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1

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

2

Office of Fissile Materials Disposition | National Nuclear Security...  

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

Fissile Materials Disposition | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

3

Fissile Material Disposition (MD) - Nuclear Engineering Division...  

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

a legacy of surplus fissile materials (primarily weapons-grade plutonium and highly enriched uranium) in the United States and the former Soviet Union. These materials pose a...

4

Fissile Materials Disposition | National Nuclear Security Administrati...  

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

Materials Disposition Since the end of the Cold War, significant quantities of plutonium and highly enriched uranium have become surplus to the defense needs of both the...

5

Fissile material disposition program: Screening of alternate immobilization candidates for disposition of surplus fissile materials  

Science Conference Proceedings (OSTI)

With the end of the Cold War, the world faces for the first time the need to dismantle vast numbers of ``excess`` nuclear weapons and dispose of the fissile materials they contain, together with fissile residues in the weapons production complex left over from the production of these weapons. If recently agreed US and Russian reductions are fully implemented, tens of thousands of nuclear weapons, containing a hundred tons or more of plutonium and hundreds of tonnes* of highly enriched uranium (HEU), will no longer be needed worldwide for military purposes. These two materials are the essential ingredients of nuclear weapons, and limits on access to them are the primary technical barrier to prospective proliferants who might desire to acquire a nuclear weapons capability. Theoretically, several kilograms of plutonium, or several times that amount of HEU, is sufficient to make a nuclear explosive device. Therefore, these materials will continue to be a potential threat to humanity for as long as they exist.

Gray, L.W.

1996-01-08T23:59:59.000Z

6

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

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

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

7

Proliferation resistance criteria for fissile material disposition issues  

Science Conference Proceedings (OSTI)

The 1994 National Acdaemy of Sciences study ``Management and Disposition of Excess Weapons Plutonium`` defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This paper proposes criteria for assessing the proliferation resistance of these options as well defining the ``Standards`` from the report. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials.

Rutherford, D.A.; Fearey, B.L.; Markin, J.T.; Close, D.A. [Los Alamos National Lab., NM (United States); Tolk, K.M.; Mangan, D.L. [Sandia National Labs., Albuquerque, NM (United States); Moore, L. [Lawrence Livermore National Lab., CA (United States)

1995-09-01T23:59:59.000Z

8

Disposition of excess fissile materials in deep boreholes  

SciTech Connect

As a result of recent changes throughout the world, a substantial inventory of excess separated plutonium is expected to result from dismantlement of US nuclear weapons. The safe and secure management and eventual disposition of this plutonium, and of a similar inventory in Russia, is a high priority. A variety of options (both interim and permanent) are under consideration to manage this material. The permanent solutions can be categorized into two broad groups: direct disposal and utilization. Plutonium utilization options have in common the generation of high-level radioactive waste which will be disposed of in a mined geologic disposal system to be developed for spent reactor fuel and defense high level waste. Other final disposition forms, such as plutonium metal, plutonium oxide and plutonium immobilized without high-level radiation sources may be better suited to placement in a custom facility. This paper discusses a leading candidate for such a facility; deep (several kilometer) borehole disposition. The deep borehole disposition concept involves placing excess plutonium deep into old stable rock formations with little free water present. The safety argument centers around ancient groundwater indicating lack of migration, and thus no expected communication with the accessible environment until the plutonium has decayed.

Halsey, W.G. [Lawrence Livermore National Lab., CA (United States); Danker, W. [USDOE, Washington, DC (United States); Morley, R. [Los Alamos National Lab., NM (United States)

1995-09-01T23:59:59.000Z

9

Storage and Disposition of Weapons-Usable Fissile Materials  

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

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

10

Summary report of the screening process to determine reasonable alternatives for long-term storage and disposition of weapons-usable fissile materials  

SciTech Connect

Significant quantities of weapons-usable fissile materials (primarily plutonium and highly enriched uranium) have become surplus to national defense needs both in the US and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety and health consequences if surplus fissile materials are not properly managed. As announced in the Notice of Intent (NOI) to prepare a Programmatic Environmental Impact Statement (PEIS), the Department of Energy is currently conducting an evaluation process for disposition of surplus weapons-usable fissile materials determined surplus to National Security needs, and long-term storage of national security and programmatic inventories, and surplus weapons-usable fissile materials that are not able to go directly from interim storage to disposition. An extensive set of long-term storage and disposition options was compiled. Five broad long-term storage options were identified; thirty-seven options were considered for plutonium disposition; nine options were considered for HEU disposition; and eight options were identified for Uranium-233 disposition. Section 2 discusses the criteria used in the screening process. Section 3 describes the options considered, and Section 4 provides a detailed summary discussions of the screening results.

NONE

1995-03-29T23:59:59.000Z

11

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

SciTech Connect

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.

1997-01-01T23:59:59.000Z

12

Deep borehole disposition of surplus fissile materials-The site selection process  

Science Conference Proceedings (OSTI)

One option for disposing of excess weapons plutonium is to place it near the base of deep boreholes in stable crystalline rocks. The technology exists to immediately begin the design of this means of disposition and there are many attractive sites available within the conterminous US. The borehole system utilizes mainly natural barriers to preven migration of Pu and U to the Earth`s surface. Careful site selection ensures favorable geologic conditions that provide natural long-lived migration barriers; they include deep, extremely stable rock formations, strongly reducing brines that exhibit increasing salinity with depth, and most importantly, demonstrated isolation or non-communication of deep fluids with the biosphere for millions of years. This isolation is the most important characteristic, with the other conditions mainly being those that will enhance the potential of locating and maintaining the isolated zones. Candidate sites will probably be located on the craton in very old Precambrian crystalline rocks, most likely the center of a granitic pluton. The sites will be located in tectonically stable areas with no recent volcanic or seismic activity, and situated away from tectonic features that might become active in the near geologic future.

Heiken, G.; WoldeGabriel, G.; Morley, R.; Plannerer, H

1996-05-01T23:59:59.000Z

13

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

Science Conference Proceedings (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

14

Plutonium Disposition Program | National Nuclear Security Administrati...  

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

Plutonium Disposition Program Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition > Plutonium Disposition Program Plutonium Disposition Program The...

15

Criticality control in shipments of fissile materials  

SciTech Connect

This paper describes a procedure for finite-array criticality analysis to ensure criticality safety of shipments of fissile materials in US DOE-certified packages. After the procedure has been performed, one can obtain the minimum transport index and determine the maximum number of fissile packages allowable in a shipment that meets the 10 CFR 71 criticality safety requirements.

Liaw, J. R.; Liu, Y. Y.

2000-03-14T23:59:59.000Z

16

Recovery of fissile materials from plutonium residues, miscellaneous spent nuclear fuel, and uranium fissile wastes  

SciTech Connect

A new process is proposed that converts complex feeds containing fissile materials into a chemical form that allows the use of existing technologies (such as PUREX and ion exchange) to recover the fissile materials and convert the resultant wastes to glass. Potential feed materials include (1) plutonium scrap and residue, (2) miscellaneous spent nuclear fuel, and (3) uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, and organics. 14 refs., 4 figs.

Forsberg, C.W.

1997-03-01T23:59:59.000Z

17

Shipping container for fissile material  

DOE Patents (OSTI)

The present invention is directed to a shipping container for the interstate transportation of enriched uranium materials. The shipping container is comprised of a rigid, high-strength, cylindrical-shaped outer vessel lined with thermal insulation. Disposed inside the thermal insulation and spaced apart from the inner walls of the outer vessel is a rigid, high-strength, cylindrical inner vessel impervious to liquid and gaseous substances and having the inner surfaces coated with a layer of cadmium to prevent nuclear criticality. The cadmium is, in turn, lined with a protective shield of high-density urethane for corrosion and wear protection. 2 figs.

Crowder, H.E.

1984-12-17T23:59:59.000Z

18

Recovery of fissile materials from nuclear wastes  

DOE Patents (OSTI)

A process is described for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium, and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, organic material and other carbon-containing material.

Forsberg, Charles W.

1997-12-01T23:59:59.000Z

19

Recovery of fissile materials from nuclear wastes  

DOE Patents (OSTI)

A process for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, organic material and other carbon-containing material.

Forsberg, Charles W. (Oak Ridge, TN)

1999-01-01T23:59:59.000Z

20

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

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

and disposal alternatives in the 2 commercial sector Review current policies and directives Provide needed oversight EM Waste and Materials Disposition & Transportation More...

Note: This page contains sample records for the topic "fissile materials disposition" 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

The environmental assessment of nuclear materials disposition options: A transportation perspective  

SciTech Connect

The US Department of Energy has undertaken a program to evaluate and select options for the long-term storage and disposition of fissile materials declared surplus to defense needs as a result of the end of the Cold War. The transport of surplus fissile material will be an important and highly visible aspect of the environmental impact studies and other planning documents required for implementation of the disposition options. This report defines the roles and requirements for transportation of fissile materials in the program, and discusses an existing methodology for determining the environmental impact in terms of risk. While it will be some time before specific alternatives are chosen that will permit the completion of detailed risk calculations, the analytical models for performing the probabilistic risk assessments already exist with much of the supporting data related to the transportation system. This report summarizes the various types of data required and identifies sources for that data.

Wilson, R.K.; Clauss, D.B.; Moyer, J.W.

1994-12-31T23:59:59.000Z

22

Nuclear Materials Disposition | Department of Energy  

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

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

23

DISSOLUTION OF FISSILE MATERIALS CONTAINING TANTALUM METAL  

Science Conference Proceedings (OSTI)

The dissolution of composite materials containing plutonium (Pu) and tantalum (Ta) metals is currently performed in Phase I of the HB-Line facility. The conditions for the present flowsheet are the dissolution of 500 g of Pu metal in the 15 L dissolver using a 4 M nitric acid (HNO{sub 3}) solution containing 0.2 M potassium fluoride (KF) at 95 C for 4-6 h.[1] The Ta metal, which is essentially insoluble in HNO{sub 3}/fluoride solutions, is rinsed with process water to remove residual acid, and then burned to destroy classified information. During the initial dissolution campaign, the total mass of Pu and Ta in the dissolver charge was limited to nominally 300 g. The reduced amount of Pu in the dissolver charge coupled with significant evaporation of solution during processing of several dissolver charges resulted in the precipitation of a fluoride salt contain Pu. Dissolution of the salt required the addition of aluminum nitrate (Al(NO{sub 3}){sub 3}) and a subsequent undesired 4 h heating cycle. As a result of this issue, HB-Line Engineering requested the Savannah River National Laboratory (SRNL) to optimize the dissolution flowsheet to reduce the cycle time, reduce the risk of precipitating solids, and obtain hydrogen (H{sub 2}) generation data at lower fluoride concentrations.[2] Using samples of the Pu/Ta composite material, we performed three experiments to demonstrate the dissolution of the Pu metal using HNO{sub 3} solutions containing 0.15 and 0.175 M KF. When 0.15 M KF was used in the dissolving solution, 95.5% of the Pu in the sample dissolved in approximately 6 h. The undissolved material included a small amount of Pu metal and plutonium oxide (PuO{sub 2}) solids. Complete dissolution of the metal would have likely occurred if the dissolution time had been extended. This assumption is based on the steady increase in the Pu concentration observed during the last several hours of the experiment. We attribute the formation of PuO{sub 2} to the complexation of fluoride by the Pu. The fluoride became unavailable to catalyze the dissolution of PuO{sub 2} as it formed on the surface of the metal. The mass of Pu dissolved is equivalent to the dissolution of 343 g of Pu in the HB-Line dissolvers. In the initial experiment with 0.175 M KF in the solution, we achieved complete dissolution of the Pu in 6 h. The mass of Pu dissolved scales to the dissolution of 358 g of Pu in the HB-Line dissolvers. The second experiment using 0.175 M KF was terminated after approximately 6 h following the dissolution of 92.7% of the Pu in the sample; however, dissolution of additional Pu was severely limited due to the slow dissolution rate observed beyond approximately 4 h. A small amount of PuO{sub 2} was also produced in the solution. The slow rate of dissolution was attributed to the diminishing surface area of the Pu and a reduction in the fluoride activity due to complexation with Pu. Given time (>4 h), the Pu metal may have dissolved using the original solution or a significant portion may have oxidized to PuO{sub 2}. If the metal oxidized to PuO{sub 2}, we expect little of the material would have dissolved due to the fluoride complexation and the low HNO{sub 3} concentration. The mass of Pu dissolved in the second experiment scales to the dissolution of 309 g of Pu in the HB-Line dissolvers. Based on the data from the Pu/Ta dissolution experiments we recommend the use of 4 M HNO{sub 3} containing 0.175 M KF for the dissolution of 300 g of Pu metal in the 15 L HB-Line dissolver. A dissolution temperature of nominally 95 C should allow for essentially complete dissolution of the metal in 6 h. Although the H{sub 2} concentration in the offgas from the experiments was at or below the detection limit of the gas chromatograph (GC) used in these experiments, small concentrations (dissolutions. Therefore, appropriate controls must be established to address the small H{sub 3} generation rates in accordance with this work and the earlier flowsheet demonstrated

Rudisill, T; Mark Crowder, M; Michael Bronikowski, M

2007-05-29T23:59:59.000Z

24

DISSOLUTION OF FISSILE MATERIALS CONTAINING TANTALUM METAL  

DOE Green Energy (OSTI)

The dissolution of composite materials containing plutonium (Pu) and tantalum (Ta) metals is currently performed in Phase I of the HB-Line facility. The conditions for the present flowsheet are the dissolution of 500 g of Pu metal in the 15 L dissolver using a 4 M nitric acid (HNO{sub 3}) solution containing 0.2 M potassium fluoride (KF) at 95 C for 4-6 h.[1] The Ta metal, which is essentially insoluble in HNO{sub 3}/fluoride solutions, is rinsed with process water to remove residual acid, and then burned to destroy classified information. During the initial dissolution campaign, the total mass of Pu and Ta in the dissolver charge was limited to nominally 300 g. The reduced amount of Pu in the dissolver charge coupled with significant evaporation of solution during processing of several dissolver charges resulted in the precipitation of a fluoride salt contain Pu. Dissolution of the salt required the addition of aluminum nitrate (Al(NO{sub 3}){sub 3}) and a subsequent undesired 4 h heating cycle. As a result of this issue, HB-Line Engineering requested the Savannah River National Laboratory (SRNL) to optimize the dissolution flowsheet to reduce the cycle time, reduce the risk of precipitating solids, and obtain hydrogen (H{sub 2}) generation data at lower fluoride concentrations.[2] Using samples of the Pu/Ta composite material, we performed three experiments to demonstrate the dissolution of the Pu metal using HNO{sub 3} solutions containing 0.15 and 0.175 M KF. When 0.15 M KF was used in the dissolving solution, 95.5% of the Pu in the sample dissolved in approximately 6 h. The undissolved material included a small amount of Pu metal and plutonium oxide (PuO{sub 2}) solids. Complete dissolution of the metal would have likely occurred if the dissolution time had been extended. This assumption is based on the steady increase in the Pu concentration observed during the last several hours of the experiment. We attribute the formation of PuO{sub 2} to the complexation of fluoride by the Pu. The fluoride became unavailable to catalyze the dissolution of PuO{sub 2} as it formed on the surface of the metal. The mass of Pu dissolved is equivalent to the dissolution of 343 g of Pu in the HB-Line dissolvers. In the initial experiment with 0.175 M KF in the solution, we achieved complete dissolution of the Pu in 6 h. The mass of Pu dissolved scales to the dissolution of 358 g of Pu in the HB-Line dissolvers. The second experiment using 0.175 M KF was terminated after approximately 6 h following the dissolution of 92.7% of the Pu in the sample; however, dissolution of additional Pu was severely limited due to the slow dissolution rate observed beyond approximately 4 h. A small amount of PuO{sub 2} was also produced in the solution. The slow rate of dissolution was attributed to the diminishing surface area of the Pu and a reduction in the fluoride activity due to complexation with Pu. Given time (>4 h), the Pu metal may have dissolved using the original solution or a significant portion may have oxidized to PuO{sub 2}. If the metal oxidized to PuO{sub 2}, we expect little of the material would have dissolved due to the fluoride complexation and the low HNO{sub 3} concentration. The mass of Pu dissolved in the second experiment scales to the dissolution of 309 g of Pu in the HB-Line dissolvers. Based on the data from the Pu/Ta dissolution experiments we recommend the use of 4 M HNO{sub 3} containing 0.175 M KF for the dissolution of 300 g of Pu metal in the 15 L HB-Line dissolver. A dissolution temperature of nominally 95 C should allow for essentially complete dissolution of the metal in 6 h. Although the H{sub 2} concentration in the offgas from the experiments was at or below the detection limit of the gas chromatograph (GC) used in these experiments, small concentrations (<3 vol %) of H{sub 2} are typically produced in the offgas during Pu metal dissolutions. Therefore, appropriate controls must be established to address the small H{sub 3} generation rates in accordance with this work and the earlier flowsheet demonstrated

Rudisill, T; Mark Crowder, M; Michael Bronikowski, M

2007-05-29T23:59:59.000Z

25

Method and apparatus for measuring reactivity of fissile material  

DOE Patents (OSTI)

Given are a method and apparatus for measuring nondestructively and non-invasively (i.e., using no internal probing) the burnup, reactivity, or fissile content of any material which emits neutrons and which has fissionable components. No external neutron-emitting interrogation source or fissile material is used and no scanning is required, although if a profile is desired scanning can be used. As in active assays, here both reactivity and content of fissionable material can be measured. The assay is accomplished by altering the return flux of neutrons into the fuel assembly. The return flux is altered by changing the reflecting material. The existing passive neutron emissions in the material being assayed are used as the source of interrogating neutrons. Two measurements of either emitted neutron or emitted gamma-ray count rates are made and are then correlated to either reactivity, burnup, or fissionable content of the material being assayed, thus providing a measurement of either reactivity, burnup, or fissionable content of the material being assayed. Spent fuel which has been freshly discharged from a reactor can be assayed using this method and apparatus. Precisions of 1000 MWd/tU appear to be feasible.

Lee, David M. (Los Alamos, NM); Lindquist, Lloyd O. (Santa Fe, NM)

1985-01-01T23:59:59.000Z

26

Some effects of packaging materials on critical arrays of fissile materials  

SciTech Connect

The surface density representation of array criticality provides a comprehensive display of criticality parameters of arrays of packaged fissile materials. The study leads to the following conclusions: (1) The mass limits established by the N 16.5 standard for air-spaced spherical units in water-reflected arrays may be adequate for transportation packages; (2) criticality assessments made for one fissile material can be extended to other materials which have defined equivalent masses for array criticality of air-spaced units; and (3) a uniform minimum margin of subcriticality can be established for transportation of packaged fissile materials.

Thomas, J.T.; Tang, J.S.

1977-01-01T23:59:59.000Z

27

Method and apparatus for measuring reactivity of fissile material  

DOE Patents (OSTI)

Given are a method and apparatus for measuring nondestructively and noninvasively (i.e., using no internal probing) the burnup, reactivity, or fissile content of any material which emits neutrons and which has fissionable components. The assay is accomplished by altering the return flux of neutrons into the fuel assembly by means of changing the reflecting material. The existing passive neutron emissions in the material being assayed are used as the source of interrogating neutrons. Two measurements of either emitted neutron or emitted gamma-ray count rates are made and are then correlated to either reactivity, burnup, or fissionable content of the material being assayed, thus providing a measurement of either reactivity, burnup, or fissionable content of the material being assayed. Spent fuel which has been freshly discharged from a reactor can be assayed using this method and apparatus. Precisions of 1000 MWd/tU appear to be feasible.

Lee, D.M.; Lindquist, L.O.

1982-09-07T23:59:59.000Z

28

Direct conversion of surplus fissile materials, spent nuclear fuel, and other materials to high-level-waste glass  

SciTech Connect

With the end of the cold war the United States, Russia, and other countries have excess plutonium and other materials from the reductions in inventories of nuclear weapons. The United States Academy of Sciences (NAS) has recommended that these surplus fissile materials (SFMs) be processed so they are no more accessible than plutonium in spent nuclear fuel (SNF). This spent fuel standard, if adopted worldwide, would prevent rapid recovery of SFMs for the manufacture of nuclear weapons. The NAS recommended investigation of three sets of options for disposition of SFMs while meeting the spent fuel standard: (1) incorporate SFMs with highly radioactive materials and dispose of as waste, (2) partly burn the SFMs in reactors with conversion of the SFMs to SNF for disposal, and (3) dispose of the SFMs in deep boreholes. The US Government is investigating these options for SFM disposition. A new method for the disposition of SFMs is described herein: the simultaneous conversion of SFMs, SNF, and other highly radioactive materials into high-level-waste (HLW) glass. The SFMs include plutonium, neptinium, americium, and {sup 233}U. The primary SFM is plutonium. The preferred SNF is degraded SNF, which may require processing before it can be accepted by a geological repository for disposal.

Forsberg, C.W.; Elam, K.R.

1995-01-31T23:59:59.000Z

29

Audit Report on "Containers Suitable for Shipping Fissile Material", DOE/IG-0490  

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

As a result of its weapons program activities, the Department of Energy (Department) has a significant inventory of surplus fissile materials. Within the Department, the National Nuclear Security...

30

ES-3100: A New Generation Shipping Container for Bulk Highly Enriched Uranium and Other Fissile Materials  

SciTech Connect

The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA) is shipping bulk quantities of surplus fissile materials, primarily highly enriched uranium (HEU), over the next 15 to 20 years for disposition purposes. The U.S. Department of Transportation (DOT) specification 6M container is the package of choice for most of these shipments. However, the 6M does not conform to the Type B packaging requirements in the ''Code of Federal Regulations'' (10CFR71) and, for that reason, is being phased out for use in the secure transportation system of DOE. BWXT Y-12 is currently developing a package to replace the DOT 6M container for HEU disposition shipping campaigns. The new package is based on state-of-the-art, proven, and patented insulation technologies that have been successfully applied in the design of other packages. The new package, designated the ES-3100, will have a 50% greater capacity for HEU than the 6M and will be easier to use. Engineering analysis on the new package includes detailed dynamic impact finite element analysis (FEA). This analysis gives the ES-3100 a high probability of complying with regulatory requirements.

Arbital, J.G.; Byington, G.A.; Tousley, D.R.

2004-07-01T23:59:59.000Z

31

An active system for the detection of special fissile material in small watercraft  

E-Print Network (OSTI)

Due to increasing terrorist threats and illegal proliferation of nuclear material and technology, there is a need for increased research in the area of detection of smuggled fissile material, some of which is designated by the International Atomic Energy Agency as special fissile material. This thesis focuses on a hypothetical scenario in which a terrorist organization has managed to smuggle an amount of special fissile material onto a personal recreational watercraft and sail it into a marina. If the boat could be forced to go through a detector system, then the contents could be interrogated and a determination made of whether any special fissile material was aboard. This thesis examines the hypothesis that active interrogation may be used successfully in the detection of special fissile material in such an environment. It shows that it is feasible to use an active neutron system to detect a significant quantity of special fissile material onboard a small boat via the differential dieaway technique. The MCNP Monte Carlo transport code was used to simulate the use of a pulsed neutron generator to induce fission in the fissile material and then estimate the detector response. The detector modeled was based on elastic scattering-induced recoil protons using pure hydrogen gas. There was a significant difference between the system with and without the presence of fissile material, and the estimated detector response for the system with fissile material present was shown to be sufficiently greater than the response due to background radiation only. Additionally, dose was estimated and found to be small enough that the system would not likely pose a significant radiological health risk to passengers on the boat.

Johansen, Norman Alfan, III

2006-08-01T23:59:59.000Z

32

SRS - Programs - H Area Nuclear Materials Disposition  

NLE Websites -- All DOE Office Websites (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.

33

A system for the detection of concealed nuclear weapons and fissile material aboard cargo cotainerships  

E-Print Network (OSTI)

A new approach to the detection of concealed nuclear weapons and fissile material aboard cargo containerships is proposed. The ship-based approach removes the constraints of current thinking by addressing the threat of ...

Gallagher, Shawn P., S.M. Massachusetts Institute of Technology

2005-01-01T23:59:59.000Z

34

EM Waste and Materials Disposition & Transportation  

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

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

35

Fissile and Non-Fissile Material Detection Using Nuclear Acoustic Resonance Signatures  

Science Conference Proceedings (OSTI)

The objective of this project is to develop anovel technique for remote, non-destructive, non-radiation-based detection of materials of interest to Nonproliferation Programs. We propse the development of a detection system based on magnetic resonance principles (NAR), which would work where radiation detection is not possible. The approach would be non-intrusive, penetrating, applicable to many materials of interest for Nonproliferation, and be able to identify the nuclear samples under investigation.

Bernhard R. Tittmann; P.M. Lenahan; David Spears; Rhys Williams

2008-11-25T23:59:59.000Z

36

Material Removal and Disposition | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Removal and Disposition | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

37

Waste and Materials Disposition Information | Department of Energy  

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

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.

38

History of the US weapons-usable plutonium disposition program leading to DOE`s record of decision  

SciTech Connect

This report highlights important events and studies concerning surplus weapons-usable plutonium disposition in the United States. Included are major events that led to the creation of the U.S. Department of Energy (DOE) Office of Fissile Materials Disposition in 1994 and to that DOE office issuing the January 1997 Record of Decision for the Storage and Disposition of Weapons-Useable Fissile Materials Final Programmatic Environmental Impact Statement. Emphasis has been given to reactor-based plutonium disposition alternatives.

Spellman, D.J.; Thomas, J.F.; Bugos, R.G.

1997-04-01T23:59:59.000Z

39

Nondestructive assay of fissile material samples in support of nuclear safeguards  

SciTech Connect

From nuclear science symposium; San Francisco, California, USA (14 Nov 1973). Samples of fissile material can be assayed by bombarding with 300- to 600- keV neutrons and counting delayed neutrons from fission. Interrogating neutron energy selection is based upon considerations of sample penetrability and insensitivity of response to nonfissile isotopes. Significant cost savings in nuclear safeguards and quality control are possible. (auth)

Evans, A.E. Jr.

1973-01-01T23:59:59.000Z

40

Glass material oxidation and dissolution system: Converting miscellaneous fissile materials to glass  

SciTech Connect

The cold war and the development of nuclear energy have resulted in significant inventories of miscellaneous fissile materials (MFMs). MFMs include (1) plutonium scrap and residue, (2) miscellaneous spent nuclear fuel (SNF), (3) certain hot cell wastes, and (4) many one-of-a-kind materials. Major concerns associated with the long-term management of these materials include: safeguards and nonproliferation issues; health, environment, and safety concerns. waste management requirements; and high storage costs. These issues can be addressed by converting the MFMs to glass for secure, long-term storage or repository disposal; however, conventional glass-making processes require oxide-like feed materials. Converting MFMs to oxide-like materials with subsequent vitrification is a complex and expensive process. A new vitrification process has been invented, the Glass Material Oxidation and Dissolution System (GMODS), which directly converts metals, ceramics, and amorphous solids to glass; oxidizes organics with the residue converted to glass; and converts chlorides to borosilicate glass and a secondary sodium chloride (NaCl) stream. Laboratory work has demonstrated the conversion of cerium (a plutonium surrogate), uranium, Zircaloy, stainless steel, multiple oxides, and other materials to glass. However, significant work is required to develop GMODS further for applications at an industrial scale. If implemented, GMODS will provide a new approach to manage these materials.

