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1

Advanced LWR Nuclear Fuel Development  

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

- Radiation (Part I) - Alkali-AggregateSilica Reaction (Part II) - Creepcreep-fracture interaction (Roadmap to be developed) Part I- Irradiated Concrete Research results...

2

Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development  

SciTech Connect

The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

Jon Carmack

2014-01-01T23:59:59.000Z

3

Advanced nuclear fuel  

SciTech Connect

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-14T23:59:59.000Z

4

Advanced nuclear fuel  

ScienceCinema (OSTI)

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-15T23:59:59.000Z

5

Development of a nuclear fuel cycle transparency framework.  

SciTech Connect

Nuclear fuel cycle transparency can be defined as a confidence building approach among political entities to ensure civilian nuclear facilities are not being used for the development of nuclear weapons. Transparency concepts facilitate the transfer of nuclear technology, as the current international political climate indicates a need for increased methods of assuring non-proliferation. This research develops a system which will augment current non-proliferation assessment activities undertaken by U.S. and international regulatory agencies. It will support the export of nuclear technologies, as well as the design and construction of Gen. IV energy systems. Additionally, the framework developed by this research will provide feedback to cooperating parties, thus ensuring full transparency of a nuclear fuel cycle. As fuel handling activities become increasingly automated, proliferation or diversion potential of nuclear material still needs to be assessed. However, with increased automation, there exists a vast amount of process data to be monitored. By designing a system that monitors process data continuously, and compares this data to declared process information and plant designs, a faster and more efficient assessment of proliferation risk can be made. Figure 1 provides an illustration of the transparency framework that has been developed. As shown in the figure, real-time process data is collected at the fuel cycle facility; a reactor, a fabrication plant, or a recycle facility, etc. Data is sent to the monitoring organization and is assessed for proliferation risk. Analysis and recommendations are made to cooperating parties, and feedback is provided to the facility. The analysis of proliferation risk is based on the following factors: (1) Material attractiveness: the quantification of factors relevant to the proliferation risk of a certain material (e.g., highly enriched Pu-239 is more attractive than that of lower enrichment) (2) The static (baseline) risk: the quantification of risk factors regarding the expected value of proliferation risk under normal (not proliferating) operations. (3) The dynamic (changing) risk: the quantification of risk factors regarding the observed value of proliferation risk, based on monitor signals from facility operations. This framework could be implemented at facilities which have been exported (for instance, to third world countries), or facilities located in sensitive countries. Sandia National Laboratories is currently working with the Japan Nuclear Cycle Development Institute (JNC) to implement a demonstration of nuclear fuel cycle transparency technology at the Fuel Handling Training Model designed for the Monju Fast Reactor at the International Cooperation and Development Training Center in Japan. This technology has broad applications, both in the U.S. and abroad. Following the demonstration, we expect to begin further testing of the technology at an Enrichment Facility, a Fast Reactor, and at a Recycle Facility.

Love, Tracia L.

2005-04-01T23:59:59.000Z

6

Interim report spent nuclear fuel retrieval system fuel handling development testing  

SciTech Connect

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

1997-06-01T23:59:59.000Z

7

Nuclear Fuels  

Science Journals Connector (OSTI)

The core of a nuclear reactor is composed of a controlled critical configuration of a fissile material, which in strict a sense is the fuel. This fissile material is contained in a matrix, normally a ceramic c...

Rudy J. M. Konings; Thierry Wiss…

2011-01-01T23:59:59.000Z

8

Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study  

SciTech Connect

The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R&D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental improvements are required in the areas of nuclear fuel composition, cladding integrity, and the fuel/cladding interaction to allow power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an “accident tolerant” fuel system that would offer improved coping time under accident scenarios. With a development time of about 20 – 25 years, advanced fuel designs must be started today and proven in current reactors if future reactor designs are to be able to use them with confidence.

Kristine Barrett; Shannon Bragg-Sitton

2012-09-01T23:59:59.000Z

9

Methods and apparatuses for the development of microstructured nuclear fuels  

DOE Patents (OSTI)

Microstructured nuclear fuel adapted for nuclear power system use includes fissile material structures of micrometer-scale dimension dispersed in a matrix material. In one method of production, fissile material particles are processed in a chemical vapor deposition (CVD) fluidized-bed reactor including a gas inlet for providing controlled gas flow into a particle coating chamber, a lower bed hot zone region to contain powder, and an upper bed region to enable powder expansion. At least one pneumatic or electric vibrator is operationally coupled to the particle coating chamber for causing vibration of the particle coater to promote uniform powder coating within the particle coater during fuel processing. An exhaust associated with the particle coating chamber and can provide a port for placement and removal of particles and powder. During use of the fuel in a nuclear power reactor, fission products escape from the fissile material structures and come to rest in the matrix material. After a period of use in a nuclear power reactor and subsequent cooling, separation of the fissile material from the matrix containing the embedded fission products will provide an efficient partitioning of the bulk of the fissile material from the fission products. The fissile material can be reused by incorporating it into new microstructured fuel. The fission products and matrix material can be incorporated into a waste form for disposal or processed to separate valuable components from the fission products mixture.

Jarvinen, Gordon D. (Los Alamos, NM); Carroll, David W. (Los Alamos, NM); Devlin, David J. (Santa Fe, NM)

2009-04-21T23:59:59.000Z

10

Advanced LWR Nuclear Fuel Cladding System Development Trade-off Study |  

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

LWR Nuclear Fuel Cladding System Development Trade-off LWR Nuclear Fuel Cladding System Development Trade-off Study Advanced LWR Nuclear Fuel Cladding System Development Trade-off Study The LWR Sustainability (LWRS) Program activities must support the timeline dictated by utility life extension decisions to demonstrate a lead test rod in a commercial reactor within 10 years. In order to maintain the demanding development schedule that must accompany this aggressive timeline, the LWRS Program focuses on advanced fuel cladding systems that retain standard UO2 fuel pellets for deployment in currently operating LWR power plants. The LWRS work scope focuses on fuel system components outside of the fuel pellet, allowing for alteration of the existing zirconium-based clad system through coatings, addition of ceramic sleeves, or complete replacement

11

Nuclear Fuels | Department of Energy  

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

Nuclear Fuels Nuclear Fuels Nuclear Fuels A reactor's ability to produce power efficiently is significantly affected by the composition and configuration of its fuel system. A nuclear fuel assembly consists of hundreds of thousands of uranium pellets, stacked and encapsulated within tubes called fuel rods or fuel pins which are then bundled together in various geometric arrangements. There are many design considerations for the material composition and geometric configuration of the various components comprising a nuclear fuel system. Future designs for the fuel and the assembly or packaging of fuel will contribute to cleaner, cheaper and safer nuclear energy. Today's process for developing and testing new fuel systems is resource and time intensive. The process to manufacture the fuel, build an assembly,

12

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

SciTech Connect

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

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

1997-11-01T23:59:59.000Z

13

Development of monolithic nuclear fuels for RERTR by hot isostatic pressing  

SciTech Connect

The RERTR Program (Reduced Enrichment for Research and Test Reactors) is developing advanced nuclear fuels for high power test reactors. Monolithic fuel design provides a higher uranium loading than that of the traditional dispersion fuel design. In order to bond monolithic fuel meat to aluminum cladding, several bonding methods such as roll bonding, friction stir bonding and hot isostatic pressing, have been explored. Hot isostatic pressing is a promising process for low cost, batch fabrication of monolithic RERTR fuel plates. The progress on the development of this process at the Idaho National Laboratory will be presented. Due to the relatively high processing temperature used, the reaction between fuel meat and aluminum cladding to form brittle intermetallic phases may be a concern. The effect of processing temperature and time on the fuel/cladding reaction will be addressed. The influence of chemical composition on the reaction will also be discussed. (author)

Jue, J.-F.; Park, Blair; Chapple, Michael; Moore, Glenn; Keiser, Dennis [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 (United States)

2008-07-15T23:59:59.000Z

14

Nuclear Reactor Materials and Fuels  

Science Journals Connector (OSTI)

Nuclear reactor materials and fuels can be classified into six categories: Nuclear fuel materials Nuclear clad materials Nuclear coolant materials Nuclear poison materials Nuclear moderator materials

Dr. James S. Tulenko

2012-01-01T23:59:59.000Z

15

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

SciTech Connect

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

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

1998-02-01T23:59:59.000Z

16

Spent Nuclear Fuel Fact Sheets  

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

management needs. By coordinating common needs for research, technology development, and testing programs, the National Spent Nuclear Fuel Program is achieving cost efficiencies...

17

Concept of development of nuclear power based on LMFBR operation in open nuclear fuel cycle  

SciTech Connect

The preliminary assessments performed show that it is reasonable to investigate in the future the possibilities of FBR efficient operation with the open NFC. To improve its safety it is expedient to use the lead-bismuth alloy as a coolant. In order to operate with depleted uranium make-up it is necessary to meet a number of requirements providing the reactor criticality due to plutonium build-up and BR > 1. These requirements are as follows: a large core (20--25 m{sup 3}); a high fuel volume fraction (> 60%); utilization of dense metallic fuel; a high fuel burn-up--at a level of 20% of h.a. Making use of these reactors should allow the NP fuel base to be extended more than 10 times without making NFC closed. It provides improving NP safety during a sufficiently long stage of its development.

Toshinsky, G.I. [Inst. of Physics and Power Engineering, Obninsk (Russian Federation)

1996-08-01T23:59:59.000Z

18

U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel Development  

SciTech Connect

A significant effort is being placed on silicon carbide ceramic matrix composite (SiC CMC) nuclear fuel cladding by Light Water Reactor Sustainability (LWRS) Advanced Light Water Reactor Nuclear Fuels Pathway. The intent of this work is to invest in a high-risk, high-reward technology that can be introduced in a relatively short time. The LWRS goal is to demonstrate successful advanced fuels technology that suitable for commercial development to support nuclear relicensing. Ceramic matrix composites are an established non-nuclear technology that utilizes ceramic fibers embedded in a ceramic matrix. A thin interfacial layer between the fibers and the matrix allows for ductile behavior. The SiC CMC has relatively high strength at high reactor accident temperatures when compared to metallic cladding. SiC also has a very low chemical reactivity and doesn't react exothermically with the reactor cooling water. The radiation behavior of SiC has also been studied extensively as structural fusion system components. The SiC CMC technology is in the early stages of development and will need to mature before confidence in the developed designs can created. The advanced SiC CMC materials do offer the potential for greatly improved safety because of their high temperature strength, chemical stability and reduced hydrogen generation.

