected for up to 48 h post-administration for determination of radioactivity distribution. Rats and mice exhaled a majority of the administered dose as either VOC (40–72%) or 14CO2 (10–30%). For rats, but not mice, the percentage of the dose exhaled as VOC increased between the mid (? 50%) and high (? 71%) dose groups; while the percentage of the dose exhaled as 14CO2 decreased (19 to 10%). The molar ratio of exhaled 14CO2 to total released bromide, which decreased as dose increased, demonstrated that the proportion of 1-BrP metabolized via oxidation relative to pathways dependent on glutathione conjugation is inversely proportional to dose in the rat. [14C]1-BrP equivalents were recovered in urine (13–17%, rats; 14–23% mice), feces (rats and mice administered i.v. 5 to 100 mg/kg [14C]1-BrP. Metabolites characterized in urine of rats and mice include N-acetyl-S-propylcysteine, N-acetyl-3-(propylsulfinyl)alanine, N-acetyl-S-(2-hydroxypropyl)cysteine, 1-bromo-2-hydroxypropane-O-glucuronide, N-acetyl-S-(2-oxopropyl)cysteine, and N-acetyl-3-[(2-oxopropyl)sulfinyl]alanine. These metabolites may be formed following oxidation of 1-bromopropane to 1-bromo-2-propanol and bromoacetone and following subsequent glutathione conjugation with either of these compounds. Rats pretreated with 1-aminobenzotriazole (ABT), a potent inhibitor of P450 excreted less in urine (?30%), exhaled as 14CO2 (?80%), or retained in liver (?90%), with a concomitant increase in radioactivity expired as VOC (?52%). Following ABT pretreatment, rat urinary metabolites were reduced in number from 10 to 1, N-acetyl-S-propylcysteine, which accounted for > 90% of the total urinary radioactivity in ABT pretreated rats. Together, these data demonstrate a role for cytochrome P450 and glutathione in the dose-dependent metabolism and disposition of 1-BrP in the rat.

C.E. Garner; S.C.J. Sumner; J.G. Davis; J.P. Burgess; Y. Yueh; J. Demeter; Q. Zhan; J. Valentine; A.R. Jeffcoat; L.T. Burka; J.M. Mathews

2006-01-01T23:59:59.000Z

367

Metabolism and disposition of 1-bromopropane in rats and mice following inhalation or intravenous administration  

SciTech Connect (OSTI)

Workplace exposure to 1-bromopropane (1-BrP) can potentially occur during its use in spray adhesives, fats, waxes, and resins. 1-BrP may be used to replace ozone depleting solvents, resulting in an increase in its annual production in the US, which currently exceeds 1 million pounds. The potential for human exposure to 1-BrP and the reports of adverse effects associated with potential occupational exposure to high levels of 1-BrP have increased the need for the development of biomarkers of exposure and an improved understanding of 1-BrP metabolism and disposition. In this study, the factors influencing the disposition and biotransformation of 1-BrP were examined in male F344 rats and B6C3F1 mice following inhalation exposure (800 ppm) or intravenous administration (5, 20, and 100 mg/kg). [1,2,3-{sup 13}C]1-BrP and [1-{sup 14}C]1-BrP were administered to enable characterization of urinary metabolites using NMR spectroscopy, LC-MS/MS, and HPLC coupled radiochromatography. Exhaled breath volatile organic chemicals (VOC), exhaled CO{sub 2}, urine, feces, and tissues were collected for up to 48 h post-administration for determination of radioactivity distribution. Rats and mice exhaled a majority of the administered dose as either VOC (40-72%) or {sup 14}CO{sub 2} (10-30%). For rats, but not mice, the percentage of the dose exhaled as VOC increased between the mid ({approx} 50%) and high ({approx} 71%) dose groups; while the percentage of the dose exhaled as {sup 14}CO{sub 2} decreased (19 to 10%). The molar ratio of exhaled {sup 14}CO{sub 2} to total released bromide, which decreased as dose increased, demonstrated that the proportion of 1-BrP metabolized via oxidation relative to pathways dependent on glutathione conjugation is inversely proportional to dose in the rat. [{sup 14}C]1-BrP equivalents were recovered in urine (13-17%, rats; 14-23% mice), feces (< 2%), or retained in the tissues and carcass (< 6%) of rats and mice administered i.v. 5 to 100 mg/kg [{sup 14}C]1-BrP. Metabolites characterized in urine of rats and mice include N-acetyl-S-propylcysteine, N-acetyl-3-(propylsulfinyl)alanine, N-acetyl-S-(2-hydroxypropyl)cysteine, 1-bromo-2-hydroxypropane-O-glucuronide, N-acetyl-S-(2-oxopropyl)cysteine, and N-acetyl-3-[(2-oxopropyl)sulfinyl]alanine. These metabolites may be formed following oxidation of 1-bromopropane to 1-bromo-2-propanol and bromoacetone and following subsequent glutathione conjugation with either of these compounds. Rats pretreated with 1-aminobenzotriazole (ABT), a potent inhibitor of P450 excreted less in urine ({down_arrow}30%), exhaled as {sup 14}CO2 ({down_arrow}80%), or retained in liver ({down_arrow}90%), with a concomitant increase in radioactivity expired as VOC ({up_arrow}52%). Following ABT pretreatment, rat urinary metabolites were reduced in number from 10 to 1, N-acetyl-S-propylcysteine, which accounted for > 90% of the total urinary radioactivity in ABT pretreated rats. Together, these data demonstrate a role for cytochrome P450 and glutathione in the dose-dependent metabolism and disposition of 1-BrP in the rat.

Garner, C.E. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)]. E-mail: cegarner@rti.org; Sumner, S.C.J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Davis, J.G. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Burgess, J.P. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Yueh, Y. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Demeter, J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Zhan, Q. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Valentine, J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Jeffcoat, A.R. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Burka, L.T. [National Institute of Environmental Health Sciences, Research Triangle Park, NC 27709 (United States); Mathews, J.M. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)

2006-08-15T23:59:59.000Z

368

GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE GLASS FOR PLUTONIUM DISPOSITION  

SciTech Connect (OSTI)

The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) in Aiken, SC, to disposition excess weapons-usable plutonium. A plutonium glass waste form is a leading candidate for immobilization of the plutonium for subsequent disposition in a geologic repository. The objectives of this present task were to fabricate plutonium-loaded lanthanide borosilicate (LaBS) Frit B glass and perform testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the proposed Federal Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit B composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support glass durability testing via the ASTM Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL). The glass was characterized with X-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. This characterization revealed some crystalline PuO{sub 2} inclusions with disk-like morphology present in the as fabricated, quench-cooled glass. A series of PCTs was conducted at SRNL with varying exposed surface area and test durations. Filtered leachates from these tests were analyzed to determine the dissolved concentrations of key elements. The leachate solutions were also ultrafiltered to quantify colloid formation. Leached solids from select PCTs were examined in an attempt to evaluate the Pu and neutron absorber release behavior from the glass and to investigate formation of alteration phases on the glass surface. A series of PCTs was conducted at 90 C in ASTM Type 1 water to compare the Pu LaBS Frit B glass durability to current requirements for High Level Waste (HLW) glass in a geologic repository. The PCT (7-day static test with powdered glass) results on the Pu-containing LaBS Frit B glass at SA/V of {approx} 2000 m{sup -1} showed that the glass was very durable with an average normalized elemental release value for boron of 0.013 g/m{sup 2}. This boron release value is {approx} 640X lower than normalized boron release from current Environmental Assessment (EA) glass used for repository acceptance. The PCT-B (7, 14, 28 and 56-day, static test with powdered glass) normalized elemental releases were similar to the normalized elemental release values from PCT-A testing, indicating that the LaBS Frit B glass is very durable as measured by the PCT. Normalized plutonium releases were essentially the same within the analytical uncertainty of the ICP-MS methods used to quantify plutonium in the 0.45 {micro}m-filtered leachates and ultra-filtered leachates, indicating that colloidal plutonium species do not form under the PCT conditions used in this study.

Crawford, C; James Marra, J; Ned Bibler, N

2007-02-12T23:59:59.000Z

369

SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

Peters, T.; Fink, S.