Forsberg, C.W.; Ferrada, J.J.

1996-03-19T23:59:59.000Z

Note: This page contains sample records for the topic "fissile materials disposition" 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

Processing fissile material mixtures containing zirconium and/or carbon  

DOE Patents (OSTI)

A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.

Johnson, Michael Ernest; Maloney, Martin David

2013-07-02T23:59:59.000Z

42

A method for managing the storage of fissile materials using criticality indices  

SciTech Connect

This paper describes a method for criticality control at fissile material storage facilities. The method involves the use criticiality indices for storage canisters. The logic, methodology, and results for selected canisters are presented. A concept for an interactive computer program using the method is also introduced. The computer program can be used in real time (using precalulated data) to select a Criticality Index (CI) for a container when it is delivered to or packaged at a site. Criticality safety is assured by controlling the sum of the CIs at each storage location below a defined Emit value when containers are moved.

Philbin, J.S.; Harms, G.A.

1995-07-01T23:59:59.000Z

43

LCA Carbon Footprints Mining Materials Mfg Transport Use Disposition  

E-Print Network (OSTI)

LCA Carbon Footprints #12;Mining Materials Mfg Transport Use Disposition Recycle Transporta;on Use End of Life Results: Yours Six Products, Six Carbon Footprints, WSJ, 2009 Transporta;on Use End of Life Results: Yours Six Products, Six Carbon Footprints, WSJ, 2009

Gutowski, Timothy

44

Highly enriched uranium (HEU) storage and disposition program plan  

SciTech Connect

Recent changes in international relations and other changes in national priorities have profoundly affected the management of weapons-usable fissile materials within the United States (US). The nuclear weapon stockpile reductions agreed to by the US and Russia have reduced the national security requirements for these fissile materials. National policies outlined by the US President seek to prevent the accumulation of nuclear weapon stockpiles of plutonium (Pu) and HEU, and to ensure that these materials are subjected to the highest standards of safety, security and international accountability. The purpose of the Highly Enriched Uranium (HEU) Storage and Disposition Program Plan is to define and establish a planned approach for storage of all HEU and disposition of surplus HEU in support of the US Department of Energy (DOE) Fissile Material Disposition Program. Elements Of this Plan, which are specific to HEU storage and disposition, include program requirements, roles and responsibilities, program activities (action plans), milestone schedules, and deliverables.

Arms, W.M.; Everitt, D.A.; O`Dell, C.L.

1995-01-01T23:59:59.000Z

45

Development of a Fissile Materials Irradiation Capability for Advanced Fuel Testing at the MIT Research Reactor  

SciTech Connect

A fissile materials irradiation capability has been developed at the Massachusetts Institute of Technology (MIT) Research Reactor (MITR) to support nuclear engineering studies in the area of advanced fuels. The focus of the expected research is to investigate the basic properties of advanced nuclear fuels using small aggregates of fissile material. As such, this program is intended to complement the ongoing fuel evaluation programs at test reactors. Candidates for study at the MITR include vibration-packed annular fuel for light water reactors and microparticle fuels for high-temperature gas reactors. Technical considerations that pertain to the design of the MITR facility are enumerated including those specified by 10 CFR 50 concerning the definition of a research reactor and those contained in a separate license amendment that was issued by the U.S. Nuclear Regulatory Commission to MIT for these types of experiments. The former includes limits on the cross-sectional area of the experiment, the physical form of the irradiated material, and the removal of heat. The latter addresses experiment reactivity worth, thermal-hydraulic considerations, avoidance of fission product release, and experiment specific temperature scrams.

Hu Linwen; Bernard, John A.; Hejzlar, Pavel; Kohse, Gordon [Massachusetts Institute of Technology (United States)

2005-05-15T23:59:59.000Z

46

EXAFS and XANES analysis of plutonium and cerium edges from titanate ceramics for fissile materials disposal.  

Science Conference Proceedings (OSTI)

We report x-ray absorption near edge structure (XANES) and extended x-ray absorption fine structure (EXAFS) spectra from the plutonium L{sub III} edge and XANES from the cerium L{sub II} edge in prototype titanate ceramic hosts. The titanate ceramics studied are based upon the hafnium-pyrochlore and zirconolite mineral structures and will serve as an immobilization host for surplus fissile materials, containing as much as 10 weight % fissile plutonium and 20 weight % (natural or depleted) uranium. Three ceramic formulations were studied: one employed cerium as a ''surrogate'' element, replacing both plutonium and uranium in the ceramic matrix, another formulation contained plutonium in a ''baseline'' ceramic formulation, and a third contained plutonium in a formulation representing a high-impurity plutonium stream. The cerium XANES from the surrogate ceramic clearly indicates a mixed III-IV oxidation state for the cerium. In contrast, XANES analysis of the two plutonium-bearing ceramics shows that the plutonium is present almost entirely as Pu(IV) and occupies the calcium site in the zirconolite and pyrochlore phases. The plutonium EXAFS real-space structure shows a strong second-shell peak, clearly distinct from that of PuO{sub 2}, with remarkably little difference in the plutonium crystal chemistry indicated between the baseline and high-impurity formulations.

Fortner, J. A.; Kropf, A. J.; Bakel, A. J.; Hash, M. C.; Aase, S. B.; Buck, E. C.; Chamerlain, D. B.

1999-11-16T23:59:59.000Z

47

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

48

ESTIMATING IMPURITIES IN SURPLUS PLUTONIUM FOR DISPOSITION  

Science Conference Proceedings (OSTI)

The United States holds at least 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 of the National Nuclear Security Administration and the DOE Office of Environmental Management. Many of the items that require disposition are only partially characterized, and SRNL uses a variety of techniques to predict the isotopic and chemical properties that are important for processing through the Mixed Oxide Fuel Fabrication Facility and alternative disposition paths. Recent advances in laboratory tools, including Prompt Gamma Analysis and Peroxide Fusion treatment, provide data on the existing inventories that will enable disposition without additional, costly sampling and destructive analysis.

Allender, J.; Moore, E.

2013-07-17T23:59:59.000Z

49

``Cats and Dogs'' disposition at Sandia: Last of the legacy materials  

SciTech Connect

Over the past 12 months, Sandia National Laboratories, New Mexico (SNL/NM), has successfully conducted an evaluation of its nuclear material holdings. As a result, approximately 46% of these holdings (36% by mass) have been reclassified as no defined use (NDU). Reclassification as NDU allows Sandia to determine the final disposition of a significant percentage of its legacy nuclear material. Disposition will begin some time in mid CY2000. This reclassification and the proposed disposition of the material has resulted in an extensive coordination effort lead by the Nuclear Materials Management Team (NMMT), which includes the nuclear material owners, the Radioactive Waste/Nuclear Material Disposition Department (7135), and DOE Albuquerque Operations Office. The process of identifying and reclassifying the cats and dogs or miscellaneous lots of nuclear material has also presented a number of important lessons learned for other sites in the DOE complex.

STRONG,WARREN R.; JACKSON,JOHN L.

2000-05-03T23:59:59.000Z

50

SELECTION OF SURPLUS PLUTONIUM MATERIALS FOR DISPOSITION TO WIPP  

SciTech Connect

The U.S. Department of Energy (DOE) is preparing a Surplus Plutonium Disposition (SPD) Supplemental Environmental Impact Statement (SEIS). Included in the evaluation are up to 6 metric tons (MT) of plutonium in the form of impure oxides and metals for which a disposition plan has not been decided, among options that include preparation as feed for the Mixed Oxide Fuel Fabrication Facility; disposing to high-level waste through the Savannah River Site (SRS) HB Line and H Canyon; can-in-canister disposal using the SRS Defense Waste Processing Facility; and preparation for disposal at the Waste Isolation Pilot Plant (WIPP). DOE and SRS have identified at least 0.5 MT of plutonium that, because of high levels of chemical and isotopic impurities, is impractical for disposition by methods other than the WIPP pathway. Characteristics of these items and the disposition strategy are discussed.

Allender, J.; Mcclard, J.; Christopher, J.

2012-06-08T23:59:59.000Z

51

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

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

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 .......................................................................

52

EPRI Report on Solid Material Disposition: Evaluation to Assess Industry Impact  

Science Conference Proceedings (OSTI)

In March 2005, the NRC staff requested Commission approval for publication of a proposed rule in the Federal Register to amend 10CFR Part 20 to include criteria for controlling the disposition of solid materials. This report provides an initial analysis of whether or not methods of solid material assessment, currently practiced at nuclear power facilities, would be sufficient to meet the disposition limits in the proposed rule.

2005-12-01T23:59:59.000Z

53

Disposition of Surplus Highly Enriched Uranium  

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

. . ------- .--- --. ---- 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

54

Disposition of Surplus Highly Enriched Uranium  

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

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

55

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

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

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 ...........................................................................................................................

56

FATE OF FISSILE MATERIAL BOUND TO MONOSODIUM TITANATE DURING COOPER CATALYZED PEROXIDE OXIDATION OF TANK 48H WASTE  

SciTech Connect

At the Savannah River Site (SRS), Tank 48H currently holds approximately 240,000 gallons of slurry which contains potassium and cesium tetraphenylborate (TPB). A copper catalyzed peroxide oxidation (CCPO) reaction is currently being examined as a method for destroying the TPB present in Tank 48H. Part of the development of that process includes an examination of the fate of the Tank 48H fissile material which is adsorbed onto monosodium titanate (MST) particles. This report details results from experiments designed to examine the potential degradation of MST during CCPO processing and the subsequent fate of the adsorbed fissile material. Experiments were conducted to simulate the CCPO process on MST solids loaded with sorbates in a simplified Tank 48H simulant. Loaded MST solids were placed into the Tank 48H simplified simulant without TPB, and the experiments were then carried through acid addition (pH adjustment to 11), peroxide addition, holding at temperature (50 C) for one week, and finally NaOH addition to bring the free hydroxide concentration to a target concentration of 1 M. Testing was conducted without TPB to show the maximum possible impact on MST since the competing oxidation of TPB with peroxide was absent. In addition, the Cu catalyst was also omitted, which will maximize the interaction of H{sub 2}O{sub 2} with the MST; however, the results may be non-conservative assuming the Cu-peroxide active intermediate is more reactive than the peroxide radical itself. The study found that both U and Pu desorb from the MST when the peroxide addition begins, although to different extents. Virtually all of the U goes into solution at the beginning of the peroxide addition, whereas Pu reaches a maximum of {approx}34% leached during the peroxide addition. Ti from the MST was also found to come into solution during the peroxide addition. Therefore, Ti is present with the fissile in solution. After the peroxide addition is complete, the Pu and Ti are found to precipitate from solution, while the U remains in solution throughout the remaining processes, including pH adjustment to 1 M free hydroxide. The Ti is likely forming a peroxotitanate material, which can then resorb the leached Pu from solution, but has a low affinity for U. Since Pu was not detected in the SEMEDS studies, it cannot be conclusively determined in what form the Pu returns to the solids; however, the Pu likely resorbed onto the peroxotitanate material. Based on the results of this experiment, Savannah River National Laboratory (SRNL) recommends the following experiments to further examine the fate of fissile material in CCPO processing of Tank 48H: (1) Repeat with full simulant matrix (organic and Cu catalyst present along with simulated radioactive sludge); and (2) Repeat of the above test after selection of final conditions (i.e., pH, temperature) if they differ from conditions tested.

Taylor-Pashow, K.

2012-08-09T23:59:59.000Z

57

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

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

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

58

The Nuclear Material Focus Area Roadmapping Process Utilizing Environmental Management Complex-Wide Nuclear Material Disposition Pathways  

SciTech Connect

This paper describes the process that the Nuclear Materials Focus Area (NMFA) has developed and utilizes in working with individual Department of Energy (DOE) sites to identify, address, and prioritize research and development efforts in the stabilization, disposition, and storage of nuclear materials. By associating site technology needs with nuclear disposition pathways and integrating those with site schedules, the NMFA is developing a complex wide roadmap for nuclear material technology development. This approach will leverage technology needs and opportunities at multiple sites and assist the NMFA in building a defensible research and development program to address the nuclear material technology needs across the complex.

Sala, D. R.; Furhman, P.; Smith, J. D.

2002-02-26T23:59:59.000Z

59

Use of a computer-assisted administrative control to enhance criticality safety in LLNL for fissile material disposition operations  

SciTech Connect

This paper deals primarily with the use of a two-person rule on the mass limit control. Main emphasis is placed on the appropriate use of a computer program to assist operators in carrying out mass control. An attempt will be exercised to compare the use of a mass control card system under a two-person rule with a computer-assist two-person system. The interface points relevant to criticality safety between computer and human operators will be identified. Features that will make a computer program useful in a multiple workstation application environment will be discussed along with the merits of the using the computer program. How such a computer-assist administrative control may be incorporated in the overall infrastructure for criticality safety will be analyzed. Suggestion of future development of using a computer program to enhance safety margin will also be made to stimulate further discussion on the application of computer technology for real-time criticality safety control.

Huang, Song T.; Lappa, D.A.; Chiao, Tang

1997-04-01T23:59:59.000Z

60

Interim Report on the Disposition of Solid Material: Comparative Review of Three Published Clearance Guides  

Science Conference Proceedings (OSTI)

As part of the rulemaking process, the U.S. Nuclear Regulatory Commission (NRC) is currently evaluating alternative approaches to control the disposition of solid material at nuclear facilities. The proposed rule would likely incorporate a dose-based criterion. While the NRC has been developing the scope and details of a rule, various national and international organizations have reported dose-based activity concentration levels that utilities may apply to clearance. This document evaluates and discusses...

2004-11-15T23:59:59.000Z

Note: This page contains sample records for the topic "fissile materials disposition" 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

SAVANNAH RIVER SITE'S H-CANYON FACILITY: IMPACTS OF FOREIGN OBLIGATIONS ON SPECIAL NUCLEAR MATERIAL DISPOSITION  

SciTech Connect

The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These ď123 agreementsĒ are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

Magoulas, V.

2013-06-03T23:59:59.000Z

62

Development of an alternate pathway for materials destined for disposition to WIPP  

Science Conference Proceedings (OSTI)

The Los Alamos National Laboratory currently has an inventory of process residues that may be viable candidates for disposition to the Waste Isolation Pilot Project (WIPP) located at Carlsbad, New Mexico. A recent 'Attractiveness Level D' exemption allows for the discard of specified intractable materials regardless of the percent plutonium. However, the limits with respect to drum loadings must be met. Cementation is a key component of the aqueous nitrate flowsheet and serves as a 'bleed-off' stream for impurities separated from the plutonium during processing operations. The main 'feed' to the cementation operations are the 'bottoms' from the evaporation process. In the majority of cases, the cemented bottoms contain less than the allowed amount per drum for WIPP acceptance. This project would expand the route to WIPP for items that have no defined disposition path, are difficult to process, have been through multiple passes, have no current recovery operations available to recover the plutonium and that are amenable to cementation. This initial work will provide the foundation for a full scale disposition pathway of the candidate materials. Once the pathway has been expanded and a cementation matrix developed, routine discard activities will be initiated.

Ayers, Georgette Y [Los Alamos National Laboratory; Mckerley, Bill [Los Alamos National Laboratory; Veazey, Gerald W [Los Alamos National Laboratory; Ricketts, Thomas E [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

63

Disposition of Surplus Highly Enriched Uranium  

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

@ @ 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

64

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

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

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 . . . . . . . . . . . . . . . .

65

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

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

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

66

Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition  

Science Conference Proceedings (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

67

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)  

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

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

68

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

SciTech Connect

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

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

1997-08-01T23:59:59.000Z

69

Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project  

SciTech Connect

This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

Reynolds, T. D.; Easterling, S. D.

2010-10-01T23:59:59.000Z

70

Response to 'A comment on 'Signatures of fissile materials:High-energy gamma rays following fission,' by Zeev B. Alfassi'  

DOE Green Energy (OSTI)

Prof. Alfassi has pointed out that radionuclides that are not fission products, but which emit {gamma} rays with energies E{sub {gamma}} > 3 MeV, can be produced by neutron irradiation. He suggested that the decays of such activation products would interfere with the identification of fissionable materials. However, the combination of the energy spectrum and the temporal variation of the fission product gamma rays can be used to distinguish fissionable material from other nuclides. The activation of nuclides that could produce interferences will depend upon the specifics of the cargo and, possibly, the local surroundings. As discussed in our original publication, in addition to the steel that Prof. Alfassi referred to in his Comment, we studied the activation of wood, polyethylene, aluminum, and sandstone. Activation by thermal neutrons will always occur, and Prof. Alfassi correctly points out that nuclides such as {sup 49}Ca and {sup 37}S can be formed in this way. These nuclides are representative of most potential interferences. Both {sup 48}Ca and {sup 36}S have very low isotopic abundances (0.187% and 0.02%, respectively) and small thermal neutron capture cross sections (0.20 barns and 0.98 barns, respectively). In addition, their half lives are more than an order of magnitude longer than the gross average observed from the fission products, and more than two orders of magnitude longer than the lifetimes of the shorter-lived fission products that contribute significantly to the total intensity in the energy range of interest. These differences make it possible to distinguish between fission products and thermal neutron activation products. Prof. Alfassi also pointed out that interferences, of which {sup 16}N is likely to be the most important, can be produced by fast neutron reactions. (As described in our original publication, we did not use a 14 MeV generator in our work.) Fortunately, a judicious choice of the source neutron energy can limit the extent of these interferences quite significantly. For example, the laboratory threshold for the reaction {sup 16}O(n,p){sup 16}N is 10.2 MeV, while that for the reaction {sup 19}F(n,{alpha}){sup 16}N is 1.6 MeV. Thus a source neutron energy around 5 MeV would completely eliminate the {sup 16}O(n,p){sup 16}N reaction and limit the {sup 19}F(n,{alpha}){sup 16}N reaction to that portion of the cargo in which neutrons with energies greater than 1.6 MeV were present. However, even in the presence of {sup 16}N, the energy spectrum and temporal variation of the fission product gamma rays should be decisive in distinguishing fissionable material from these interferences.

Norman, Eric B.; Prussin, Stanley G.; Larimer, Ruth-Mary; Shugart, Howard; Browne, Edgardo; Smith, Alan R.; McDonald, Richard J.; Nitsche, Heino; Gupta, Puja; Frank, Michael I.; Gosnell, Thomas B.

2004-06-03T23:59:59.000Z

71

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

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

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

72

DEVELOPMENT OF GLASS AND CRYSTALLINE CERAMIC FORMS FOR DISPOSITION OF EXCESS PLUTONIUM  

SciTech Connect

In the aftermath of the Cold War, the United States Department of Energy (DOE) has identified up to 50 metric tons of excess plutonium that needs to be dispositioned. The bulk of the material is slated to be blended with uranium and fabricated into a Mixed Oxide (MOX) fuel for subsequent burning in commercial nuclear reactors. Excess plutonium-containing impurity materials making it unsuitable for fabrication into MOX fuel will need to be dispositioned via other means. Glass and crystalline ceramics have been developed and studied as candidate forms to immobilize these impure plutonium feeds. A titanate-based ceramic was identified as an excellent actinide material host. This composition was based on Synroc compositions previously developed for nuclear waste immobilization. These titanate ceramics were found to be able to accommodate extremely high quantities of fissile material and exhibit excellent aqueous durability. A lanthanide borosilicate (LaBS) glass was developed to accommodate high concentrations of plutonium and to be very tolerant of impurities yet still maintain good aqueous durability. Recent testing of alkali borosilicate compositions showed promise of using these compositions to disposition lower concentrations of plutonium using existing high level waste vitrification processes. The developed waste forms all appear to be suitable for Pu disposition. Depending on the actual types and concentrations of the Pu residue streams slated for disposition, each waste form offers unique advantages.

Marra, James; Cozzi, A; Crawford, C.; Herman, C.; Marra, John; Peeler, D.

2009-09-10T23:59:59.000Z

73

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

Science Conference Proceedings (OSTI)

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis. Interstate waste and materials shipments. Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the period from April 1, 2001 through June 30, 2001, under the NGA grant.

Ethan W. Brown

2001-09-01T23:59:59.000Z

74

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

75

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

SciTech Connect

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; Interstate waste and materials shipments; and Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from May 1, 1999, through July 30, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and continued to facilitate interactions between the states and DOE to develop a foundation for an ongoing substantive relationship between the Governors of key states and Secretary Richardson.

Ann M. Beauchesne

1999-07-30T23:59:59.000Z

76

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

Science Conference Proceedings (OSTI)

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; Interstate waste and materials shipments; and Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from February 1, 1999, through April 30, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and EM Integration activities; and continued to serve as a liaison between the NGA FFCA Task Force states and the Department.

Ann M. Beauchesne

1999-04-30T23:59:59.000Z

77

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

SciTech Connect

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in DOE's Accelerating Cleanup: Paths to Closure strategy and contractor integration analysis. Interstate waste and materials shipments. Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from December 31, 1997 through April 30, 1998 under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and provided ongoing support to state-DOE interactions in preparation for the March 30-31, 1998 NGA Federal Facilities Compliance Task Force Meeting with DOE. maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, DOE's Environmental Management Budget, and DOE's proposed Intersite Discussions.

NONE

1998-04-01T23:59:59.000Z

78

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

SciTech Connect

Through the National Governors Association (NGA) project ``Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; Interstate waste and materials shipments; and Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the period from October 1, 1999 through January 31, 2000, under the NGA grant. The work accomplished by the NGA project team during the past three months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; convened and facilitated the October 6--8 NGA FFCA Task Force Meeting in Oak Ridge, Tennessee; maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and continued to facilitate interactions between the states and DOE to develop a foundation for an ongoing substantive relationship between the Governors of key states and the Department.

Ann M. Beauchesne

2000-01-01T23:59:59.000Z

79

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

Science Conference Proceedings (OSTI)

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in DOE's Accelerating Cleanup: Paths to Closure strategy and contractor integration analysis. Interstate waste and materials shipments. Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from April 30, 1998 through June 30, 1998 under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and provided ongoing support to state-DOE interactions. maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, DOE's Environmental Management Budget, and DOE's proposed Intersite Discussions.

NONE

1998-07-01T23:59:59.000Z

80

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

Science Conference Proceedings (OSTI)

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: (1) Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; (2) Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; (3) Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; (4) Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; (5) Interstate waste and materials shipments; and (6) Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from October 1, 1998 through January 31, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: (1) maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; (2) maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and EM Integration activities; and (3) continued to serve as a liaison between the NGA FFCA Task Force states and the Department.

Ann M. Beauchesne

1999-01-31T23:59:59.000Z

Note: This page contains sample records for the topic "fissile materials disposition" 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

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

SciTech Connect

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: (1) Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; (2) Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; (3) Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; (4) Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; (5) Interstate waste and materials shipments; and (6) Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from June 1, 1998 through September 30, 1998, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: (1) maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; (2) maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and EM Integration activities; and (3) continued to serve as a liaison between the NGA FFCA Task Force states and the Department.

Ann B. Beauchesne

1998-09-30T23:59:59.000Z

82

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

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

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

83

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

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

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

84

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

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

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

85

Integrated Facilities Disposition Program  

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

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

86

Evaluation of options for disposition of dispersible material in B-Cell  

SciTech Connect

The radioactive contaminants in the dispersible material in B-cell of the 324 Building Radiochemical Energy (RE) hot-cell complex at the Hanford Site in southeastern Washington exceed the allowable level. In 1986, there was a spill of 1.3 million curies of concentrated cesium and strontium in B-cell. Cleanup is required, and candidate technologies for cleaning up or otherwise addressing problems associated with the dispersible material are being evaluated by Pacific Northwest Laboratory (PNL). The RE hot-cell complex in 324 Building was constructed in the late 1950s. From the early 1960s until today the complex has been the site of numerous research, development, and demonstration programs using radioactive and hazardous materials. In mid-FY 1988, a program to clean B-cell was initiated. At present, dispersible material has been collected from 45% of the cell floor area, and 64% of the equipment and support racks have been removed from the cell. The evaluation of decontamination procedures are described.

Tokarz, R.D.; Defferding, L.J.; Adickes, M.D.; Keene, K.E.; Pilger, J.P.; Alzheimer, J.M. [Pacific Northwest Lab., Richland, WA (United States); Paxton, M.M. [Westinghouse Hanford Co., Richland, WA (United States)

1993-10-01T23:59:59.000Z

87

A Program to Stabilize Nuclear Materials as Managed by the Plutonium Focus Area  

Science Conference Proceedings (OSTI)

This paper describes the program to stabilize nuclear materials, consistent with the Department of Energy Office of Environmental Management (EM) plan, Accelerating Cleanup: Paths to Closure. The program is managed by the Plutonium Stabilization and Disposition Focus Area, which defines and manages technology development programs to stabilize nuclear materials and assure their subsequent safe storage and final disposition. The scope of the Plutonium Stabilization and Disposition Focus Area (PFA) activities includes non-weapons plutonium materials, special isotopes, and other fissile materials. The PFA provides solutions to site-specific and complex wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. Our paper describes an important programmatic function of the Department of Energy nuclear materials stabilization program, including the tie-in of policy to research needs and funding for the nuclear materials disposition area. The PFA uses a rigorous systems engineering determination of technology needs and gaps, under the guidance of a Technical Advisory Panel, consisting of complex-wide experts. The Research and Development planning provides an example for other waste areas and should be of interest to Research and Development managers. The materials disposition maps developed by the PFA and described in this paper provide an evaluation of research needs, data gaps and subsequent guidance for the development of technologies for nuclear materials disposition. This paper also addresses the PFA prioritization methodology and its ability to forecast actual time to implementation.

B. Kenley (Kenley Consulting); B. Scott; B. Seidel (ANL-W); D. Knecht (LMITCO); F. Southworth; K. Osborne (DOE-ID); N. Chipman; T. Creque

1999-03-01T23:59:59.000Z

88

Nuclear Forensic Reference Materials (RM) for Attribution of ...  

Science Conference Proceedings (OSTI)

... Nuclear Materials ē Fuel cycles ē Limit fissile material production ē Reactor conversion Securing SNM ē Reliable inventories ē Physical Security ē ...

2012-12-06T23:59:59.000Z

89

Integration of health physics, safety and operational processes for management and disposition of recycled uranium wastes at the Fernald Environmental Management Project (FEMP)  

Science Conference Proceedings (OSTI)

Fluor Fernald, Inc. (Fluor Fernald), the contractor for the U. S. Department of Energy (DOE) Fernald Environmental Management Project (FEMP), recently submitted a new baseline plan for achieving site closure by the end of calendar year 2006. This plan was submitted at DOE's request, as the FEMP was selected as one of the sites for their accelerated closure initiative. In accordance with the accelerated baseline, the FEMP Waste Management Project (WMP) is actively evaluating innovative processes for the management and disposition of low-level uranium, fissile material, and thorium, all of which have been classified as waste. These activities are being conducted by the Low Level Waste (LLW) and Uranium Waste Disposition (UWD) projects. Alternatives associated with operational processing of individual waste streams, each of which poses potentially unique health physics, industrial hygiene and industrial hazards, are being evaluated for determination of the most cost effective and safe met hod for handling and disposition. Low-level Mixed Waste (LLMW) projects are not addressed in this paper. This paper summarizes historical uranium recycling programs and resultant trace quantity contamination of uranium waste streams with radionuclides, other than uranium. The presentation then describes how waste characterization data is reviewed for radiological and/or chemical hazards and exposure mitigation techniques, in conjunction with proposed operations for handling and disposition. The final part of the presentation consists of an overview of recent operations within LLW and UWD project dispositions, which have been safely completed, and a description of several current operations.