George W. Griffith

2011-10-01T23:59:59.000Z

19

6 Nuclear Fuel Designs  

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

Message from the Director Message from the Director 2 Nuclear Power & Researrh Reactors 3 Discovery of Promethium 4 Nuclear Isotopes 4 Nuclear Medicine 5 Nuclear Fuel Processes & Software 6 Nuclear Fuel Designs 6 Nuclear Safety 7 Nuclear Desalination 7 Nuclear Nonproliferation 8 Neutron Scattering 9 Semiconductors & Superconductors 10 lon-Implanted Joints 10 Environmental Impact Analyses 11 Environmental Quality 12 Space Exploration 12 Graphite & Carbon Products 13 Advanced Materials: Alloys 14 Advanced Materials: Ceramics 15 Biological Systems 16 Biological Systems 17 Computational Biology 18 Biomedical Technologies 19 Intelligent Machines 20 Health Physics & Radiation Dosimetry 21 Radiation Shielding 21 Information Centers 22 Energy Efficiency: Cooling & Heating

20

Department of Energy Awards $15 Million for Nuclear Fuel Cycle...  

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

Million for Nuclear Fuel Cycle Technology Research and Development Department of Energy Awards 15 Million for Nuclear Fuel Cycle Technology Research and Development August 1,...

Note: This page contains sample records for the topic "development nuclear fuels" 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

Nuclear fuels technologies fiscal year 1998 research and development test plan  

SciTech Connect

A number of research and development (R and D) activities are planned at Los Alamos National Laboratory (LANL) in FY98 in support of the Department of Energy Office of Fissile Materials Disposition (DOE-MD). During the past few years, the ability to fabricate mixed oxide (MOX) nuclear fuel using surplus-weapons plutonium has been researched, and various experiments have been performed. This research effort will be continued in FY98 to support further development of the technology required for MOX fuel fabrication for reactor-based plutonium disposition. R and D activities for FY98 have been divided into four major areas: (1) feed qualification/supply, (2) fuel fabrication development, (3) analytical methods development, and (4) gallium removal. Feed qualification and supply activities encompass those associated with the production of both PuO{sub 2} and UO{sub 2} feed materials. Fuel fabrication development efforts include studies with a new UO{sub 2} feed material, alternate sources of PuO{sub 2}, and determining the effects of gallium on the sintering process. The intent of analytical methods development is to upgrade and improve several analytical measurement techniques in support of other R and D and test fuel fabrication tasks. Finally, the purpose of the gallium removal system activity is to develop and integrate a gallium removal system into the Pit Disassembly and Conversion Facility (PDCF) design and the Phase 2 Advanced Recovery and Integrated Extraction System (ARIES) demonstration line. These four activities will be coordinated and integrated appropriately so that they benefit the Fissile Materials Disposition Program. This plan describes the activities that will occur in FY98 and presents the schedule and milestones for these activities.

Alberstein, D.; Blair, H.T.; Buksa, J.J. [and others

1998-06-01T23:59:59.000Z

22

On the Development of a Distillation Process for the Electrometallurgical Treatment of Irradiated Spent Nuclear Fuel  

SciTech Connect

As part of the spent fuel treatment program at the Idaho National Laboratory, a vacuum distillation process is being employed for the recovery of actinide products following an electrorefining process. Separation of the actinide products from a molten salt electrolyte and cadmium is achieved by a batch operation called cathode processing. A cathode processor has been designed and developed to efficiently remove the process chemicals and consolidate the actinide products for further processing. This paper describes the fundamentals of cathode processing, the evolution of the equipment design, the operation and efficiency of the equipment, and recent developments at the cathode processor. In addition, challenges encountered during the processing of irradiated spent nuclear fuel in the cathode processor will be discussed.

B.R. Westphal; K.C. Marsden; J.C. Price; D.V. Laug

2008-04-01T23:59:59.000Z

23

Development of Real-Time Fuel Management Capability at the Texas A&M Nuclear Science Center  

E-Print Network (OSTI)

For the Texas A&M University Nuclear Science Center reactor a fuel depletion code was created to develop real-time fuel management capability. This code package links MCNP8 and ORIGEN26 and is interfaced through a Visual Basic code. Microsoft Visual...

Parham, Neil A.

2010-07-14T23:59:59.000Z

24

DEVELOPMENT OF METHODOLOGY AND FIELD DEPLOYABLE SAMPLING TOOLS FOR SPENT NUCLEAR FUEL INTERROGATION IN LIQUID STORAGE  

SciTech Connect

This project developed methodology and field deployable tools (test kits) to analyze the chemical and microbiological condition of the fuel storage medium and determine the oxide thickness on the spent fuel basin materials. The overall objective of this project was to determine the amount of time fuel has spent in a storage basin to determine if the operation of the reactor and storage basin is consistent with safeguard declarations or expectations. This project developed and validated forensic tools that can be used to predict the age and condition of spent nuclear fuels stored in liquid basins based on key physical, chemical and microbiological basin characteristics. Key parameters were identified based on a literature review, the parameters were used to design test cells for corrosion analyses, tools were purchased to analyze the key parameters, and these were used to characterize an active spent fuel basin, the Savannah River Site (SRS) L-Area basin. The key parameters identified in the literature review included chloride concentration, conductivity, and total organic carbon level. Focus was also placed on aluminum based cladding because of their application to weapons production. The literature review was helpful in identifying important parameters, but relationships between these parameters and corrosion rates were not available. Bench scale test systems were designed, operated, harvested, and analyzed to determine corrosion relationships between water parameters and water conditions, chemistry and microbiological conditions. The data from the bench scale system indicated that corrosion rates were dependent on total organic carbon levels and chloride concentrations. The highest corrosion rates were observed in test cells amended with sediment, a large microbial inoculum and an organic carbon source. A complete characterization test kit was field tested to characterize the SRS L-Area spent fuel basin. The sampling kit consisted of a TOC analyzer, a YSI multiprobe, and a thickness probe. The tools were field tested to determine their ease of use, reliability, and determine the quality of data that each tool could provide. Characterization was done over a two day period in June 2011, and confirmed that the L Area basin is a well operated facility with low corrosion potential.

Berry, T.; Milliken, C.; Martinez-Rodriguez, M.; Hathcock, D.; Heitkamp, M.

2012-06-04T23:59:59.000Z

25

Spent Nuclear Fuel (SNF) Storage Project Fuel Basket Handling Grapple Design Development Test Report  

SciTech Connect

Acceptance testing of the SNF Fuel Basket Lift Grapple was accomplished to verify the design adequacy. This report shows the results affirming the design. The test was successful in demonstrating the adequacy of the grapple assembly's inconel actuator shaft and engagement balls for in loads excess of design basis loads (3200 pounds), 3X design basis loads (9600 pounds), and 5X design basis loads (16,000 pounds). The test data showed that no appreciable yielding for the inconel actuator shaft and engagement balls at loads in excess of 5X Design Basis loads. The test data also showed the grapple assembly and components to be fully functional after loads in excess of 5X Design Basis were applied and maintained for over 10 minutes. Following testing, each actuator shaft (Item 7) was liquid penetrant inspected per ASME Section 111, Division 1 1989 and accepted per requirements of NF-5350. This examination was performed to insure that no cracking had occurred. The test indicated that no cracking had occurred. The examination reports are included as Appendix C to this document. From this test, it is concluded that the design configuration meets or exceeds the requirements specified in ANSI N 14 6 for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More.

CHENAULT, D.M.

2000-01-06T23:59:59.000Z

26

Nuclear reactors and the nuclear fuel cycle  

SciTech Connect

According to the author, the first sustained nuclear fission chain reaction was not at the University of Chicago, but at the Oklo site in the African country of Gabon. Proof of this phenomenon is provided by mass spectrometric and analytical chemical measurements by French scientists. The U.S. experience in developing power-producing reactors and their related fuel and fuel cycles is discussed.

Pearlman, H

1989-11-01T23:59:59.000Z

27

Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel  

SciTech Connect

In conventional criticality evaluations of nuclear powder systems, effects of particulate behavior were not considered. In other words, it is difficult to take into account the particle motion in the criticality evaluations. We have developed a novel criticality evaluation code to resolve this problem. The criticality evaluation code, coupling a discrete element method simulation code with a continuous-energy Monte Carlo transport code, makes it possible to study the effects of the particulate dynamics on criticality. This criticality evaluation code is applied to the mixed-oxide (MOX) fuel powder agitation process. The criticality evaluations are performed while mixing the MOX fuel powder and an additive powder in a stirred vessel to investigate the effects of the powder free surface deformation and the particulate mixture state on the effective multiplication factor. The evaluation results reveal that the effective multiplication factor decreases due to the powder boundary deformation while it increases as the mixture condition of MOX powder and Zn-St powder is close to homogeneous.

Sakai, Mikio; Yamamoto, Toshihiro; Murazaki, Minoru; Miyoshi, Yoshinori [Japan Atomic Energy Research Institute (Japan)

2005-02-15T23:59:59.000Z

28

Enterprise SRS: leveraging ongoing operations to advance nuclear fuel cycles research and development programs  

SciTech Connect

The Savannah River Site (SRS) is re-purposing its vast array of assets (including H Canyon - a nuclear chemical separation plant) to solve issues regarding advanced nuclear fuel cycle technologies, nuclear materials processing, packaging, storage and disposition. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for 'all things nuclear' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into SRS facilities but also in other facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, a center for applied nuclear materials processing and engineering research has been established in SRS.