2012-04-24T23:59:59.000Z

370

Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives  

SciTech Connect (OSTI)

This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

NONE

1997-01-01T23:59:59.000Z

371

Isotope hydrology of catchment basins: lithogenic and cosmogenic isotopic systems  

SciTech Connect (OSTI)

A variety of physical processes affect solute concentrations within catchment waters. The isotopic compositions of the solutes can indicate which processes have determined the observed concentrations. These processes together constitute the physical history of the water. Many solutes in natural waters are derived from the interaction between the water and the rock and/or soil within the system - these are termed `lithogenic` solutes. The isotopic compositions of these solutes provide information regarding rock-water interactions. Many other solutes have their isotopic compositions determined both within and outside of the catchment - i.e., in addition to being derived from catchment rock and soil, they are solutes that are also transported into the catchment. Important members of this group include solutes that have isotopic compositions produced by atomic particle interactions with other nuclides. The source of the atomic particles can be cosmic radiation (producing `cosmogenic` nuclides in the atmosphere and land surface), anthropogenic nuclear reactions (producing `thermonuclear` nuclides), or radioactive and fission decay of naturally-occurring elements, principally {sup 238}U (producing `in-situ` lithogenic nuclides in the deep subsurface). Current language usage often combines all of the atomic particle-produced nuclides under the heading `cosmogenic nuclides`, and for simplicity we will often follow that usage here, although always indicating which variety is being discussed. This paper addresses the processes that affect the lithogenic and cosmogenic solute concentrations in catchment waters, and how the isotopic compositions of the solutes can be used in integrative ways to identify these processes, thereby revealing the physical history of the water within a catchment system. The concept of a `system` is important in catchment hydrology. A catchment is the smallest landscape unit that can both participate in all of the aspects of the hydrologic cycle and also be treated as a mostly closed system for mass balance considerations. It is the near closure of the system that permits well- constrained chemical mass balance calculations to be made. These calculations generally focus of lithogenic solutes, and therefore in our discussions of lithogenic nuclides in the paper, the concept of chemical mass balance in a nearly dosed system will play an important role. Examination of the isotopic compositions of solutes provides a better understanding of the variety of processes controlling mass balance. It is with this approach that we examined the variety of processes occurring within the catchment system, such as weathering and soil production, generation of stormflow and streamflow (hydrograph separation), movement of soil pore water, groundwater flow, and the overall processes involved with basinal water balance. In this paper, the term `nuclide` will be used when referring to a nuclear species that contains a particular number of protons and neutrons. The term is not specific to any element. The term `isotope` will be used to distinguish nuclear species of a given element (atoms with the same number of protons). That is to say, there are many nuclides in nature - for example, {sup 36}Cl, {sup 87}Sr, {sup 238}U; the element has four naturally-occurring isotopes - {sup 87}Sr, and {sup 88}Sr. This paper will first discuss the general principles that underlie the study of lithogenic and cosmogenic nuclides in hydrology, and provide references to some of the more important studies applying these principles and nuclides. We then turn in the second section to a discussion of their specific applications in catchment- scale systems. The final section of this paper discusses new directions in the application of lithogenic and cosmogenic nuclides to catchment hydrology, with some thoughts concerning possible applications that still remain unexplored.

Nimz, G. J., LLNL

1998-06-01T23:59:59.000Z

372

The Effects of Music-Mathematics Integrated Curriculum and Instruction on Elementary Students’ Mathematics Achievement and Dispositions  

E-Print Network [OSTI]

THE EFFECTS OF MUSIC-MATHEMATICS INTEGRATED CURRICULUM AND INSTRUCTION ON ELEMENTARY STUDENTS? MATHEMATICS ACHIEVEMENT AND DISPOSITIONS A Dissertation by SONG AN Submitted to the Office of Graduate Studies of Texas A...&M University in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY May 2012 Major Subject: Curriculum and Instruction THE EFFECTS OF MUSIC-MATHEMATICS INTEGRATED CURRICULUM AND INSTRUCTION ON ELEMENTARY STUDENTS...

An, Song

2012-07-16T23:59:59.000Z

373

Evaluation of Udder Conformation, Weight, Body Condition, Reproduction, Disposition, and Calf Growth in Bos indicus – Bos taurus Cows  

E-Print Network [OSTI]

Condition, Reproduction, Disposition, and Calf Growth in Bos indicus ? Bos taurus Cows. (August 2011) Aaron Jay Cooper, B.S., Texas A&M University; M.S., University of Nebraska-Lincoln Chair of Advisory Committee: Dr. James O. Sanders Data were... of Texas A&M University in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY August 2011 Major Subject: Animal Breeding Evaluation of Udder Conformation, Weight, Body...

Cooper, Aaron Jay

2011-10-21T23:59:59.000Z

374

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

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site(SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. SRS has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 2 or 3 facility with storage of bulk PuO{sub 2} and assembly, storage, and shipping of fuel bundles in an S and S Category 1 facility. The total Category 1 approach, which is the recommended option, would be done in the 221-H Canyon Building. A facility that was never in service will be removed from one area, and a hardened wall will be constructed in another area to accommodate execution of the LA fuel fabrication. The non-Category 1 approach would require removal of process equipment in the FB-Line metal production and packaging glove boxes, which requires work in a contamination area. The Immobilization Hot Demonstration Program equipment in the Savannah River Technology Center would need to be removed to accommodate pellet fabrication. This work would also be in a contaminated area.

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

1998-08-01T23:59:59.000Z

375

Kinetic Isotope Effects in Cycloreversion of Rhenium (V) Diolates  

Science Journals Connector (OSTI)

The isotope effects were all calculated from these ratios according to the equation25 (F = extent of reaction; R = isotopic ratio vs reference at extent of reaction F; R0 = initial isotopic ratio vs reference). ... The magnitudes of small kinetic isotope effects (KIEs) are amplified in the isotopic compn. of starting materials recovered from reactions taken to high conversions. ... The magnitudes of small kinetic isotope effects (KIEs) are amplified in the isotopic compn. of starting materials recovered from reactions taken to high conversions. ...

Kevin P. Gable; Fedor A. Zhuravlev

2002-03-21T23:59:59.000Z

376

Transfer of excess nuclear material from Los Alamos to Savannah River site for long-term disposition  

SciTech Connect (OSTI)

Los Alamos National Laboratory is preparing excess nuclear material for shipment to Savannah River Site (SRS) for final disposition. Prior to shipment the nuclear material will be stabilized and packaged to meet strict criteria. The criterion that must be met include: (1) the DOE stabilization, packaging and storage requirements for plutonium bearing materials, DOE-STD-3013, (2) shipping container packaging requirements, (3) SRS packaging and storage criteria, and (4) DOE Material Disposition criteria for either immobilization or MOX reactor fuel. Another issue in preparing for this transfer is the DOE certification of shipping containers and the availability of shipping containers. This transfer of the nuclear material is fully supported by the EM, DP and NN Sections of the DOE, as well as, by LANL and SRS, yet a strong collaboration is needed to meet all established requirements relating to stabilization, packaging, shipment, storage and final disposition. This paper will present the overall objectives, the issues and the planned strategy to accomplish this nuclear material transfer.

Hoth, C. W. (Carl W.); Yarbro, T. F. (Tresa F.); Foster, Lynn A.

2001-06-01T23:59:59.000Z

377

Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program  

SciTech Connect (OSTI)

This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

1997-12-01T23:59:59.000Z

378

Ethics in medical research  

Science Journals Connector (OSTI)

Abstract Ethics, an essential dimension of human research, is considered both as discipline and practice. For clinical research, ethically justified criteria for the design, conduct, and review of clinical investigation can be identified by obligations to both the researcher and human subject. Informed consent, confidentiality, privacy, privileged communication, and respect and responsibility are key elements of ethics in research. A systematic literature search of English-language articles on Medline, ISI web of knowledge, Sciencedirect, Google scholar, the Cochrane database of evidence-based reviews, and the Database of Abstracts of Reviews of Effects was performed by connecting the Mesh terms (“ethics”, “medical research”, research ethics”, “medical education”, “research ethics principles”. The abstracts of 461 articles were reviewed for the relevancy of topic and analyzed in terms of application and validity. Out of these, 21 studies were found relevant as they concentrated principles of ethics in medical research, their practical applications, and suggested guidelines for future research. Research ethics committees must promote greater understanding of ethical issues on biomedical research. These committees function for submission, consideration, evaluation, and communication of findings. Application, research protocol, patient information leaflet and informed consent form, and any other supporting documentation are thoroughly reviewed by research ethics committees for legal and moral safety, integrity, and welfare of the research subjects.

Salman Yousuf Guraya; N.J.M. London; Shaista Salman Guraya

2014-01-01T23:59:59.000Z

379

Third Annual Medical Education Day  

E-Print Network [OSTI]

Fellowships 16 Branstad Distinguished Educator 17 Medical Education Posters #12;5 Related Center Faculty1 Third Annual Medical Education Day February 1, 2013 Center for Education in Medicine Northwestern University Feinberg School of Medicine #12;Third Annual Medical Education Day at Northwestern University

Engman, David M.