Barber, James; Buckley, James

2003-02-23T23:59:59.000Z

90

DOE/EA-1651: FINDING OF NO SIGNIFICANT IMPACT Uranium-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (01/13/10)  

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

URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT 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 Oak Ridge National Laboratory (ORNL) facilities; process the ORNL inventory of uranium-233 (U-233); and transport the processed material to a long-term disposal facility. Small quantities of similar material currently stored at other DOE sites may also be included in this initiative. The

91

Development of an Air Transport Type A Fissile Package  

SciTech Connect

This paper presents the summary of testing by the Savannah River National Laboratory (SRNL) to support development of a light weight (<140 lbs) air transport qualified Type A Fissile Packaging. The package design incorporates features and materials specifically designed to minimize packaging weight. The light weight package is being designed to provide confinement to the contents when subjected to the normal and hypothetical conditions required of an air transportable Type A Fissile radioactive material shipping package. The objective of these tests was to provide design input to the final design for the LORX Type A Fissile Air Transport Packaging when subjected to the performance requirements of the drop, crush and puncture probe test of 10CFR71. The post test evaluation of the prototype packages indicates that all of the tested designs would satisfactorily confine the content within the packaging. The differences in the performance of the prototypes varied significantly depending on the core materials and their relative densities. Information gathered from these tests is being used to develop the final design for the Department of Homeland Security.

Blanton, P.; Ebert, K.

2011-07-13T23:59:59.000Z

92

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

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

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

93

A Proposed Methodology For The Analysis And Selection Of Alternatives For The Disposition Of Surplus Plutonium  

E-Print Network (OSTI)

A Proposed Methodology for the Analysis and Selection of Alternatives for the Disposition of Surplus Plutonium The nuclear states are currently involved in the development of comprehensive approaches to the long-term storage and management of fissile materials. A major objective of this effort is to provide a framework for prevention of the proliferation of nuclear weapons. The evaluation should include non-proliferation, economic, technical, institutional, schedule, environmental, and health and safety issues. The ANRCP has proposed that an evaluation of alternatives be guided by the principles of decision analysis, a logical and formal approach to the solution of complicated problems that are too complex to solve informally. This approach would consist of four steps: 1) identification of alternatives and objectives, 2) estimation of the performance of the alternatives with respect to the objectives, 3) development of values and weights for the objectives, and 4) evaluation of ...

James S. Dyer; James S; John C. Butler; Jianmin Jia; Thomas Edmunds

1996-01-01T23:59:59.000Z

94

Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement  

Science Conference Proceedings (OSTI)

On May 22, 1997, DOE published a Notice of Intent in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS)''. ''The Surplus Plutonium Disposition Draft Environmental Impact Statement'' (SPD Draft EIS) (DOWEIS-0283-D) was prepared in accordance with NEPA and issued in July 1998. It identified the potential environmental impacts of reasonable alternatives for the proposed siting, construction, and operation of three facilities for plutonium disposition. These three facilities would accomplish pit disassembly and conversion, immobilization, and MOX fuel fabrication. For the alternatives that included MOX fuel fabrication, the draft also described the potential environmental impacts of using from three to eight commercial nuclear reactors to irradiate MOX fuel. The potential impacts were based on a generic reactor analysis that used actual reactor data and a range of potential site conditions. In May 1998, DCE initiated a procurement process to obtain MOX fuel fabrication and reactor irradiation services. The request for proposals defined limited activities that may be performed prior to issuance of the SPD EIS Record of Decision (ROD) including non-site-specific work associated with the development of the initial design for the MOX fuel fabrication facility, and plans (paper studies) for outreach, long lead-time procurements, regulatory management, facility quality assurance, safeguards, security, fuel qualification, and deactivation. No construction on the proposed MOX facility would begin before an SPD EIS ROD is issued. In March 1999, DOE awarded a contract to Duke Engineering & Services; COGEMA, Inc.; and Stone & Webster (known as DCS) to provide the requested services. The procurement process included the environmental review specified in DOE's NEPA regulations in 10 CFR 1021.216. The six reactors selected are Catawba Nuclear Station Units 1 and 2 in South Carolina McGuire Nuclear Station Units 1 and 2 in North Carolina, and North Anna Power Station Units 1 and 2 in Virginia. The Supplement describes 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.

N /A

1999-05-14T23:59:59.000Z

95

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

SciTech Connect

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

96

BIOLOGICAL EVIDENCE disposition process  

Science Conference Proceedings (OSTI)

... Notification of destruction sent per statutory requirements In-house ďticklerĒ system tracks evidence and identifies upcoming disposition time ...

2013-05-14T23:59:59.000Z

97

Advanced research workshop: nuclear materials safety  

SciTech Connect

The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of nuclear experience on a common objective—the safe and secure storage and disposition of excess fissile nuclear materials.

Jardine, L J; Moshkov, M M

1999-01-28T23:59:59.000Z

98

Source modulation-correlation measurement for fissile mass flow in gas or liquid fissile streams  

SciTech Connect

The method of monitoring fissile mass flow on all three legs of a blending point, where the input is high-enriched uranium (HEU) and low-enriched uranium (LEU) and the product is PEU, can yield the fissile stream velocity and, with calibration, the [sup235]U content. The product of velocity and content integrated over the pipe gives the fissile mass flow in each leg. Also, the ratio of fissile contents in each pipe: HEU/LEU, HEU/PEU, and PEU/LEU, are obtained. By modulating the source on the input HEU pipe differently from that on the output pipe, the HEU gas can be tracked through the blend point. This method can be useful for monitoring flow velocity, fissile content, and fissile mass flow in HEU blenddown of UF[sub 6] if the pressures are high enough to contain some of the induced fission products. This method can also be used to monitor transfer of fissile liquids and other gases and liquids that emit radiation delayed from particle capture. These preliminary experiments with the Oak Ridge apparatus show that the method will work and the modeling is adequate.

Mihalczo, J.T.; March-Leuba, J.A.; Valentine, T.E.; Abston, R.A.; Mattingly, J.K.; Mullens, J.A.

1996-09-01T23:59:59.000Z

99

Dry Blending to Achieve Isotopic Dilution of Highly Enriched Uranium Oxide Materials  

SciTech Connect

The end of the cold war produced large amounts of excess fissile materials in the United States and Russia. The Department of Energy has initiated numerous activities to focus on identifying material management strategies for disposition of these excess materials. To date, many of these planning strategies have included isotopic dilution of highly enriched uranium as a means of reducing the proliferation and safety risks. Isotopic dilution by dry blending highly enriched uranium with natural and/or depleted uranium has been identified as one non-aqueous method to achieve these risk (proliferation and criticality safety) reductions. This paper reviews the technology of dry blending as applied to free flowing oxide materials.

Henry, Roger Neil; Chipman, Nathan Alan; Rajamani, R. K.

2001-04-01T23:59:59.000Z

100

Programmatic Environmental Assessment for the U. S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials  

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

93 93 FINAL Programmatic Environmental Assessment for the U.S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials FINDING OF NO SIGNIFICANT IMPMZT PROGR4MMATIC ENVIRONMENTAL ASSESSME?X FOR THE U.S. DEPARTMENT OF ENERGY, OAK RIDGE OPER4TIOSS IMPLEMENTATION OF A COMPREHENSIVE MANAGEMEKT PROGK4hl FOR THE STORAGE, TRANSPORTATION, AND DISPOSITION OF POTENTIALLY REUSABLE URANJUh4 MATERIALS AGEhCY: U.S. DEPARTMENT OF ENERGY (DOE) ACTION: FINDI?iG OF NO SIGNIFICANT 1~IPAC-I SUMI\!L4RY: The U. S. DOE has completed a Programmatic Environmental Assessment (PE:,4) (DOE/E?,- 1393), which is incorporated herein by this reference. Tile purpose of the

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101

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

102

Fusion-Fission Hybrid for Fissile Fuel Production without Processing  

SciTech Connect

Two scenarios are typically envisioned for thorium fuel cycles: 'open' cycles based on irradiation of {sup 232}Th and fission of {sup 233}U in situ without reprocessing or 'closed' cycles based on irradiation of {sup 232}Th followed by reprocessing, and recycling of {sup 233}U either in situ or in critical fission reactors. This study evaluates a third option based on the possibility of breeding fissile material in a fusion-fission hybrid reactor and burning the same fuel in a critical reactor without any reprocessing or reconditioning. This fuel cycle requires the hybrid and the critical reactor to use the same fuel form. TRISO particles embedded in carbon pebbles were selected as the preferred form of fuel and an inertial laser fusion system featuring a subcritical blanket was combined with critical pebble bed reactors, either gas-cooled or liquid-salt-cooled. The hybrid reactor was modeled based on the earlier, hybrid version of the LLNL Laser Inertial Fusion Energy (LIFE1) system, whereas the critical reactors were modeled according to the Pebble Bed Modular Reactor (PBMR) and the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) design. An extensive neutronic analysis was carried out for both the hybrid and the fission reactors in order to track the fuel composition at each stage of the fuel cycle and ultimately determine the plant support ratio, which has been defined as the ratio between the thermal power generated in fission reactors and the fusion power required to breed the fissile fuel burnt in these fission reactors. It was found that the maximum attainable plant support ratio for a thorium fuel cycle that employs neither enrichment nor reprocessing is about 2. This requires tuning the neutron energy towards high energy for breeding and towards thermal energy for burning. A high fuel loading in the pebbles allows a faster spectrum in the hybrid blanket; mixing dummy carbon pebbles with fuel pebbles enables a softer spectrum in the critical reactors. This combination consumes about 20% of the thorium initially loaded in the hybrid reactor ({approx}200 GWd/tHM), partially during hybrid operation, but mostly during operation in the critical reactor. The plant support ratio is low compared to the one attainable using continuous fuel chemical reprocessing, which can yield a plant support ratio of about 20, but the resulting fuel cycle offers better proliferation resistance as fissile material is never separated from the other fuel components.

Fratoni, M; Moir, R W; Kramer, K J; Latkowski, J F; Meier, W R; Powers, J J

2012-01-02T23:59:59.000Z

103

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

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

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

104

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

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

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

105

Plutonium Disposition Program | National Nuclear Security Administration  

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

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

106

CRUSH TESTING OF 9977 GENERAL PURPOSE FISSILE PACKAGINGS  

SciTech Connect

The 9977 General Purpose Fissile Package (GPFP) was designed in response to the adoption of the crush test requirement in the US regulations for packages for radioactive materials (10 CFR 71). This presentation on crush testing of the 9977 GPFP Reviews origins of Crush Test Requirements and implementation of crush test requirements in 10 CFR 71. SANDIA testing performed to support the rule making is reviewed. The differences in practice, on the part of the US Department of Energy from those required by the NRC for commercial purposes, are explained. The design features incorporated into the 9977 GPFP to enable it to withstand the crush test and the crush tests performed on the 9977 are described. Lessons learned from crush testing of GPFP packagings are given.

Smith, A.

2010-07-28T23:59:59.000Z

107

Request For Records Disposition | Department of Energy  

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

Strategic Petroleum Reserve Request For Records Disposition More Documents & Publications Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management...

108

Reactor and Material Supply | Y-12 National Security Complex  

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

Reactor and Reactor and Material Supply Reactor and Material Supply Y-12 has processed highly enriched uranium for more than 60 years in support of the nation's defense. The end of the Cold War and ensuing strategic arms control treaties have resulted in an excess of HEU materials. In 1994, approximately 174 metric tons of weapons-usable HEU was declared surplus to defense needs. The HEU disposition program was established to make the surplus HEU unsuitable for use in weapons by blending it down to low-enriched uranium and to recover the economic value of the materials to the extent practical. In 2005, the Secretary of Energy announced that an additional 200 metric tons of HEU would be removed from further use as fissile material in U.S. nuclear weapons. Approximately 20 metric tons of this material will

109

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

110

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

111

A Methodology for the Analysis and Selection of Alternative for the Disposition of Surplus Plutonium  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) - Office of Fissile Materials Disposition (OFMD) has announced a Record of Decision (ROD) selecting alternatives for disposition of surplus plutonium. A major objective of this decision was to further U.S. efforts to prevent the proliferation of nuclear weapons. Other concerns that were addressed include economic, technical, institutional, schedule, environmental, and health and safety issues. The technical, environmental, and nonproliferation analyses supporting the ROD are documented in three DOE reports [DOE-TSR 96, DOE-PEIS 96, and DOE-NN 97, respectively]. At the request of OFMD, a team of analysts from the Amarillo National Resource Center for Plutonium (ANRCP) provided an independent evaluation of the alternatives for plutonium that were considered during the evaluation effort. This report outlines the methodology used by the ANRCP team. This methodology, referred to as multiattribute utility theory (MAU), provides a structure for assembling results of detailed technical, economic, schedule, environment, and nonproliferation analyses for OFMD, DOE policy makers, other stakeholders, and the general public in a systematic way. The MAU methodology has been supported for use in similar situations by the National Research Council, an agency of the National Academy of Sciences.1 It is important to emphasize that the MAU process does not lead to a computerized model that actually determines the decision for a complex problem. MAU is a management tool that is one component, albeit a key component, of a decision process. We subscribe to the philosophy that the result of using models should be insights, not numbers. The MAU approach consists of four steps: (1) identification of alternatives, objectives, and performance measures, (2) estimation of the performance of the alternatives with respect to the objectives, (3) development of value functions and weights for the objectives, and (4) evaluation of the alternatives and sensitivity analysis. These steps are described below.

NONE

1999-08-31T23:59:59.000Z

112

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental  

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

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

113

SRS - Programs - Liquid Waste Disposition  

NLE Websites -- All DOE Office Websites (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.

114

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY Atomic Energy Commission REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications...

115

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

RECORDS DISPOSITION AUTHORITY More Documents & Publications Disposition Schedule: Human Radiation Experiments REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS...

116

Used Fuel Disposition R&D Documents | Department of Energy  

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

Technologies Used Fuel Disposition Research & Development Used Fuel Disposition R&D Documents Used Fuel Disposition R&D Documents April 30, 2012 Office of UNF Disposition...

117

Major Risk Factors to the Integrated Facility Disposition Project  

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

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.

118

Supplement Analysis for the Storage of Surplus Plutonium Materials at the Savannah River Site (DOE/EIS-0229-SA-4)(09/05/07)  

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

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

119

Facility Disposition Safety Strategy RM  

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

The Facility Disposition Safety Strategy (FDSS) Review Module is a tool that assists DOE federal project review teams in evaluating the adequacy of the facility documentation, preparations or...

120

Programmatic Environmental Assessment for the U. S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials  

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

IMPMZT IMPMZT PROGR4MMATIC ENVIRONMENTAL ASSESSME?X FOR THE U.S. DEPARTMENT OF ENERGY, OAK RIDGE OPER4TIOSS IMPLEMENTATION OF A COMPREHENSIVE MANAGEMEKT PROGK4hl FOR THE STORAGE, TRANSPORTATION, AND DISPOSITION OF POTENTIALLY REUSABLE URANJUh4 MATERIALS AGEhCY: U.S. DEPARTMENT OF ENERGY (DOE) ACTION: FINDI?iG OF NO SIGNIFICANT 1~IPAC-I SUMI\!L4RY: The U. S. DOE has completed a Programmatic Environmental Assessment (PE:,4) (DOE/E?,- 1393), which is incorporated herein by this reference. Tile purpose of the PEA is in assess potential enJ?ronmental impacts of the implementation of a comprehek-e management program for potentiaIly reusable ICW enriched uranium (LEU). norr,:al uranium (NU), and depleted uranium (DU). --l?prosimately 14,200 MTU (h?etric Tons of Uranium) of potentially reusable uranium is located at 15s

Note: This page contains sample records for the topic "fissile materials disposition" 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

Plutonium Disposition Now!  

SciTech Connect

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

Buckner, M.R.

1995-05-24T23:59:59.000Z

122

Dismantlement and Disposition | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Dismantlement and Disposition Home > Our Mission > Managing the Stockpile > Dismantlement and Disposition Dismantlement...

123

CHARACTERIZATION OF SURPLUS PLUTONIUM FOR DISPOSITION OPTIONS  

SciTech Connect

The United States (U.S.) 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. Except for materials that remain in use for programs outside of national defense, including programs for nuclear-energy development, the 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. Some items will be disposed as transuranic waste, low-level waste, or spent fuel. The remaining surplus plutonium will be managed through: (1) the Mixed Oxide (MOX) Fuel Fabrication Facility (FFF), to be constructed at the Savannah River Site (SRS), where the plutonium will be converted to fuel that will be irradiated in civilian power reactors and later disposed to a high-level waste (HLW) repository as spent fuel; (2) the SRS H-Area facilities, by dissolving and transfer to HLW systems, also for disposal to the repository; or (3) alternative immobilization techniques that would provide durable and secure disposal. From the beginning of the U.S. program for surplus plutonium disposition, DOE has sponsored research to characterize the surplus materials and to judge their suitability for planned disposition options. Because many of the items are stored without extensive analyses of their current chemical content, the characterization involves three interacting components: laboratory sample analysis, if available; non-destructive assay data; and rigorous evaluation of records for the processing history for items and inventory groups. This information is collected from subject-matter experts at inventory sites and from materials stabilization and surveillance programs, in cooperation with the design agencies for the disposition facilities. This report describes the operation and status of the characterization program.

Allender, J; Edwin Moore, E; Scott Davies, S

2008-07-15T23:59:59.000Z

124

DOE NCSP Review of TRUPACT-II/HalfPACT Fissile Limits  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) Environmental Management (EM) Office of Nuclear Material & Spent Fuel, EM-21, tasked the CSSG to perform a scoping study to determine the feasibility of increasing the fissile mass loading limits for specified TRUPACT-II and HalfPACT packages and containers. The results of the scoping study may provide insights and technical guidance for establishing fissile mass loading limits at waste generator sites and at the waste repository. The goal is to reduce costs of transporting fissile material to the WIPP from EM's various closure sites. This report documents the results of the scoping study and demonstrates that it is feasible to significantly increase the fissile mass loading limits in the TRUPACT-II and HalfPACT packages and containers. Depending upon the particular payload containers used, the number of shipments to WIPP could be reduced by at least a factor of 2 and as much as a factor of 16 and the number of total payload containers required ''down-hole'' at WIPP could be reduced by at least a factor of 2 and as much as about 6. These cost savings result simply from applying a more realistic criticality analysis model rather than the very conservative, hypothetical, bounding analysis used to support the existing fissile mass loading limits. However, the applications of existing and developmental computational tools, nuclear data, and experiments from the DOE Nuclear Criticality Safety Program have the potential to further reduce transportation and disposal container costs on the order of 7% to 17%. It is suggested that EM proceed with an effort to do the required formal analyses and pursue SARP supplements to take advantage of these savings. The success of these analyses are dependent upon the availability of the majority of the infrastructure supported by the DOE Nuclear Criticality Safety Program as defined in the Five-Year Plan for the program. Finally, it should be noted that these potential cost savings are based only on a criticality safety feasibility study and do not take into account other technical factors from other disciplines that may or may not impact the final approved loadings. The CSSG concurs that the results of this scoping study addresses the tasking statement provided by EM-21.

Goluoglu, S.

2002-03-28T23:59:59.000Z

125

Characterization of fissile material using low energy neutron interrogation  

E-Print Network (OSTI)

The glaring need to develop methods for detecting and interdicting illicit nuclear trafficking has resulted in the exploration of various methods for active neutron interrogation, specifically for the presence of special ...

Padilla, Eduardo A

2007-01-01T23:59:59.000Z

126

Some Aspects of Fissile Materials Recycling with Innovative ...  

Science Conference Proceedings (OSTI)

Nano-structures of ?-SiC Formed by Pyrolosis of Agricultural Waste ∑ Nanothermites: Unconventional Nanomaterials with High Energy Output ∑ Next- generation†...

127

Remote detection of fissile material : Cherenkov counters for gamma detection  

E-Print Network (OSTI)

The need for large-size detectors for long-range active interrogation (Al) detection has generated interest in water-based detector technologies. AI is done using external radiation sources to induce fission and to detect, ...

Erickson, Anna S

2011-01-01T23:59:59.000Z

128

Impact of delayed neutron precursor mobility in fissile solution systems  

Science Conference Proceedings (OSTI)

A research version of the Monte Carlo software package MCNP6 is modified to incorporate advection and diffusion of delayed neutron precursors, resulting in the emission of delayed neutrons at locations different from the original fission sites. Results of two test problems, a pipe carrying flowing fissile solution and a sphere of fissile solution with precursor diffusion, show that the fission product mobility tends to perturb the fundamental mode, has a negative reactivity effect, and, perhaps most importantly, causes a decrease in the effective delayed neutron fraction. (authors)

Kiedrowski, B. C. [X-Computational Physics Div., Los Alamos National Laboratory, MS A143, P.O. Box 1663, Los Alamos, NM 87545 (United States)

2012-07-01T23:59:59.000Z

129

Characteristics of Spent Fuel from Plutonium Disposition Reactors. Vol. 3: A Westinghouse Pressurized-Water Reactor Design  

Science Conference Proceedings (OSTI)

This report discusses the results of a simulation study involving the burnup of mixed-oxide (MOX) fuel in a Westinghouse pressurized-water reactor (PWR). The MOX was composed of uranium and plutonium oxides, where the plutonium was of weapons-grade composition. The study was part of the Fissile Materials Disposition Program and considered the possibility of fueling commercial reactors with weapons plutonium. The isotopic composition, the activities, and the decay heat, together with the gamma and neutron dose rates are discussed for the spent fuel. For the steady-state situation involving this PWR burning MOX fuel, two burn histories are reported. In one case, an assembly is burned in the reactor for two cycles, and in the second case and assembly is burned for three cycles. Furthermore, assemblies containing wet annular burnable absorbers (WABAs) and assemblies that do not contain WABAs are considered in all cases. The two-cycle cases have a burnup of 35 GWd/t, and the three-cycle cases have a burnup of 52.5 GWd/t.

Murphy, B.D.

1997-07-01T23:59:59.000Z

130

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)

131

Apparatus and method for quantitatively evaluating total fissile and total fertile nuclide content in samples  

DOE Patents (OSTI)

Simultaneous photon and neutron interrogation of samples for the quantitative determination of total fissile nuclide and total fertile nuclide material present is made possible by the use of an electron accelerator. Prompt and delayed neutrons produced from resulting induced fissions are counted using a single detection system and allow the resolution of the contributions from each interrogating flux leading in turn to the quantitative determination sought. Detection limits for .sup.239 Pu are estimated to be about 3 mg using prompt fission neutrons and about 6 mg using delayed neutrons.

Caldwell, John T. (Los Alamos, NM); Kunz, Walter E. (Santa Fe, NM); Cates, Michael R. (Oak Ridge, TN); Franks, Larry A. (Santa Barbara, CA)

1985-01-01T23:59:59.000Z

132

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY U. S. Atomic Energy Commision REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents &...

133

Request For Records Disposition Authority | Department of Energy  

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

Oil and Gas Division Request For Records Disposition Authority More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Request For Records Disposition Autnority...

134

Request For Records Disposition Authority | Department of Energy  

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

Disposition Authority Request For Records Disposition Authority Naval Petroleum and Oil Shale Reserves Request For Records Disposition Authority More Documents & Publications...

135

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

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.

136

Used Fuel Disposition Research & Development | Department of Energy  

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

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

137

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

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.

138

Russian-U.S. joint program on the safe management of nuclear materials  

SciTech Connect

The Russian-US joint program on the safety of nuclear materials was initiated in response to the 1993 Tomsk-7 accident. The bases for this program are the common technical issues confronting the US and Russia in the safe management of excess weapons grade nuclear materials. The US and Russian weapons dismantlement process is producing hundreds of tons of excess Pu and HEU fissile materials. The US is on a two path approach for disposition of excess Pu: (1) use Pu in existing reactors and/or (2) immobilize Pu in glass or ceramics followed by geologic disposal. Russian plans are to fuel reactors with excess Pu. US and Russia are both converting and blending HEU into LEU for use in existing reactors. Fissile nuclear materials storage, handling, processing, and transportation will be occurring in both countries for tens of years. A table provides a history of the major events comprising the Russian-US joint program on the safety of nuclear materials. A paper delineating program efforts was delivered at the SPECTRUM '96 conference. This paper provides an update on program activities since then.

Witmer, F.E.; Krumpe, P.F. [Dept. of Energy, Washington, DC (US); Carlson, D.D. [Sandia National Labs., Albuquerque, NM (US)] [and others

1997-12-01T23:59:59.000Z

139

NRC comprehensive records disposition schedule  

SciTech Connect

Title 44 United States Code, Public Printing and Documents,'' regulations cited in the General Services Administration's (GSA) Federal Information Resources Management Regulations'' (FIRMR), Part 201-9, Creation, Maintenance, and Use of Records,'' and regulation issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter XII, Subchapter B, Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 2, contains NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 2 totally reorganizes the records schedules from a functional arrangement to an arrangement by the host office. A subject index and a conversion table have also been developed for the NRC schedules to allow staff to identify the new schedule numbers easily and to improve their ability to locate applicable schedules.

Not Available

1992-03-01T23:59:59.000Z

140

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

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

Note: This page contains sample records for the topic "fissile materials disposition" 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

IX disposition project, project management plan  

SciTech Connect

This subproject management plan defines the roles, responsibilities, and actions required for the execution of the IX Disposition Project.

WILLIAMS, N.H.

1999-05-11T23:59:59.000Z

142

Disposition Schedule: Human Radiation Experiments | Department...  

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

Schedule: Human Radiation Experiments Disposition Schedule: Human Radiation Experiments This database contains information on records collections related to human radiation...

143

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

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

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

144

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

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

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.

145

RECORDS DISPOSITION AUTHORIZATION STATE AGENCIES  

E-Print Network (OSTI)

RECORDS DISPOSITION AUTHORIZATION ­ STATE AGENCIES Form RC-108 (Revised 07/2011) STATE, CT 06106 www.cslib.org/publicrecords AUTHORITY: State agencies in the Executive branch and certain or Transfer Agreement), and retain pursuant to S1-390. STATE AGENCY: DIVISION / UNIT: ADDRESS (for return

Oliver, Douglas L.

146

Neutron Assay System for Confinement Vessel Disposition  

Science Conference Proceedings (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

147

Facility Disposition Safety Strategy RM  

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

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,

148

DEVELOPMENT OF THE HS99 AIR TRANSPORT TYPE A FISSILE PACKAGE  

SciTech Connect

An air-transport Type A Fissile radioactive shipping package for the transport of special form uranium sources has been developed by the Savannah River National Laboratory (SRNL) for the Department of Homeland Security. The Package model number is HS99 for Homeland Security Model 99. This paper presents the major design features of the HS99 and highlights engineered materials necessary for meeting the design requirements for this light-weight Type AF packaging. A discussion is provided demonstrating how the HS99 complies with the regulatory safety requirements of the Nuclear Regulatory Commission. The paper summarizes the results of structural testing to specified in 10 CFR 71 for Normal Conditions of Transport and Hypothetical Accident Conditions events. Planned and proposed future missions for this packaging are also addressed.