Murray, A.M.; Marra, J.E.; Wilmarth, W.R. [Savannah River National Laboratory, Aiken, SC 29808 (United States); McGuire, P.W.; Wheeler, V.B. [Department of Energy-Savannah River Operations Office, Aiken SC 29808 (United States)

2013-07-01T23:59:59.000Z

29

Nuclear fuel cycle information workshop  

SciTech Connect

This overview of the nuclear fuel cycle is divided into three parts. First, is a brief discussion of the basic principles of how nuclear reactors work; second, is a look at the major types of nuclear reactors being used and world-wide nuclear capacity; and third, is an overview of the nuclear fuel cycle and the present industrial capability in the US.

Not Available

1983-01-01T23:59:59.000Z

30

Spent nuclear fuel reprocessing modeling  

SciTech Connect

The long-term wide development of nuclear power requires new approaches towards the realization of nuclear fuel cycle, namely, closed nuclear fuel cycle (CNFC) with respect to fission materials. Plant nuclear fuel cycle (PNFC), which is in fact the reprocessing of spent nuclear fuel unloaded from the reactor and the production of new nuclear fuel (NF) at the same place together with reactor plant, can be one variant of CNFC. Developing and projecting of PNFC is a complicated high-technology innovative process that requires modern information support. One of the components of this information support is developed by the authors. This component is the programme conducting calculations for various variants of process flow sheets for reprocessing SNF and production of NF. Central in this programme is the blocks library, where the blocks contain mathematical description of separate processes and operations. The calculating programme itself has such a structure that one can configure the complex of blocks and correlations between blocks, appropriate for any given flow sheet. For the ready sequence of operations balance calculations are made of all flows, i.e. expenses, element and substance makeup, heat emission and radiation rate are determined. The programme is open and the block library can be updated. This means that more complicated and detailed models of technological processes will be added to the library basing on the results of testing processes using real equipment, in test operating mode. The development of the model for the realization of technical-economic analysis of various variants of technologic PNFC schemes and the organization of 'operator's advisor' is expected. (authors)

Tretyakova, S.; Shmidt, O.; Podymova, T.; Shadrin, A.; Tkachenko, V. [Bochvar Institute, 5 Rogova str., Moscow 123098 (Russian Federation); Makeyeva, I.; Tkachenko, V.; Verbitskaya, O.; Schultz, O.; Peshkichev, I. [Russian Federal Nuclear Center - VNIITF E.I. Zababakhin, p.o.box 245, Snezhinsk, 456770 (Russian Federation)

2013-07-01T23:59:59.000Z

31

Nuclear Spent Fuel Program Drivers  

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

was created to plan and coordinate the management of Department of Energy-owned spent nuclear fuel. It was established as a result of a 1992 decision to stop spent nuclear fuel...

32

Nuclear Industry Input to the Development of Concepts for the Consolidated Storage of Used Nuclear Fuel - 13411  

SciTech Connect

EnergySolutions and its team partners, NAC International, Exelon Nuclear Partners, Talisman International, TerranearPMC, Booz Allen Hamilton and Sargent and Lundy, have carried out a study to develop concepts for a Consolidated Storage Facility (CSF) for the USA's stocks of commercial Used Nuclear Fuel (UNF), and the packaging and transport provisions required to move the UNF to the CSF. The UNF is currently stored at all 65 operating nuclear reactor sites in the US, and at 10 shutdown sites. The study was funded by the US Department of Energy and followed the recommendations of the Blue Ribbon Commission on America's Nuclear Future (BRC), one of which was that the US should make prompt efforts to develop one or more consolidated storage facilities for commercial UNF. The study showed that viable schemes can be devised to move all UNF and store it at a CSF, but that a range of schemes is required to accommodate the present widely varying UNF storage arrangements. Although most UNF that is currently stored at operating reactor sites is in water-filled pools, a significant amount is now dry stored in concrete casks. At the shutdown sites, the UNF is dry stored at all but two of the ten sites. Various types of UNF dry storage configurations are used at the operating sites and shutdown sites that include vertical storage casks that are also licensed for transportation, vertical casks that are licensed for storage only, and horizontally orientated storage modules. The shutdown sites have limited to nonexistent UNF handling infrastructure and several no longer have railroad connections, complicating UNF handling and transport off the site. However four methods were identified that will satisfactorily retrieve the UNF canisters within the storage casks and transport them to the CSF. The study showed that all of the issues associated with the transportation and storage of UNF from all sites in the US can be accommodated by adopting a staged approach to the construction of the CSF. Stage 1 requires only a cask storage pad and railroad interface to be constructed, and the CSF can then receive the UNF that is in transportable storage casks. Stage 2 adds a canister handling facility, a storage cask fabrication facility and an expanded storage pad, and enables the receipt of all canistered UNF from both operating and shutdown sites. Stage 3 provides a repackaging facility with a water-filled pool that provides flexibility for a range of repackaging scenarios. This includes receiving and repackaging 'bare' UNF into suitable canisters that can be placed into interim storage at the CSF, and enables UNF that is being received, or already in storage onsite, to be repackaged into canisters that are suitable for disposal at a geologic repository. The study used the 'Total System Model' (TSM) to analyze a range of CSF capacities and operating scenarios with differing parameters covering UNF pickup orders, one or more CSF sites, CSF start dates, CSF receipt rates and geologic repository start dates. The TSM was originally developed to model movement of UNF to the Yucca Mountain repository and was modified for this study to enable the CSF to become the 'gateway' to a future geologic repository. The TSM analysis enabled costs to be estimated for each scenario and showed how these are influenced by each of the parameters. This information will provide essential underpinning for a future Conceptual Design preparation. (authors)

Phillips, Chris; Thomas, Ivan; McNiven, Steven [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States)] [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States); Lanthrum, Gary [NAC International, 3930 East Jones Bridge Road, Norcross, GA, 30092 (United States)] [NAC International, 3930 East Jones Bridge Road, Norcross, GA, 30092 (United States)

2013-07-01T23:59:59.000Z

33

Development of U-Frame Bending System for Studying the Vibration Integrity of Spent Nuclear Fuel  

SciTech Connect

A bending fatigue system developed to evaluate the response of spent nuclear fuel rods to vibration loads is presented. Design and analysis, fabrication, modification, calibration, and instrumentation are described. The system is composed of a U-frame testing setup for imposing bending loads on the spent fuel rod test specimen and a method for measuring the curvature of the rod during bending. The U-frame setup consists of two rigid arms, linking members, and linkages to a universal testing machine. The test specimen s curvature of bending is obtained through a three-point deflection measurement method consisting of three LVDTs mounted to the side connecting plates of the U-frame to capture the deformation of the test specimen. The system has some unique features: 1) The test specimen is installed by simple insertion using linear bearings incorporated with rigid sleeves. 2) Reverse cyclic bending tests can be carried out effectively and efficiently by push and pull at the loading point of the setup. Any test machine with a linear motion function can be used to drive the setup. 3) The embedded and preloaded linear roller bearings eliminate the backlash that exists in the conventional reverse bend tests. 4) The number of linkages between the U-frame and the universal machine is minimized. Namely, there are only two linkages needed at the two loading points of a U-frame setup, whereas a conventional four/three-point bend test frame requires four linkages. 5) The curvature measurement is immune to the effects arising from compliant layers and the rigid body motion of the machine. The compliant layers are used at the holding areas of the specimen to prevent contact damage. The tests using surrogate specimens composed of SS cladding/tube revealed several important phenomena that may cast light on the expected response of a spent fuel rod: 1) Cyclic quasi-static load (10 N/s under force control) in compressive mode (with respect to that at the loading point of the U-frame) produced increased irreversible or plastic curvature and also increased flexural rigidity of the surrogate rod. 2) Dynamic cyclic load (at least 1 Hz) in compressive mode resulted in increased flexural rigidity of the surrogate rod prior to SS cladding fracture. 3) Pellets and epoxy bonding exhibited various effects on the response of surrogate rods during the loading process as validated from static tests. 4) Dynamic cyclic load (2 Hz) in reverse mode demonstrated a substantial cyclic softening before the fracture of the surrogate rod. The degree of decrease in flexural rigidity was consistent in both measurement and on-line monitoring. The developed U-frame system is thus verified and demonstrated to be ready for further pursuit in hot-cell tests.

Wang, Hong [ORNL; Wang, Jy-An John [ORNL; Tan, Ting [ORNL; Jiang, Hao [ORNL; Cox, Thomas S [ORNL; Howard, Rob L [ORNL; Bevard, Bruce Balkcom [ORNL; Flanagan, Michelle E [ORNL

2013-01-01T23:59:59.000Z

34

Fuel Cycle Science & Technology | Nuclear Science | ORNL  

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

Advanced Fuel Cycle Systems Radiochemical Separation & Processing Recycle & Waste Management Uranium Enrichment Used Nuclear Fuel Storage, Transportation, and Disposal Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research Areas | Fuel Cycle Science & Technology SHARE Fuel Cycle Science and Technology The ORNL expertise and experience across the entire nuclear fuel cycle is underpinned by extensive facilities and a comprehensive modeling and simulation capability ORNL supports the understanding, development, evaluation and deployment of

35

Report of the Fuel Cycle Research and Development Subcommittee of the Nuclear Energy Advisory Committee  

SciTech Connect

The Fuel Cycle (FC) Subcommittee of NEAC met February 7-8, 2012 in Washington (Drs. Hoffmann and Juzaitis were unable to attend). While the meeting was originally scheduled to occur after the submission of the President’s FY 2013 budget, the submission was delayed a week; thus, we could have no discussion on balance in the NE program. The Agenda is attached as Appendix A. The main focus of the meeting was on accident tolerant fuels, an important post Fukushima issue, and on issues related to the report of the Blue Ribbon Commission on America’s Nuclear Future (BRC) as related to the responsibility for used fuel disposal which was assigned to the FC program with the end of the Office of Civilian Radioactive Waste Management. In addition we heard an update on the systems study program which is aimed at helping chose the best options for advanced reactors, and possible new study on separation and waste form relevance to used fuel disposal (these two items are only discussed in this section of the report).