380

Fusion reactions with germanium isotopes  

Science Journals Connector (OSTI)

Measurements of the fusion of 16O and 27Al with a series of germanium isotopes are analyzed within a coupled-channels approach. It is found that couplings based interactions that are linear in the deformation amplitudes are insufficient in reproducing the data. In order to obtain reasonable fits, it is necessary also to include couplings based on quadratic interactions. The analysis suggests that the nuclear radius of 72Ge is significantly smaller than predicted from a smooth interpolation between other germanium isotopes. The large prolate deformation of 74Ge, which has been proposed as the preferred solution to measurements of the quadrupole moment of the 2+ state, is not supported by the analysis; the near spherical solution is more likely.

H. Esbensen

2003-09-04T23:59:59.000Z

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


381

Magnesium Isotopes in Halo Stars  

E-Print Network [OSTI]

We have determined Mg isotope ratios in halo field dwarfs and giants in the globular cluster M71 based on high S/N high spectral resolution (R = 10$^5$) Keck HIRES spectra. Unlike previous claims of an important contribution from intermediate-mass AGB stars to the Galactic halo, we find that our $^{26}$Mg/$^{24}$Mg ratios can be explained by massive stars.

Jorge Melendez; Judith G. Cohen

2007-08-29T23:59:59.000Z

382

Process modeling of plutonium conversion and MOX fabrication for plutonium disposition  

SciTech Connect (OSTI)

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

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

1998-10-01T23:59:59.000Z

383

Transportable Vitrification System RCRA Closure Practical Waste Disposition Saves Time And Money  

SciTech Connect (OSTI)

The Transportable Vitrification System (TVS) was a large-scale vitrification system for the treatment of mixed wastes. The wastes contained both hazardous and radioactive materials in the form of sludge, soil, and ash. The TVS was developed to be moved to various United States Department of Energy (DOE) facilities to vitrify mixed waste as needed. The TVS consists of four primary modules: (1) Waste and Additive Materials Processing Module; (2) Melter Module; (3) Emissions Control Module; and (4) Control and Services Module. The TVS was demonstrated at the East Tennessee Technology Park (ETTP) during September and October of 1997. During this period, approximately 16,000 pounds of actual mixed waste was processed, producing over 17,000 pounds of glass. After the demonstration was complete it was determined that it was more expensive to use the TVS unit to treat and dispose of mixed waste than to direct bury this waste in Utah permitted facility. Thus, DOE had to perform a Resource Conservation and Recovery Act (RCRA) closure of the facility and find a reuse for as much of the equipment as possible. This paper will focus on the following items associated with this successful RCRA closure project: TVS site closure design and implementation; characterization activities focused on waste disposition; pollution prevention through reuse; waste minimization efforts to reduce mixed waste to be disposed; and lessons learned that would be integrated in future projects of this magnitude.

Brill, Angie; Boles, Roger; Byars, Woody

2003-02-26T23:59:59.000Z

384

Lessons Learned from Three Mile Island Packaging, Transportation and Disposition that Apply to Fukushima Daiichi Recovery  

SciTech Connect (OSTI)

Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics: packaging, transportation, and disposition. This research work was performed as a collaboration between Japan’s Central Research Institute of Electric Power Industry (CRIEPI) and the Idaho National Laboratory (INL). Hundreds of TMI-2 related documents were searched and pertinent information was gleaned from these documents. Other important information was also obtained by interviewing employees who were involved first hand in various aspects of the TMI-2 cleanup effort. This paper is organized into three main sections: (1) Transport from Three Mile Island to Central Facilities Area at INL, (2) Transport from INL Central Receiving Facility to INL Test Area North (TAN) and wet storage at TAN, and (3) Transport from TAN to INL Idaho Nuclear Technology and Engineering Center (INTEC) and Dry Storage at INTEC. Within each of these sections, lessons learned from performing recovery activities are presented and their applicability to the Fukushima Daiichi nuclear power plant cleanup are outlined.

Layne Pincock; Wendell Hintze; Dr. Koji Shirai

2012-07-01T23:59:59.000Z

385

Nuclear Energy Protocol for Research Isotopes Owen Lowe  

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

Protocol for Protocol for Research Isotopes Owen Lowe Office of Isotopes for Medicine and Science Office of Nuclear Energy, Science and Technology April 16, 2002 Isotopes for Life Isotopes for Life Isotopes for Life Office of Nuclear Energy, Science and Technology Lowe/April16_02 NEPRI to NERAC.ppt (2) Nuclear Energy Protocol For Research Isotopes Nuclear Energy Protocol For Research Isotopes Why NEPRI? 6 NEPRI implements DOE funding priorities for fiscal year 2003 6 NEPRI will * Bring order to DOE's responses to requests for research isotopes * Introduce a high-quality peer review to the selection of research isotopes * Enable DOE to concentrate on operating its unique isotope production facilities Isotopes for Life Isotopes for Life Isotopes for Life Office of Nuclear Energy, Science and Technology

386

Strategic Isotope Production | ornl.gov  

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

Strategic Isotope Strategic Isotope Production SHARE Strategic Isotope Production Typical capsules used in the transport of 252Cf source material inside heavily shielded shipping casks. ORNL's unique facilities at the High Flux Isotope Reactor (HFIR), Radiochemical Engineering Development Center (REDC), Irradiated Fuels Examination Laboratory (IFEL), and Irradiated Materials Examination Testing facility (IMET) are routinely used in the production, purification, packaging, and shipping of a number of isotopes of national importance, including: 75Se, 63Ni, 238Pu, 252Cf, and others. The intense neutron flux of the HFIR (2.0 x 1015 neutrons/cm²·s) permits the rapid formation of such isotopes. These highly irradiated materials are then processed and packaged for shipping using the facilities at the REDC, IFEL, and IMET.

387

Electromagnetic Isotope Separation Lab (EMIS) | ORNL  

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

Electromagnetic Isotope Separation Lab Electromagnetic Isotope Separation Lab May 30, 2013 ORNL established the Stable Isotope Enrichment Laboratory (SIEL) as part of a project funded by the DOE Office of Science, Nuclear Physics Program to develop a modernized electromagnetic isotope separator (EMIS), optimized for separation of a wide range of stable isotopes. The SIEL is located in the Building 6010 Shield Test Station, space formerly allocated to the Oak Ridge Electron Linear Accelerator, on the main campus of ORNL. ORNL staff have designed and built a nominal 10 mA ion current EMIS (sum of all isotopes at the collector) in the SIEL. This EMIS is currently being tested to determine basic performance metrics such as throughput and enrichment factor per pass. This EMIS unit and space will be used to

388

Medical Screening | Department of Energy  

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

Program Program Implementation » Medical Screening Medical Screening Medical Screening: Provide medical screening exams that are designed to check for health conditions related to occupational exposures to former workers who choose to participate in the program, including a re-screen exam every three years. Conventional Medical Screening Program Medical screening is a strategy used to identify diseases or conditions in a select population at an early stage, often before signs and symptoms develop, and to refer individuals with suspicious findings to their personal physician or a specialist for further testing, diagnosis, and treatment. The program is not intended to serve as a substitute for routine medical exams through an individual's personal physician. Early Lung Cancer Detection Program

389

Providence Newberg Medical Center  

High Performance Buildings Database

Newberg, OR In 2002, Providence Health & Services began planning a new 188,000 square foot medical center in Newberg, Oregon to respond to the growing community's need for accessible health care. Since this was Providence's first new hospital in almost thirty years, its leaders decided to approach the project through innovative planning, design, and construction, including the achievement of lifecycle energy savings and a potential LEED certification. The hospital is comprised of 40 inpatient beds with views out to the surrounding rural landscape or into lushly planted internal courtyards.

390

Enforcement Letter, International Isotopes Idaho Inc - August...  

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

Isotopes Idaho, Inc. related to the Relocation of an Irradiated Pellet at the Test Reactor Area Hot Cell Facility at the Idaho National Engineering and Environmental...

391

Category:Isotope Geothermometry | Open Energy Information  

Open Energy Info (EERE)

Login | Sign Up Search Category Edit History Facebook icon Twitter icon Category:Isotope Geothermometry Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home...

392

Integration of Nontraditional Isotopic Systems Into Reaction...  

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

minerals in geothermal systems (feldspars, epidote, and calcite) often control fracture permeability changes. Measurements of Ca and Sr isotopic fractionation at high...

393

Science with Beams of Radioactive Isotopes  

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

2015 The International Chemical Congress of Pacific Basin Societies Science with Beams of Radioactive Isotopes ( 340) Honolulu, Hawaii, USA December 15-20, 2015 Science...

394

Integration of Nontraditional Isotopic Systems Into Reaction...  

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

of EGS For Exploration, Evaluation of Water-Rock Interaction, and Impacts of Water Chemistry on Reservoir Sustainability Integration of Nontraditional Isotopic Systems Into...

395

Medical Exam Scheduling - HPMC Occupational Health Services  

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

Analysis Human Reliability Program (HRP) Industrial Rehabilitation & Ergonomics Infection Control & Immunizations Influenza Immunization Program Medical Exam Scheduling Medical...