Blanton, P.; Eberl, K.

2012-07-10T23:59:59.000Z

149

Disposition options for {sup 233}U  

SciTech Connect

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

150

Savannah River Site Waste Disposition Project  

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

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

151

The ultimate disposition of depleted uranium  

SciTech Connect

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

152

Summary - Major Risk Factors Integrated Facility Disposition...  

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

& 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...

153

Major Risk Factors Integrated Facility Disposition Project -...  

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

- Oak Ridge Summary - Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN More Documents & Publications Major Risk Factors to the Integrated...

154

Uranium Downblending and Disposition Project Technology Readiness...  

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

Centers Field Sites Power Marketing Administration Other Agencies You are here Home Uranium Downblending and Disposition Project Technology Readiness Assessment Uranium...

155

Uranium Downblending and Disposition Project Technology Readiness...  

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

Simulated Operational Environment Environment that uses a range of waste simulants for testing of a virtual prototype. iv 233 Uranium Downblending and Disposition Project...

156

Request For Records Disposition Authority: Strategic Petroleum...  

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

Authority: Strategic Petroleum Reserve Project Management Office Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Paper case files...

157

Weapons Dismantlement and Disposition NNSS Capabilities  

Science Conference Proceedings (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

158

Personal Property Disposition - Community Reuse Organizations...  

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

Disposition of Excess Personal Property BACKGROUND AND PURPOSE CROs have been operating asset conversion and personal property transfer programs since shortly after the passage of...

159

Microsoft PowerPoint - REVWaste_Disposition_Update.061411.pptx  

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

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

160

Apparatus and method for quantitatively evaluating total fissile and total fertile nuclide content in samples. [Patent application  

DOE Patents (OSTI)

Simultaneous photon and neutron interrogation of samples for the quantitative determination of total fissile nuclide and total fertile nuclide material present is made possible by the use of an electron accelerator. Prompt and delayed neutrons produced from resulting induced fission are counted using a single detection system and allow the resolution of the contributions from each interrogating flux leading in turn to the quantitative determination sought. Detection limits for /sup 239/Pu are estimated to be about 3 mg using prompt fission neutrons and about 6 mg using delayed neutrons.

Caldwell, J.T.; Kunz, W.E.; Cates, M.R.; Franks, L.A.

1982-07-07T23:59:59.000Z

Note: This page contains sample records for the topic "fissile materials disposition" 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

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

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

162

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

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

163

Evaluation of Calcine Disposition Path Forward  

SciTech Connect

This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward.

Birrer, S.A.; Heiser, M.B.

2003-02-26T23:59:59.000Z

164

Evaluation of Calcine Disposition - Path Forward  

SciTech Connect

This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward.

Steve Birrer

2003-02-01T23:59:59.000Z

165

Major Risk Factors to the Integrated Facility Disposition Project...  

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

Facility Disposition Project The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the...

166

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

This disposition requests describe records of the History Division under the Office Executive Secretariat at the Department of Energy Headquarters REQUEST FOR RECORDS DISPOSITION...

167

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

National Nuclear Security Administration (NNSA)

Agreement U.S. and Russia Sign Plutonium Disposition Agreement September 01, 2000 Washington, DC U.S. and Russia Sign Plutonium Disposition Agreement After two years of...

168

EM Makes Significant Progress on Dispositioning Transuranic Waste...  

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

Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 -...

169

Request For Records Disposition Authority | Department of Energy  

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

Authority Request For Records Disposition Authority Office of Naval Petroleum and Shale Oil Reserves Request For Records Disposition Authority More Documents & Publications...

170

Request For Records Disposition Authority | Department of Energy  

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

Naval Petroleum and Oil Shale Reserves Request For Records Disposition Authority More Documents & Publications Request For Records Disposition Authority Request For Records...

171

PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES...  

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

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

172

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

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

For Records Disposition Authority-Nuclear Weapons Request For Records Disposition Authority-Nuclear Weapons This document identifies the nuclear weapon records generated by the...

173

Topic Index to the DOE Administrative Records Disposition Schedules...  

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

Topic Index to the DOE Administrative Records Disposition Schedules Topic Index to the DOE Administrative Records Disposition Schedules Topic Index to the DOE Administrative...

174

I REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

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

175

Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium  

Science Conference Proceedings (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

176

DOE Amends Record of Decision for Plutonium Consolidation  

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

DOE amended the Record of Decision (ROD) for the Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement. Specifically, DOE decided to take the...

177

EIS-0229: Record of Decision (November 2003) | Department of...  

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

for safe and secure storage of weapons-usable fissile materials (plutonium and highly enriched uranium HEU) and a strategy for the disposition of surplus weapons- usable...

178

EIS-0229: Record of Decision (January 1997) | Department of Energy  

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

for safe and secure storage of weapons-usable fissile materials (plutonium and highly enriched uranium HEU) and a strategy for the disposition of surplus weapons- usable...

179

Microsoft Word - Chapter 07 References.doc  

National Nuclear Security Administration (NNSA)

of Fissile Materials Disposition, Washington, DC, December. DOE (U.S. Department of Energy) 1997a, Environmental Assessment for the Proposed CMR Building Upgrades at the Los...

180

Used Fuel Disposition Campaign International Activities Implementation Plan  

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

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

Note: This page contains sample records for the topic "fissile materials disposition" 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

Plutonium disposition via immobilization in ceramic or glass  

SciTech Connect

The management of surplus weapons plutonium is an important and urgent task with profound environmental, national, and international security implications. In the aftermath of the Cold War, Presidential Policy Directive 13, and various analyses by renown scientific, technical, and international policy organizations have brought about a focused effort within the Department of Energy to identify and implement paths for the long term disposition of surplus weapons- usable plutonium. The central goal of this effort is to render surplus weapons plutonium as inaccessible and unattractive for reuse in nuclear weapons as the much larger and growing stock of plutonium contained in spent fuel from civilian reactors. One disposition option being considered for surplus plutonium is immobilization, in which the plutonium would be incorporated into a glass or ceramic material that would ultimately be entombed permanently in a geologic repository for high-level waste.

Gray, L.W.; Kan, T.; Shaw, H.F.; Armantrout, A.

1997-03-05T23:59:59.000Z

182

Used Fuel Disposition Campaign Disposal  

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

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

183

TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION  

Science Conference Proceedings (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

184

Testing of Liquid Scintillator Materials for Gamma and Neutron Detection  

Science Conference Proceedings (OSTI)

The key fact about fissile material is that a sufficient quantity of the material can produce chains of fissions, including some very long chains. A chain of fissions will give rise to a detected burst of neutrons with longer chains generally producing larger bursts. These bursts produce distinctive time correlations in a detector near the multiplying material. These correlations are measurable and can be analyzed to infer attributes of the fissile material including fissile material mass, assembly neutron multiplication, characteristic fast fission chain evolution time scale, also known as the {alpha} time scale, thermalization time scale. The correlation signal is very robust with respect to background and to neutron absorbing material.

Verbeke, J M; Nakae, L; Kerr, P; Dietrich, D; Dougan, A

2009-06-19T23:59:59.000Z

185

Waste Disposition Update by Christine Gelles  

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

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

186

EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement  

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

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

187

Disposition of excess highly enriched uranium status and update  

SciTech Connect

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

188

EIS-0240: Disposition of Surplus Highly Enriched Uranium  

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

The Department proposes to eliminate the proliferation threat of surplus highly enriched uranium (HEU) by blending it down to low enriched uranium (LEU), which is not weapons-usable. The EIS assesses the disposition of a nominal 200 metric tons of surplus HEU. The Preferred Alternative is, where practical, to blend the material for use as LEU and use overtime, in commercial nuclear reactor field to recover its economic value. Material that cannot be economically recovered would be blended to LEU for disposal as low-level radioactive waste.

189

Disposition of actinides released from high-level waste glass  

SciTech Connect

A series of static leach tests was conducted using glasses developed for vitrifying tank wastes at the Savannah River Site to monitor the disposition of actinide elements upon corrosion of the glasses. In these tests, glasses produced from SRL 131 and SRL 202 frits were corroded at 90{degrees}C in a tuff groundwater. Tests were conducted using crushed glass at different glass surface area-to-solution volume (S/V) ratios to assess the effect of the S/V on the solution chemistry, the corrosion of the glass, and the disposition of actinide elements. Observations regarding the effects of the S/V on the solution chemistry and the corrosion of the glass matrix have been reported previously. This paper highlights the solution analyses performed to assess how the S/V used in a static leach test affects the disposition of actinide elements between fractions that are suspended or dissolved in the solution, and retained by the altered glass or other materials.

Ebert, W.L.; Bates, J.K.; Buck, E.C.; Gong, M.; Wolf, S.F.

1994-05-01T23:59:59.000Z

190

Accelerating the disposition of transuranic waste from LANL - 9495  

Science Conference Proceedings (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

191

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

SciTech Connect

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

192

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

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;

193

NRC comprehensive records disposition schedule. Revision 2  

SciTech Connect

Title 44 United States Code, ``Public Printing and Documents,`` regulations cited in the General Services Administration`s (GSA) ``Federal Information Resources Management Regulations`` (FIRMR), Part 201-9, ``Creation, Maintenance, and Use of Records,`` and regulation issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter XII, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 2, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 2 totally reorganizes the records schedules from a functional arrangement to an arrangement by the host office. A subject index and a conversion table have also been developed for the NRC schedules to allow staff to identify the new schedule numbers easily and to improve their ability to locate applicable schedules.

Not Available

1992-03-01T23:59:59.000Z

194

NRC comprehensive records disposition schedule. Revision 3  

Science Conference Proceedings (OSTI)

Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

NONE

1998-02-01T23:59:59.000Z

195

Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel  

E-Print Network (OSTI)

The development of non-destructive assay (NDA) capabilities to directly measure the fissile content in spent fuel is needed to improve the timely detection of the diversion of significant quantities of fissile material. Currently, the International Atomic Energy Agency (IAEA) does not have effective NDA methods to verify spent fuel and recover continuity of knowledge in the event of a containment and surveillance systems failure. This issue has become increasingly critical with the worldwide expansion of nuclear power, adoption of enhanced safeguards criteria for spent fuel verification, and recent efforts by the IAEA to incorporate an integrated safeguards regime. In order to address these issues, the use of Self-Interrogation Neutron Resonance Densitometry (SINRD) has been developed to improve existing nuclear safeguards and material accountability measurements. The following characteristics of SINRD were analyzed: (1) ability to measure the fissile content in Light Water Reactors (LWR) fuel assemblies and (2) sensitivity and penetrability of SINRD to the removal of fuel pins from an assembly. The Monte Carlo Neutral Particle eXtended (MCNPX) transport code was used to simulate SINRD for different geometries. Experimental measurements were also performed with SINRD and were compared to MCNPX simulations of the experiment to verify the accuracy of the MCNPX model of SINRD. Based on the results from these simulations and measurements, we have concluded that SINRD provides a number of improvements over current IAEA verification methods. These improvements include: 1) SINRD provides absolute measurements of burnup independent of the operatorís declaration. 2) SINRD is sensitive to pin removal over the entire burnup range and can verify the diversion of 6% of fuel pins within 3? from LWR spent LEU and MOX fuel. 3) SINRD is insensitive to the boron concentration and initial fuel enrichment and can therefore be used at multiple spent fuel storage facilities. 4) The calibration of SINRD at one reactor facility carries over to reactor sites in different countries because it uses the ratio of fission chambers (FCs) that are not facility dependent. 5) SINRD can distinguish fresh and 1-cycle spent MOX fuel from 3- and 4-cycles spent LEU fuel without using reactor burnup codes.

Lafleur, Adrienne

2011-08-01T23:59:59.000Z

196

Weapons-grade plutonium dispositioning. Volume 4. Plutonium dispositioning in light water reactors  

SciTech Connect

This study is in response to a request by the Reactor Panel Subcommittee of the National Academy of Sciences (NAS) Committee on International Security and Arms Control (CISAC) to evaluate the feasibility of using plutonium fuels (without uranium) for disposal in existing conventional or advanced light water reactor (LWR) designs and in low temperature/pressure LWR designs that might be developed for plutonium disposal. Three plutonium-based fuel forms (oxides, aluminum metallics, and carbides) are evaluated for neutronic performance, fabrication technology, and material and compatibility issues. For the carbides, only the fabrication technologies are addressed. Viable plutonium oxide fuels for conventional or advanced LWRs include plutonium-zirconium-calcium oxide (PuO{sub 2}-ZrO{sub 2}-CaO) with the addition of thorium oxide (ThO{sub 2}) or a burnable poison such as erbium oxide (Er{sub 2}O{sub 3}) or europium oxide (Eu{sub 2}O{sub 3}) to achieve acceptable neutronic performance. Thorium will breed fissile uranium that may be unacceptable from a proliferation standpoint. Fabrication of uranium and mixed uranium-plutonium oxide fuels is well established; however, fabrication of plutonium-based oxide fuels will require further development. Viable aluminum-plutonium metallic fuels for a low temperature/pressure LWR include plutonium aluminide in an aluminum matrix (PuAl{sub 4}-Al) with the addition of a burnable poison such as erbium (Er) or europium (Eu). Fabrication of low-enriched plutonium in aluminum-plutonium metallic fuel rods was initially established 30 years ago and will require development to recapture and adapt the technology to meet current environmental and safety regulations. Fabrication of high-enriched uranium plate fuel by the picture-frame process is a well established process, but the use of plutonium would require the process to be upgraded in the United States to conform with current regulations and minimize the waste streams.

Sterbentz, J.W.; Olsen, C.S.; Sinha, U.P.

1993-06-01T23:59:59.000Z

197

PEIS data report: Upgrading the Y-12 Plant for long-term HEU storage  

SciTech Connect

The Department of Energy (DOE) is planning the future of weapons-capable fissile materials owned by the United States (U.S.). Under its Disposition Program, DOE is evaluating its options for: (a) storage of fissile materials needed for specific national programs, and (b) disposal of surplus fissile materials. In accordance with the National Environmental Policy Act (NEPA), DOE is preparing the {open_quotes}Programmatic Environmental Impact Statement (PEIS) for Long-Term Storage and Disposition of Weapons-Usable Fissile Materials{close_quotes} (Disposition PEIS). This paper discusses storage options for highly enriched uranium at the Y-12 plant.

Everitt, D.A.; Johnson, J.P.; Phillips, J.K.; Snider, J.D.

1996-02-01T23:59:59.000Z

198

Excess plutonium disposition: The deep borehole option  

SciTech Connect

This report reviews the current status of technologies required for the disposition of plutonium in Very Deep Holes (VDH). It is in response to a recent National Academy of Sciences (NAS) report which addressed the management of excess weapons plutonium and recommended three approaches to the ultimate disposition of excess plutonium: (1) fabrication and use as a fuel in existing or modified reactors in a once-through cycle, (2) vitrification with high-level radioactive waste for repository disposition, (3) burial in deep boreholes. As indicated in the NAS report, substantial effort would be required to address the broad range of issues related to deep bore-hole emplacement. Subjects reviewed in this report include geology and hydrology, design and engineering, safety and licensing, policy decisions that can impact the viability of the concept, and applicable international programs. Key technical areas that would require attention should decisions be made to further develop the borehole emplacement option are identified.

Ferguson, K.L.

1994-08-09T23:59:59.000Z

199

Ceramics for Nuclear Waste Disposition  

Science Conference Proceedings (OSTI)

Oct 27, 2009 ... Materials Solutions for the Nuclear Renaissance: Ceramics for .... In-situ Decommissioning of Heavy Water Reactor Disassembly Basin:†...

200

Surplus Highly Enriched Uranium Disposition Program plan  

SciTech Connect

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.

1996-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "fissile materials disposition" 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

Supply and Disposition of Crude Oil and Petroleum Products  

U.S. Energy Information Administration (EIA)

Supply Disposition Ending Stocks; Field Production Renewable Fuels & Oxygenate Plant New Production Refinery & Blender Net Production Imports Net Receipts

202

Supply and Disposition of Crude Oil and Petroleum Products  

U.S. Energy Information Administration (EIA)

Supply Disposition Ending Stocks; Field Production Renewable Fuels & Oxygenate Plant Net Production Refinery & Blender Net Production Imports Net Receipts

203

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

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

Plutonium Disposition Agreement | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

204

Supply and Disposition of Crude Oil and Petroleum Products  

U.S. Energy Information Administration (EIA)

Supply Disposition Ending Stocks; Field Production Renewable Fuels & Oxygenate Plant New Production Refinery & Blender Net Production Imports ...

205

Mission Need Statement: Calcine Disposition Project Major Systems Acquisition Project  

SciTech Connect

This document identifies the need to establish the Calcine Disposition Project to determine and implement the final disposition of calcine including characterization, retrieval, treatment (if necessary), packaging, loading, onsite interim storage pending shipment to a repository or interim storage facility, and disposition of related facilities.

J. T. Beck

2007-04-26T23:59:59.000Z

206

Surplus Plutonium Disposition (SPD) Environmental Data Summary  

Science Conference Proceedings (OSTI)

This document provides an overview of existing environmental and ecological information at areas identified as potential locations of the Savannah River Site's (SRS) Surplus Plutonium Disposition (SPD) facilities. This information is required to document existing environmental and baseline conditions from which SPD construction and operation impacts can be defined. It will be used in developing the required preoperational monitoring plan to be used at specific SPD facilities construction sites.

Fledderman, P.D.

2000-08-24T23:59:59.000Z

207

Disposal criticality analysis methodology for fissile waste forms  

SciTech Connect

A general methodology has been developed to evaluate the criticality potential of the wide range of waste forms planned for geologic disposal. The range of waste forms include commercial spent fuel, high level waste, DOE spent fuel (including highly enriched), MOX using weapons grade plutonium, and immobilized plutonium. The disposal of these waste forms will be in a container with sufficiently thick corrosion resistant barriers to prevent water penetration for up to 10,000 years. The criticality control for DOE spent fuel is primarily provided by neutron absorber material incorporated into the basket holding the individual assemblies. For the immobilized plutonium, the neutron absorber material is incorporated into the waste form itself. The disposal criticality analysis methodology includes the analysis of geochemical and physical processes that can breach the waste package and affect the waste forms within. The basic purpose of the methodology is to guide the criticality control features of the waste package design, and to demonstrate that the final design meets the criticality control licensing requirements. The methodology can also be extended to the analysis of criticality consequences (primarily increased radionuclide inventory), which will support the total performance assessment for the respository.

Davis, J.W. [Framatome Cogema Fuels, Las Vegas, NV (United States); Gottlieb, P. [TRW Environmental Safety Systems, Las Vegas, NV (United States)

1998-03-01T23:59:59.000Z

208

Update of the Used Fuel Disposition Campaign Implementation Plan |  

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

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

209

Disposition of nuclear waste using subcritical accelerator-driven systems  

Science Conference Proceedings (OSTI)

Spent fuel from nuclear power plants contains large quantities of Pu, other actinides, and fission products (FP). This creates challenges for permanent disposal because of the long half-lives of some isotopes and the potential for diversion of the fissile material. Two issues of concern for the US repository concept are: (1) long-term radiological risk peaking tens-of-thousands of years in the future; and (2) short-term thermal loading (decay heat) that limits capacity. An accelerator-driven neutron source can destroy actinides through fission, and can convert long-lived fission products to shorter-lived or stable isotopes. Studies over the past decade have established that accelerator transmutation of waste (ATW) can have a major beneficial impact on the nuclear waste problem. Specifically, the ATW concept the authors are evaluating: (1) destroys over 99.9% of the actinides; (2) destroys over 99.9% of the Tc and I; (3) separates Sr-90 and Cs-137; (4) separates uranium from the spent fuel; (5) produces electric power.

Venneri, F.; Li, N.; Williamson, M.; Houts, M.; Lawrence, G.

1998-12-31T23:59:59.000Z

210

Measuring of fissile isotopes partial antineutrino spectra in direct experiment at nuclear reactor  

E-Print Network (OSTI)

The direct measuring method is considered to get nuclear reactor antineutrino spectrum. We suppose to isolate partial spectra of the fissile isotopes by using the method of antineutrino spectrum extraction from the inverse beta decay positron spectrum applied at Rovno experiment. This admits to increase the accuracy of partial antineutrino spectra forming the total nuclear reactor spectrum. It is important for the analysis of the reactor core fuel composition and could be applied for non-proliferation purposes.

V. V. Sinev

2009-02-22T23:59:59.000Z

211

Measuring of fissile isotopes partial antineutrino spectra in direct experiment at nuclear reactor  

E-Print Network (OSTI)

The direct measuring method is considered to get nuclear reactor antineutrino spectrum. We suppose to isolate partial spectra of the fissile isotopes by using the method of antineutrino spectrum extraction from the inverse beta decay positron spectrum applied at Rovno experiment. This admits to increase the accuracy of partial antineutrino spectra forming the total nuclear reactor spectrum. It is important for the analysis of the reactor core fuel composition and could be applied for non-proliferation purposes.

Sinev, V V

2009-01-01T23:59:59.000Z

212

Materials for Nuclear Power: Digital Resource Center - ARTICLES ...  

Science Conference Proceedings (OSTI)

Jan 4, 2008 ... The January 2008 JOM offers the following articles covering disposition of nuclear waste: Material Corrosion Issues for Nuclear Waste†...

213

Fissile Flow and Enrichment Monitor for GCEP Advanced Safeguards Application  

SciTech Connect

This paper presents experimental data that demonstrate a concept for a {sup 235}U flow and enrichment monitor (FEMO) based on passive measurements of process equipment in gaseous centrifuge enrichment plants (GCEPs). The primary goal of the FEMO is to prevent, without using pipe penetrations or active interrogation with external sources, the production and diversion of undeclared nuclear material. This FEMO concept utilizes: (1) calibrated measurements of {sup 235}U density in cascade headers, and (2) measurements of pump inlet pressure and volumetric flow rate, which are correlated to the electrical power consumed by the GCEP pumps that transport UF{sub 6} from the cascade to the condensation cylinders. The {sup 235}U density is measured by counting 186 keV emissions using a NaI gamma detector located upstream of the pump. The pump inlet pressure and volumetric flow rate are determined using a correlation that is a function of the measured pump operational parameters (e.g., electric power consumption and rotational frequency) and the pumping configuration. The concept has been demonstrated in a low-pressure flow loop at Oak Ridge National Laboratory.

March-Leuba, Jose A [ORNL; Uckan, Taner [ORNL

2010-01-01T23:59:59.000Z

214

Measurements on an inventory of mixed fissile materials in shipping containers  

SciTech Connect

An inventory contained a large number of previously unmeasured items, many with both uranium and plutonium. We have assembled a suite of instruments and measured the items in a variety of ways. This report first considers the measurements and deduced results in detail before summarizing the important differences with the declarations of the inventory`s database. The appendices referred to in this report are part of a classified version only and are not attached to this unclassified version. The classified report is by the same authors as this report, has the same title (which is unclassified), and is classified as {open_quotes}SRD.{close_quotes}

Rinard, P.M.; Krick, M.S.; Kelley, T.A. [and others

1997-09-01T23:59:59.000Z

215

Monte Carlo model of a low-energy neutron interrogation system for detecting fissile material  

E-Print Network (OSTI)

(cont.) Further MCNP simulations of the neutron source impinging on cargo containers suggest that this technique can respond, as expected, qualitatively differently to containers containing SNM from containers that do not. ...

Johnson, Erik D., Ph. D. Massachusetts Institute of Technology

2006-01-01T23:59:59.000Z

216

Open Skies and monitoring a fissile materials cut-off treaty  

SciTech Connect

The Treaty on Open Skies (Open Skies) is intended among other things to provide, in the words of its preamble, means ``to facilitate the monitoring of compliance with existing or future arms control agreements.`` Open Skies permits overflights of the territory of member states by aircraft equipped with an array of sensors of various types. Their types and capabilities are treaty-limited. To find useful application in monitoring a cut-off treaty Open Skies would need to be amended. The number of signatories would need to be expanded so as to provide greater geographical coverage, and restrictions on sensor-array capabilities would need to be relaxed. To facilitate the detection of impending violations of a cut-off convention by Open Skies overflights, the data base provided by parties to the former should include among other things an enumeration of existing and former fuel cycle and research facilities including those converted to other uses, their precise geographic location, and a site plan.

Allentuck, J.; Lemley, J.R.

1995-09-01T23:59:59.000Z

217

In situ removal of the ``hockey stick`` fissile material deposit at the East Tennessee Technology Park  

Science Conference Proceedings (OSTI)

Prior to shutdown of the gaseous diffusion process at the Oak Ridge K-25 Plant (now East Tennessee Technology Park), leakage of humid air into the process piping and equipment caused reactions with UF{sub 6}, which produced nonvolatile uranyl fluoride (UO{sub 2}F{sub 2}) deposition and other solid uranium fluoride compounds. During the period 1988--1991, Lockheed Martin Energy Systems performed nondestructive analysis (NDA) radiological surveys of the K-25 Site process facilities that previously had contained or processed uranium. These surveys were made to estimate the mass and {sup 235}U assay of localized uranium deposits remaining within the process piping and equipment. Three deposits were identified that had sufficient mass to achieve criticality. Two of these, the horizontal pipe and the T pipe deposits, required the addition of a moderator before a criticality accident could occur. The third was a very large uranium deposit determined by NDA to be distributed annularly in the process piping. Because of the shape of the system, it came to be called the hockey stick deposit. Because of the foregoing concerns with the hockey stick deposit, it was decided to gain experience by removing the less hazardous smaller deposits with their less complicated geometries first. Thus, the horizontal pipe deposit, the simplest and least reactive case, was handled first, in June 1997. Next, the T pipe, which was an intersection of large-diameter pipes and which posed additional problems because of a more complex geometry, was handled in August 1997. From this experience, the deposit removal techniques and procedures were refined. In December 1997, this large deposit was removed, and the contents were placed in a safe array configuration.

Lewis, K.D.; Tollefson, D.A. [Lockheed Martin Energy Systems (United States)

1998-12-31T23:59:59.000Z

218

Feasibility analysis of scanning 100% of maritime cargo containers for fissile material  

E-Print Network (OSTI)

On August 3, 2007, President George W. Bush signed into law H.R. 1: Implementing Recommendations of the 9/11 Commission Act of 2007. The law mandates that 100% of air and maritime cargo must be scanned prior to entering ...

Foley, William E., III

2008-01-01T23:59:59.000Z

219

RECORDS DISPOSITION SCHEDULE: Year 2000 Project Records | Department...  

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

Year 2000 Project Records RECORDS DISPOSITION SCHEDULE: Year 2000 Project Records Year 2000 (Y2K) Project records have been created to document the effort of the Department...

220

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at...  

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

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...

Note: This page contains sample records for the topic "fissile materials disposition" 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

Request For Records Disposition Authority: Strategic Petroleum Reserve  

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

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

222

A Model Ceramic System for Plutonium Disposition - Programmaster ...  

Science Conference Proceedings (OSTI)

As-Cast Microstructures in Alloys of U, Pu, and Zr with Minor Actinides (Np, Am) ... Irradiation Effects in Ceramics for Inert Matrix Fuel and Plutonium Disposition.

223

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

Crude Oil REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications Oil Overcharge Refund Cases 2003 Oil Overcharge Refund Cases 1996 Oil Overcharge Refund Cases 1999...

224

Used Fuel Disposition Campaign Disposal Research and Development...  