Richter, Burton; Chu, Margaret; Hoffman, Darleane; Juzaitis, Ray; Mtingwa, Sekazi; Omberg, Ronald P.; Rempe, Joy L.; Warin, Dominique

2012-06-12T23:59:59.000Z

36

Developments of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory  

SciTech Connect

This paper summarizes research in used fuel pyroprocessing that has been published by Idaho National Laboratory over the last decade. It includes work done both on treatment of Experimental Breeder Reactor-II and development of advanced technology for potential scale-up and commercialization. Collaborations with universities and other laboratories is included in the cited work.

Michael F. Simpson

2012-03-01T23:59:59.000Z

37

Inverse Sensitivity/Uncertainty Methods Development for Nuclear Fuel Cycle Applications  

Science Journals Connector (OSTI)

Abstract The Standardized Computer Analyses for Licensing Evaluation (SCALE) software package developed at the Oak Ridge National Laboratory includes codes that propagate uncertainties available in the nuclear data libraries to compute uncertainties in nuclear application performance parameters. We report on our recent efforts to extend this capability to develop an inverse sensitivity/uncertainty (IS/U) methodology that identifies the improvements in nuclear data that are needed to compute application responses within prescribed tolerances, while minimizing the cost of such data improvements. We report on our progress to date and present a simple test case for our method. Our methodology is directly applicable to thermal and intermediate neutron energy systems because it addresses the implicit neutron resonance self-shielding effects that are essential to accurate modeling of thermal and intermediate systems. This methodology is likely to increase the efficiency of nuclear data efforts.

G. Arbanas; M.E. Dunn; M.L. Williams

2014-01-01T23:59:59.000Z

38

TEPP - Spent Nuclear Fuel | Department of Energy  

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

- Spent Nuclear Fuel - Spent Nuclear Fuel TEPP - Spent Nuclear Fuel This scenario provides the planning instructions, guidance, and evaluation forms necessary to conduct an exercise involving a highway shipment of spent nuclear fuel. This exercise manual is one in a series of five scenarios developed by the Department of Energy Transportation Emergency Preparedness Program. Responding agencies may include several or more of the following: local municipal and county fire, police, sheriff, and Emergency Medical Services (EMS) personnel; state, local, and federal emergency response teams; emergency response contractors;and other emergency response resources that could potentially be provided by the carrier and the originating facility (shipper). Spent Nuclear Fuel.docx More Documents & Publications

39

Swelling-resistant nuclear fuel  

DOE Patents (OSTI)

A nuclear fuel according to one embodiment includes an assembly of nuclear fuel particles; and continuous open channels defined between at least some of the nuclear fuel particles, wherein the channels are characterized as allowing fission gasses produced in an interior of the assembly to escape from the interior of the assembly to an exterior thereof without causing significant swelling of the assembly. Additional embodiments, including methods, are also presented.

Arsenlis, Athanasios (Hayward, CA); Satcher, Jr., Joe (Patterson, CA); Kucheyev, Sergei O. (Oakland, CA)

2011-12-27T23:59:59.000Z

40

Development of pyro-processing technology at CRIEPI for carving out the future of nuclear fuel cycle  

SciTech Connect

Pyro-processing has been attracting increasing attention as a promising candidate as an advanced nuclear fuel cycle technology. It provides economic advantage as well as reduction in proliferation risk and burden of long live radioactive waste, especially when it is combined with advanced fuels such as metallic or nitride fuel which gives excellent burning efficiency of minor actinides (MA). CRIEPI has been developing pyro-processing technology since late eighties with both domestic and international collaborations. In the early stage, electrochemical and thermodynamic properties in LiCl-KCl eutectic melt, and fundamental feasibility of core technology like electrorefining were chiefly investigated. Currently, stress in the process chemistry development is also placed on supporting technologies, such as treatment of anode residue and high temperature distillation for cathode product from electrorefining, and so on. Waste treatment process development, such as studies on adsorption behavior of various FP elements into zeolite and conditions for the fabrication of glass-bonded sodalite waste form, are steadily improved as well. In parallel, dedicated pyro-processing equipment such as zeolite column for treatment of spent electro-refiner salt is currently in progress. Recently, an integrated engineering-scale fuel cycle tests were performed funded by Japanese government (MEXT) as an important step before proceeding to large scale hot demonstration of pyro-processing. Oxide fuels can be readily introduced into the pyro-processing by reducing them to metals by adoption of electrochemical reduction technique. Making use of this advantage, the pyro-processing is currently under preliminary evaluation for its applicability to the treatment of the corium, mainly consisting of (U,Zr)O{sub 2}, formed in different composition during the accident of the Fukushima Daiichi nuclear power plant. (authors)

Iizuka, M.; Koyama, T.; Sakamura, Y.; Uozumi, K.; Fujihata, K.; Kato, T.; Murakami, T.; Tsukada, T. [Central Research Institute of Electric Power Industry, Komae-shi, Tokyo 201-8511 (Japan); Glatz, J.P. [European Commission, JRC, Institute for Transuranium Elements (Germany)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Pyrochemical Treatment of Spent Nuclear Fuel  

SciTech Connect

Over the last 10 years, pyrochemical treatment of spent nuclear fuel has progressed from demonstration activities to engineering-scale production operations. As part of the Advanced Fuel Cycle Initiative within the U.S. Department of Energy’s Office of Nuclear Energy, Science and Technology, pyrochemical treatment operations are being performed as part of the treatment of fuel from the Experimental Breeder Reactor II at the Idaho National Laboratory. Integral to these treatment operations are research and development activities that are focused on scaling further the technology, developing and implementing process improvements, qualifying the resulting high-level waste forms, and demonstrating the overall pyrochemical fuel cycle.

K. M. Goff; K. L. Howden; G. M. Teske; T. A. Johnson

2005-10-01T23:59:59.000Z

42

Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear  

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

Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear Safeguards Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear Safeguards GNEP will help prevent misuse of civilian nuclear facilities for nonpeaceful purposes by developing enhanced safeguards programs and technologies. International nuclear safeguards are integral to implementing the GNEP vision of a peaceful expansion of nuclear energy and demonstration of more proliferation-resistant fuel cycle technologies. Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear Safeguards More Documents & Publications GNEP Element:Develop Enhanced Nuclear Safeguards Global Nuclear Energy Partnership Fact Sheet Global Nuclear Energy Partnership Fact Sheet - Demonstrate Small-Scale

43

Enterprise SRS: Leveraging Ongoing Operations To Advance Nuclear Fuel Cycles Research And Development Programs  

SciTech Connect

The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for ''all things nuclear'' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The Department of Energy, Savannah River Operations Office, Savannah River Nuclear Solutions, the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key proposition of this initiative is to bridge the gap between promising transformational nuclear fuel cycle processing discoveries and large commercial-scale-technology deployment by leveraging SRS assets as facilities for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the research team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform research demonstrations at other facilities. Unique to this approach is the fact that these SRS assets will continue to accomplish DOE's critical nuclear material missions (e.g., processing in H-Canyon and plutonium storage in K-Area). Thus, the demonstration can be accomplished by leveraging the incremental cost of performing demonstrations without needing to cover the full operational cost of the facility. Current Center activities have been focused on integrating advanced safeguards monitoring technologies demonstrations into the SRS H-Canyon and advanced location technologies demonstrations into K-Area Materials Storage. These demonstrations are providing valuable information to researchers and customers as well as providing the Center with an improved protocol for demonstration management that can be exercised across the entire SRS (as well as to offsite venues) so that future demonstrations can be done more efficiently and provide an opportunity to utilize these unique assets for multiple purposes involving national laboratories, academia, and commercial entities. Key among the envisioned future demonstrations is the use of H-Canyon to demonstrate new nuclear materials separations technologies critical for advancing the mission needs DOE-Nuclear Energy (DOE-NE) to advance the research for next generation fuel cycle technologies. The concept is to install processing equipment on frames. The frames are then positioned into an H-Canyon cell and testing in a relevant radiological environment involving prototypic radioactive materials can be performed.

Murray, Alice M.; Marra, John E.; Wilmarth, William R.; Mcguire, Patrick W.; Wheeler, Vickie B.

2013-07-03T23:59:59.000Z

44

Nuclear Fuel Cycle and Waste Management Technologies - Nuclear Engineering  

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

Nuclear Fuel Cycle and Nuclear Fuel Cycle and Waste Management Technologies Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Fuel Cycle and Waste Management Technologies Overview Bookmark and Share Much of the NE Division's research is directed toward developing software and performing analyses, system engineering design, and experiments to support the demonstration and optimization of the electrometallurgical

45

Nuclear power and the fuel cycle  

Science Journals Connector (OSTI)

Due to rising energy costs and climate concerns, nuclear power is once again being seriously considered as an energy source by several countries. This revival of nuclear power is closely linked with the choice of fuel cycles available, and the intentions of countries pursuing nuclear power are likely to be, correctly or incorrectly, judged by the choice of fuel cycle they make. The needs and constraints of the emerging nuclear powers may, however, be different from the expectations of a segment of the world community. If this potential growth in nuclear power is not to be stifled, it is imperative that a climate of mutual trust is developed respecting every country's right to develop peaceful uses of nuclear power without leading to an atmosphere of mistrust regarding the 'intentions' behind the pursuit of peaceful nuclear power. While it will be a near impossibility to completely decouple the peaceful uses of nuclear power from its more destructive applications, it is important that aspiring countries develop a clear and transparent process. Technology-supplier countries also need to develop and follow clear and consistent treaties and national policies, avoiding ad hoc country-specific arrangements. We review here the state of interest in nuclear power and current policies and discuss fuel cycle options that may pave the way for the future growth of nuclear power.