396

Medical Exams - HPMC Occupational Health Services  

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

Analysis Human Reliability Program (HRP) Industrial Rehabilitation & Ergonomics Infection Control & Immunizations Influenza Immunization Program Medical Exam Scheduling Medical...

397

Medical Monitoring Exam - HPMC Occupational Health Services  

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

Analysis Human Reliability Program (HRP) Industrial Rehabilitation & Ergonomics Infection Control & Immunizations Influenza Immunization Program Medical Exam Scheduling Medical...

398

Research with fast radioactive isotope beams at RIKEN  

Science Journals Connector (OSTI)

......moments of neutron-rich boron isotopes were measured by the...many neutron-rich isotopes. To exploit fully the...most straightforward determination of the charge distribution...called KISS (KEK isotope separation system......

Tohru Motobayashi; Hiroyoshi Sakurai

2012-01-01T23:59:59.000Z

399

Isotope-Selective Detection and Imaging of Organic Nanolayers  

Science Journals Connector (OSTI)

Isotope-Selective Detection and Imaging of Organic Nanolayers ... We show isotopic selectivity of MRFM for three nuclei, 1H, 31P, and 13C, in organic materials. ... data to further distinguish and characterize the 2 isotopes. ...

H. J. Mamin; T. H. Oosterkamp; M. Poggio; C. L. Degen; C. T. Rettner; D. Rugar

2009-07-09T23:59:59.000Z

400

Medical image classification with multiple kernel learning  

Science Journals Connector (OSTI)

Nowadays, medical images are generated by hospitals and medical centers rapidly. The large volume of medical image data produces a strong need to effective medical image retrieval. The visual characteristic of medical image, such as modality, anatomical ... Keywords: feature fusion, image classification, medical imaging, multiple kernel learning

Hong Wu; Hao Zhang; Chao Li

2010-12-01T23:59:59.000Z

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


401

Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

Peters, T. B.; Washington, A. L. II

2013-08-08T23:59:59.000Z

402

Medical Screening Protocol for the Former Worker Medical Screening...  

Office of Environmental Management (EM)

Medical Screening Program (FWP) is to provide interested former workers with targeted testing to screen for selected adverse health effects potentially related to their work in...

403

Solvent Isotope-Induced Equilibrium Perturbation for Isocitrate Lyase  

Science Journals Connector (OSTI)

Solvent Isotope-Induced Equilibrium Perturbation for Isocitrate Lyase ... Solvent isotopic composition can influence both the rates of enzyme-catalyzed reactions (solvent kinetic isotope effects) and, in the case of solvent-derived deuterium incorporation into nonexchangeable C–H bonds in products, solvent equilibrium isotope effects. ... In this study, we report the solvent isotope-induced transient change in the concentration and isotopic composition of the reactants. ...

Christine E. Quartararo; Timin Hadi; Sean M. Cahill; John S. Blanchard

2013-11-21T23:59:59.000Z

404

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope...  

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

Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G...

405

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope...  

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

Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of...

406

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope...  

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

Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR...

407

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope...  

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

Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR...

408

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope...  

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

Management- Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C...

409

Stable Isotope, Site-Specific Mass Tagging For Protein Identification  

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

Stable Isotope, Site-Specific Mass Tagging For Protein Identification Stable Isotope, Site-Specific Mass Tagging For Protein Identification Proteolytic peptide mass mapping as...

410

Enriched Stable Isotope Materials and Chemistry | ornl.gov  

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

Enriched Stable Isotope Materials and Chemistry SHARE Enriched Stable Isotope Materials and Chemistry Reductiondistillation of calcium-48 metal valued at over 900,000. An...

411

Isotopic Analysis- Gas At Chena Geothermal Area (Kolker, Et Al...  

Open Energy Info (EERE)

Laboratory sampling and analysis of He isotopes from Chena Hot Springs. Notes Helium isotope measurements indicate there is no magmatic or mantle input at the Chena Geothermal...

412

Development of a Micropyrolyzer for Enhanced Isotope Ratio Measurement...  

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

Micropyrolyzer for Enhanced Isotope Ratio Measurement. Development of a Micropyrolyzer for Enhanced Isotope Ratio Measurement. Abstract: This paper presents design, fabrication and...

413

Medical Screening | Department of Energy  

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

for routine medical exams through an individual's personal physician. Early Lung Cancer Detection Program Since 2000, DOE has made screening for occupational lung cancer with...

414

Medication List- September 14, 2010  

Broader source: Energy.gov [DOE]

This scale is created to provide a guide for the physician determination of ability to work for HRP certified persons with certain conditions and while taking certain medications.

415

Faculty Position Therapeutic Medical Physics  

E-Print Network [OSTI]

spectroscopy, fluoroscopy, ultrasound, digital radiography, and nuclear medicine. The Colorado State University of subjects in Radiation Therapy Physics, Medical Imaging Physics, and Radiological Physics and Dosimetry

416

The Quest for the Heaviest Uranium Isotope  

E-Print Network [OSTI]

We study Uranium isotopes and surrounding elements at very large neutron number excess. Relativistic mean field and Skyrme-type approaches with different parametrizations are used in the study. Most models show clear indications for isotopes that are stable with respect to neutron emission far beyond N=184 up to the range of around N=258.

S. Schramm; D. Gridnev; D. V. Tarasov; V. N. Tarasov; W. Greiner

2011-07-06T23:59:59.000Z

417

Advanced Mass Spectrometers for Hydrogen Isotope Analyses  

SciTech Connect (OSTI)

This report is a summary of the results of a joint Savannah River Laboratory (SRL) - Savannah River Plant (SRP) ''Hydrogen Isotope Mass Spectrometer Evaluation Program''. The program was undertaken to evaluate two prototype hydrogen isotope mass spectrometers and obtain sufficient data to permit SRP personnel to specify the mass spectrometers to replace obsolete instruments.

Chastagner, P.

2001-08-01T23:59:59.000Z

418

Isotopes  

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

are saving lives, advancing cutting-edge research and keeping the U.S. safe. Strontium-82 produced at Los Alamos is used in hospitals nation- and world-wide for critical...

419

ISOTOPES  

E-Print Network [OSTI]

Research, Division of Nuclear Sciences of the Basic Energy Sciences ProgramResearch, Division of Nuclear Sciences of the Basic Energy Sciences Program

Lederer, C. Michael

2013-01-01T23:59:59.000Z

420

ISOTOPES  

E-Print Network [OSTI]

5-7. 1975, British Nuclear Engineering Society (1975). 87.London, March British Nuclear Engineering Society (1975).T.H. Pigford, Nuclear Chemical Engineering (1St edition),

Lederer, C. Michael

2013-01-01T23:59:59.000Z

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


421

ISOTOPES  

E-Print Network [OSTI]

uranium, heavy-water-moderated CANDU reactor, as contrastedis important, and in the CANDU power reactor, which uses

Lederer, C. Michael

2013-01-01T23:59:59.000Z

422

It's Elemental - Isotopes of the Element Francium  

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

Radon Radon Previous Element (Radon) The Periodic Table of Elements Next Element (Radium) Radium Isotopes of the Element Francium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Francium has no naturally occurring isotopes. Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 199 12 milliseconds Alpha Decay > 0.00% Electron Capture No Data Available 200 49 milliseconds Alpha Decay 100.00% 201 62 milliseconds Alpha Decay 100.00% 201m 19 milliseconds Alpha Decay 100.00% 202 0.30 seconds Alpha Decay 100.00% 202m 0.29 seconds Alpha Decay 100.00% 203 0.55 seconds Alpha Decay <= 100.00% 204 1.8 seconds Alpha Decay 92.00%

423

It's Elemental - Isotopes of the Element Radon  

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

Astatine Astatine Previous Element (Astatine) The Periodic Table of Elements Next Element (Francium) Francium Isotopes of the Element Radon [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Radon has no naturally occurring isotopes. Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 193 1.15 milliseconds Alpha Decay 100.00% 194 0.78 milliseconds Alpha Decay 100.00% 195 6 milliseconds Alpha Decay 100.00% 195m 5 milliseconds Alpha Decay 100.00% 196 4.4 milliseconds Alpha Decay 99.90% Electron Capture ~ 0.10% 197 53 milliseconds Alpha Decay 100.00% 197m 25 milliseconds Alpha Decay 100.00% 198 65 milliseconds Alpha Decay No Data Available

424

Device and method for separating oxygen isotopes  

DOE Patents [OSTI]

A device and method for separating oxygen isotopes with an ArF laser which produces coherent radiation at approximately 193 nm. The output of the ArF laser is filtered in natural air and applied to an irradiation cell where it preferentially photodissociates molecules of oxygen gas containing .sup.17 O or .sup.18 O oxygen nuclides. A scavenger such as O.sub.2, CO or ethylene is used to collect the preferentially dissociated oxygen atoms and recycled to produce isotopically enriched molecular oxygen gas. Other embodiments utilize an ArF laser which is narrowly tuned with a prism or diffraction grating to preferentially photodissociate desired isotopes. Similarly, desired mixtures of isotopic gas can be used as a filter to photodissociate enriched preselected isotopes of oxygen.