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

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)...

225

EIA Data: 2011 United States Coal Supply, Disposition, and Price...  

Open Energy Info (EERE)

Search Share this page on Facebook icon Twitter icon EIA Data: 2011 United States Coal Supply, Disposition, and Price Dataset Summary Description This dataset is the 2011...

226

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

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

227

Disposition Record Request: Oil Import Appeals Board | Department...  

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

Record Request: Oil Import Appeals Board Disposition Record Request: Oil Import Appeals Board OIAB Case Files. Records consist of company requests for relief from hardship imposed...

228

AEO2011: Total Energy Supply, Disposition, and Price Summary...  

Open Energy Info (EERE)

Total Energy Supply, Disposition, and Price Summary This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report...

229

DRAFT EM SSAB Chairźs Meeting Waste Disposition Strategies...  

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

EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5...

230

Joel Case Calcine Disposition Project Federal Project Director  

ē Results in large life-cycle cost savings through final disposition. 6 6 Basic Hot Isostatic Pressing Process ... nuclear fuel in 1964.

231

AEO2011: Coal Supply, Disposition, and Prices This dataset comes...  

Open Energy Info (EERE)

Supply, Disposition, and Prices This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is...

232

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

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

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...

233

Additional public meeting on plutonium disposition on September...  

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

produce an oxide form of plutonium suitable for disposition and the use of mixed oxide (MOX) fuel fabricated from surplus plutonium in domestic commercial nuclear power reactors...

234

Office of UNF Disposition International Program - Strategic Plan |  

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

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

235

Commissioning Measurements and Experience Obtained from the Installation of a Fissile Mass Flow monitor in the URAL Electrochemical Integrated Plant (UEIP) in Novouralsk  

SciTech Connect

The Blend Down Monitoring System (BDMS) equipment sent earlier to the Ural Electrochemical Integrated Plant (UEIP) at Novouralsk, Russia, was installed and implemented successfully on February 2, 1999. The BDMS installation supports the highly enriched uranium (HEU) Transparency Implementation Program for material subject to monitoring under the HEU purchase agreement between the United States of America (USA) and the Russian Federation (RF). The BDMS consists of the Oak Ridge National Laboratory (ORNL) Fissile (uranium-235) Mass Flow Monitor (FMFM) and the Los Alamos National Laboratory (LANL) Enrichment Monitor (EM). Two BDMS?s for monitoring the Main and Reserve HEU blending process lines were installed at UEIP. Independent operation of the FMFM Main and FMFM Reserve was successfully demonstrated for monitoring the fissile mass flow as well as the traceability of HEU to the product low enriched uranium. The FMFM systems failed when both systems were activated during the calibration phase due to a synchronization problem between the systems. This operational failure was caused by the presence of strong electromagnetic interference (EMI) in the blend point. The source-modulator shutter motion of the two FMFM systems was not being properly synchronized because of EMI producing a spurious signal on the synchronization cable connecting the two FMFM cabinets. The signature of this failure was successfully reproduced at ORNL after the visit. This unexpected problem was eliminated by a hardware modification and software improvements during a recent visit (June 9-11, 1999) to UEIP, and both systems are now operating as expected.

March-Leuba, J.; Mastal, E.; Powell, D.; Sumner, J.; Uckan, T.; Vines, V.

1999-07-25T23:59:59.000Z

236

Study of plutonium disposition using the GE Advanced Boiling Water Reactor (ABWR)  

SciTech Connect

The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the U.S. to disposition 50 to 100 metric tons of excess of plutonium in parallel with a similar program in Russia. 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 long-term diversion resistance to this material. The NAS study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} 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 U.S. 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 1350 MWe GE Advanced Boiling Water Reactor (ABWR) is utilized to convert the plutonium to spent fuel. The ABWR represents the integration of over 30 years of experience gained worldwide in the design, construction and operation of BWRs. It incorporates advanced features to enhance reliability and safety, minimize waste and reduce worker exposure. For example, the core is never uncovered nor is any operator action required for 72 hours after any design basis accident. Phase 1 of this study was documented in a GE report dated May 13, 1993. DOE`s Phase 1 evaluations cited the ABWR as a proven technical approach for the disposition of plutonium. This Phase 2 study addresses specific areas which the DOE authorized as appropriate for more in-depth evaluations. A separate report addresses the findings relative to the use of existing BWRs to achieve the same goal.

NONE

1994-04-30T23:59:59.000Z

237

Hight-Level Waste & Facilities Disposition  

NLE Websites -- All DOE Office Websites (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¬ģ PDF format and require the Adobe¬ģ 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]

238

Fuel conditioning facility material accountancy  

SciTech Connect

The operation of the Fuel conditioning Facility (FCF) is based on the electrometallurgical processing of spent metallic reactor fuel. It differs significantly, therefore, from traditional PUREX process facilities in both processing technology and safeguards implications. For example, the fissile material is processed in FCF only in batches and is transferred within the facility only as solid, well-characterized items; there are no liquid steams containing fissile material within the facility, nor entering or leaving the facility. The analysis of a single batch lends itself also to an analytical relationship between the safeguards criteria, such as alarm limit, detection probability, and maximum significant amount of fissile material, and the accounting system`s performance, as it is reflected in the variance associated with the estimate of the inventory difference. This relation, together with the sensitivity of the inventory difference to the uncertainties in the measurements, allows a thorough evaluation of the power of the accounting system. The system for the accountancy of the fissile material in the FCF has two main components: a system to gather and store information during the operation of the facility, and a system to interpret this information with regard to meeting safeguards criteria. These are described and the precision of the inventory closure over one batch evaluated.

Yacout, A.M.; Bucher, R.G.; Orechwa, Y.

1995-08-01T23:59:59.000Z

239

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

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

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...

240

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

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

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

Note: This page contains sample records for the topic "fissile materials disposition" 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

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

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

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

242

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

Science Conference Proceedings (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

243

First experiment on fission transients in highly fissile spherical nuclei produced by fragmentation of radioactive beams  

E-Print Network (OSTI)

We report on a novel experimental approach for studying the dissipative spreading of collective motion in a meta-stable nuclear system, using, for the first time, highly fissile nuclei with spherical shape. This was achieved by fragmentation of 45 radioactive heavy-ion beams at GSI, Darmstadt. The use of inverse kinematics and a dedicated experimental set-up allowed for the identification in atomic number of both fission fragments. From the width of their charge distributions, a transient time of (3.3 +/- 0.7) 10-21 s is deduced for initially spherical nuclei.

C. Schmitt; P. N. Nadtochy; A. Heinz; B. Jurado; A. Kelic; K. -H. Schmidt

2007-02-12T23:59:59.000Z

244

PROGRESS IN REDUCING THE NUCLEAR THREAT: UNITED STATES PLUTONIUM CONSOLIDATION AND DISPOSITION  

SciTech Connect

Following the end of the Cold War, the United States identified 61.5 metric tons (MT) of plutonium and larger quantities of enriched uranium that are permanently excess to use in nuclear weapons programs. The Department of Energy (DOE) also began shutting down, stabilizing, and removing inventories from production facilities that were no longer needed to support weapons programs and non-weapons activities. The storage of 'Category I' nuclear materials at Rocky Flats, Sandia National Laboratories, and several smaller sites has been terminated to reduce costs and safeguards risks. De-inventory continues at the Hanford site and the Lawrence Livermore National Laboratory. Consolidation of inventories works in concert with the permanent disposition of excess inventories, including several tonnes of plutonium that have already been disposed to waste repositories and the preparation for transfers to the planned Mixed Oxide (MOX) Fuel Fabrication Facility (for the bulk of the excess plutonium) and alternative disposition methods for material that cannot be used readily in the MOX fuel cycle. This report describes status of plutonium consolidation and disposition activities and their impacts on continuing operations, particularly at the Savannah River Site.

Allender, J.; Koenig, R.; Davies, S.

2009-06-01T23:59:59.000Z

245

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options  

Science Conference Proceedings (OSTI)

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

1993-06-01T23:59:59.000Z

246

HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY  

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

- - 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

247

REQUEST FOR RECORDS DISPOSITION AUTHORITY S  

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

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

248

FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative  

SciTech Connect

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative.

Greene, S.R.; Fisher, S.E.; Bevard, B.B. [and others

1996-09-01T23:59:59.000Z

249

FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative  

SciTech Connect

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative.

Greene, S.R.; Spellman, D.J.; Bevard, B.B. [and others

1996-09-01T23:59:59.000Z

250

Apparatus for in situ determination of burnup, cooling time and fissile content of an irradiated nuclear fuel assembly in a fuel storage pond  

DOE Patents (OSTI)

A detector head for in situ inspection of irradiated nuclear fuel assemblies submerged in a water-filled nuclear fuel storage pond. The detector head includes two parallel arms which extend from a housing and which are spaced apart so as to be positionable on opposite sides of a submerged fuel assembly. Each arm includes an ionization chamber and two fission chambers. One fission chamber in each arm is enclosed in a cadmium shield and the other fission chamber is unshielded. The ratio of the outputs of the shielded and unshielded fission chambers is used to determine the boron content of the pond water. Correcting for the boron content, the neutron flux and gamma ray intensity are then used to verify the declared exposure, cooling time and fissile material content of the irradiated fuel assembly.

Phillips, J.R.; Halbig, J.K.; Menlove, H.O.; Klosterbuer, S.F.

1984-01-01T23:59:59.000Z

251

Apparatus for in situ determination of burnup, cooling time and fissile content of an irradiated nuclear fuel assembly in a fuel storage pond  

DOE Patents (OSTI)

A detector head for in situ inspection of irradiated nuclear fuel assemblies submerged in a water-filled nuclear fuel storage pond. The detector head includes two parallel arms which extend from a housing and which are spaced apart so as to be positionable on opposite sides of a submerged fuel assembly. Each arm includes an ionization chamber and two fission chambers. One fission chamber in each arm is enclosed in a cadmium shield and the other fission chamber is unshielded. The ratio of the outputs of the shielded and unshielded fission chambers is used to determine the boron content of the pond water. Correcting for the boron content, the neutron flux and gamma ray intensity are then used to verify the declared exposure, cooling time and fissile material content of the irradiated fuel assembly.

Phillips, John R. (Los Alamos, NM); Halbig, James K. (Los Alamos, NM); Menlove, Howard O. (Los Alamos, NM); Klosterbuer, Shirley F. (Los Alamos, NM)

1985-01-01T23:59:59.000Z

252

Influence of the Density Law on Various Fissile Single Unit and Array Storage Methods  

SciTech Connect

The advancement of computational technology has resulted in the wide-spread availability of powerful radiation transport Monte Carlo codes. Prevailing practices today rely heavily on Monte Carlo codes to provide the basis for assessing the reactivity of various fissile systems for nuclear criticality safety (NCS). In 1958, Weinberg and Wigner expressed their concerns on a 'deplorable trend in reactor design - the tendency to substitute a code for a theory'. Unfortunately, their concerns have largely become a reality in many modern NCS practices. lacking the time or information to understand the underlying neutron physics of the fissile system under consideration is indeed a deplorable trend. The purpose of this paper is to demonstrate that many features of criticality hand calculation methods are indeed based upon the fundamentals of the density law and that many correlations of important physics parameters can be more easily understood from such a perspective. Historically, the density law was recognized by many pioneers in the field, including during the Manhattan Project. However, it was by and large an 'oral tradition' in that bits and pieces of great physical insights of the pioneers were scattered in many earlier publications. This paper attempts to bring together some of the 'jewels' of the pioneers which might have been lost or forgotten.

Huang, S T

2011-03-02T23:59:59.000Z

253

Influence of the Density Law on Various Fissile Single Unit and Array Storage Methods  

SciTech Connect

The advancement of computational technology has resulted in the wide-spread availability of powerful radiation transport Monte Carlo codes. Prevailing practices today rely heavily on Monte Carlo codes to provide the basis for assessing the reactivity of various fissile systems for nuclear criticality safety (NCS). In 1958, Weinberg and Wigner expressed their concerns on a 'deplorable trend in reactor design - the tendency to substitute a code for a theory'. Unfortunately, their concerns have largely become a reality in many modern NCS practices. lacking the time or information to understand the underlying neutron physics of the fissile system under consideration is indeed a deplorable trend. The purpose of this paper is to demonstrate that many features of criticality hand calculation methods are indeed based upon the fundamentals of the density law and that many correlations of important physics parameters can be more easily understood from such a perspective. Historically, the density law was recognized by many pioneers in the field, including during the Manhattan Project. However, it was by and large an 'oral tradition' in that bits and pieces of great physical insights of the pioneers were scattered in many earlier publications. This paper attempts to bring together some of the 'jewels' of the pioneers which might have been lost or forgotten.

Huang, S T

2011-03-02T23:59:59.000Z

254

Study of plutonium disposition using existing GE advanced Boiling Water Reactors  

SciTech Connect

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

255

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

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

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

256

Integrated Tool Development for Used Fuel Disposition Natural System  

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

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

257

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)

258

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

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

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

259

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

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)

260

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

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

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

Note: This page contains sample records for the topic "fissile materials disposition" 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
to obtain the most current and comprehensive results.


261

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

262

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

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

263

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

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)

264

Low Level Waste Disposition - Quantity and Inventory | Department of  

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

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

265

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

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

266

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

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

267

Low Level Waste Disposition - Quantity and Inventory | Department of  

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

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

268

Integrated Tool Development for Used Fuel Disposition Natural System  

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

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

269

EIA Data: 2011 United States Coal Supply, Disposition, and Price...  

Open Energy Info (EERE)

EIA Data: 2011 United States Coal Supply, Disposition, and Price This...

270

AEO2011:Total Energy Supply, Disposition, and Price Summary ...  

Open Energy Info (EERE)

AEO2011:Total Energy Supply, Disposition, and Price Summary

271

EIS-0327: Disposition of Scrap Metals Programmatic EIS  

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

272

DOE Chooses Contractor to Disposition Waste at the Advanced Mixed...  

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

U.S. DEPARTMENT OF ENERGY IDAHO FALLS, IDAHO, 83403 DOE Chooses Contractor to Disposition Waste at the Advanced Mixed Waste Treatment Project (AMWTP) CH2M Hill Newport News...

273

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

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

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...

274

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at...  

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

doe logo Media Contact: Brad Bugger (208) 526-0833 For Immediate Release: Friday, May 27, 2011 DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed...

275

THERMAL TESTING OF PROTOTYPE GENERAL PURPOSE FISSILE PACKAGES USING A FURNACE  

SciTech Connect

The 9977/9978 General Purpose Fissile Package (GPFP) was designed by SRNL to replace the DOT 6M Specification Package and ship Plutonium and Uranium metals and oxides. Urethane foam was used for the overpack to ensure the package would withstand the 10CFR71.73(c)(2) crush test, which is a severe test for drum-type packages. In addition, it was necessary to confirm that the urethane foam configuration provided adequate thermal protection for the containment vessel during the subsequent 10CFR71.73(c)(4) thermal test. Development tests were performed on early prototype test specimens of different diameter overpacks and a range of urethane foam densities. The thermal test was performed using an industrial furnace. Test results were used to optimize the selection of package diameter and foam density, and provided the basis for design enhancements incorporated into the final package design.

Smith, A; Lawrence Gelder, L; Paul Blanton, P

2007-02-16T23:59:59.000Z

276

Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response  

DOE Patents (OSTI)

Apparatus and method for the direct, nondestructive evaluation of the .sup.235 U nuclide content of samples containing UF.sub.6, UF.sub.4, or UO.sub.2 utilizing the passive neutron self-interrogation of the sample resulting from the intrinsic production of neutrons therein. The ratio of the emitted neutron coincidence count rate to the total emitted neutron count rate is determined and yields a measure of the bulk fissile mass. The accuracy of the method is 6.8% (1.sigma.) for cylinders containing UF.sub.6 with enrichments ranging from 6% to 98% with measurement times varying from 3-6 min. The samples contained from below 1 kg to greater than 16 kg. Since the subject invention relies on fast neutron self-interrogation, complete sampling of the UF.sub.6 takes place, reducing difficulties arising from inhomogeneity of the sample which adversely affects other assay procedures.

Menlove, Howard O. (Los Alamos, NM); Stewart, James E. (Los Alamos, NM)

1986-01-01T23:59:59.000Z

277

Direct fissile assay of enriched uranium using random self-interrogation and neutron coincidence response  

DOE Patents (OSTI)

Apparatus and method for the direct, nondestructive evaluation of the /sup 235/U nuclide content of samples containing UF/sub 6/, UF/sub 4/, or UO/sub 2/ utilizing the passive neutron self-interrogation of the sample resulting from the intrinsic production of neutrons therein. The ratio of the emitted neutron coincidence count rate to the total emitted neutron count rate is determined and yields a measure of the bulk fissile mass. The accuracy of the method is 6.8% (1sigma) for cylinders containing UF/sub 6/ with enrichments ranging from 6% to 98% with measurement times varying from 3-6 min. The samples contained from below 1 kg to greater than 16 kg. Since the subject invention relies on fast neutron self-interrogation, complete sampling of the UF/sub 6/ takes place, reducing difficulties arising from inhomogeneity of the sample which adversely affects other assay procedures. 4 figs., 1 tab.

Menlove, H.O.; Stewart, J.E.

1985-02-04T23:59:59.000Z

278

Applied Science  

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

Nuclear Science EXAFS and XANES of plutonium and uranium edges from titanate ceramics for fissile materials disposition J.A. Fortner, A.J. Kropf, R.J. Finch, M.C. Hash, S.B. Aase,...

279

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

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

280

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

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

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


281

SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 5 for the Integrated Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. Results of the analyses of the Tank 21H samples from this report in conjunction with the findings of the previous report, indicates that the material does not display any unusual characteristics.

Peters, T.; Fink, S.

2012-03-26T23:59:59.000Z

282

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

Science Conference Proceedings (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

283

University Loaned Normal Uranium Slug Disposition Study: University survey responses. Predecisional draft  

SciTech Connect

During the 1950`s and 1960`s, the Atomic Energy Commission loaned rejected natural uranium slugs from the Savannah River Site to United States universities for use in subcritical assemblies. Currently, there are sixty-two universities holding 91,798 slugs, containing about 167 metric tons of natural uranium. It was originally planned that the universities would return the material to Fernald when they no longer required it. Fernald has not received slugs since it was shut down in 1988. The Department of Energy`s Office of Weapons and Materials Planning requested that the Planning Support Group develop information to assist them in facilitating the return of the unwanted slugs to one or more of their facilities and develop alternatives for the ultimate disposition of this material. This supplemental report to the University Loaned Normal Uranium Slug Disposition Study documents responses to and summarizes the results of a survey of fifty-eight universities. University contacts and survey responses covering loaned slug descriptions, historical information, radiological data, current status, and plans and schedules are documented.

Becker, G.W. Jr.

1992-09-01T23:59:59.000Z

284

Materials  

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

Materials Materials and methods are available as supplementary materials on Science Online. 16. W. Benz, A. G. W. Cameron, H. J. Melosh, Icarus 81, 113 (1989). 17. S. L. Thompson, H. S. Lauson, Technical Rep. SC-RR-710714, Sandia Nat. Labs (1972). 18. H. J. Melosh, Meteorit. Planet. Sci. 42, 2079 (2007). 19. S. Ida, R. M. Canup, G. R. Stewart, Nature 389, 353 (1997). 20. E. Kokubo, J. Makino, S. Ida, Icarus 148, 419 (2000). 21. M. M. M. Meier, A. Reufer, W. Benz, R. Wieler, Annual Meeting of the Meteoritical Society LXXIV, abstr. 5039 (2011). 22. C. B. Agnor, R. M. Canup, H. F. Levison, Icarus 142, 219 (1999). 23. D. P. O'Brien, A. Morbidelli, H. F. Levison, Icarus 184, 39 (2006). 24. R. M. Canup, Science 307, 546 (2005). 25. J. J. Salmon, R. M. Canup, Lunar Planet. Sci. XLIII, 2540 (2012). Acknowledgments: SPH simulation data are contained in tables S2 to S5 of the supplementary materials. Financial support

285

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

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

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

286

Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 |  

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

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 √ʬĬúSafety and Security begins with Me√Ę¬Ä¬Ě 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.

287

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and  

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

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

288

Paducah Demolition Debris Shipped for Disposition | Department of Energy  

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

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.

289

Material  

DOE Green Energy (OSTI)

Li(Ni{sub 0.4}Co{sub 0.15}Al{sub 0.05}Mn{sub 0.4})O{sub 2} was investigated to understand the effect of replacement of the cobalt by aluminum on the structural and electrochemical properties. In situ X-ray absorption spectroscopy (XAS) was performed, utilizing a novel in situ electrochemical cell, specifically designed for long-term X-ray experiments. The cell was cycled at a moderate rate through a typical Li-ion battery operating voltage range. (1.0-4.7 V) XAS measurements were performed at different states of charge (SOC) during cycling, at the Ni, Co, and the Mn edges, revealing details about the response of the cathode to Li insertion and extraction processes. The extended X-ray absorption fine structure (EXAFS) region of the spectra revealed the changes of bond distance and coordination number of Ni, Co, and Mn absorbers as a function of the SOC of the material. The oxidation states of the transition metals in the system are Ni{sup 2+}, Co{sup 3+}, and Mn{sup 4+} in the as-made material (fully discharged), while during charging the Ni{sup 2+} is oxidized to Ni{sup 4+} through an intermediate stage of Ni{sup 3+}, Co{sup 3+} is oxidized toward Co{sup 4+}, and Mn was found to be electrochemically inactive and remained as Mn{sup 4+}. The EXAFS results during cycling show that the Ni-O changes the most, followed by Co-O, and Mn-O varies the least. These measurements on this cathode material confirmed that the material retains its symmetry and good structural short-range order leading to the superior cycling reported earlier.

Rumble, C.; Conry, T.E.; Doeff, Marca; Cairns, Elton J.; Penner-Hahn, James E.; Deb, Aniruddha

2010-06-14T23:59:59.000Z

290

Decision model for evaluating reactor disposition of excess plutonium  

Science Conference Proceedings (OSTI)

The US Department of Energy is currently considering a range of technologies for disposition of excess weapon plutonium. Use of plutonium fuel in fission reactors to generate spent fuel is one class of technology options. This report describes the inputs and results of decision analyses conducted to evaluate four evolutionary/advanced and three existing fission reactor designs for plutonium disposition. The evaluation incorporates multiple objectives or decision criteria, and accounts for uncertainty. The purpose of the study is to identify important and discriminating decision criteria, and to identify combinations of value judgments and assumptions that tend to favor one reactor design over another.

Edmunds, T.

1995-02-01T23:59:59.000Z

291

THERMAL TESTING OF 9977 GENERAL PURPOSE FISSILE PACKAGE USING A POOL FIRE  

Science Conference Proceedings (OSTI)

The 9977/9978 General Purpose Fissile Package (GPFP), has been designed as a cost-effective, user-friendly replacement for the DOT 6M Specification Package for transporting Plutonium and Uranium metals and oxides. To ensure the capability of the 9977 GPFP to withstand the regulatory crush test, urethane foam was chosen for the impact absorbing overpack. As part of the package development it was necessary to confirm that the urethane foam overpack would provide the required protection for the containment vessel during the thermal test portion of the Hypothetical Accident Conditions Sequential Tests. Development tests of early prototypes were performed, using a furnace. Based on the results of the development tests, detailed design enhancements were incorporated into the final design. Examples of the definitive 9977 design configuration were subjected to an all-engulfing pool fire test, as part of the HAC Sequential Tests, to support the application for certification. Testing has confirmed the package's ability to withstand the HAC thermal tests.

Smith, A; Cecil May, C; Lawrence Gelder, L; Glenn Abramczyk, G

2007-02-15T23:59:59.000Z

292

NEPA Cases Filed in 2010 2010 NEPA Case Dispositions  

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

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

293

U.S. Natural Gas Annual Supply and Disposition Balance  

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

Storage 482,088 135,794 49,126 68,636 98,854 101,604 1973-2013 Disposition Consumption 2,508,032 1,947,684 1,739,493 1,726,304 1,911,261 1,910,113 2001-2013 Injections...

294

Dispositions, disciplines, and marble runs: a case study of resourcefulness  

Science Conference Proceedings (OSTI)

In this paper, three researchers and two teachers have zoomed in on three 'mid-level' episodes of learning in a childcare centre and analyzed them using two lenses: a dispositional lens and a disciplinary (science) practices lens. We wonder how these ...

Margaret Carr; Jane McChesney; Bronwen Cowie; Robert Miles-Kingston; Lorraine Sands

2010-06-01T23:59:59.000Z

295

NUCLEAR FUEL MATERIAL  

DOE Patents (OSTI)

An improved method is given for making the carbides of nuclear fuel material. The metal of the fuel material, which may be a fissile and/or fertile material, is transformed into a silicide, after which the silicide is comminuted to the desired particle size. This silicide is then carburized at an elevated temperature, either above or below the melting point of the silicide, to produce an intimate mixture of the carbide of the fuel material and the carbide of silicon. This mixture of the fuel material carbide and the silicon carbide is relatively stable in the presence of moisture and does not exhibit the highly reactive surface condition which is observed with fuel material carbides made by most other known methods. (AEC)

Goeddel, W.V.

1962-06-26T23:59:59.000Z

296

Physics studies of weapons plutonium disposition in the IFR closed fuel cycle  

SciTech Connect

The core performance impact of weapons plutonium introduction into the IFR closed fuel cycle is investigated by comparing three disposition scenarios: a power production mode, a moderate destruction mode, and a maximum destruction mode all at a constant heat rating of 840 MWt. For each scenario, two fuel cycle models are evaluated: cores using weapons material as the sole source of transuranics in a once-through mode, and recycle corns using weapons material only as required for a make-up feed. Calculated results include mass flows, detailed isotopic distributions, neutronic performance characteristics, and reactivity feedback coefficients. In general, it is shown that weapons plutonium feed does not have an adverse impact on IFR core performance characteristics.

Hill, R.N.; Wade, D.C.; Liaw, J.R.; Fujita, E.K.