Rizwan-uddin

2010-01-01T23:59:59.000Z

46

Nuclear Fuel Cycle | Department of Energy  

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

Fuel Cycle Fuel Cycle Nuclear Fuel Cycle GC-52 provides legal advice to DOE regarding research and development of nuclear fuel and waste management technologies that meet the nation's energy supply, environmental, and energy security needs. GC-52 also advises DOE on issues involving support for international fuel cycle initiatives aimed at advancing a common vision of the necessity of the expansion of nuclear energy for peaceful purposes worldwide in a safe and secure manner. In addition, GC-52 provides legal advice to DOE regarding the management and disposition of excess uranium in DOE's uranium stockpile. GC-52 attorneys participate in meetings of DOE's Uranium Inventory Management Coordinating Committee and provide advice on compliance with statutory requirements for the sale or transfer of uranium.

47

Advances in Metallic Nuclear Fuel  

Science Journals Connector (OSTI)

Metallic nuclear fuels have generated renewed interest for advanced ... operations is excellent. Ongoing irradiation tests in Argonne-West’s Idaho-based Experimental Breeder Reactor ... fast reactor (IFR) concept...

B. R. Seidel; L. C. Walters; Y. I. Chang

1987-04-01T23:59:59.000Z

48

Nuclear Fuel Cycle & Vulnerabilities  

SciTech Connect

The objective of safeguards is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection. The safeguards system should be designed to provide credible assurances that there has been no diversion of declared nuclear material and no undeclared nuclear material and activities.

Boyer, Brian D. [Los Alamos National Laboratory

2012-06-18T23:59:59.000Z

49

Sustainability Features of Nuclear Fuel Cycle Options  

E-Print Network (OSTI)

The nuclear fuel cycle is the series of stages that nuclear fuel materials go through in a cradle to grave framework. The Once Through Cycle (OTC) is the current fuel cycle implemented in the United States; in which an ...

Passerini, Stefano

50

Nuclear fuel recycling in 4 minutes | Argonne National Laboratory  

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

Nuclear fuel recycling in 4 minutes Share Topic Energy Energy sources Nuclear energy Nuclear fuel cycle Reactors...

51

Nuclear Fuels & Materials Spotlight Volume 4  

SciTech Connect

As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • The first identification of silver and palladium migrating through the SiC layer in TRISO fuel • A description of irradiation assisted stress corrosion testing capabilities that support commercial light water reactor life extension • Results of high-temperature safety testing on coated particle fuels irradiated in the ATR • New methods for testing the integrity of irradiated plate-type reactor fuel • Description of a 'Smart Fuel' concept that wirelessly provides real time information about changes in nuclear fuel properties and operating conditions • Development and testing of ultrasonic transducers and real-time flux sensors for use inside reactor cores, and • An example of a capsule irradiation test. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps to spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at INL, and hope that you find this issue informative.

I. J. van Rooyen,; T. M. Lillo; Y. Q. WU; P.A. Demkowicz; L. Scott; D.M. Scates; E. L. Reber; J. H. Jackson; J. A. Smith; D.L. Cottle; B.H. Rabin; M.R. Tonks; S.B. Biner; Y. Zhang; R.L. Williamson; S.R. Novascone; B.W. Spencer; J.D. Hales; D.R. Gaston; C.J. Permann; D. Anders; S.L. Hayes; P.C. Millett; D. Andersson; C. Stanek; R. Ali; S.L. Garrett; J.E. Daw; J.L. Rempe; J. Palmer; B. Tittmann; B. Reinhardt; G. Kohse; P. Ramuhali; H.T. Chien; T. Unruh; B.M. Chase; D.W. Nigg; G. Imel; J. T. Harris

2014-04-01T23:59:59.000Z

52

Requirements for a Dynamic Solvent Extraction Module to Support Development of Advanced Technologies for the Recycle of Used Nuclear Fuel  

SciTech Connect

The Department of Energy's Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program has been established to create and deploy next generation, verified and validated nuclear energy modeling and simulation capabilities for the design, implementation, and operation of future nuclear energy systems to improve the U.S. energy security. As part of the NEAMS program, Integrated Performance and Safety Codes (IPSC's) are being produced to significantly advance the status of modeling and simulation of energy systems beyond what is currently available to the extent that the new codes be readily functional in the short term and extensible in the longer term. The four IPSC areas include Safeguards and Separations, Reactors, Fuels, and Waste Forms. As part of the Safeguards and Separations (SafeSeps) IPSC effort, interoperable process models are being developed that enable dynamic simulation of an advanced separations plant. A SafeSepss IPSC 'toolkit' is in development to enable the integration of separation process modules and safeguards tools into the design process by providing an environment to compose, verify and validate a simulation application to be used for analysis of various plant configurations and operating conditions. The modules of this toolkit will be implemented on a modern, expandable architecture with the flexibility to explore and evaluate a wide range of process options while preserving their stand-alone usability. Modules implemented at the plant-level will initially incorporate relatively simple representations for each process through a reduced modeling approach. Final versions will incorporate the capability to bridge to subscale models to provide required fidelity in chemical and physical processes. A dynamic solvent extraction model and its module implementation are needed to support the development of this integrated plant model. As a stand-alone application, it will also support solvent development of extraction flowsheets and integrated safeguards approaches within the Fuel Cycle Research and Development (FCR&D) Program. The purpose of this document is to identify the requirements for this dynamic solvent extraction model to guide process modelers and code developers to produce a computational module that meets anticipated future needs.

Jack Law; Veronica Rutledge; Candido Pereira; Jackie Copple; Kurt Frey; John Krebs; Laura Maggos; Kevin Nichols; Kent Wardle; Pratap Sadasivan; Valmor DeAlmieda; David Depaoli

2011-06-01T23:59:59.000Z

53

DEVELOPMENT OF A HYDROGEN MORDENITE SORBENT FOR THE CAPTURE OF KRYPTON FROM USED NUCLEAR FUEL REPROCESSING OFF-GAS STREAMS  

SciTech Connect

A novel new sorbent for the separation of krypton from off-gas streams resulting from the reprocessing of used nuclear fuel has been developed and evaluated. A hydrogen mordenite powder was successfully incorporated into a macroporous polymer binder and formed into spherical beads. The engineered form sorbent retained the characteristic surface area and microporosity indicative of mordenite powder. The sorbent was evaluated for krypton adsorption capacities utilizing thermal swing operations achieving capacities of 100 mmol of krypton per kilogram of sorbent at a temperature of 191 K. A krypton adsorption isotherm was also obtained at 191 K with varying krypton feed gas concentrations. Adsorption/desorption cycling effects were also evaluated with results indicating that the sorbent experienced no decrease in krypton capacity throughout testing.

Mitchell Greenhalgh; Troy G. Garn; Jack D. Law

2014-04-01T23:59:59.000Z

54

Dynamic Systems Analysis Report for Nuclear Fuel Recycle  

SciTech Connect

This report examines the time-dependent dynamics of transitioning from the current United States (U.S.) nuclear fuel cycle where used nuclear fuel is disposed in a repository to a closed fuel cycle where the used fuel is recycled and only fission products and waste are disposed. The report is intended to help inform policy developers, decision makers, and program managers of system-level options and constraints as they guide the formulation and implementation of advanced fuel cycle development and demonstration efforts and move toward deployment of nuclear fuel recycling infrastructure.

Brent Dixon; Sonny Kim; David Shropshire; Steven Piet; Gretchen Matthern; Bill Halsey

2008-12-01T23:59:59.000Z

55

Pilot Application to Nuclear Fuel Cycle Options | Department of Energy  

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

Pilot Application to Nuclear Fuel Cycle Options Pilot Application to Nuclear Fuel Cycle Options Pilot Application to Nuclear Fuel Cycle Options A Screening Method for Guiding R&D Decisions: Pilot Application to Screen Nuclear Fuel Cycle Options The Department of Energy's Office of Nuclear Energy (DOE-NE) invests in research and development (R&D) to ensure that the United States will maintain its domestic nuclear energy capability and scientific and technical leadership in the international community of nuclear power nations in the years ahead. The 2010 Nuclear Energy Research and Development Roadmap presents a high-level vision and framework for R&D activities that are needed to keep the nuclear energy option viable in the near term and to expand its use in the decades ahead. The roadmap identifies the development

56

Transportation capabilities study of DOE-owned spent nuclear fuel  

SciTech Connect

This study evaluates current capabilities for transporting spent nuclear fuel owned by the US Department of Energy. Currently licensed irradiated fuel shipping packages that have the potential for shipping the spent nuclear fuel are identified and then matched against the various spent nuclear fuel types. Also included are the results of a limited investigation into other certified packages and new packages currently under development. This study is intended to support top-level planning for the disposition of the Department of Energy`s spent nuclear fuel inventory.

Clark, G.L.; Johnson, R.A.; Smith, R.W. [Packaging Technology, Inc., Tacoma, WA (United States); Abbott, D.G.; Tyacke, M.J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1994-10-01T23:59:59.000Z

57

Fuel Cycle Research and Development Program  

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

Development Program Presentation to Office of Environmental Management Tank Waste Corporate Board James C. Bresee, ScD, JD Advisory Board Member Office of Nuclear Energy July 29, 2009 July 29, 2009 Fuel Cycle Research and Development DM 195665 2 Outline Fuel Cycle R&D Mission Changes from the Former Advanced Fuel Cycle Initiative The Science-Based Approach Key Collaborators Budget History Program Elements Summary July 29, 2009 Fuel Cycle Research and Development DM 195665 3 Fuel Cycle R&D Mission The mission of Fuel Cycle Research and Development is to develop options to current fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while reducing proliferation risks by conducting

58

A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department of  

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

A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu Former Secretary of Energy The Blue Ribbon Commission on America's Nuclear Future was formed at the direction of the President to conduct a comprehensive review of polices for managing the back end of the nuclear fuel cycle. If we are going to ensure that the United States remains at the forefront of nuclear safety and security, non-proliferation, and nuclear energy technology we must develop an effective strategy and workable plan for the safe and secure management and disposal of used nuclear fuel and nuclear waste. That is why I asked General Scowcroft and Representative Hamilton to draw on their

59

Activities Related to Storage of Spent Nuclear Fuel | Department...  