Rockwood, Stephen D. (Los Alamos, NM); Sander, Robert K. (Los Alamos, NM)

1984-01-01T23:59:59.000Z

425

Selected Isotopes for Optimized Fuel Assembly Tags  

SciTech Connect (OSTI)

In support of our ongoing signatures project we present information on 3 isotopes selected for possible application in optimized tags that could be applied to fuel assemblies to provide an objective measure of burnup. 1. Important factors for an optimized tag are compatibility with the reactor environment (corrosion resistance), low radioactive activation, at least 2 stable isotopes, moderate neutron absorption cross-section, which gives significant changes in isotope ratios over typical fuel assembly irradiation levels, and ease of measurement in the SIMS machine 2. From the candidate isotopes presented in the 3rd FY 08 Quarterly Report, the most promising appear to be Titanium, Hafnium, and Platinum. The other candidate isotopes (Iron, Tungsten, exhibited inadequate corrosion resistance and/or had neutron capture cross-sections either too high or too low for the burnup range of interest.

Gerlach, David C.; Mitchell, Mark R.; Reid, Bruce D.; Gesh, Christopher J.; Hurley, David E.

2008-10-01T23:59:59.000Z

426

Atomic vapor laser isotope separation of lead-210 isotope  

DOE Patents [OSTI]

An isotopically selective laser process and apparatus for removal of Pb-210 from natural lead that involves a one-photon near-resonant, two-photon resonant excitation of one or more Rydberg levels, followed by field ionization and then electrostatic extraction. The wavelength to the near-resonant intermediate state is counter propagated with respect to the second wavelength required to populate the final Rydberg state. This scheme takes advantage of the large first excited state cross section, and only modest laser fluences are required. The non-resonant process helps to avoid two problems: first, stimulated Raman Gain due to the nearby F=3/2 hyperfine component of Pb-207 and, second, direct absorption of the first transition process light by Pb-207.

Scheibner, Karl F. (Tracy, CA); Haynam, Christopher A. (Pleasanton, CA); Johnson, Michael A. (Pleasanton, CA); Worden, Earl F. (Diablo, CA)

1999-01-01T23:59:59.000Z

427

Atomic vapor laser isotope separation of lead-210 isotope  

DOE Patents [OSTI]

An isotopically selective laser process and apparatus for removal of Pb-210 from natural lead that involves a one-photon near-resonant, two-photon resonant excitation of one or more Rydberg levels, followed by field ionization and then electrostatic extraction. The wavelength to the near-resonant intermediate state is counter propagated with respect to the second wavelength required to populate the final Rydberg state. This scheme takes advantage of the large first excited state cross section, and only modest laser fluences are required. The non-resonant process helps to avoid two problems: first, stimulated Raman Gain due to the nearby F=3/2 hyperfine component of Pb-207 and, second, direct absorption of the first transition process light by Pb-207. 5 figs.

Scheibner, K.F.; Haynam, C.A.; Johnson, M.A.; Worden, E.F.

1999-08-31T23:59:59.000Z

428

Discover your Library Medical Library  

E-Print Network [OSTI]

Discover your Library Medical Library Welcome to the Gus Fraenkel Medical Library. The Library is a branch of the Flinders University Libraries including: Central (on the Plaza of the north ridge precinct) Law (on level 3 of the Central Library building) Sturt (at the Sturt precinct) as well

429

Technology Advances in Medical Microbiology  

Science Journals Connector (OSTI)

Abstract Medical microbiology is the branch of microbiology devoted to the study of the physiological and pathogenic processes that underlie microbial infections in human and animal hosts. Technical advances including development and implementation of -omic technologies have made constant and enormous progress in various medical microbiology areas, including etiology, pathogenesis, epidemiology, diagnosis and treatment.

Y.-W. Tang

2014-01-01T23:59:59.000Z

430

Dartmouth Medical School Curriculum Redesign  

E-Print Network [OSTI]

&ng(hearts(&(minds((((((((((((((to(transform(people's(lives( Knowledgeable and curious Collaborators Critical thinkers Professionals Innovators 3( THE LEADERS OF 2020 #12 an innovative curriculum that optimizes medical student education & sets a global standard for medical education for remediation and splitting · Preservation of dual degree programs #12;Key Educational Themes for Students

Myers, Lawrence C.

431

The quality of medical care  

Science Journals Connector (OSTI)

...handed over its own powers and responsibilities...un-derstand why the system of monitoring has delegated...nullified (48). The system of medical care as it...Utilization Review: A Handbook for the Medical Staff...and the promotion and restoration of health. Overall...

A Donabedian

1978-05-26T23:59:59.000Z

432

Medical imaging systems  

DOE Patents [OSTI]

A medical imaging system provides simultaneous rendering of visible light and fluorescent images. The system may employ dyes in a small-molecule form that remains in a subject's blood stream for several minutes, allowing real-time imaging of the subject's circulatory system superimposed upon a conventional, visible light image of the subject. The system may also employ dyes or other fluorescent substances associated with antibodies, antibody fragments, or ligands that accumulate within a region of diagnostic significance. In one embodiment, the system provides an excitation light source to excite the fluorescent substance and a visible light source for general illumination within the same optical guide that is used to capture images. In another embodiment, the system is configured for use in open surgical procedures by providing an operating area that is closed to ambient light. More broadly, the systems described herein may be used in imaging applications where a visible light image may be usefully supplemented by an image formed from fluorescent emissions from a fluorescent substance that marks areas of functional interest.

Frangioni, John V. (Wayland, MA)

2012-07-24T23:59:59.000Z

433

Isotopic composition of Silurian seawater  

SciTech Connect (OSTI)

Direct isotopic analyses of 21 samples of the Silurian hydrosphere preserved as fluid inclusions in Silurian halite deposits in the Michigan Basin Salina Group yield delta/sup 18/O, deltaD ranging from 0.2 to +5.9 and -26 to -73, respectively. delta/sup 18/O has the same range as observed for modern halite facies evaporite waters and is a few per thousand higher than 100 analyses of fluid inclusions in Permian halite. deltaD is about 20 to 30 per thousand lower than modern and Permian examples. The trajectory of evaporating seawater on a deltaD-delta/sup 18/O diagram initially has a positive slope of 3-6, but hooks strongly downward to negative values, the shape of the hook depending upon humidity. Halite begins to precipitate at delta values similar to those observed for the most /sup 18/O rich fluid inclusions. Subsequent evaporation yields progressively more negative delta values as observed for the fluid inclusions. The fluid inclusion data can be readily explained in terms of evaporating seawater and are consistent with the degree of evaporation deduced from measured bromide profiles. These data are strongly inconsistent with arguments that Silurian seawater was 5.5 per thousand depleted in /sup 18/O. delta/sup 18/O for evaporite waters is systematically related to that of seawater, and does not show a -5.5 per thousand shift in the Silurian, even allowing for variables which affect the isotope evaporation trajectory. The lower deltaD may indicate a component of gypsum dehydration waters or may suggest a D-depleted Silurian hydrosphere.

Knauth, L.P.; Kealy, S.; Larimer, S.

1985-01-01T23:59:59.000Z

434

Medical Knowledge Morphing: Towards Case-Specific Integration of Heterogeneous Medical Knowledge Resources  

E-Print Network [OSTI]

Medical Knowledge Morphing: Towards Case-Specific Integration of Heterogeneous Medical Knowledge interplay between various medical knowledge modalities--the spectrum of medical knowledge modalities spanning from tacit knowledge to experiential knowledge to explicit knowledge to data-induced knowledge

Abidi, Syed Sibte Raza

435

Laser Ablation Molecular Isotopic Spectrometry: Parameter influence on boron isotope measurements  

Science Journals Connector (OSTI)

Laser Ablation Molecular Isotopic Spectrometry (LAMIS) was recently reported for optical isotopic analysis of condensed samples in ambient air and at ambient pressure. LAMIS utilizes molecular emissions which exhibit larger isotopic spectral shits than in atomic transitions. For boron monoxide 10BO and 11BO, the isotopic shifts extend from 114 cm?1 (0.74 nm) to 145–238 cm?1 (5–8 nm) at the B 2?+ (v = 0) ? X 2?+ (v = 2) and A 2?i (v = 0) ? X 2?+ (v = 3) transitions, respectively. These molecular isotopic shifts are over two orders of magnitude larger than the maximum isotopic shift of approximately 0.6 cm?1 in atomic boron. This paper describes how boron isotope abundance can be quantitatively determined using LAMIS and how atomic, ionic, and molecular optical emission develops in a plasma emanating from laser ablation of solid samples with various boron isotopic composition. We demonstrate that requirements for spectral resolution of the measurement system can be significantly relaxed when the isotopic abundance ratio is determined using chemometric analysis of spectra. Sensitivity can be improved by using a second slightly delayed laser pulse arriving into an expanding plume created by the first ablation pulse.