1994-03-01T23:59:59.000Z

297

INFORMATION: Management Alert on Environmental Management's Select Strategy for Disposition of Savannah River Site Depleted Uranium Oxides  

SciTech Connect

The Administration and the Congress, through policy statements and passage of the American Recovery and Reinvestment Act of 2009 (Recovery Act), have signaled that they hope that proactive actions by agency Inspectors General will help ensure that Federal Recovery Act activities are transparent, effective and efficient. In that context, the purpose of this management alert is to share with you concerns that have been raised to the Office of Inspector General regarding the planned disposition of the Savannah River Site's (SRS) inventory of Depleted Uranium (DU) oxides. This inventory, generated as a by-product of the nuclear weapons production process and amounting to approximately 15,600 drums of DU oxides, has been stored at SRS for decades. A Department source we deem reliable and credible recently came to the Office of Inspector General expressing concern that imminent actions are planned that may not provide for the most cost effective disposition of these materials. During April 2009, the Department chose to use funds provided under the Recovery Act to accelerate final disposition of the SRS inventory of DU oxides. After coordination with State of Utah regulators, elected officials and the U.S. Nuclear Regulatory Commission, the Department initiated a campaign to ship the material to a facility operated by EnergySolutions in Clive, Utah. Although one shipment of a portion of the material has already been sent to the EnergySolutions facility, the majority of the product remains at SRS. As had been planned, both for the shipment already made and those planned in the near term, the EnergySolutions facility was to have been the final disposal location for the material. Recently, a member of Congress and various Utah State officials raised questions regarding the radioactive and other constituents present in the DU oxides to be disposed of at the Clive, Utah, facility. These concerns revolved around the characterization of the material and its acceptability under existing licensing criteria. As a consequence, the Governor of Utah met with Department officials to voice concerns regarding further shipments of the material and to seek return of the initial shipment of DU oxides to SRS. Utah's objections and the Department's agreement to accede to the State's demands effectively prohibit the transfer of the remaining material from South Carolina to Utah. In response, the Department evaluated its options and issued a draft decision paper on March 1, 2010, which outlined an alternative for temporary storage until the final disposition issue could be resolved. Under the terms of the proposed option, the remaining shipments from SRS are to be sent on an interim basis to a facility owned by Waste Control Specialists (WCS) in Andrews, Texas. Clearly, this choice carries with it a number of significant logistical burdens, including substantial additional costs for, among several items, repackaging at SRS, transportation to Texas, storage at the interim site, and, repackaging and transportation to the yet-to-be-determined final disposition point. The Department source expressed the concern that the proposal to store the material on an interim basis in Texas was inefficient and unnecessary, asserting: (1) that the materials could remain at SRS until a final disposition path is identified, and that this could be done safely, securely and cost effectively; and, (2) that the nature of the material was not subject to existing compliance agreements with the State of South Carolina, suggesting the viability of keeping the material in storage at SRS until a permanent disposal site is definitively established. We noted that, while the Department's decision paper referred to 'numerous project and programmatic factors that make it impractical to retain the remaining inventory at Savannah River,' it did not outline the specific issues involved nor did it provide any substantive economic or environmental analysis supporting the need for the planned interim storage action. The only apparent driver in this case was a Recovery Act-related goal esta

None

2010-04-01T23:59:59.000Z

298

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

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

299

Used Fuel Disposition Campaign Disposal Research and Development Roadmap  

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

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

300

EPRI Global LLW Profile - Generation, Treatment, Conditioning, and Disposition  

Science Conference Proceedings (OSTI)

In the past several years, the Electric Power Research Instituteís (EPRIís) international membership has expanded significantly. As EPRIís membership demographics shift, the absence of a comprehensive global understanding of low level waste (LLW) practices limits our ability to effectively provide technically accurate dialogue and assistance. Understanding LLW waste generation, classification, packaging, treatment, conditioning and disposition profiles is imperative when providing ...

2012-11-29T23:59:59.000Z

Note: This page contains sample records for the topic "fissile materials disposition" 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

Detecting fission from special nuclear material sources  

DOE Patents (OSTI)

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a graphing component that displays the plot of the neutron distribution from the unknown source over a Poisson distribution and a plot of neutrons due to background or environmental sources. The system further includes a known neutron source placed in proximity to the unknown source to actively interrogate the unknown source in order to accentuate differences in neutron emission from the unknown source from Poisson distributions and/or environmental sources.

Rowland, Mark S. (Alamo, CA); Snyderman, Neal J. (Berkeley, CA)

2012-06-05T23:59:59.000Z

302

Response to 'A comment on "Signatures of fissile materials: High-energy gamma rays following fission," by Zeev B. Alfassi'  

E-Print Network (OSTI)

high-energy ? rays following fission" by Zeev B. Alfassi ,radionuclides that are not fission products, but which emittemporal variation of the fission product gamma rays should

2004-01-01T23:59:59.000Z

303

APPLICATION OF VACUUM SALT DISTILLATION TECHNOLOGY FOR THE REMOVAL OF FLUORIDE AND CHLORIDE FROM LEGACY FISSILE MATERIALS  

Science Conference Proceedings (OSTI)

Between September 2009 and January 2011, the Savannah River National Laboratory (SRNL) and the Savannah River Site (SRS) HB-Line Facility designed, developed, tested, and successfully deployed a production-scale system for the distillation of sodium chloride (NaCl) and potassium chloride (KCl) from plutonium oxide (PuO{sub 2}). Subsequent efforts adapted the vacuum salt distillation (VSD) technology for the removal of chloride and fluoride from less-volatile halide salts at the same process temperature and vacuum. Calcium chloride (CaCl{sub 2}), calcium fluoride (CaF{sub 2}), and plutonium fluoride (PuF{sub 3}) were of particular concern. To enable the use of the same operating conditions for the distillation process, SRNL employed in situ exchange reactions to convert the less-volatile halide salts to compounds that facilitated the distillation of halide without removal of plutonium. SRNL demonstrated the removal of halide from CaCl{sub 2}, CaF{sub 2} and PuF{sub 3} below 1000 C using VSD technology.

Pierce, R.; Peters, T.

2011-11-01T23:59:59.000Z

304

Loose Nukes: Nuclear Material Security in G.P.Gilfoyle  

E-Print Network (OSTI)

Shinrikyo and Osama bin Laden's group (two terrorist organi- zations) supposedly tried to obtain fissile material. #12;What Can An Opponent Do? · The opponents are nation-states (e.g. Iraq) and terrorist? · What can a terrorist organization do? ­ Acquiring the necessary technology to enrich uranium

Gilfoyle, Jerry

305

Used fuel disposition campaign international activities implementation plan.  

Science Conference Proceedings (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

306

SAMPLE RESULTS FROM THE INTERIM SALT DISPOSITION PROGRAM MACROBATCH 7 TANK 21H QUALIFICATION MST SOLIDS SAMPLE  

Science Conference Proceedings (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.; Peters, T.

2013-09-19T23:59:59.000Z

307

Porcelain enamel neutron absorbing material  

DOE Patents (OSTI)

A porcelain enamel composition as a neutron absorbing material can be prepared of a major proportion by weight of a cadmium compound and a minor proportion of compound of boron, lithium and silicon. These compounds in the form of a porcelain enamel coating or layer on several alloys has been found to be particularly effective in enhancing the nuclear safety of equipment for use in the processing and storage of fissile material. The composition of the porcelain enamel coating can be tailored to match the coefficient of thermal expansion of the equipment to be coated and excellent coating adhesion can be achieved. 2 figs.

Iverson, D.C.

1987-11-20T23:59:59.000Z

308

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

Science Conference Proceedings (OSTI)

The purpose of this study is to identify, assess, and rank potential sites for the proposed Surplus Plutonium Disposition Facilities complex at the Savannah River Site.

Wike, L.D.

2000-12-13T23:59:59.000Z

309

EIS-0229: Amended Record of Decision | Department of Energy  

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

Decision Decision EIS-0229: Amended Record of Decision Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic Environmental Impact Statement The U.S. Department of Energy (DOE) is amending the Record of Decision (ROD) for the Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement (DOE/EIS-0229, 1996; Storage and Disposition PEIS). Specifically, DOE has decided to take the actions necessary to transfer approximately 2,511 additional 3013-compliant packages 1 containing surplus non-pit weapons-usable plutonium metals and oxides to the Savannah River Site (SRS), near Aiken, South Carolina. DOE/EIS-0229, Amended Record of Decision for the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic Environmental Impact

310

Draft Environmental Assessment on the Remote-handled Waste Disposition  

NLE Websites -- All DOE Office Websites (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 DepartmentÔŅĹs 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.

311

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

312

MANAGING HANFORD'S LEGACY NO-PATH-FORWARD WASTES TO DISPOSITION  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) Richland Operations Office (RL) has adopted the 2015 Vision for Cleanup of the Hanford Site. This vision will protect the Columbia River, reduce the Site footprint, and reduce Site mortgage costs. The CH2M HILL Plateau Remediation Company's (CHPRC) Waste and Fuels Management Project (W&FMP) and their partners support this mission by providing centralized waste management services for the Hanford Site waste generating organizations. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 m{sup 3} of waste was defined as 'no-path-forward waste.' The majority of these wastes are suspect transuranic mixed (TRUM) wastes which are currently stored in the low-level Burial Grounds (LLBG), or stored above ground in the Central Waste Complex (CWC). A portion of the waste will be generated during ongoing and future site cleanup activities. The DOE-RL and CHPRC have collaborated to identify and deliver safe, cost-effective disposition paths for 90% ({approx}8,000 m{sup 3}) of these problematic wastes. These paths include accelerated disposition through expanded use of offsite treatment capabilities. Disposal paths were selected that minimize the need to develop new technologies, minimize the need for new, on-site capabilities, and accelerate shipments of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico.

WEST LD

2011-01-13T23:59:59.000Z

313

Disposition of ORNL's Spent Nuclear Fuel  

SciTech Connect

This paper describes the process of retrieving, repackaging, and preparing Oak Ridge spent nuclear fuel (SNF) for off-site disposition. The objective of the Oak Ridge SNF Project is to safely, reliably, and efficiently manage SNF that is stored on the Oak Ridge Reservation until it can be shipped off-site. The project required development of several unique processes and the design and fabrication of special equipment to enable the successful retrieval, transfer, and repackaging of Oak Ridge SNF. SNF was retrieved and transferred to a hot cell for repackaging. After retrieval of SNF packages, the storage positions were decontaminated and stainless steel liners were installed to resolve the vulnerability of water infiltration. Each repackaged SNF canister has been transferred from the hot cell back to dry storage until off-site shipments can be made. Three shipments of aluminum-clad SNF were made to the Savannah River Site (SRS), and five shipments of non-aluminum-clad SNF are planned to the Idaho National Engineering and Environmental Laboratory (INEEL). Through the integrated cooperation of several organizations including the U.S. Department of Energy (DOE), Bechtel Jacobs Company LLC (BJC), Oak Ridge National Laboratory (ORNL), and various subcontractors, preparations for the disposition of SNF in Oak Ridge have been performed in a safe and successful manner.

Turner, D. W.; DeMonia, B. C.; Horton, L. L.

2002-02-26T23:59:59.000Z

314

Major Risk Factors Integrated Facility Disposition Project - Oak Ridge  

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

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

315

Predicting fissile content of spent nuclear fuel assemblies with the passive neutron Albedo reactivity technique and Monte Carlo code emulation  

SciTech Connect

There is a great need in the safeguards community to be able to nondestructively quantify the mass of plutonium of a spent nuclear fuel assembly. As part of the Next Generation of Safeguards Initiative, we are investigating several techniques, or detector systems, which, when integrated, will be capable of quantifying the plutonium mass of a spent fuel assembly without dismantling the assembly. This paper reports on the simulation of one of these techniques, the Passive Neutron Albedo Reactivity with Fission Chambers (PNAR-FC) system. The response of this system over a wide range of spent fuel assemblies with different burnup, initial enrichment, and cooling time characteristics is shown. A Monte Carlo method of using these modeled results to estimate the fissile content of a spent fuel assembly has been developed. A few numerical simulations of using this method are shown. Finally, additional developments still needed and being worked on are discussed.

Conlin, Jeremy Lloyd [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory

2010-10-13T23:59:59.000Z

316

Blend Down Monitoring System Fissile Mass Flow Monitor Implementation at the ElectroChemical Plant, Zelenogorsk, Russia  

SciTech Connect

The implementation plans and preparations for installation of the Fissile Mass Flow Monitor (FMFM) equipment at the ElectroChemical Plant (ECP), Zelenogorsk, Russia, are presented in this report. The FMFM, developed at Oak Ridge National Laboratory, is part of the Blend Down Monitoring System (BDMS), developed for the U.S. Department of Energy Highly Enriched Uranium (HEU) Transparency Implementation Program. The BDMS provides confidence to the United States that the Russian nuclear facilities supplying the lower-assay ({approx}4%) product low enriched uranium (P-LEU) to the United States from down-blended weapons-grade HEU are meeting the nonproliferation goals of the government-to-government HEU Purchase Agreement, signed between the Russian Federation and the United States in 1993. The first BDMS has been operational at Ural Electrochemical Integrated Plant, Novouralsk, since February 1999 and is successfully providing HEU transparency data to the United States. The second BDMS was installed at ECP in February 2003. The FMFM makes use of a set of thermalized californium-252 ({sup 252}Cf) spontaneous neutron sources for a modulated fission activation of the UF{sub 6} gas stream for measuring the {sup 235}U fissile mass flow rate. To do this, the FMFM measures the transport time of the fission fragments created from the fission activation process under the modulated source to the downstream detectors by detecting the delayed gamma rays from the fission fragments. The FMFM provides unattended, nonintrusive measurements of the {sup 235}U mass flow in the HEU, LEU blend stock, and P-LEU process legs. The FMFM also provides the traceability of the HEU flow to the product process leg. This report documents the technical installation requirements and the expected operational characteristics of the ECP FMFM.

Uckan, T.

2005-11-11T23:59:59.000Z

317

Fissile Mass Flow Monitor Implementation for Transparency in HEU Blenddown at the URAL Electrochemical Integrated Plant (UEIP) in Novouralsk  

SciTech Connect

The Oak Ridge National Laboratory (ORNL) Fissile Mass Flow Monitor (FMFM) was deployed at the Ural Electrochemical Integrated Plant (UEIP) highly enriched uranium (HEU) blending facility in January and February 1999 at Novouralsk in Russia for the DOE HEU Transparency Program. The FMFM provides unattended monitoring of the fissile mass flow of the uranium hexafluoride (UF{sub 6}) gas in the process lines of HEU, the low enriched uranium (LEU) blend stock, and the product LEU (P-LEU) of the blending tee non-intrusively. To do this, uranium-235 (U-235) fissions are induced in the UF{sub 6} by a thermalized and modulated californium-252 (Cf-252) neutron source placed on each process line. A set of detectors, located downstream of source, measure delayed gamma rays emitted by the resulting fission fragments. The observed delay in the time correlated measurement between the source and the detector signal provides the velocity of UF{sub 6} and its amplitude is related to the U- 235 content in UF{sub 6}. An on-line computer controls the source modulator, processes the collected detector data, and displays the results. The UEIP Main and the Reserved process lines were implemented with minor modifications. The FMFM monitors the HEU blending operation by measuring UF{sub 6} flows in the process blending lines, and the traceability of the HEU flow from the blend point to the P-LEU. The detail operational characteristics of the FMFM software (FM2) and the measurement methodology used are presented.

March-Leuba, J.; Mastal, E.; Powell, D.; Sumner, J.; Uckan, T.; Vines, B.

1999-07-25T23:59:59.000Z

318

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

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

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

319

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

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

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)

320

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

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

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

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321

Materials of Criticality Safety Concern in Waste Packages  

Science Conference Proceedings (OSTI)

10 CFR 71.55 requires in part that the fissile material package remain subcritical when considering 'the most reactive credible configuration consistent with the chemical and physical form of the material'. As waste drums and packages may contain unlimited types of materials, determination of the appropriately bounding moderator and reflector materials to ensure compliance with 71.55 requires a comprehensive analysis. Such an analysis was performed to determine the materials or elements that produce the most reactive configuration with regards to both moderation and reflection of a Pu-239 system. The study was originally performed for the TRUPACT-II shipping package and thus the historical fissile mass limit for the package, 325 g Pu-239, was used [1]. Reactivity calculations were performed with the SCALE package to numerically assess the moderation or reflection merits of the materials [2]. Additional details and results are given in SAIC-1322-001 [3]. The development of payload controls utilizing process knowledge to determine the classification of special moderator and/or reflector materials and the associated fissile mass limit is also addressed. (authors)

Larson, S.L. [Science Applications International Corporation, 301 Laboratory Road, Oak Ridge, TN 37830 (United States); Day, B.A. [Washington TRU Solutions LLC, 4021 National Parks Highway, Carlsbad, NM 88220 (United States)

2006-07-01T23:59:59.000Z

322

Nuclear Isotopic Dilution of Highly-Enriched Uranium-235 and Uranium-233 by Dry Blending via the RM-2 Mill Technology  

SciTech Connect

The United States Department of Energy has initiated numerous activities to identify strategies to disposition various excess fissile materials. Two such materials are the off-specification highly enriched uranium-235 oxide powder and the uranium-233 contained in unirradiated nuclear fuel both currently stored at the Idaho National Engineering and Environmental Laboratory. This report describes the development of a technology that could dilute these materials to levels categorized as low-enriched uranium, or further dilute the materials to a level categorized as waste. This dilution technology opens additional pathways for the disposition of these excess fissile materials as existing processing infrastructure continues to be retired.

N. A. Chipman; R. N. Henry; R. K. Rajamani; S. Latchireddi; V. Devrani; H. Sethi; J. L. Malhotra

2004-02-01T23:59:59.000Z

323

Evaluation of Possible Surrogates for Validation of the Oxidation Furnace for the Plutonium Disposition Project  

Science Conference Proceedings (OSTI)

The Plutonium Disposition project (PuD) is considering an alternative furnace design for direct metal oxidation (DMO) of plutonium metal to use as a feed for potential disposition routes. The proposed design will use a retort to oxidize the feed at temperatures up to 500 C. The atmosphere will be controlled using a metered mixture of oxygen, helium and argon to control the oxidation at approximately 400 torr. Since plutonium melts at 664 C, and may potentially react with retort material to form a lower melting point eutectic, the oxidation process will be controlled by metering the flow of oxygen to ensure that the bulk temperature of the material does not exceed this temperature. A batch processing time of <24 hours is desirable to meet anticipated furnace throughput requirements. The design project includes demonstration of concept in a small-scale demonstration test (i.e., small scale) and validation of design in a full-scale test. These tests are recommended to be performed using Pu surrogates due to challenges in consideration of the nature of plutonium and operational constraints required when handling large quantities of accountable material. The potential for spreading contamination and exposing workers to harmful levels of cumulative radioactive dose are motivation to utilize non-radioactive surrogates. Once the design is demonstrated and optimized, implementation would take place in a facility designed to accommodate these constraints. Until then, the use of surrogates would be a safer, less expensive option for the validation phase of the project. This report examines the potential for use of surrogates in the demonstration and validation of the DMO furnace for PuD. This report provides a compilation of the technical information and process requirements for the conversion of plutonium metal to oxide by burning in dry environments. Several potential surrogates were evaluated by various criteria in order to select a suitable candidate for large scale demonstration. First, the structure of the plutonium metal/oxide interface was compared to potential surrogates. Second the data for plutonium oxidation kinetics were reviewed and rates for oxidation were compared with surrogates. The criteria used as a basis for recommendation was selected in order to provide a reasonable oxidation rate during the validation phase. Several reference documents were reviewed and used to compile the information in this report. Since oxidation of large monolithic pieces of plutonium in 75% oxygen is the preferable oxidizing atmosphere for the intended process, this report does not focus on the oxidation of powders, but focuses instead on larger samples in flowing gas.

Duncan, A.

2007-12-31T23:59:59.000Z

324

Nuclear Material Management Abstract  

Science Conference Proceedings (OSTI)

Nevada Test Site (NTS) has transitioned from its historical and critical role of weapons testing to another critical role for the nation. This new role focuses on being a integral element in solving the multiple challenges facing the National Nuclear Security Administration (NNSA) with nuclear material management. NTS is positioned to be a solution for other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to consolidate and modernize the production complex . With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through disposition and consolidation. This includes moving material from other sites to NTS. State of the art nuclear material management and control practices at NTS are essential for NTS to ensure that assigned activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS activities and challenges will be addressed.

Jesse C. Schreiber

2007-07-10T23:59:59.000Z

325

Master EM Project Definition Rating Index - Facility Disposition Definitions  

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

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

326

Microsoft Word - BingenSwitchDisposition_CXMemo.doc  

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

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,

327

Microsoft Word - DOE Records Disposition Schedule Changes3.doc  

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

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

328

Topic Index to the DOE Administrative Records Disposition Schedules  

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

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

329

ABSTRACT REQUESTER CONTRACT SCOPE OF WORK RATIONAL FOR DECISION DISPOSITION  

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

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

330

Nonconforming Material Process  

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

11 Nonconforming Material / Product Process 11_0304 Page 1 of 6 11 Nonconforming Material / Product Process 11_0304 Page 1 of 6 EOTA - Business Process Document Title: Nonconforming Material / Product Process Document Number: P-011 Rev. 11_0304 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: Q-001, Quality Manual Notify of Changes: EOTA Employees Referenced Document(s): F-015 Nonconformance Report, REG-003 Record Register, ISDP-002 Training Production Process P-011 Nonconforming Material / Product Process 11_0304 Page 2 of 6 Revision History: Rev. Description of Change A Initial Release 08_0416 Added verbiage CAR/PAR/IO to Step 2 P-011 Nonconforming Material / Product Process 11_0304 Page 3 of 6 I. Purpose To establish the process for nonconforming material to be identified, segregated and dispositioned to prevent its unintended

331

,"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"

332

,"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"

333

Blend Down Monitoring System Fissile Mass Flow Monitor and its Implementation at the Siberian Chemical Enterprise, Seversk, Russia  

SciTech Connect

In this paper the implementation plans and preparations for installation of the Fissile Mass Flow Monitor (FMFM) equipment at the Siberian Chemical Enterprise (SChE), Seversk, Russia, are presented. The FMFM, developed by Oak Ridge National Laboratory, is part of the Blend Down Monitoring System (BDMS) for the U.S. Department of Energy Highly Enriched Uranium (HEU) Transparency Implementation Program. The BDMS provides confidence to the United States that the Russian nuclear facilities supplying the lower assay ({approx}4%) product low enriched uranium (PLEU) to the United States from down-blended weapon-grade HEU are meeting the nonproliferation goals of the government-to-government HEU purchase agreement signed between the Russian Federation and the United States in 1993. The first BDMS has been operational at Ural Electrochemical Integrated Plant, Novouralsk, since February 1999. The second BDMS has been operational at Electro Chemical Plant, Zelenogorsk, since March 2003. These systems are successfully providing HEU transparency data to the United States. The third BDMS was successfully installed on the HEU down-blending tee in the SChE Enrichment Plant in October 2004. The FMFM makes use of a set of thermalized {sup 252}Cf spontaneous neutron sources for modulated fission activation of the UF{sub 6} gas stream for measuring the {sup 235}U fissile mass flow rate. To do this, the FMFM measures the transport time of the fission fragments created from the fission activation process under the modulated source to the downstream detectors by detecting the delayed gamma rays from the fission fragments retained in the flow. The FMFM provides unattended nonintrusive measurements of the {sup 235}U mass flow of the UF{sub 6} gas in the blending tee legs of HEU, the LEU blend stock, and the resulting P-LEU. The FMFM also confirms that highly enriched UF{sub 6} gas identified in the HEU leg flows through the blending tee into the P-LEU leg. This report contains details of the SChE FMFM equipment characteristics as well as the technical installation requirements and the latest measurement results.

Uckan, T

2005-07-28T23:59:59.000Z

334

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

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

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

335

Used Fuel Disposition R&D Documents | Department of Energy  

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

Used Fuel Disposition Used Fuel Disposition Research & Development ¬Ľ 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

336

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

337

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

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

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

338

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

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

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

339

Microsoft Word - CX-MountainAvenueDispositionFY12_WEB.doc  

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

Joan Kendall Realty Specialist - TERR-3 Proposed Action: Disposition of Mountain Avenue Substation and Tap Line Categorical Exclusion Applied (from Subpart D, 10 C.F.R. Part 1021):...

340

105-N basin sediment disposition phase-two sampling and analysis plan  

DOE Green Energy (OSTI)

The sampling and analysis plan for Phase 2 of the 105-N Basin sediment disposition task defines the sampling and analytical activities that will be performed to support characterization of the sediment and selection of an appropriate sediment disposal option.

NONE

1997-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "fissile materials disposition" 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

On Solar Energy Disposition:A Perspective from Observation and Modeling  

Science Conference Proceedings (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

342

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)

343

Environmental Assessment Addendum Disposition of Additional Waste at the Paducah Site  

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

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.......................................................................................................................................

344

Disposition Options for Hanford Site K-Basin Spent Nuclear Fuel Sludge  

SciTech Connect

This report provides summary-level information about a group of options that have been identified for the disposition of spent-nuclear-fuel sludge in the K-Basins at the Hanford Site. These options are representative of the range of likely candidates that may be considered for disposition of the sludge. The product of each treatment option would be treated sludge that would meet waste acceptance requirements for disposal as transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP).

Mellinger, George B.; Delegard, Calvin H.; Gerber, Mark A.; Naft, Barry N.; Schmidt, Andrew J.; Walton, Terry L.

2004-01-18T23:59:59.000Z

345

FMDP reactor alternative summary report. Volume 1 - existing LWR alternative  

SciTech Connect

Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] are becoming surplus to national defense needs in both the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. This document summarizes the results of analysis concerned with existing light water reactor plutonium disposition alternatives.

Greene, S.R.; Bevard, B.B. [and others

1996-10-07T23:59:59.000Z

346

Critical masses of highly enriched uranium diluted with matrix material.  

SciTech Connect

Radioactive waste containing fissile material is frequently encountered in decontamination and decommissioning activities. For the most part, this waste is placed in containers or drums and stored in storage facilities. The amount of fissile material in each drum is generally small because of criticality safety limits that have been calculated with computer transport codes such as MCNP,1 KENO,2 or ONEDANT.3 To the best of our knowledge, no experimental critical mass data are available to verify the accuracy of these calculations or any calculations for systems containing fissile material (U-235, Pu-239, U-233) in contact with matrix material such as Al2O3, CaO, SiO2, Al, MgO, etc. The experiments presented in this paper establish the critical masses of highly enriched uranium foils diluted to various X/235U ratios with polyethylene and SiO2, polyethylene and aluminum, polyethylene and MgO, polyethylene and Gd, polyethylene and Fe, and moderated and reflected with polyethylene. In addition, these critical mass experimental data will be used to validate cross section data.

Sanchez, R. G. (Rene G.); Loaiza, D. J. (David J.); Kimpland, R. H. (Robert H.)

2002-01-01T23:59:59.000Z

347

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

348

Disposition of nuclear waste using subcritical accelerator-driven systems  

Science Conference Proceedings (OSTI)

Studies have shown that the repository long-term radiological risk is from the long-lived transuranics and the fission products Tc-99 and I-129, thermal loading concerns arise mainly form the short-lived fission products Sr-90 and Cs-137. In relation to the disposition of nuclear waste, ATW is expected to accomplish the following: (1) destroy over 99.9% of the actinides; (2) destroy over 99.9% of the Tc and I; (3) separate Sr and Cs (short half-life isotopes); (4) separate uranium; (5) produce electricity. In the ATW concept, spent fuel would be shipped to a ATW site where the plutonium, other transuranics and selected long-lived fission products would be destroyed by fission or transmutation in their only pass through the facility. This approach contrasts with the present-day reprocessing practices in Europe and Japan, during which high purity plutonium is produced and used in the fabrication of fresh mixed-oxide fuel (MOX) that is shipped off-site for use in light water reactors.

Venneri, F.; Li, N.; Williamson, M.; Houts, M.; Lawrence, G.