Office of Environmental Management (EM)

Activities Related to Storage of Spent Nuclear Fuel Activities Related to Storage of Spent Nuclear Fuel Activities Related to Storage of Spent Nuclear Fuel More Documents &...

60

Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors  

E-Print Network (OSTI)

of hydride fueled BWRs. Nuclear Engineering and Design, 239:Fueled PWR Cores. Nuclear Engineering and Design, 239:1489–Hydride Fueled LWRs. Nuclear Engineering and Design, 239:

Terrani, Kurt Amir

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

EIS-0203: Spent Nuclear Fuel Management and Idaho National Engineering  

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

EIS-0203: Spent Nuclear Fuel Management and Idaho National EIS-0203: Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs EIS-0203: Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs SUMMARY This EIS considers programmatic (DOE-wide) alternative approaches to safely, efficiently, and responsibly manage existing and projected quantities of spent nuclear fuel until the year 2035. This amount of time may be required to make and implement a decision on the ultimate disposition of spent nuclear fuel. DOE's spent nuclear fuel responsibilities include fuel generated by DOE production, research, and development reactors; naval reactors; university and foreign research reactors; domestic non-DOE reactors such as those at the National Institute

62

Development of the fundamental attributes and inputs for proliferation resistance assessments of nuclear fuel cycles  

E-Print Network (OSTI)

. ...........................................................72 Fig. 14. Graphical representation of methodology elements..........................................77 Fig. 15. Utility function for mass/SQ. ............................................................................81 Fig. 16. Utility...-term geological storage of nuclear material, and 14. allow for discrimination between different facilities and technologies. 3 The objective of this work was to use these criteria as a basis for identifying a limited set of critical system and material...

Giannangeli, Donald D. J., III

2007-09-17T23:59:59.000Z

63

Computational Design of Advanced Nuclear Fuels  

SciTech Connect

The objective of the project was to develop a method for theoretical understanding of nuclear fuel materials whose physical and thermophysical properties can be predicted from first principles using a novel dynamical mean field method for electronic structure calculations. We concentrated our study on uranium, plutonium, their oxides, nitrides, carbides, as well as some rare earth materials whose 4f eletrons provide a simplified framework for understanding complex behavior of the f electrons. We addressed the issues connected to the electronic structure, lattice instabilities, phonon and magnon dynamics as well as thermal conductivity. This allowed us to evaluate characteristics of advanced nuclear fuel systems using computer based simulations and avoid costly experiments.

Savrasov, Sergey; Kotliar, Gabriel; Haule, Kristjan

2014-06-03T23:59:59.000Z

64

Fuel Cell Development Status  

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

Development Status Michael Short Systems Engineering Manager United Technologies Corporation Research Center Hamilton Sundstrand UTC Power UTC Fire & Security Fortune 50 corporation $52.9B in annual sales in 2009 ~60% of Sales are in building technologies Transportation Stationary Fuel Cells Space & Defense * Fuel cell technology leader since 1958 * ~ 550 employees * 768+ Active U.S. patents, more than 300 additional U.S. patents pending * Global leader in efficient, reliable, and sustainable fuel cell solutions UTC Power About Us PureCell ® Model 400 Solution Process Overview Power Conditioner Converts DC power to high-quality AC power 3 Fuel Cell Stack Generates DC power from hydrogen and air 2 Fuel Processor Converts natural gas fuel to hydrogen

65

Energy Department Announces New Investment in Nuclear Fuel Storage Research  

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

Investment in Nuclear Fuel Storage Investment in Nuclear Fuel Storage Research Energy Department Announces New Investment in Nuclear Fuel Storage Research April 16, 2013 - 12:19pm Addthis NEWS MEDIA CONTACT (202) 586-4940 WASHINGTON - As part of its commitment to developing an effective strategy for the safe and secure storage and management of used nuclear fuel, the Energy Department today announced a new dry storage research and development project led by the Electric Power Research Institute (EPRI). The project will design and demonstrate dry storage cask technology for high burn-up spent nuclear fuels that have been removed from commercial nuclear power plants. "The Energy Department is committed to advancing clean, reliable and safe nuclear power - which provides the largest source of low-carbon

66

Energy Department Announces New Investment in Nuclear Fuel Storage Research  

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

Announces New Investment in Nuclear Fuel Storage Announces New Investment in Nuclear Fuel Storage Research Energy Department Announces New Investment in Nuclear Fuel Storage Research April 16, 2013 - 12:19pm Addthis NEWS MEDIA CONTACT (202) 586-4940 WASHINGTON - As part of its commitment to developing an effective strategy for the safe and secure storage and management of used nuclear fuel, the Energy Department today announced a new dry storage research and development project led by the Electric Power Research Institute (EPRI). The project will design and demonstrate dry storage cask technology for high burn-up spent nuclear fuels that have been removed from commercial nuclear power plants. "The Energy Department is committed to advancing clean, reliable and safe nuclear power - which provides the largest source of low-carbon

67

Review of Used Nuclear Fuel Storage and Transportation Technical Gap  

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

Analyses Analyses Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analyses The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development activities related to storage, transportation, and disposal of used nuclear fuel and high-level radioactive waste. 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 (UNF) and wastes generated by existing and future nuclear fuel cycles. The Storage and Transportation activities within the UFDC are being developed to address issues regarding the extended storage of UNF and its subsequent

68

Coated Particle Fuel Development Lab (CPFDL) | ORNL  

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

Coated Particle Fuel Development Lab Coated Particle Fuel Development Lab May 30, 2013 Computer controlled fluidized bed CVD particle coating system The Coated Particle Fuel Development Laboratory is a modern, integrated facility for laboratory scale fabrication and characterization of uranium-bearing coated particle fuel (CPF). Within this facility, tri-isotropic (TRISO) coatings are deposited on various fuel kernels by chemical vapor deposition (CVD), particles are pressed into fuel compacts for irradiation, and state-of-the-art materials property characterization is performed, all under an NQA-1 compliant Quality Assurance program. Current work includes fabrication and characterization of coated particle fuels to support the Next Generation Nuclear Plant, Advanced Small Modular Reactors, Nuclear Thermal Propulsion, and Advanced Light Water Reactor

69

Safeguarding and Protecting the Nuclear Fuel Cycle  

SciTech Connect

International safeguards as applied by the International Atomic Energy Agency (IAEA) are a vital cornerstone of the global nuclear nonproliferation regime - they protect against the peaceful nuclear fuel cycle becoming the undetected vehicle for nuclear weapons proliferation by States. Likewise, domestic safeguards and nuclear security are essential to combating theft, sabotage, and nuclear terrorism by non-State actors. While current approaches to safeguarding and protecting the nuclear fuel cycle have been very successful, there is significant, active interest to further improve the efficiency and effectiveness of safeguards and security, particularly in light of the anticipated growth of nuclear energy and the increase in the global threat environment. This article will address two recent developments called Safeguards-by-Design and Security-by-Design, which are receiving increasing broad international attention and support. Expected benefits include facilities that are inherently more economical to effectively safeguard and protect. However, the technical measures of safeguards and security alone are not enough - they must continue to be broadly supported by dynamic and adaptive nonproliferation and security regimes. To this end, at the level of the global fuel cycle architecture, 'nonproliferation and security by design' remains a worthy objective that is also the subject of very active, international focus.

Trond Bjornard; Humberto Garcia; William Desmond; Scott Demuth

2010-11-01T23:59:59.000Z

70

Compositions and methods for treating nuclear fuel  

DOE Patents (OSTI)

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

Soderquist, Chuck Z; Johnsen, Amanda M; McNamara, Bruce K; Hanson, Brady D; Smith, Steven C; Peper, Shane M

2013-08-13T23:59:59.000Z

71

Compositions and methods for treating nuclear fuel  

DOE Patents (OSTI)

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

Soderquist, Chuck Z; Johnsen, Amanda M; McNamara, Bruce K; Hanson, Brady D; Smith, Steven C; Peper, Shane M

2014-01-28T23:59:59.000Z

72

Surrogate Spent Nuclear Fuel Vibration Integrity Investigation  

SciTech Connect

Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During transportation, SNF experiences unique conditions and challenges to cladding integrity due to the vibrational and impact loading encountered during road or rail shipment. ORNL has been developing testing capabilities that can be used to improve our understanding of the impacts of vibration loading on SNF integrity, especially for high burn-up SNF in normal transportation operation conditions. This information can be used to meet nuclear industry and U.S. Nuclear Regulatory Commission needs in the area of safety of SNF storage and transportation operations.

Wang, Jy-An John [ORNL; Wang, Hong [ORNL; Bevard, Bruce Balkcom [ORNL; Howard, Rob L [ORNL

2014-01-01T23:59:59.000Z

73

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

74

Spent Nuclear Fuel Alternative Technology Decision Analysis  

SciTech Connect

The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

Shedrow, C.B.

1999-11-29T23:59:59.000Z

75

Nuclear Fuel Cycle Integrated System Analysis  

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

Fuel Cycle Integrated System Analysis Fuel Cycle Integrated System Analysis Abdellatif M. Yacout Argonne National Laboratory Nuclear Engineering Division The nuclear fuel cycle is a complex system with multiple components and activities that are combined to provide nuclear energy to a variety of end users. The end uses of nuclear energy are diverse and include electricity, process heat, water desalination, district heating, and possibly future hydrogen production for transportation and energy storage uses. Components of the nuclear fuel cycle include front end components such as uranium mining, conversion and enrichment, fuel fabrication, and the reactor component. Back end of the fuel cycle include used fuel coming out the reactor, used fuel temporary and permanent storage, and fuel reprocessing. Combined with those components there

76

Breakthrough Vehicle Development - Fuel Cells  

Fuel Cell Technologies Publication and Product Library (EERE)

Document describing research and development program for fuel cell power systems for transportation applications.

77

Nuclear Fuel Storage and Transportation Planning Project Overview...  

Office of Environmental Management (EM)

Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project...

78

Fuel Cycle Options for Optimized Recycling of Nuclear Fuel  

E-Print Network (OSTI)

The reduction of transuranic inventories of spent nuclear fuel depends upon the deployment of advanced fuels that can be loaded with recycled transuranics (TRU), and the availability of facilities to separate and reprocess ...