Xianglei Mao; Alexander A. Bol'shakov; Dale L. Perry; Osman Sorkhabi; Richard E. Russo

2011-01-01T23:59:59.000Z

436

Selective Gaseous Extraction: Research, Development and Training for Isotope Production, Final Technical Report  

SciTech Connect (OSTI)

General Atomics and the University of Missouri Research Reactor (MURR) completed research and development of selective gaseous extraction of fission products from irradiated fuel, which included training and education of MURR students. The process used porous fuel and after irradiation flowed product gases through the fuel to selectively removed desired fission products with the primary goal of demonstrating the removal of rhodium 105. High removal rates for the ruthenium/rhodium (Ru/Rh), tellurium/iodine (Te/I) and molybdenum/technetium (Mo/Tc) series were demonstrated. The success of this research provides for the reuse of the target for further production, significantly reducing the production of actinide wastes relative to processes that dissolve the target. This effort was conducted under DOE funding (DE-SC0007772). General Atomics objective of the project was to conduct R&D on alternative methods to produce a number of radioactive isotopes currently needed for medical and industry applications to include rhodium-105 and other useful isotopes. Selective gaseous extraction was shown to be effective at removing radioisotopes of the ruthenium/rhodium, tellurium/iodine and molybdenum/technetium decay chains while having trace to no quantities of other fission products or actinides. This adds a new, credible method to the area of certain commercial isotope production beyond current techniques, while providing significant potential reduction of process wastes. Waste reduction, along with reduced processing time/cost provides for superior economic feasibility which may allow domestic production under full cost recovery practices. This provides the potential for improved access to domestically produced isotopes for medical diagnostics and treatment at reduced cost, providing for the public good.

Bertch, Timothy C, [General Atomics

2014-03-31T23:59:59.000Z

437

It's Elemental - Isotopes of the Element Magnesium  

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

Sodium Sodium Previous Element (Sodium) The Periodic Table of Elements Next Element (Aluminum) Aluminum Isotopes of the Element Magnesium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 24 78.99% STABLE 25 10.00% STABLE 26 11.01% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 19 4.0 picoseconds Double Proton Emission 100.00% 20 90.8 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission ~ 27.00% 21 122 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 32.60% Electron Capture with delayed Alpha Decay < 0.50%

438

It's Elemental - Isotopes of the Element Chlorine  

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

Sulfur Sulfur Previous Element (Sulfur) The Periodic Table of Elements Next Element (Argon) Argon Isotopes of the Element Chlorine [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 35 75.76% STABLE 37 24.24% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 28 No Data Available Proton Emission (suspected) No Data Available 29 < 20 nanoseconds Proton Emission No Data Available 30 < 30 nanoseconds Proton Emission No Data Available 31 150 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 0.70% 32 298 milliseconds Electron Capture 100.00%

439

It's Elemental - Isotopes of the Element Potassium  

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

Argon Argon Previous Element (Argon) The Periodic Table of Elements Next Element (Calcium) Calcium Isotopes of the Element Potassium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 39 93.2581% STABLE 40 0.0117% 1.248×10+9 years 41 6.7302% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 32 No Data Available Proton Emission (suspected) No Data Available 33 < 25 nanoseconds Proton Emission No Data Available 34 < 25 nanoseconds Proton Emission No Data Available 35 178 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 0.37% 36 342 milliseconds Electron Capture 100.00%

440

It's Elemental - Isotopes of the Element Phosphorus  

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

Silicon Silicon Previous Element (Silicon) The Periodic Table of Elements Next Element (Sulfur) Sulfur Isotopes of the Element Phosphorus [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 31 100% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 24 No Data Available Electron Capture (suspected) No Data Available Proton Emission (suspected) No Data Available 25 < 30 nanoseconds Proton Emission 100.00% 26 43.7 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission No Data Available 27 260 milliseconds Electron Capture 100.00% Electron Capture with

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


441

It's Elemental - Isotopes of the Element Oxygen  

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

Nitrogen Nitrogen Previous Element (Nitrogen) The Periodic Table of Elements Next Element (Fluorine) Fluorine Isotopes of the Element Oxygen [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 16 99.757% STABLE 17 0.038% STABLE 18 0.205% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 12 1.139×10-21 seconds Proton Emission No Data Available 13 8.58 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 100.00% 14 70.620 seconds Electron Capture 100.00% 15 122.24 seconds Electron Capture 100.00% 16 STABLE - - 17 STABLE - - 18 STABLE - - 19 26.88 seconds Beta-minus Decay 100.00%

442

It's Elemental - Isotopes of the Element Gallium  

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

Zinc Zinc Previous Element (Zinc) The Periodic Table of Elements Next Element (Germanium) Germanium Isotopes of the Element Gallium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 69 60.108% STABLE 71 39.892% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 56 No Data Available Proton Emission (suspected) No Data Available 57 No Data Available Proton Emission (suspected) No Data Available 58 No Data Available Proton Emission (suspected) No Data Available 59 No Data Available Proton Emission (suspected) No Data Available 60 70 milliseconds Electron Capture 98.40%

443

It's Elemental - Isotopes of the Element Sodium  

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

Neon Neon Previous Element (Neon) The Periodic Table of Elements Next Element (Magnesium) Magnesium Isotopes of the Element Sodium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 23 100% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 18 1.3×10-21 seconds Proton Emission 100.00% 19 < 40 nanoseconds Proton Emission No Data Available 20 447.9 milliseconds Electron Capture with delayed Alpha Decay 20.05% Electron Capture 100.00% 21 22.49 seconds Electron Capture 100.00% 22 2.6027 years Electron Capture 100.00% 23 STABLE - - 24 14.997 hours Beta-minus Decay 100.00%

444

It's Elemental - Isotopes of the Element Neon  

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

Fluorine Fluorine Previous Element (Fluorine) The Periodic Table of Elements Next Element (Sodium) Sodium Isotopes of the Element Neon [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 20 90.48% STABLE 21 0.27% STABLE 22 9.25% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 16 9×10-21 seconds Double Proton Emission 100.00% 17 109.2 milliseconds Electron Capture with delayed Alpha Decay No Data Available Electron Capture 100.00% Electron Capture with delayed Proton Emission 100.00% 18 1.6670 seconds Electron Capture 100.00% 19 17.22 seconds Electron Capture 100.00% 20 STABLE - -

445

It's Elemental - Isotopes of the Element Copper  

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

Nickel Nickel Previous Element (Nickel) The Periodic Table of Elements Next Element (Zinc) Zinc Isotopes of the Element Copper [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 63 69.15% STABLE 65 30.85% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 52 No Data Available Proton Emission No Data Available 53 < 300 nanoseconds Electron Capture No Data Available Proton Emission No Data Available 54 < 75 nanoseconds Proton Emission No Data Available 55 27 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 15.0% 56 93 milliseconds Electron Capture 100.00%

446

It's Elemental - Isotopes of the Element Boron  

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

Beryllium Beryllium Previous Element (Beryllium) The Periodic Table of Elements Next Element (Carbon) Carbon Isotopes of the Element Boron [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 10 19.9% STABLE 11 80.1% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 6 No Data Available Double Proton Emission (suspected) No Data Available 7 3.255×10-22 seconds Proton Emission No Data Available Alpha Decay No Data Available 8 770 milliseconds Electron Capture 100.00% Electron Capture with delayed Alpha Decay 100.00% 9 8.439×10-19 seconds Proton Emission 100.00% Double Alpha Decay 100.00%

447

It's Elemental - Isotopes of the Element Tungsten  

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

Tantalum Tantalum Previous Element (Tantalum) The Periodic Table of Elements Next Element (Rhenium) Rhenium Isotopes of the Element Tungsten [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 180 0.12% >= 6.6×10+17 years 182 26.50% STABLE 183 14.31% > 1.3×10+19 years 184 30.64% STABLE 186 28.43% > 2.3×10+19 years Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 157 275 milliseconds Electron Capture No Data Available 158 1.25 milliseconds Alpha Decay 100.00% 158m 0.143 milliseconds Isomeric Transition No Data Available Alpha Decay No Data Available 159 7.3 milliseconds Alpha Decay ~ 99.90%