1998-12-01T23:59:59.000Z

349

Plutonium disposition study phase 1b final report  

Science Conference Proceedings (OSTI)

This report provides the results of the Westinghouse activities performed as part of the Plutonium Disposition Study Phase 1b. These activities, which took place from May 16, 1993 to September 15, 1993, build upon the work completed in Phase 1a, which concluded on May 15, 1993. In Phase 1a, three Plutonium Disposal Reactor (PDR) options were developed for the disposal of excess weapons grade plutonium from returned and dismantled nuclear weapons. This report documents the results of several tasks that were performed to further knowledge in specific areas leading up to Phase 2 of the PDR Study. The Westinghouse activities for Phase 1b are summarized as follows: (1) resolved technical issues concerning reactor physics including equilibrium cycle calculations, use of gadolinium, moderator temperature coefficient, and others as documented in Section 2.0; (2) analyzed large Westinghouse commercial plants for plutonium disposal; (3) reactor safety issues including the steam line break were resolved, and are included in Section 2.0; (4) several tasks related to the PDR Fuel Cycle were examined; (5) cost and deployment options were examined to determine optimal configuration for both plutonium disposal and tritium production; (6) response to questions from DOE and National Academy of Scientists (NAS) reviewers concerning the PDR Phase 1a report are included in Appendix A.

NONE

1993-09-15T23:59:59.000Z

350

Disposition of Weapons-Grade Plutonium in Westinghouse Reactors  

E-Print Network (OSTI)

Disposition of Weapons-Grade Plutonium in Westinghouse Reactors Abdelhalim Ali Alsaed and Marvin Adams We have studied the feasibility of using weapons-grade plutonium in the form of mixed-oxide (MOX) fuel in existing Westinghouse reactors. We have designed three transition cycles from an all LEU core to a partial MOX core. We found that four-loop Westinghouse reactors such as the Vogtle power plant are capable of handling up to 45 percent weapons-grade MOX loading without any modifications. We have also designed two kinds of weapons-grade MOX assemblies with three enrichments per assembly and four total enrichments. Wet annular burnable absorber (WABA) rods were used in all the MOX feed assemblies, some burned MOX assemblies, and some LEU feed assemblies. Integral fuel burnable absorber (IFBA) was used in the rest of the LEU feed assemblies. The average discharge burnup of MOX assemblies was over 47,000 MWD/MTM, which is more than enough to meet the "spent fuel standard." One unit is ...

No. De-fc-al; Abdelhalim Ali Alsaed; Abdelhalim Ali Alsaed; Marvin Adams; Marvin Adams

1998-01-01T23:59:59.000Z

351

Angular Distributions of Fragments Originating from the Spontaneous Fission of Oriented Nuclei and Problem of the Conservation of the Spin Projection onto the Symmetry Axis of a Fissile Nucleus  

Science Conference Proceedings (OSTI)

The concept of transition fission states, which was successfully used to describe the angular distributions of fragments for the spontaneous and low-energy induced fission of axisymmetric nuclei, proves to be correct if the spin projection onto the symmetry axis of a fissile nucleus is an integral of the motion for the external region from the descent of the fissile nucleus from the external fission barrier to the scission point. Upon heating a fissile nucleus in this region to temperatures of T {approx_equal} 1 MeV (this is predicted by many theoretical models of the fission process), the Coriolis interaction uniformly mixes the possible projections of the fissile-nucleus spin for the case of low spin values, this leading to the loss of memory about transition fission states in the asymptotic region where the angular distributions of fragments are formed. Within quantum-mechanical fission theory, which takes into account deviations from A. Bohr's formula, the angular distributions of fragments are calculated for spontaneously fissile nuclei aligned by an external magnetic field at ultralow temperatures, and it is shown that an analysis of experimental angular distributions of fragments would make it possible to solve the problem of spin-projection conservation for fissile nuclei in the external region.

Kadmensky, S.G.; Rodionova, L.V. [Voronezh State University, Universitetskaya pl. 1, Voronezh, 394693 (Russian Federation)

2005-09-01T23:59:59.000Z

352

DOE - Safety of Radioactive Material Transportation  

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

Specific Activity Specific Activity Low Specific Activity (LSA) material means Class 7 (radioactive) material with limited specific activity which satisfies the descriptions and limits set forth below. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. LSA material must be in one of three groups: LSA-I (i) Ores containing only naturally occurring radionuclides (e.g., uranium, thorium) and uranium or thorium concentrates of such ores; or (ii) Solid unirradiated natural uranium or depleted uranium or natural thorium or their solid or liquid compounds or mixtures; or (iii) Class 7 (radioactive) material, other than fissile material, for which the A2 value is unlimited; or

353

DOE G 430.1-2, Implementation Guide for Surveillance and Maintenance during Facility Transition and Disposition  

Directives, Delegations, and Requirements

As DOE facilities complete mission operations and are declared excess, they pass into a transition phase that ultimately prepares them for disposition. The ...

1999-09-29T23:59:59.000Z

354

Complications Associated with Long-Term Disposition of Newly-Generated Transuranic Waste: A National Laboratory Perspective  

SciTech Connect

The Idaho National Laboratory (INL) is a multipurpose national laboratory delivering specialized science and engineering solutions for the U.S. Department of Energy (DOE). Sponsorship of INL was formally transferred to the DOE Office of Nuclear Energy, Science and Technology (NE) by Secretary Spencer Abraham in July 2002. The move to NE, and designation as the DOE lead nuclear energy laboratory for reactor technology, supports the nationís expanding nuclear energy initiatives, placing INL at the center of work to develop advanced Generation IV nuclear energy systems; nuclear energy/hydrogen coproduction technology; advanced nuclear energy fuel cycle technologies; and providing national security answers to national infrastructure needs. As a result of the Laboratoryís NE mission, INL generates both contact-handled and remote-handled transuranic (TRU) waste from ongoing operations. Generation rates are relatively small and fluctuate based on specific programs and project activities being conducted; however, the Laboratory will continue to generate TRU waste well into the future in association with the NE mission. Currently, plans and capabilities are being established to transfer INLís contact-handled TRU waste to the Advanced Mixed Waste Treatment Plant (AMWTP) for certification and disposal to the Waste Isolation Pilot Plant (WIPP). Remote-handled TRU waste is currently placed in storage at the Materials and Fuels Complex (MFC). In an effort to minimize future liabilities associated with the INL NE mission, INL is evaluating and assessing options for the management and disposition of all its TRU waste on a real-time basis at time of generation. This paper summarizes near-term activities to minimize future re handling of INLís TRU waste, as well as, potential complications associated with the long-term disposition of newly-generated TRU waste. Potential complications impacting the disposition of INL newly-generated TRU waste include, but are not limited to: 1) required remote-handled TRU packaging configuration(s) vs. current facility capabilities, 2) long-term NE mission activities, 3) WIPP certification requirements, and 4) budget considerations.

B.J. Orchard; L.A. Harvego; T.L. Carlson; R.P. Grant

2009-03-01T23:59:59.000Z

355

Disposition of Unirradiated Sodium Bonded EBR-II Driver Fuel Elements and HEU Scrap: Work Performed for FY 2007  

SciTech Connect

Specific surplus high enriched uranium (HEU) materials at the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) will be transferred to a designated off-site receiving facility. The DOE High Enriched Uranium Disposition Program Office (HDPO) will determine which materials, if any, will be prepared and transferred to an off-site facility for processing and eventual fabrication of fuel for nuclear reactors. These surplus HEU materials include approximately 7200 kg unirradiated sodium-bonded EBR-II driver fuel elements, and nearly 800 kg of HEU casting scrap from the process which formed various sodium-bonded fuels (including the EBR-II driver elements). Before the driver fuel can be packaged for shipment, the fuel elements will require removal of the sodium bond. The HEU scrap will also require repackaging in preparation for off-site transport. Preliminary work on this task was authorized by BWXT Y-12 on Nov 6, 2006 and performed in three areas: ē Facility Modifications ē Safety Documentation ē Project Management

Karen A Moore

2007-04-01T23:59:59.000Z

356

Analysis of material disposition for Illinois {number_sign}6 coal POC testing at the CFFF  

DOE Green Energy (OSTI)

The Illinois No.6 coal Proof-of-Concept (POC) bottoming cycle testing began in August of 1987 with test LMF4K. POC testing of this coal was completed in November of 1990 with test LMF4V, and included a total of over 2003 hours of coal-fired operation. This testing was conducted to permit the evaluation of effects of long duration operation on a number of critical design issues. During all of the POC testing, all Heat-Recovery/Seed Recovery (HRSR) components, with the exception of the wet electrostatic precipitator (ESP), were installed and operational. Throughout this time, measurements were made of all major solid feed and product streams entering and leaving the CFFF flow train. In addition, key process variables, including mass flowrates and gas compositions, were measured continuously during testing. Particulate samples were obtained and chemically analyzed, and dust loading measurements, at several locations in the flow train, were made during many of the tests. After testing, major waste and product streams were analyzed for chemical composition. Combined, this information was sufficient to enable an overall mass balance as well as a number of elemental balances to be performed around the flow train for each test.

Jackson, D.M.

1993-06-01T23:59:59.000Z

357

Plutonium destruction in a non-fertile, ZrO{sub 2}-based fuel: A reactor option for disposition of surplus plutonium  

SciTech Connect

The United States and Russia are assessing options for disposition of surplus weapon-grade plutonium. This paper reviews the options under consideration by the US Department of Energy and suggests an additional option that fits within the framework of the environmental analysis provided in the draft PEIS (Programmatic Environmental Impact Statement). In addition to the burning of Pu in mixed U-Pu oxide fuel, we recommend consideration of a non-fertile fuel based on zirconia with inclusion of rare earth elements for phase stabilization and control of reactivity. The zirconia based fuel could also be used to burn plutonium generated in commercial reactor fuels, which represent a larger inventory of plutonium than the weapon-grade material. The increasing inventories of civilian plutonium potentially represent a larger threat with respect to diversion weapons usable material than the stocks of weapon-grade material considered for disposition by the US and Russia. We discuss the use of zirconia-based fuel and pyrochemical processing of spent commercial reactor fuels as a means of decreasing world-wide plutonium inventories. The experience gained in burning weapon-grade plutonium in the new non-fertile fuel would shorten the time required to gain acceptance of the fuel for commercial reactor use.

Oversby, V.M. [Lawrence Livermore National Lab., CA (United States); McPheeters, C.C. [Argonne National Lab., IL (United States)

1996-02-01T23:59:59.000Z

358

FMDP reactor alternative summary report: Volume 4, Evolutionary LWR alternative  

SciTech Connect

Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] have become surplus to national defense needs both in the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. The purpose of this report is to provide schedule, cost, and technical information that will be used to support the Record of Process (ROD). Following the screening process, DOE/MD via its national laboratories initiated a more detailed analysis activity to further evaluate each of the ten plutonium disposition alternatives that survived the screening process. Three ``Alternative Teams,`` chartered by DOE and comprised of technical experts from across the DOE national laboratory complex, conducted these analyses. One team was chartered for each of the major disposition classes (borehole, immobilization, and reactors). During the last year and a half, the Fissile Materials Disposition Program (FMDP) Reactor Alternative Team (RxAT) has conducted extensive analyses of the cost, schedule, technical maturity, S&S, and other characteristics of reactor-based plutonium disposition. The results of the RxAT`s analyses of the existing LWR, CANDU, and partially complete LWR alternatives are documented in Volumes 1-3 of this report. This document (Volume 4) summarizes the results of these analyses for the ELWR-based plutonium disposition option.

NONE

1996-09-01T23:59:59.000Z

359

Used Fuel Disposition R&D Documents | Department of Energy  

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

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

360

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

Note: This page contains sample records for the topic "fissile materials disposition" 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

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

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

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

362

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

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

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

363

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

NLE Websites -- All DOE Office Websites (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.

364

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

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

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

365

Estimating discharged plutonium using measurements of structural material activation products  

Science Conference Proceedings (OSTI)

As the US and Russia move to lower numbers of deployed nuclear weapons, transparency regarding the quantity of weapons usable fissile material available in each country may become more important. In some cases detailed historical information regarding material production at individual facilities may be incomplete or not readily available, e.g., at decommissioned facilities. In such cases tools may be needed to produce estimates of aggregate material production as part of a bilateral agreement. Such measurement techniques could also provide increased confidence in declared production quantities.

Charlton, W. S. (William S.); Lumley-Woodyear, A. de; Budlong-Sylvester, K. W. (Kory W.)

2002-01-01T23:59:59.000Z

366

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

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

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 ____________________________________ ____________________________________

367

Alternatives for the disposition of fuel stored in the PUREX facility  

SciTech Connect

This document provides an evaluation of five alternatives for the disposition of 3.4 metric tons of irradiated fuel from PUREX to support facility turnover following deactivation. The alternatives for disposition of the fuel include transfer to the K Basins, transfer to T Plant, passivation and dry vault storage, and dissolution and underground tank storage. The five alternatives were compared and it was determined that the fuel should be transferred from PUREX to the K Basins where it would be placed into pool storage.

Enghusen, M.B.; Gore, D.B.

1995-01-01T23:59:59.000Z

368

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

SciTech Connect

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

369

Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium  

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

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

370

Summary - Preliminary TRA of the Calcine Disposition Project  

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

Calcine The Id materi Dec. 2 Press additiv form w those project anticip 2012 a CD-1 a selecte Level ( assess Eleme assign prepar The as below achiev * R * Ba * C The Ele Site: I...

371

DEVELOPING AN INTEGRATED NATIONAL STRATEGY FOR THE DISPOSITION OF SPENT NUCLEAR FUEL  

Science Conference Proceedings (OSTI)

This paper summarizes the Department of Energy's (DOE's) current efforts to strengthen its activities for the management and disposition of DOE-owned spent nuclear fuel (SNF). In August 2002 an integrated, ''corporate project'' was initiated by the Office of Environmental Management (EM) to develop a fully integrated strategy for disposition of the approximately {approx}250,000 DOE SNF assemblies currently managed by EM. Through the course of preliminary design, the focus of this project rapidly evolved to become DOE-wide. It is supported by all DOE organizations involved in SNF management, and represents a marked change in the way DOE conducts its business. This paper provides an overview of the Corporate Project for Integrated/Risk-Driven Disposition of SNF (Corporate SNF Project), including a description of its purpose, scope and deliverables. It also summarizes the results of the integrated project team's (IPT's) conceptual design efforts, including the identification of project/system requirements and alternatives. Finally, this paper highlights the schedule of the corporate project, and its progress towards development of a DOE corporate strategy for SNF disposition.

Gelles, C.M.

2003-02-27T23:59:59.000Z

372

HLW Salt Disposition Alternatives Identification Preconceptual Phase I Summary Report (Including Attachments)  

SciTech Connect

The purpose of this report is to summarize the process used by the Team to systematically develop alternative methods or technologies for final disposition of HLW salt. Additionally, this report summarizes the process utilized to reduce the total list of identified alternatives to an ''initial list'' for further evaluation. This report constitutes completion of the team charter major milestone Phase I Deliverable.

Piccolo, S.F.

1999-07-09T23:59:59.000Z

373

Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples  

SciTech Connect

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

Peters, T. B.; Fink, S. D.

2012-12-11T23:59:59.000Z

374

Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

Peters, T. B.; Fink, S. D.

2012-12-20T23:59:59.000Z

375

Reactor options for disposition of excess weapon plutonium: Selection criteria and decision process for assessment  

Science Conference Proceedings (OSTI)

DOE is currently considering a wide range of alternatives for disposition of excess weapon plutonium, including using plutonium in mixed oxide fuel for light water reactors (LWRs). Lawrence Livermore National Laboratory (LLNL) has been tasked to assist DOE in its efforts to develop a decision process and criteria for evaluating the technologies and reactor designs that have been proposed for the fission disposition alternative. This report outlines an approach for establishing such a decision process and selection criteria. The approach includes the capability to address multiple, sometimes conflicting, objectives, and to incorporate the impact of uncertainty. The approach has a firm theoretical foundation and similar approaches have been used successfully by private industry, DOE, and other government agencies to support and document complex, high impact technology choice decisions. Because of their similarity and relatively simple technology, this report focuses on three light water reactors studied in Phase 1 of the DOE Plutonium Disposition Study. The decision process can be extended to allow evaluation of other reactor technologies and disposition options such as direct disposal and retrievable storage.

Edmunds, T.; Buonpane, L.; Sicherman, A.; Sutcliffe, W.; Walter, C.; Holman, G.

1994-01-01T23:59:59.000Z

376

A Multiattribute Utility Analysis of Alternatives for the Disposition of Surplus Weapons-Grade Plutonium  

Science Conference Proceedings (OSTI)

This paper describes an application of multiattribute utility theory to support the selection of a technology for the disposition of surplus weapons-grade plutonium by the Department of Energy (DOE). This analysis evaluated 13 alternatives, examined ... Keywords: Utility/preference, applications, multiattribute

James S. Dyer; Thomas Edmunds; John C. Butler; Jianmin Jia

1998-06-01T23:59:59.000Z

377

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

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

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

378

Nonuniform character of the population of spin projections K for a fissile nucleus at the scission point and anisotropies in the angular distributions of fragments originating from the induced fission of nuclei  

Science Conference Proceedings (OSTI)

It is shown that the emergence of anisotropies in the angular distributions of fragments originating from the spontaneous and induced fission of oriented actinide nuclei is possible only if nonuniformities in the population of the projectionsM (K) of the fissile-nucleus spin onto the z axis of the laboratory frame (fissile-nucleus symmetry axis) appear simultaneously in the vicinity of the scission point but not in the vicinity of the outer saddle point of the deformation potential. The possibilities for creating the orientation of fissile nuclei for spontaneous and induced fission and the effect of these orientations on the anisotropies under analysis are considered. The role of Coriolis interaction as a unique source of the mixing of different-K fissile-nucleus states at all stages of the fission process is studied with allowance for the dynamical enhancement of this interaction for excited thermalized states of the nucleus involved that is characterized by a high energy density. It is shown that the absence of thermalization of excited states of the fissile nucleus that appear because of the effect of nonadiabaticity of its collective deformation motion in the vicinity of the scission point is a condition of conservation of the influence that transition fission states formed at the inner and outer fission barriers exerts on the distribution of the spin projections K for lowenergy spontaneous nuclear fission. It is confirmed that anisotropies observed in the angular distributions of fragments originating from the fission of nuclei that is induced by fast light particles (multiply charged ions) are due to the appearance of strongly excited equilibrium(nonequilibrium) states of the fissile nucleus in the vicinity of its scission point that have a Gibbs (non-Gibbs) distribution of projections K.

Kadmensky, S. G., E-mail: kadmensky@phys.vsu.ru [Voronezh State University (Russian Federation); Bunakov, V. E. [Russian Academy of Sciences, Petersburg Nuclear Physics Institute (Russian Federation); Kadmensky, S. S. [Voronezh State University (Russian Federation)

2012-11-15T23:59:59.000Z

379

Initial report on characterization of excess highly enriched uranium  

SciTech Connect

DOE`s Office of Fissile Materials Disposition assigned to this Y-12 division the task of preparing a report on the 174.4 metric tons of excess highly enriched U. Characterization included identification by category, gathering existing data (assay), defining the likely needed processing steps for prepping for transfer to a blending site, and developing a range of preliminary cost estimates for those steps. Focus is on making commercial reactor fuel as a final disposition path.

1996-07-01T23:59:59.000Z

380

Used fuel disposition research and development roadmap - FY10 status.  

SciTech Connect

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

Note: This page contains sample records for the topic "fissile materials disposition" 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

Audit Report: IG-0490 | Department of Energy  

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

0 0 Audit Report: IG-0490 November 28, 2000 Containers Suitable for Shipping Fissile Material As a result of its weapons program activities, the Department of Energy (Department) has a significant inventory of surplus fissile materials. Within the Department, the National Nuclear Security Administration and the Office of Environmental Management are responsible for managing this inventory, including its protection and disposal. To accomplish these objectives, the Department has established a program to ship the fissile materials, including surplus pits and plutonium metals, oxides, fluorides, and residues, from several Department facilities to a final designated disposition location. The various fissile materials are to be shipped in Type B containers certified by the Department or the Nuclear Regulatory

382

Audit Report: IG-0490 | Department of Energy  

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

90 90 Audit Report: IG-0490 November 28, 2000 Containers Suitable for Shipping Fissile Material As a result of its weapons program activities, the Department of Energy (Department) has a significant inventory of surplus fissile materials. Within the Department, the National Nuclear Security Administration and the Office of Environmental Management are responsible for managing this inventory, including its protection and disposal. To accomplish these objectives, the Department has established a program to ship the fissile materials, including surplus pits and plutonium metals, oxides, fluorides, and residues, from several Department facilities to a final designated disposition location. The various fissile materials are to be shipped in Type B containers certified by the Department or the Nuclear Regulatory

383

Microsoft Word - Final Lead Assembly SA.doc  

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

EIS-0229-SA3 EIS-0229-SA3 SUPPLEMENT ANALYSIS FABRICATION OF MIXED OXIDE FUEL LEAD ASSEMBLIES IN EUROPE November 2003 U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. i Table of Contents 1.0 Introduction............................................................................................................................ 1 2.0 Purpose................................................................................................................................... 2 3.0 Background ............................................................................................................................ 2 4.0 Proposed Action.....................................................................................................................

384

Potential for and consequences of criticality resulting from hydrogeochemically concentrated fissile uranium blended with soil in low-level waste disposal facilities  

SciTech Connect

Evaluations were done to determine conditions that could permit nuclear criticality with fissile uranium in low-level-waste (LLW) facilities and to estimate potential radiation exposures to personnel if there were such an accident. Simultaneous hydrogeochemical and nuclear criticality studies were done (1) to identify some realistic scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) to model groundwater transport and subsequent concentration via sorption or precipitation of uranium, (3) to evaluate the potential for nuclear criticality resulting from potential increases in uranium concentration over disposal limits, and (4) to estimate potential radiation exposures to personnel resulting from criticality consequences. The scope of the referenced work was restricted to uranium at an assumed 100 wt% {sup 235}U enrichment. Three outcomes of uranium concentration are possible: uranium concentration is increased to levels that do pose a criticality safety concern; uranium concentration is increased, but levels do not pose a criticality safety concern; or uranium concentration does not increase.

Hopper, C.M.; Parks, C.V.

1997-08-01T23:59:59.000Z

385

2012 Annual Workforce Analysis and Staffing Plan Report - NNSA for Safety and Health - NA-26  

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

1 Annual Workforce Analysis and Staffing Plan Report Draft as of December 31, 2012 Reporting Office: _NA-26 Office of Fissile Material Disposition at SRS____ Section 1: Current Mission(s) of the Organization and Potential Changes 1. The Office of Fissile Material Disposition (NA-26) is part of the National Nuclear Security Administration (NNSA). NA-26 supports NNSA Strategic Plan Goal #2, "Provide technical leadership to limit or prevent the spread of materials, technology, and expertise relating to weapons of mass destruction; advance the technologies to detect the proliferation of weapons of mass destruction worldwide, and eliminate or secure inventories of surplus materials and infrastructure usable for nuclear weapons." The NA-26 organization focuses on the safe and secure disposition of

386

Environmental Assessment Addendum Disposition of Additional Waste at the Paducah Site  

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

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

387

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

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

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

388

DOE Plutonium Disposition Study: Pu consumption in ALWRs. Volume 1, Final report  

SciTech Connect

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 1, presents a technical description of the various elements of the System 80 + Standard Plant Design upon which the Plutonium Disposition Study was based. The System 80 + Standard Design is fully developed and directly suited to meeting the mission objectives for plutonium disposal. The bass U0{sub 2} plant design is discussed here.

Not Available

1993-05-15T23:59:59.000Z

389

DRAFT EM SSAB Chair¬źs Meeting Waste Disposition Strategies Update  

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

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

390

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

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

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

391

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

392

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

SciTech Connect

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

393

Disposition and transportation of surplus radioactive low specific activity nitric acid. Volume 1, Environmental Assessment  

Science Conference Proceedings (OSTI)

DOE is deactivating the PUREX plant at Hanford; this will involve the disposition of about 692,000 liters (183,000 gallons) of surplus nitric acid contaminated with low levels of U and other radionuclides. The nitric acid, designated as low specific activity, is stored in 4 storage tanks at PUREX. Five principal alternatives were evaluated: transfer for reuse (sale to BNF plc), no action, continued storage in Hanford upgraded or new facility, consolidation of DOE surplus acid, and processing the LSA nitric acid as waste. The transfer to BNF plc is the preferred alternative. From the analysis, it is concluded that the proposed disposition and transportation of the acid does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

NONE

1995-05-01T23:59:59.000Z

394

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

E-Print Network (OSTI)

A comprehensive case study was conducted on the policy problem of disposing of U.S. 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 U.S. 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.

Gonzalez, Vanessa L

1998-01-01T23:59:59.000Z

395

Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and Waste Treatment, Storage and Disposal Activities  

SciTech Connect

A fifth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held February 16-18, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 46 Russian attendees from 14 different Russian organizations and six non-Russian attendees, four from the US and two from France. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C.

Jardine, L J; Borisov, G B

2004-07-21T23:59:59.000Z

396

Microsoft PowerPoint - FY09_11 Disposition Plan_090804  

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

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%

397

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

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

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.

398

The effect of chlorine substitution on the disposition of polychlorinated biphenyls following dermal administration  

SciTech Connect

The fate of selected polychlorobiphenyls (PCBs) was investigated following single dermal administration (0.4 mg/kg) to determine the effects of chlorine content and position on the disposition of PCBs following dermal absorption. Single dermal doses of {sup 14}C-labeled mono-, di-, tetra- and hexachlorobiphenyls were administered to 1 cm{sup 2} areas on the backs of F-344 male rats. Distribution of radioactivity in selected tissues and excreta was determined by serial sacrifice at time points up to 2 weeks. Unabsorbed radioactivity was removed from the dose site at either sacrifice or 48 h post-dose. The time course of radioactivity in the tissues showed a dependence on rate and extent of absorption. The most rapidly absorbed PCBs reached peak tissue concentrations at early times and were cleared from the tissues rapidly. The higher chlorinated PCBs were slowly absorbed and tended to accumulate in the adipose and skin after removal of unabsorbed dose. Excretion of absorbed radioactivity varied with chlorine content ranging from 27% to ca. 100% at 2 weeks post-dose. Excretion profiles following dermal doses tended to differ from profiles following equivalent IV doses, as did the metabolite profiles in excreta. Skin slice incubation experiments suggested that first pass metabolism in the dermal dose site was responsible for metabolism and disposition differences between routes of administration. The data further suggest that the rate of absorption, and therefore the disposition of PCBs following dermal administration may be mediated, either in part or fully, by transdermal metabolism.