Aquien, A.

79

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

80

Ceramic-composite waste forms from the electrometallurgical treatment of spent nuclear fuel  

Science Journals Connector (OSTI)

Argonne National Laboratory is developing a method to treat spent nuclear fuel in a molten-salt electrorefiner. Glass...

C. Pereira; M. Hash; M. Lewis; M. Richmann

1997-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Alternative Fuels Data Center: Ethanol Fueling Infrastructure Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Fueling Infrastructure Development to someone by E-mail Share Alternative Fuels Data Center: Ethanol Fueling Infrastructure Development on Facebook Tweet about Alternative Fuels Data Center: Ethanol Fueling Infrastructure Development on Twitter Bookmark Alternative Fuels Data Center: Ethanol Fueling Infrastructure Development on Google Bookmark Alternative Fuels Data Center: Ethanol Fueling Infrastructure Development on Delicious Rank Alternative Fuels Data Center: Ethanol Fueling Infrastructure Development on Digg Find More places to share Alternative Fuels Data Center: Ethanol Fueling Infrastructure Development on AddThis.com... More in this section... Ethanol Basics Benefits & Considerations Stations Locations Infrastructure Development Business Case Equipment Options

82

Alternative Fuels Data Center: Hydrogen Fueling Infrastructure Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Fueling Infrastructure Development to someone by E-mail Share Alternative Fuels Data Center: Hydrogen Fueling Infrastructure Development on Facebook Tweet about Alternative Fuels Data Center: Hydrogen Fueling Infrastructure Development on Twitter Bookmark Alternative Fuels Data Center: Hydrogen Fueling Infrastructure Development on Google Bookmark Alternative Fuels Data Center: Hydrogen Fueling Infrastructure Development on Delicious Rank Alternative Fuels Data Center: Hydrogen Fueling Infrastructure Development on Digg Find More places to share Alternative Fuels Data Center: Hydrogen Fueling Infrastructure Development on AddThis.com... More in this section... Hydrogen Basics Benefits & Considerations Stations Locations Infrastructure Development Vehicles Laws & Incentives

83

Alternative Fuels Data Center: Alternative Fuel Research and Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel Research and Development Funding to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Research and Development Funding on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Research and Development Funding on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Research and Development Funding on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Research and Development Funding on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Research and Development Funding on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Research and Development Funding on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type

84

Development of a novel solvent for the simultaneous separation of strontium and cesium from dissolved Spent Nuclear Fuel solutions  

SciTech Connect

The recovery of Cs and Sr from acidic solutions by solvent extraction has been investigated. The goal of this project was to develop an extraction process to remove Cs and Sr from high-level waste in an effort to reduce the heat loading in storage. Solvents for the extraction of Cs and Sr separately have been used on both caustic and acidic spent nuclear fuel waste in the past. The objective of this research was to find a suitable solvent for the extraction of both Cs and Sr simultaneously from acidic nitrate media. The solvents selected for this research possess good stability and extraction behavior when mixed together. The extraction experiments were performed with 4 ,4,(5 )-Di-(tbutyldicyclohexano)- 18-crown-6 {DtBuCH18C6}, Calix[4]arene-bis-(tert-octylbenzocrown-6) {BOBCalixC6} and 1-(2,2,3,3-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol {Cs-7SB modifier} in a branched aliphatic kerosene {Isopar® L}. The BOBCalixC6 and Cs-7SB modifier were developed at Oak Ridge National Laboratory (ORNL) by Bonnesen et al. [1]. The values obtained from the SREX solvent for DSr in 1 M nitric acid ranged from 0.7 to 2.2 at 25oC and 10oC respectively. The values for DCs in 1 M nitric acid with the CSSX solvent ranged from 8.0 to 46.0 at 25oC and 10oC respectively. A new mixed solvent, developed at the Idaho National Engineering and Environmental Laboratory (INEEL) by Riddle et al. [2], showed distributions for Sr ranging from 8.8 to 17.4 in 1 M nitric acid at 25oC and 10oC respectively. The DCs for the mixed solvent ranged from 7.7 to 20.2 in 1 M nitric acid at 25oC to 10oC respectively. The unexpectedly high distributions for Sr at both 25oC and 10oC show a synergy in the mixed solvent. The DCs, although lower than with CSSX solvent, still showed good extraction behavior.

Catherine L. Riddle; John D. Baker; Jack D. Law; Christopher A. McGrath; David H. Meikrantz; Bruce J. Mincher; Dean R. Peterman; Terry A. Todd

2004-10-01T23:59:59.000Z

85

VISION - Verifiable Fuel Cycle Simulation of Nuclear Fuel Cycle Dynamics  

SciTech Connect

The U.S. DOE Advanced Fuel Cycle Initiative’s (AFCI) fundamental objective is to provide technology options that - if implemented - would enable long-term growth of nuclear power while improving sustainability and energy security. The AFCI organization structure consists of four areas; Systems Analysis, Fuels, Separations and Transmutations. The Systems Analysis Working Group is tasked with bridging the program technical areas and providing the models, tools, and analyses required to assess the feasibility of design and deployment options and inform key decision makers. An integral part of the Systems Analysis tool set is the development of a system level model that can be used to examine the implications of the different mixes of reactors, implications of fuel reprocessing, impact of deployment technologies, as well as potential "exit" or "off ramp" approaches to phase out technologies, waste management issues and long-term repository needs. The Verifiable Fuel Cycle Simulation Model (VISION) is a computer-based simulation model that allows performing dynamic simulations of fuel cycles to quantify infrastructure requirements and identify key trade-offs between alternatives. It is based on the current AFCI system analysis tool "DYMOND-US" functionalities in addition to economics, isotopic decay, and other new functionalities. VISION is intended to serve as a broad systems analysis and study tool applicable to work conducted as part of the AFCI and Generation IV reactor development studies.

Steven J. Piet; A. M. Yacout; J. J. Jacobson; C. Laws; G. E. Matthern; D. E. Shropshire

2006-02-01T23:59:59.000Z

86

Nuclear Fuel Cycle | Department of Energy  

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

Cycle Cycle Nuclear Fuel Cycle This is an illustration of a nuclear fuel cycle that shows the required steps to process natural uranium from ore for preparation for fuel to be loaded in nuclear reactors. This is an illustration of a nuclear fuel cycle that shows the required steps to process natural uranium from ore for preparation for fuel to be loaded in nuclear reactors. The mission of NE-54 is primarily focused on activities related to the front end of the nuclear fuel cycle which includes mining, milling, conversion, and enrichment. Uranium Mining Both "conventional" open pit, underground mining, and in situ techniques are used to recover uranium ore. In general, open pit mining is used where deposits are close to the surface and underground mining is used

87

Hydrogen Fuel Quality - Focus: Analytical Methods Development...  

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

Fuel Quality - Focus: Analytical Methods Development & Hydrogen Fuel Quality Results Hydrogen Fuel Quality - Focus: Analytical Methods Development & Hydrogen Fuel Quality Results...

88

Used Nuclear Fuel Loading and Structural Performance Under Normal  

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

Nuclear Fuel Loading and Structural Performance Under Normal Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Demonstration of Approach and Results of Used Fuel Performance Characterization Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Demonstration of Approach and Results of Used Fuel Performance Characterization This report provides results of the initial demonstration of the modeling capability developed to perform preliminary deterministic evaluations of moderate-to-high burnup used nuclear fuel (UNF) mechanical performance under normal conditions of storage (NCS) and normal conditions of transport (NCT) conditions. This report also provides results from the sensitivity studies, and discussion on the long-term goals and objectives of this

89

Spent nuclear fuel project - criteria document spent nuclear fuel final safety analysis report  

SciTech Connect

The criteria document provides the criteria and planning guidance for developing the Spent Nuclear Fuel (SNF) Final Safety Analysis Report (FSAR). This FSAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, installation acceptance testing, startup, and operation of the SNF Project facilities (K Basins, Cold Vacuum Drying Facility, and Canister Storage Building).

MORGAN, R.G.

1999-02-23T23:59:59.000Z

90

Nuclear core and fuel assemblies  

DOE Patents (OSTI)

A fast flux nuclear core of a plurality of rodded, open-lattice assemblies having a rod pattern rotated relative to a rod support structure pattern. Elongated fuel rods are oriented on a triangular array and laterally supported by grid structures positioned along the length of the assembly. Initial inter-assembly contact is through strongbacks at the corners of the support pattern and peripheral fuel rods between adjacent assemblies are nested so as to maintain a triangular pitch across a clearance gap between the other portions of adjacent assemblies. The rod pattern is rotated relative to the strongback support pattern by an angle .alpha. equal to sin .sup.-1 (p/2c), where p is the intra-assembly rod pitch and c is the center-to-center spacing among adjacent assemblies.

Downs, Robert E. (Monroeville, PA)

1981-01-01T23:59:59.000Z

91

Alternative Fuels Data Center: Propane Fueling Infrastructure Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Infrastructure Development to someone by E-mail Infrastructure Development to someone by E-mail Share Alternative Fuels Data Center: Propane Fueling Infrastructure Development on Facebook Tweet about Alternative Fuels Data Center: Propane Fueling Infrastructure Development on Twitter Bookmark Alternative Fuels Data Center: Propane Fueling Infrastructure Development on Google Bookmark Alternative Fuels Data Center: Propane Fueling Infrastructure Development on Delicious Rank Alternative Fuels Data Center: Propane Fueling Infrastructure Development on Digg Find More places to share Alternative Fuels Data Center: Propane Fueling Infrastructure Development on AddThis.com... More in this section... Propane Basics Benefits & Considerations Stations Locations Infrastructure Development Vehicles Laws & Incentives

92

Alternative Fuels Data Center: Biodiesel Fueling Infrastructure Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Infrastructure Development to someone by E-mail Infrastructure Development to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Fueling Infrastructure Development on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Fueling Infrastructure Development on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Fueling Infrastructure Development on Google Bookmark Alternative Fuels Data Center: Biodiesel Fueling Infrastructure Development on Delicious Rank Alternative Fuels Data Center: Biodiesel Fueling Infrastructure Development on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Fueling Infrastructure Development on AddThis.com... More in this section... Biodiesel Basics Benefits & Considerations Stations Locations Infrastructure Development Vehicles Laws & Incentives

93

Plasma processing of spent nuclear fuel by two-frequency ion cyclotron resonance heating  

Science Journals Connector (OSTI)

A previously developed method for analyzing the plasma processing of spent nuclear fuel is generalized to a plasma containing multicharged fuel ions. In such a plasma, ion cyclotron resonance heating of nuclear a...