448

It's Elemental - Isotopes of the Element Carbon  

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

Boron Boron Previous Element (Boron) The Periodic Table of Elements Next Element (Nitrogen) Nitrogen Isotopes of the Element Carbon [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 12 98.93% STABLE 13 1.07% STABLE Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 8 1.981×10-21 seconds Proton Emission 100.00% Alpha Decay No Data Available 9 126.5 milliseconds Electron Capture 100.00% Electron Capture with delayed Proton Emission 61.60% Electron Capture with delayed Alpha Decay 38.40% 10 19.308 seconds Electron Capture 100.00% 11 20.334 minutes Electron Capture 100.00% 12 STABLE - -

449

It's Elemental - Isotopes of the Element Rhenium  

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

Tungsten Tungsten Previous Element (Tungsten) The Periodic Table of Elements Next Element (Osmium) Osmium Isotopes of the Element Rhenium [Click for Main Data] Most of the isotope data on this site has been obtained from the National Nuclear Data Center. Please visit their site for more information. Naturally Occurring Isotopes Mass Number Natural Abundance Half-life 185 37.40% STABLE 187 62.60% 4.33×10+10 years Known Isotopes Mass Number Half-life Decay Mode Branching Percentage 159 No Data Available No Data Available No Data Available 160 0.82 milliseconds Proton Emission 91.00% Alpha Decay 9.00% 161 0.44 milliseconds Proton Emission 100.00% Alpha Decay <= 1.40% 161m 14.7 milliseconds Alpha Decay 93.00% Proton Emission 7.00% 162 107 milliseconds Alpha Decay 94.00% Electron Capture 6.00%

450

Isotope ratio determination in boron analysis  

Science Journals Connector (OSTI)

Traditionally, boron (B) isotope ratios have been determined using thermal ionization...+, Cs+, or O-...for analyte ionization. TIMS can be used in negative or positive ion modes with high sensitivity and precisi...

Ram N. Sah; Patrick H. Brown

1998-12-01T23:59:59.000Z

451

Magnetic moments of long isotopic chains  

E-Print Network [OSTI]

Dipole magnetic moments of several long isotopic chains are analyzed within the self-consistent Finite Fermi System theory based on the Generalized Energy Density Functional method with exact account for the pairing and quasi-particle continuum. New data for nuclei far from the beta-stability valley are included in the analysis. For a number of semi-magic isotopes of the tin and lead chains a good description of the data is obtained, with accuracy of 0.1 - 0.2 mu_N. A chain of non-magic isotopes of copper is also analyzed in detail. It is found that the systematic analysis of magnetic moments of this long chain yields rich information on the evolution of the nuclear structure of the Cu isotopes. In particular, it may give a signal of deformation for the ground state of some nuclei in the chain.

I. N. Borzov; E. E. Saperstein; S. V. Tolokonnikov; G. Neyens; N. Severijns

2008-04-28T23:59:59.000Z

452

ICE CORE RECORDS | Greenland Stable Isotopes  

Science Journals Connector (OSTI)

Abstract Greenland ice cores contain a wealth of information on past climatic conditions throughout the Northern Hemisphere. A historical perspective on the climatic interpretation of stable isotopes in water and ice is presented in the introduction, while the remainder of the article is devoted to the current interpretation of stable isotope data from Greenland ice cores. The progress in our understanding of stable isotope signals, on timescales from seasons to glacial cycles, is discussed and evaluated through numerous examples from Greenland ice cores. Stable isotope profiles from the Camp Century, Dye-3, GISP2, GRIP, NGRIP, and Renland deep ice cores are emphasized, as they all provide climatic information dating back into the Eemian period.

B.M. Vinther; S.J. Johnsen

2013-01-01T23:59:59.000Z

453

Nuclear Astrophysics in Rare Isotope Facilities  

E-Print Network [OSTI]

Nuclear reactions in stars are difficult to measure directly in the laboratory at the small astrophysical energies. In recent years indirect methods with rare isotopes have been developed and applied to extract low-energy astrophysical cross sections.

C. A. Bertulani

2009-11-02T23:59:59.000Z

454

Gaseous isotope separation using solar wind phenomena  

Science Journals Connector (OSTI)

...isotope separation using solar wind phenomena Chia-Gee...essentially the same as that of the solar wind propagation, in which...the author was measuring solar wind parameters under Dr. H. S. Bridge at Massachusetts Institute of Technology in...

Chia-Gee Wang

1980-01-01T23:59:59.000Z

455

NONRADIOGENIC ISOTOPES IN GEOLOGY: A REVIEW  

Science Journals Connector (OSTI)

...has revised Brown's figures. Seaborg and Pearlman (1948) and more recently...51, p. 263-300. and Jenks, Glenn (1944) Isotopic composition of...Science,vol. 79, p. 565. Seaborg, Glenn T., and Pearlman, I. (1948...

456

Storage of Hydrogen Isotopes in Uranium Alloys  

Science Journals Connector (OSTI)

Tritium Properties and Interactions with Material / Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988)

T. Yamamoto; Supardjo; T. Terai; F. Ono; S. Tanaka; M. Yamawaki

457

Le Rglement des tudes, la Dclaration des droits des tudiants et des tudiantes, les Dispositions relatives l'application de la politique sur l'usage du franais  

E-Print Network [OSTI]

Dispositions relatives à l'application de la politique sur l'usage du français à l'Université Laval, la Politique sur l'usage du français à l'Université Laval ainsi que le Règlement disciplinaire à l

Laval, Université

458

PSI # Date Time Location Incident Description Disposition 4341 9/2/2011 8:00 Blue Ridge Bicycle Theft Norco Mountain bike BPD notified  

E-Print Network [OSTI]

PSI # Date Time Location Incident Description Disposition 4341 9/2/2011 8:00 Blue Ridge Bicycle Four or more citations received Fine issued 4353 9/8/2011 16:00 Elizabeth Rogers Bicycle Theft Bluish Green bicycle BPD notified 4354 9/9/2011 13:49 Short St Hair Salon Criminal Damage Graffiti on the rear

Baltisberger, Jay H.

459

Mechanistic studies using kinetic isotope effects  

E-Print Network [OSTI]

MECHANISTIC STUDIES USING KINETIC ISOTOPE EFFECTS A Thesis by BRIAN E. SCHULMFIER Submitted to the Office of Graduate Studies of Texas ARM University in partial fulfillment of the requtrements for the degree of MASTER OF SCIENCE December... 1999 Major Subject: Chemistry MECHANISTIC STUDIES USING KINETIC ISOTOPE EFFECTS A Thesis by BRIAN E. SCHULMEIER Submitted to Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved...

Schulmeier, Brian E.

2012-06-07T23:59:59.000Z

460

Isotope/element fractionation during surface adsorption  

Science Journals Connector (OSTI)

The adsorption of ions onto mineral surfaces accompanies isotope/element fractionation in planets and asteroids. A model based on simple classical physics is presented to predict these fractionations. The agreement between the experimentally observed isotope/element ratios and their predicted values is found to be excellent. This fractionation can be demonstrated experimentally in advanced physics laboratories using macroscopic particles. The success of the model shows students that even a very complex naturally occurring process can be explained quantitatively with simple physics.

Gamini Seneviratne; Asiri Nanayakkara

2004-01-01T23:59:59.000Z

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


461

Manifestation and Origin of the Isotope Effect  

E-Print Network [OSTI]

This article reviews from one point of view the current status of the manifestations of isotope effect in a nuclear, atomic and molecular as well as solid state physics. Although these manifestations vary, they have one common feature - they all depend on mass. At present time the Standard Model can't explain the origin of the mass of elementary particles and their hierarchy. The last one don't permit to find the origin of the isotope effect.

V. G. Plekhanov

2009-07-12T23:59:59.000Z

462

The Oxygen core inside the Magnesium isotopes  

E-Print Network [OSTI]

We have studied the ground state bulk properties of magnesium isotopes using axially symmetric relativistic mean field formalism. The BCS pairing approach is employed to take care of the pairing correlation for the open shell nuclei. The contour plot of the nucleons distribution are analyzed at various parts of the nucleus, where clusters are located. The presence of an $^{16}$O core along bubble like $\\alpha$-particle(s) and few {\\it nucleons} are found in the Mg isotopes.

Bhuyan, M

2013-01-01T23:59:59.000Z

463

Former Worker Program Medical Protocol  

Broader source: Energy.gov [DOE]

The medical protocol is intended to identify work-related health outcomes of relevance to DOE workers for which there are screening tests that are reasonably likely to be effective and beneficial to program participants.

464

Physical Activity Readiness Medical Examination  

E-Print Network [OSTI]

Conveyance/Referral: NAME ______________________________________________________ ADDRESS or prescribed exercise. · Physical Activity Readiness Conveyance/Referral Form - an optional tear-off tab for the physician to convey clearance for physical activity participation, or to make a referral to a medically

Waterloo, University of

465

DEDICATED HEAVY ION MEDICAL ACCELERATORS  

E-Print Network [OSTI]

Lancaster, R.B. Yourd, Pre~,Accelerator A w·ideroe~,Basedcarbon beam medical accelerator facility. N "' . ,;j "' ::lEat the MARIA Workshop III: Accelerator Systems for Relat ic

Gough, R.A.