Garner, C. Edwin [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)]. E-mail: cegarner@rti.org; Demeter, Jennifer [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Matthews, H.B. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)

2006-10-01T23:59:59.000Z

399

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices  

SciTech Connect

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

NONE

1998-05-01T23:59:59.000Z

400

Summary - Preliminary TRA of the Calcine Disposition Project  

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

Calcine Calcine The Id materi Dec. 2 Press additiv form w those project anticip 2012 a CD-1 a selecte Level ( assess Eleme assign prepar The as below achiev * R * Ba * C The Ele Site: I roject: C Report Date: ited States Prelim Why DOE e HIP Treatment daho high-level al designated t 2009) to underg (HIP) process. ves, converts th with durability a of borosilicate t is currently in pates Critical D authorizing the approval, it is t ed technology (TRL) of 4 or h sment was to id ents (CTEs) of t n the TRLs that ration for CD-1 What th ssessment team along with the ved prior to CD etrieval//Pneum atching and Mi eramic Additive To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin daho Nationa Calcine Dispo February 201 Departmen minary T E-EM Did This t Process Flow D waste calcine through an am

Note: This page contains sample records for the topic "fissile materials disposition" 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

Fabrication of zircon for disposition of weapons plutonium  

SciTech Connect

This is the final report of a one-year, Laboratory-Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). In an effort to address the problems of long term storage and nuclear waste minimization, zircon has been proposed as a host medium for plutonium and other actinides recovered from dismantled nuclear weapons. The objective of this work is to investigate the feasibility of large scale fabrication of Pu-bearing zircon. Since PuO{sub 2} is thermodynamically less stable than ZrO{sub 2}, it is expected that the process parameters determined for synthesizing ZrSiO{sub 4} (zircon) would be applicable to those for PuSiO{sub 4} (Pu-zircon). Furthermore, since the foremost concern in plutonium processing is the potential for contamination release, this work emphasizes the development of process parameters, using zircon first, to anticipate potential material problems in the containment system for reaction mixtures during processing. Stoichiometric mixtures of ZrO{sub 2} and SiO{sub 2}, in hundred-gram batches, have been subjected to hot isostatic pressing (HIP) at temperatures near 1,500 C and pressures approximately 10,000 psi. The product materials have been analyzed by x-ray powder diffraction, and are found to consist of zircon after approximately two hours of reaction time. From this work, it is clear that the fabrication of large quantities of Pu-zircon is feasible. The most notable result of this work is evidence for the existence of container problems. This result, in turn, suggests potential solutions to these problems. Experiments with the quartz inner container, the glass sealant, a sacrificial metal barrier, and a metal outer container are being investigated to mitigate these potential hazards.

Kim, K.C.; Huang, J.Y.; Serrano, P.L. [and others

1997-07-01T23:59:59.000Z

402

SLUDGE TREATMENT PROJECT KOP DISPOSITION - THERMAL AND GAS ANALYSIS FOR THE COLD VACUUM DRYING FACILITY  

DOE Green Energy (OSTI)

The purpose of this document is to present conceptual design phase thermal process calculations that support the process design and process safety basis for the cold vacuum drying of K Basin KOP material. This document is intended to demonstrate that the conceptual approach: (1) Represents a workable process design that is suitable for development in preliminary design; and (2) Will support formal safety documentation to be prepared during the definitive design phase to establish an acceptable safety basis. The Sludge Treatment Project (STP) is responsible for the disposition of Knock Out Pot (KOP) sludge within the 105-K West (KW) Basin. KOP sludge consists of size segregated material (primarily canister particulate) from the fuel and scrap cleaning process used in the Spent Nuclear Fuel process at K Basin. The KOP sludge will be pre-treated to remove fines and some of the constituents containing chemically bound water, after which it is referred to as KOP material. The KOP material will then be loaded into a Multi-Canister Overpack (MCO), dried at the Cold Vacuum Drying Facility (CVDF) and stored in the Canister Storage Building (CSB). This process is patterned after the successful drying of 2100 metric tons of spent fuel, and uses the same facilities and much of the same equipment that was used for drying fuel and scrap. Table ES-l present similarities and differences between KOP material and fuel and between MCOs loaded with these materials. The potential content of bound water bearing constituents limits the mass ofKOP material in an MCO load to a fraction of that in an MCO containing fuel and scrap; however, the small particle size of the KOP material causes the surface area to be significantly higher. This relatively large reactive surface area represents an input to the KOP thermal calculations that is significantly different from the calculations for fuel MCOs. The conceptual design provides for a copper insert block that limits the volume available to receive KOP material, enhances heat conduction, and functions as a heat source and sink during drying operations. This use of the copper insert represents a significant change to the thermal model compared to that used for the fuel calculations. A number of cases were run representing a spectrum of normal and upset conditions for the drying process. Dozens of cases have been run on cold vacuum drying of fuel MCOs. Analysis of these previous calculations identified four cases that provide a solid basis for judgments on the behavior of MCO in drying operations. These four cases are: (1) Normal Process; (2) Degraded vacuum pumping; (3) Open MCO with loss of annulus water; and (4) Cool down after vacuum drying. The four cases were run for two sets of input parameters for KOP MCOs: (1) a set of parameters drawn from safety basis values from the technical data book and (2) a sensitivity set using parameters selected to evaluate the impact of lower void volume and smaller particle size on MCO behavior. Results of the calculations for the drying phase cases are shown in Table ES-2. Cases using data book safety basis values showed dry out in 9.7 hours and heat rejection sufficient to hold temperature rise to less than 25 C. Sensitivity cases which included unrealistically small particle sizes and corresponding high reactive surface area showed higher temperature increases that were limited by water consumption. In this document and in the attachment (Apthorpe, R. and M.G. Plys, 2010) cases using Technical Databook safety basis values are referred to as nominal cases. In future calculations such cases will be called safety basis cases. Also in these documents cases using parameters that are less favorable to acceptable performance than databook safety values are referred to as safety cases. In future calculations such cases will be called sensitivity cases or sensitivity evaluations Calculations to be performed in support of the detailed design and formal safety basis documentation will expand the calculations presented in this document to include: additional features of th

SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

2010-03-09T23:59:59.000Z

403

Responsible stewardship of nuclear materials  

SciTech Connect

The ability to tap the massive energy potential of nuclear fission was first developed as a weapon to end a terrible world war. Nuclear fission is also a virtually inexhaustible energy resource, and is the only energy supply in certain areas in Russia, Kazakhstan and elsewhere. The potential link between civilian and military applications has been and continues to be a source of concern. With the end of the Cold War, this issue has taken a dramatic turn. The U.S. and Russia have agreed to reduce their nuclear weapons stockpiles by as much as two-thirds. This will make some 100 tonnes of separated plutonium and 500 tonnes of highly enriched uranium available, in a form that is obviously directly usable for weapons. The total world inventory of plutonium is now around 1000 tonnes and is increasing at 60-70 tonnes per year. There is even more highly enriched uranium. Fortunately the correct answer to what to do with excess weapons material is also the most attractive. It should be used and reused as fuel for fast reactors. Material in use (particularly nuclear material) is very easy to monitor and control, and is quite unattractive for diversion. Active management of fissile materials not only makes a major contribution to economic stability and well-being, but also simplifies accountability, inspection and other safeguards processes; provides a revenue stream to pay for the necessary safeguards; and, most importantly, limits the prospective world inventory of plutonium to only that which is used and useful.

Hannum, W.H.

1994-10-01T23:59:59.000Z

404

Disposition of Nuclear Waste Using Subcritical Accelerator-Driven Systems  

SciTech Connect

ATW destroys virtually all the plutonium and higher actinides without reprocessing the spent fuel in a way that could lead to weapons material diversion. An ATW facility consists of three major elements: (1) a high-power proton linear accelerator; (2) a pyrochemical spent fuel treatment i waste cleanup system; (3) a liquid lead-bismuth cooled burner that produces and utilizes an intense source-driven neutron flux for transmutation in a heterogeneous (solid fuel) core. The concept is the result of many years of development at LANL as well as other major international research centers. Once demonstrated and developed, ATW could be an essential part of a global non-proliferation strategy for countries that could build up large quantities of plutonium from their commercial reactor waste. ATW technology, initially proposed in the US, has received wide and rapidly increasing attention abroad, especially in Europe and the Far East with major programs now being planned, organized and tided. Substantial convergence presently exists on the technology choices among the programs, opening the possibility of a strong and effective international collaboration on the phased development of the ATW technology.

Doolen, G.D.; Venneri, F.; Li, N.; Williamson, M.A.; Houts, M.; Lawrence, G.

1998-06-27T23:59:59.000Z

405

Assessment of Facilities, Materials, and Wastes Proposed for Transfer to EM  

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

Non-Integrated Facilities Disposition Non-Integrated Facilities Disposition Project Technical Assistance Page 1 of 2 Complex-Wide Multi-State Assessment of Facilities, Materials, and Wastes Proposed for Transfer 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). Transfers of facilities, materials, and waste to EM will generate liabilities that are currently unfunded. For purposes of overall planning, it is important to understand the impacts of proposed transfers with regard to technical

406

Supply and Disposition of Crude Oil and Petroleum Products  

Gasoline and Diesel Fuel Update (EIA)

10,433 1,047 18,983 9,592 488 -617 17,890 3,998 19,273 10,433 1,047 18,983 9,592 488 -617 17,890 3,998 19,273 PADD 1 130 25 3,403 1,515 3,374 230 -269 3,374 264 5,307 PADD 2 1,993 892 4,464 2,094 500 -317 -225 4,240 386 5,224 PADD 3 6,249 96 7,346 4,283 -3,758 511 -211 6,723 2,976 5,239 PADD 4 887 14 643 287 -425 -18 51 615 10 713 PADD 5 1,174 20 3,127 1,413 310 82 36 2,939 362 2,789 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Imports at the PAD District level represent the PAD District in which the material entered the U.S. and not necessarily where the crude oil or product is processed and/or consumed. PAD District level net receipts includes implied net receipts for fuel ethanol and oxygenates (excluding fuel ethanol). Implied net receipts are calculated as the sum of stock change, refinery and blender net inputs, and exports minus the sum of renewable fuels and oxygenate plant net production, imports, and adjustments. Adjustments include an adjustment for crude oil, previously referred to as Unaccounted For Crude Oil. Also included is an adjustment for motor gasoline blending components, fuel ethanol, and distillate fuel oil. A negative stock change indicates a decrease in stocks and a positive number indicates an increase in stocks. Total stocks do not include distillate fuel oil stocks located in the Northeast Heating Oil Reserve. Total residual fuel oil stocks include stocks held at pipelines. Residual fuel oil stocks by sulfur content exclude pipeline stocks. Therefore, the sum of residual fuel oil stocks by sulfur content may not equal total residual fuel oil stocks. Exports of distillate fuel oil with sulfur greater than 15 ppm to 500 ppm may include distillate fuel oil with sulfur content 15 ppm and under due to product detail limitations in exports data received from the U.S. Census Bureau. LRG = Liquefied Refinery Gas. Data may not add to total due to independent rounding. See Definitions, Sources, and Notes link above for more information on this table.

407

Supply and Disposition of Crude Oil and Petroleum Products  

Gasoline and Diesel Fuel Update (EIA)

23,431 32,462 588,466 297,359 15,122 -19,137 554,586 123,943 23,431 32,462 588,466 297,359 15,122 -19,137 554,586 123,943 597,448 1,812,484 PADD 1 4,022 783 105,480 46,972 104,579 7,133 -8,328 104,584 8,184 164,527 145,574 PADD 2 61,781 27,645 138,371 64,904 15,509 -9,838 -6,968 131,427 11,955 161,957 273,603 PADD 3 193,724 2,967 227,728 132,784 -116,513 15,829 -6,533 208,398 92,256 162,398 1,211,066 PADD 4 27,499 433 19,935 8,906 -13,181 -544 1,567 19,066 310 22,105 38,275 PADD 5 36,406 635 96,952 43,793 9,606 2,542 1,124 91,111 11,237 86,461 143,965 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Imports at the PAD District level represent the PAD District in which the material entered the U.S. and not necessarily where the crude oil or product is processed and/or consumed. PAD District level net receipts includes implied net receipts for fuel ethanol and oxygenates (excluding fuel ethanol). Implied net receipts are calculated as the sum of stock change, refinery and blender net inputs, and exports minus the sum of renewable fuels and oxygenate plant net production, imports, and adjustments. Adjustments include an adjustment for crude oil, previously referred to as Unaccounted For Crude Oil. Also included is an adjustment for motor gasoline blending components, fuel ethanol, and distillate fuel oil. A negative stock change indicates a decrease in stocks and a positive number indicates an increase in stocks. Total stocks do not include distillate fuel oil stocks located in the Northeast Heating Oil Reserve. Total residual fuel oil stocks include stocks held at pipelines. Residual fuel oil stocks by sulfur content exclude pipeline stocks. Therefore, the sum of residual fuel oil stocks by sulfur content may not equal total residual fuel oil stocks. Exports of distillate fuel oil with sulfur greater than 15 ppm to 500 ppm may include distillate fuel oil with sulfur content 15 ppm and under due to product detail limitations in exports data received from the U.S. Census Bureau. LRG = Liquefied Refinery Gas. Data may not add to total due to independent rounding. See Definitions, Sources, and Notes link above for more information on this table.

408

Page not found | Department of Energy  

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

21 - 17530 of 28,560 results. 21 - 17530 of 28,560 results. Page EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials 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. http://energy.gov/nepa/eis-0229-storage-and-disposition-weapons-usable-fissile-materials Download Letter of Direction to Contractor The Department of Energy has issued a revised Disposal Authorization Statement (DAS) for the Savannah River Site Saltstone Disposal Facility (SDF), and authorizes the required start-up testing... http://energy.gov/em/downloads/letter-direction-contractor Download Terms and Conditions for EM Clean Up to the Office of Science This document outlines the terms and conditions for managing and funding

409

HEU to LEU Conversion and Blending Facility: UNH blending alternative to produce LEU UNH for commercial use  

SciTech Connect

US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. The nuclear material is converted to a form that is more proliferation-resistant than the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. Five technologies for blending HEU will be assessed. This document provides data to be used in the environmental impact analysis for the UNH blending HEU disposition option. Process requirements, resource needs, employment needs, waste/emissions from plant, hazards, accident scenarios, and intersite transportation are discussed.

1995-09-01T23:59:59.000Z

410

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

SciTech Connect

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

411

Disposition of excess weapon plutonium in deep boreholes - site selection handbook  

Science Conference Proceedings (OSTI)

One of the options for disposing of excess weapons plutonium is to place it near the base of deep boreholes in stable crystalline rocks. The technology needed to begin designing this means of disposition already exists, and there are many attractive sites available within the conterminous United States. There are even more potential sites for this option within Russia. The successful design of a borehole system must address two criteria: (1) how to dispose of 50 metric tons of weapons plutonium while making it inaccessible for unauthorized retrieval, and (2) how to prevent contamination of the accessible biosphere, defined here as the Earth`s surface and usable groundwaters.

Heiken, G.; Woldegabriel, G.; Morley, R.; Plannerer, H.; Rowley, J.

1996-09-01T23:59:59.000Z

412

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

SciTech Connect

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 the preferred option 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 in the late 1990's. 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. Recent FY05 studies have further investigated the LaBS Frit B formulation as well as development of a newer LaBS formulation denoted as LaBS Frit X. The objectives of this present task were to fabricate plutonium loaded LaBS Frit X glass and perform corrosion 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 X 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). The glass was thoroughly 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 using quenched Pu Frit X glass with varying exposed surface areas. Effects of isothermal and can-in-canister heat treatments on the Pu Frit X glass were also investigated. Another series of PCTs were performed on these different heat-treated Pu Frit X glasses. Leachates from all these PCTs 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.

Marra, J

2006-11-15T23:59:59.000Z

413

Age identity, gender, and perceptions of decline: Does feeling older lead to pessimistic dispositions about cognitive aging  

E-Print Network (OSTI)

Objectives. Drawing on past studies of age identity, this article examined whether feeling older was associated with more pessimistic views about cognitive aging. Methods. Using respondents aged 55 years and older in the Midlife Development in the United States study, we estimated a series of linear regression models to predict people í s dispositions toward their cognitive aging. The main comparison is whether the effects of age identity on cognitive aging differ for men and women. Results. Beyond the effects of chronological age, older age identities were associated with more pessimistic dispositions about cognitive aging. This relationship, however, was found only among women. Discussion. Age identity shapes cognitive aging dispositions, though the gendered nature of this relationship remains somewhat unclear. The findings give further evidence about the far-reaching implications of age identity for successful aging and suggest that future work can explicate how subjective aging processes may differ by gender.

Markus H. Schafer

2010-01-01T23:59:59.000Z

414

Neutron Correlations in Special Nuclear Materials, Experiments and Simulations  

SciTech Connect

Fissile materials emit neutrons with an unmistakable signature that can reveal characteristics of the material. We describe here measurements, simulations, and predicted signals expected and prospects for application of neutron correlation measurement methods to detection of special nuclear materials (SNM). The occurrence of fission chains in SNM can give rise to this distinctive, measurable time correlation signal. The neutron signals can be analyzed to detect the presence and to infer attributes of the SNM and surrounding materials. For instance, it is possible to infer attributes of an assembly containing a few kilograms of uranium, purely passively, using detectors of modest size in a reasonable time. Neutron signals of three radioactive sources are shown to illustrate the neutron correlation and analysis method. Measurements are compared with Monte Carlo calculations of the authenticated sources.

Verbeke, J; Dougan, A; Nakae, L; Sale, K; Snyderman, N

2007-06-05T23:59:59.000Z

415

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1: Technical standard  

Science Conference Proceedings (OSTI)

This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities.

NONE

1998-05-01T23:59:59.000Z

416

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

Science Conference Proceedings (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

417

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

SciTech Connect

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

NONE

1996-09-01T23:59:59.000Z

418

Toward the Framework and Implementation for Clearance of Materials from Regulated Facilities  

SciTech Connect

The disposition of solid materials from nuclear facilities has been a subject of public debate for several decades. The primary concern has been the potential health effects resulting from exposure to residual radioactive materials to be released for unrestricted use. These debates have intensified in the last decade as many regulated facilities are seeking viable management decisions on the disposition of the large amounts of materials potentially containing very low levels of residual radioactivity. Such facilities include the nuclear weapons complex sites managed by the U.S. Department of Energy (DOE), commercial power plants licensed by the U.S. Nuclear Regulatory Commission (NRC), and other materials licensees regulated by the NRC or the Agreement States. Other facilities that generate radioactive material containing naturally occurring radioactive materials (NORM) or technologically enhanced NORM (TENORM) are also seeking to dispose of similar materials that may be radioactively contaminated. In contrast to the facilities operated by the DOE and the nuclear power plants licensed by the NRC, NORM and TENORM facilities are regulated by the individual states. Current federal laws and regulations do not specify criteria for releasing these materials that may contain residual radioactivity of either man-made or natural origin from regulatory controls. In fact, the current regulatory scheme offers no explicit provision as to permit materials being released as ''non-radioactive'', including those that are essentially free of contamination. The only method used to date with limited success has been case-by-case evaluation and approval. In addition, there is a poorly defined and inconsistent regulatory framework for regulating NORM and TENORM. Some years ago, the International Atomic Energy Agency (IAEA) introduced the concept of clearance, that is, controlling releases of any such materials within the regulatory domain. This paper aims to clarify clearance as an important disposition option for solid materials, establish the framework and basis of release, and discuss resolutions regarding the implementation of such a disposition option.

Chen, Shih-Yew; Moeller, Dade W.; Dornsife, William P.; Meyer, H Robert; Lamastra, Anthony; Lubenau, Joel O.; Strom, Daniel J.; Yusko, James G.

2005-08-01T23:59:59.000Z

419

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

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

420

Assessment of Facilities, Materials, and Wastes Proposed for Transfer to EM  

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

Facilities, Materials, and Wastes Proposed for Facilities, Materials, and Wastes Proposed for Transfer to EM Assessment of Facilities, Materials, and Wastes Proposed for Transfer 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 Facilities, Materials, and Wastes Proposed for Transfer to EM More Documents & Publications Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

Note: This page contains sample records for the topic "fissile materials disposition" 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

Apparatus and method for quantitative assay of samples of transuranic waste contained in barrels in the presence of matrix material  

DOE Patents (OSTI)

Apparatus and method for performing corrections for matrix material effects on the neutron measurements generated from analysis of transuranic waste drums using the differential-dieaway technique. By measuring the absorption index and the moderator index for a particular drum, correction factors can be determined for the effects of matrix materials on the ''observed'' quantity of fissile and fertile material present therein in order to determine the actual assays thereof. A barrel flux monitor is introduced into the measurement chamber to accomplish these measurements as a new contribution to the differential-dieaway technology. 9 figs.

Caldwell, J.T.; Herrera, G.C.; Hastings, R.D.; Shunk, E.R.; Kunz, W.E.

1987-08-28T23:59:59.000Z

422

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

NLE Websites -- All DOE Office Websites (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

423

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

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

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

424

A Little Here, A Little There, A Fairly Big Problem Everywhere: Small Quantity Site Transuranic Waste Disposition Alternatives  

Science Conference Proceedings (OSTI)

Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National Laboratory (LANL), Oak Ridge (OR), and Hanford. At least 14 additional DOE sites having TRU waste may be able to save significant money if cost savings are similar to the four evaluated thus far.

Luke, Dale Elden; Parker, Douglas Wayne; Moss, J.; Monk, Thomas Hugh; Fritz, Lori Lee; Daugherty, B.; Hladek, K.; Kosiewicx, S.

2000-03-01T23:59:59.000Z

425

A little here, a little there, a fairly big problem everywhere: Small quantity site transuranic waste disposition alternatives  

Science Conference Proceedings (OSTI)

Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound Laboratory. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National Laboratory (LANL), Oak Ridge (OR), and Hanford. At least 14 additional DOE sites having TRU waste may be able to save significant money if cost savings are similar to the four evaluated thus far.

D. Luke; D. Parker; J. Moss; T. Monk (INEEL); L. Fritz (DOE-ID); B. Daugherty (SRS); K. Hladek (WM Federal Services Hanford); S. Kosiewicx (LANL)

2000-02-27T23:59:59.000Z

426

Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control  

SciTech Connect

The US investigated the use of {sup 233}U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use {sup 233}U on a large scale. Most of the {sup 233}U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some {sup 233}U-containing materials. Because of these changes, significant activities associated with {sup 233}U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for defining when {sup 233}U-containing materials can be managed as waste and when they must be managed as concentrated fissile materials has been developed. The requirements for storage, transport, and disposal of radioactive wastes are significantly different than those for fissile materials. Because of these differences, it is important to classify material in its appropriate category. The establishment of a definition of what is waste and what is fissile material will provide the guidance for appropriate management of these materials. Wastes are defined in this report as materials containing sufficiently small masses or low concentrations of fissile materials such that they can be managed as typical radioactive waste. Concentrated fissile materials are defined herein as materials containing sufficient fissile content such as to warrant special handling to address nuclear criticality, safeguards, and arms control concerns.

Forsberg, C.W.; Storch, S.N. [Oak Ridge National Lab., TN (United States); Lewis, L.C. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

1998-07-07T23:59:59.000Z

427

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

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

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

428

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

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

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.

429

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

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

¬ĶCi/cc microcuries per cubic centimeter ¬ĶCi/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

430

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

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

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

431

Used Fuel Disposition Campaign Phase I Ring Compression Testing of High  

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

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¬ģ 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.

432

Microsoft PowerPoint - S08-05_Leishear_Salt Disposition Initiative.ppt  

NLE Websites -- All DOE Office Websites (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-

433

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

Science Conference Proceedings (OSTI)

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

Wike, L.D.

2000-08-17T23:59:59.000Z

434

GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSHILICATE FRIT X COMPOSITION FOR PLUTONIUM DISPOSITION  

SciTech Connect

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 the preferred option 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 in the late 1990's. 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. Recent FY05 studies have further investigated the LaBS Frit B formulation as well as development of a newer LaBS formulation denoted as LaBS Frit X. The objectives of this present task were to fabricate plutonium loaded LaBS Frit X glass and perform corrosion 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 X 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). The glass was thoroughly 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 using quenched Pu Frit X glass with varying exposed surface areas. Effects of isothermal and can-in-canister heat treatments on the Pu Frit X glass were also investigated. Another series of PCTs were performed on these different heat-treated Pu Frit X glasses. Leachates from all these PCTs 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. Characterization of the quenched Pu Frit X glass prior to testing revealed that some crystalline plutonium oxide was present in the glass. The crystalline particles had a disklike morphology and likely formed via coarsening of particles in areas compositionally enriched in plutonium. Similar results had also been observed in previous Pu Frit B studies. Isothermal 1250 C heat-treated Pu Frit X glasses showed two different crystalline phases (PuO{sub 2} and Nd{sub 2}Hf{sub 2}O{sub 7}), as well as a peak shift in the XRD spectra that is likely due to a solid solution phase PuO{sub 2}-HfO{sub 2} formation. Micrographs of this glass showed a clustering of some of the crystalline phases. Pu Frit X glass subjected to the can-in-canister heating profile also displayed the two PuO{sub 2} and Nd{sub 2}Hf{sub 2}O{sub 7} phases from XRD analysis. Additional micrographs indicate crystalline phases in this glass were of varying forms (a spherical PuO{sub 2} phase that appeared to range in size from submicron to {approx}5 micron, a dendritic-type phase that was comprised of mixed lanthanides and plutonium, and a minor phase that contained Pu and Hf), and clustering of the phases was also observed.

Marra, J

2006-11-21T23:59:59.000Z

435

Development of a Weldable Neutron Absorbing Structural Material  

Science Conference Proceedings (OSTI)

The National Spent Nuclear Fuel Program, located at the Idaho National Laboratory, coordinates and integrates national efforts in management and disposal of U.S. Department of Energy (DOE)-owned spent nuclear fuel. These management functions include development of standardized systems for packaging, storage, treatment, transport, and long-term disposal in the proposed Yucca Mountain Repository. Nuclear criticality control measures are needed in these systems to avoid restrictive fissile loading limits because of the enrichment and total quantity of fissile material in some types of the DOE spent nuclear fuel. This paper will outline the results to date of a metallurgical development program that is investigating the alloying of gadolinium into a nickel-chromium-molybdenum alloy matrix. Gadolinium has been chosen as the neutron absorption alloying element due to its high thermal neutron absorption cross section and low solubility in the expected repository environment. The nickel-chromium-molybdenum alloy family was chosen for its known corrosion performance, mechanical properties, and weldability. The workflow of this program includes chemical composition definition, primary melting and secondary refining studies, ingot conversion process evaluations, mechanical/physical properties and corrosion testing, welding studies, and national consensus codes, and standards work.

R. E. Mizia; W. L. Hurt; C. V. Robino; J. N. DuPont

2006-04-01T23:59:59.000Z

436

Nuclear Materials Identification System (NMIS) with Gamma Spectrometry for Attributes of Pu, HEU, and Detection of HE and Chemical Agents  

SciTech Connect

A combined Nuclear Materials Identification System (NMIS)-gamma ray spectrometry system can be used passively to obtain the following attributes of Pu: presence, fissile mass, 240/239 ratio, and metal vs. oxide. This system can also be used with a small, portable, DT neutron generator to measure the attributes of highly enriched uranium (HEU): presence, fissile mass, enrichment, metal vs. oxide; and detect the presence of high explosives (HE). For the passive system, time-dependent coincidence distributions can be used for the presence, fissile mass, metal vs. oxide for Pu, and gamma-ray spectrometry can be used for 239/240 ratio and presence. So presence can be confirmed by two methods. For the active system with a DT neutron generator, all four attributes for both Pu and HEU can be determined from various features of the time-dependent coincidence distribution measurements for both Pu and HEU. Active gamma ray spectrometry would also give presence and 240/239 ratio for Pu, enrichment for HEU, and metal vs. oxide for both. Active gamma ray spectrometry would determine the presence of HE. The various features of time-dependent coincidence distributions and gamma ray spectrometry that determine these attributes are discussed with some examples from previous determinations.

Mihalczo, J. T.; Mattingly, J. K.; Mullens, J. A.; Neal, J. S.

2002-05-01T23:59:59.000Z

437

Materials Science  

Science Conference Proceedings (OSTI)

Materials Science. Summary: ... Description: Group focus in materials science (inkjet metrology, micro-macro, advanced characterizations). ...

2012-10-02T23:59:59.000Z