2013-01-01T23:59:59.000Z

466

ORISE: Worker Health Studies - Medical Data Management  

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

Medical Data Management Medical Data Management The Oak Ridge Institute for Science and Education (ORISE) provides the U.S. Department of Energy (DOE) and other government agencies...

467

The old Egyptian medical papyri  

E-Print Network [OSTI]

, then secretary of the Pharmacology Laboratory at the University of California Medical Cen ter. Among my most pleasant memories are those asso ciated with the sessions we held together in the sheltering Redwoods at Pharmaglen in the Santa Cruz mountains. When.... Such a study may be both enlightening and humbling. Difficult has it been to select what may be most inter esting and pertinent about old Egyptian medicine for the intelligent layman, physician, or medical student, from the abundance of detailed...

Leake, Chauncey Depew

1952-01-01T23:59:59.000Z

468

Assessment of Non-traditional Isotopic Ratios by Mass Spectrometry for Analysis of Nuclear Activities: Annual Report Year 2  

SciTech Connect (OSTI)

The objective of this work is to identify isotopic ratios suitable for analysis via mass spectrometry that distinguish between commercial nuclear reactor fuel cycles, fuel cycles for weapons grade plutonium, and products from nuclear weapons explosions. Methods will also be determined to distinguish the above from medical and industrial radionuclide sources. Mass spectrometry systems will be identified that are suitable for field measurement of such isotopes in an expedient manner. Significant progress has been made with this project within the past year: (1) Isotope production from commercial nuclear fuel cycles and nuclear weapons fuel cycles have been modeled with the ORIGEN and MCNPX codes. (2) MCNPX has been utilized to calculate isotopic inventories produced in a short burst fast bare sphere reactor (to approximate the signature of a nuclear weapon). (3) Isotopic ratios have been identified that are good for distinguishing between commercial and military fuel cycles as well as between nuclear weapons and commercial nuclear fuel cycles. (4) Mass spectrometry systems have been assessed for analysis of the fission products of interest. (5) A short-list of forensic ratios have been identified that are well suited for use in portable mass spectrometry systems.

Biegalski, S; Buchholz, B

2009-08-26T23:59:59.000Z

469

Radioisotopes for Medical Diagnostics and Cancer Therapy at BNL | U.S. DOE  

Office of Science (SC) Website

Radioisotopes for Medical Diagnostics Radioisotopes for Medical Diagnostics and Cancer Therapy at BNL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Spinoff Applications Spinoff Archives SBIR/STTR Applications of Nuclear Science and Technology Funding Opportunities Nuclear Science Advisory Committee (NSAC) News & Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: sc.np@science.doe.gov More Information » Spinoff Archives Radioisotopes for Medical Diagnostics and Cancer Therapy at BNL Print Text Size: A A A RSS Feeds FeedbackShare Page Application/Instrumentation: Brookhaven Linac Isotope Producer (BLIP) Developed at: Brookhaven National Laboratory

470

E-Print Network 3.0 - abundance isotopic Sample Search Results  

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

Search Sample search results for: abundance isotopic Page: << < 1 2 3 4 5 > >> 1 ISOTOPE FRACTIONATION Isotopes are atoms whose nuclei contain the same number of protons but...

471

E-Print Network 3.0 - alpha-deuterium isotope effects Sample...  

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

deuterium isotope effects Search Powered by Explorit Topic List Advanced Search Sample search results for: alpha-deuterium isotope effects Page: << < 1 2 3 4 5 > >> 1 ISOTOPE...

472

Strontium and carbon isotope stratigraphy of the Llandovery (Early Silurian): Implications for tectonics and weathering  

E-Print Network [OSTI]

Strontium and carbon isotope stratigraphy of the Llandovery (Early Silurian): Implications online 2 June 2010 Keywords: Silurian Strontium isotopes Carbon isotopes Weathering K-bentonites A high

Saltzman, Matthew R.

473

Isotope Program Facilities | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

include the High Flux Isotope Reactor at Oak Ridge National Laboratory and the Advanced Test Reactor at Idaho National Laboratory. The DOE Isotope Program also supports isotope...

474

Oxygen isotope fractionation in the vacuum ultraviolet photodissociation of carbon monoxide: Wavelength, pressure and temperature dependency.  

E-Print Network [OSTI]

Oxygen isotope fractionation in the vacuum ultravioletmeasurement of the associated oxygen isotopic composition ofwavelength dependency of the oxygen isotopic composition in

Chakraborty, Subrata

2013-01-01T23:59:59.000Z

475

E-Print Network 3.0 - applied isotope techniques Sample Search...  

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

Sciences and Ecology ; Biology and Medicine 100 Electrochemical Isotope Effect and Lithium Isotope Separation Jay R. Black, Summary: that the magnitude of isotopic...

476

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

SciTech Connect (OSTI)

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

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

1995-12-31T23:59:59.000Z

477

Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

Washington, A. L. II; Peters, T. B.

2013-09-19T23:59:59.000Z

478

Evaluation of disposition scores in Bos indicus/Bos taurus cross calves at different stages of production  

E-Print Network [OSTI]

to 5. Between sires for overall disposition, calves by 297J were lowest at weaning (2.83), before slaughter (2.84), and at slaughter (2.45) and second lowest in first calf heifers (2.27). Calves by 437J were highest at weaning (4.10), before... Family Sire Dam Offspring Bulls Heifers Steers 70 297J 431H 33 0 15 18 71 297J 760H 63 2 29 32 72 432H 511G 45 1 20 24 73 432H 732H 8 0 2 6 74 437J 640H 8 0 4 4 75 437J 728H 36 1 19 16 76 551G 664J 7 0 2 5 77 551G 787G 41 1 17 23 80 551G 429H 66...

Funkhouser, Rena Rebecca

2008-10-10T23:59:59.000Z

479

Potential role of ABC-assisted repositories in U.S. plutonium and high-level waste disposition  

SciTech Connect (OSTI)

This paper characterizes the issues involving deep geologic disposal of LWR spent fuel rods, then presents results of an investigation to quantify the potential role of Accelerator-Based Conversion (ABC) in an integrated national nuclear materials and high level waste disposition strategy. The investigation used the deep geological repository envisioned for Yucca Mt., Nevada as a baseline and considered complementary roles for integrated ABC transmutation systems. The results indicate that although a U.S. geologic waste repository will continue to be required, waste partitioning and accelerator transmutation of plutonium, the minor actinides, and selected long-lived fission products can result in the following substantial benefits: plutonium burndown to near zero levels, a dramatic reduction of the long term hazard associated with geologic repositories, an ability to place several-fold more high level nuclear waste in a single repository, electricity sales to compensate for capital and operating costs.

Berwald, David; Favale, Anthony; Myers, Timothy; McDaniel, Jerry [Grumman Aerospace Corporation, Bethpage New York 11714 (United States); Bechtel Corporation, 50 Beal St., San Francisco, California 94105 (United States)

1995-09-15T23:59:59.000Z

480

Medical isotope production: A new research initiative for the Annular Core Research Reactor  

SciTech Connect (OSTI)

An investigation has been performed to evaluate the capabilities of the Annular Core Research Reactor and its supporting Hot Cell Facility for the production of {sup 99}Mo and its separation from the fission product stream. Various target irradiation locations for a variety of core configurations were investigated, including the central cavity, fuel and reflector locations, and special target configurations outside the active fuel region. Monte Carlo techniques, in particular MCNP using ENDF B-V cross sections, were employed for the evaluation. The results indicate that the reactor, as currently configured, and with its supporting Hot Cell Facility, would be capable in meeting the current US demand if called upon. Modest modifications, such as increasing the capacity of the external heat exchangers, would permit significantly higher continuous power operation and even greater {sup 99}Mo production ensuring adequate capacity for future years.

Coats, R.L.; Parma, E.J.

1993-12-31T23:59:59.000Z

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


481

Medical Isotope Production With The Accelerator Production of Tritium (APT) Facility  

SciTech Connect (OSTI)

In order to meet US tritium needs to maintain the nuclear weapons deterrent, the Department of Energy (DOE) is pursuing a dual track program to provide a new tritium source. A record of decision is planned for late in 1998 to select either the Accelerator Production of Tritium (APT) or the Commercial Light Water Reactor (CLWR) as the technology for new tritium production in the next century. To support this decision, an APT Project was undertaken to develop an accelerator design capable of producing 3 kg of tritium per year by 2007 (START I requirements). The Los Alamos National Laboratory (LANL) was se