A. V. Timofeev

2009-11-01T23:59:59.000Z

94

Pyrochemical processing of DOE spent nuclear fuel  

SciTech Connect

A compact, efficient method for conditioning spent nuclear fuel is under development. This method, known as pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United States Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (>99.9%) separation of transuranics. The resultant waste forms from the pyroprocess, are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and avoid the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.

Laidler, J.J.

1995-02-01T23:59:59.000Z

95

Reactor Physics and Fuel Cycle Analysis - Nuclear Engineering Division  

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

Analysis Analysis Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Bookmark and Share Reactor physics and fuel cycle analysis is a core competency of the Nuclear Engineering (NE) Division. The Division has played a major role in the design and analysis of advanced reactors, particularly liquid-metal-cooled reactors. NE researchers have concentrated on developing computer codes for

96

Laser-based characterization of nuclear fuel plates  

SciTech Connect

Ensuring the integrity of fuel-clad and clad-clad bonding in nuclear fuels is important for safe reactor operation and assessment of fuel performance, yet the measurement of bond strengths in actual fuels has proved challenging. The laser shockwave technique (LST) originally developed to characterize structural adhesion in composites is being employed to characterize interface strength in a new type of plate fuel being developed at Idaho National Laboratory (INL). LST is a non-contact method that uses lasers for the generation and detection of large-amplitude acoustic waves and is well suited for application to both fresh and irradiated nuclear-fuel plates. This paper will report on initial characterization results obtained from fresh fuel plates manufactured by different processes, including hot isostatic pressing, friction stir welding, and hot rolling.

Smith, James A.; Cottle, Dave L.; Rabin, Barry H. [Idaho National Laboratory, Fuel Performance and Design, P.O. Box 1625, Idaho Falls, Idaho, 83415-6188 (United States)

2014-02-18T23:59:59.000Z

97

Examining 239Pu and 240Pu Nuclear Resonance Fluorescence Measurements on Spent Fuel for Nuclear Safeguards  

E-Print Network (OSTI)

on Spent Fuel for Nuclear Safeguards Brian J. Quiter, ?resonances on nuclear safeguards measurements will be

Quiter, Brian

2013-01-01T23:59:59.000Z

98

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

99

Materials Modeling and Simulation for Nuclear Fuels (MMSNF) Workshops  

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

Aerial photo of Argonne National Laboratory Argonne National Laboratory University of Chicago Chicago Photography courtesy Thomas F Ewing Privacy and Security Notice The MMSNF Workshops The goal of the Materials Modeling and Simulation for Nuclear Fuels (MMSNF) workshops is to stimulate research and discussions on modeling and simulations of nuclear fuels, to assist the design of improved fuels and the evaluation of fuel performance. In addition to research focused on existing or improved types of LWR reactors, recent modeling programs, networks, and links have been created to develop innovative nuclear fuels and materials for future generations of nuclear reactors. Examples can be found in Europe (e.g. F-BRIDGE project and ACTINET network and SAMANTHA cooperative network), in the USA (e.g. CASL, NEAMS, CESAR and CMSN network

100

Used Nuclear Fuel Loading and Structural Performance Under Normal  

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

Nuclear Fuel Loading and Structural Performance Under Normal Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan Used nuclear fuel (UNF) must maintain its integrity during the storage period in such a way that it can withstand the physical forces of handling and transportation associated with restaging the fuel and transporting it to treatment or recycling facilities, or to a geologic repository. This RD&D plan describes a methodology, including development and use of analytical models, to evaluate loading and associated mechanical responses of UNF rods and key structural components. The plan objective is to

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


101

Used Nuclear Fuel Loading and Structural Performance Under Normal  

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

Used Nuclear Fuel Loading and Structural Performance Under Normal Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan Used nuclear fuel (UNF) must maintain its integrity during the storage period in such a way that it can withstand the physical forces of handling and transportation associated with restaging the fuel and transporting it to treatment or recycling facilities, or to a geologic repository. This RD&D plan describes a methodology, including development and use of analytical models, to evaluate loading and associated mechanical responses of UNF rods and key structural components. The plan objective is to

102

Spent Nuclear Fuel (SNF) Project Execution Plan  

SciTech Connect

The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities.

LEROY, P.G.

2000-11-03T23:59:59.000Z

103

Uranium to Electricity: The Chemistry of the Nuclear Fuel Cycle  

Science Journals Connector (OSTI)

The nuclear fuel cycle consists of a series of industrial processes that produce fuel for the production of electricity in nuclear reactors, use the fuel to generate electricity, and subsequently manage the spent reactor fuel. While the physics and ...

Frank A. Settle

2009-03-01T23:59:59.000Z

104

Mississippi Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,251",8.0,"9,643",17.7 "Coal","2,526",16.1,"13,629",25.0 "Natural Gas","11,640",74.2,"29,619",54.4 "Other1",4,"*",10,"*" "Other Renewable1",235,1.5,"1,504",2.8 "Petroleum",35,0.2,81,0.1 "Total","15,691",100.0,"54,487",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

105

Iowa Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",601,4.1,"4,451",7.7 "Coal","6,956",47.7,"41,283",71.8 "Hydro and Pumped Storage",144,1.0,948,1.6 "Natural Gas","2,299",15.8,"1,312",2.3 "Other Renewable1","3,584",24.6,"9,360",16.3 "Petroleum","1,007",6.9,154,0.3 "Total","14,592",100.0,"57,509",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

106

Vermont Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",620,55.0,"4,782",72.2 "Hydro and Pumped Storage",324,28.7,"1,347",20.3 "Natural Gas","-","-",4,0.1 "Other Renewable1",84,7.5,482,7.3 "Petroleum",100,8.9,5,0.1 "Total","1,128",100.0,"6,620",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

107

Ohio Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,134",6.5,"15,805",11.0 "Coal","21,360",64.6,"117,828",82.1 "Hydro and Pumped Storage",101,0.3,429,0.3 "Natural Gas","8,203",24.8,"7,128",5.0 "Other1",123,0.4,266,0.2 "Other Renewable1",130,0.4,700,0.5 "Petroleum","1,019",3.1,"1,442",1.0 "Total","33,071",100.0,"143,598",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

108

Maryland Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,705",13.6,"13,994",32.1 "Coal","4,886",39.0,"23,668",54.3 "Hydro and Pumped Storage",590,4.7,"1,667",3.8 "Natural Gas","2,041",16.3,"2,897",6.6 "Other1",152,1.2,485,1.1 "Other Renewable1",209,1.7,574,1.3 "Petroleum","2,933",23.4,322,0.7 "Total","12,516",100.0,"43,607",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

109

Kansas Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,160",9.2,"9,556",19.9 "Coal","5,179",41.3,"32,505",67.8 "Hydro and Pumped Storage",3,"*",13,"*" "Natural Gas","4,573",36.5,"2,287",4.8 "Other Renewable1","1,079",8.6,"3,459",7.2 "Petroleum",550,4.4,103,0.2 "Total","12,543",100.0,"47,924",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

110

Connecticut Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,103",25.4,"16,750",50.2 "Coal",564,6.8,"2,604",7.8 "Hydro and Pumped Storage",151,1.8,400,1.2 "Natural Gas","2,292",27.7,"11,716",35.1 "Other1",27,0.3,730,2.2 "Other Renewable1",159,1.9,740,2.2 "Petroleum","2,989",36.1,409,1.2 "Total","8,284",100.0,"33,350",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

111

Nebraska Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,245",15.8,"11,054",30.2 "Coal","3,932",50.0,"23,363",63.8 "Hydro and Pumped Storage",278,3.5,"1,314",3.6 "Natural Gas","1,849",23.5,375,1.0 "Other Renewable1",165,2.1,493,1.3 "Petroleum",387,4.9,31,0.1 "Total","7,857",100.0,"36,630",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

112

Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Fuel  

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

Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Fuel Services Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Fuel Services GNEP would build and strengthen a reliable international fuel services consortium under which "fuel supplier nations" would choose to operate both nuclear power plants and fuel production and handling facilities, providing reliable fuel services to "user nations" that choose to only operate nuclear power plants. This international consortium is a critical component of the GNEP initiative to build an improved, more proliferation-resistant nuclear fuel cycle that recycles used fuel, while Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Fuel Services More Documents & Publications

113

Fuel Cycle Research & Development | Department of Energy  

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

Fuel Cycle Research & Fuel Cycle Research & Development Fuel Cycle Research & Development Fuel Cycle Research & Development The mission of the Fuel Cycle Research and Development (FCRD) program is to conduct research and development to help develop sustainable fuel cycles, as described in the Nuclear Energy Research and Development Roadmap. Sustainable fuel cycle options are those that improve uranium resource utilization, maximize energy generation, minimize waste generation, improve safety, and limit proliferation risk. The FCRD program will develop a suite of options to enable future policymakers to make informed decisions about how best to manage used fuel from nuclear reactors. The overall goal is to demonstrate the technologies necessary to allow commercial deployment of solutions for the sustainable management of used

114

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

E-Print Network (OSTI)

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...

Lafleur, Adrienne

2011-10-21T23:59:59.000Z

115

World nuclear fuel cycle requirements 1990  

SciTech Connect

This analysis report presents the projected requirements for uranium concentrate and uranium enrichment services to fuel the nuclear power plants expected to be operating under three nuclear supply scenarios. Two of these scenarios, the Lower Reference and Upper Reference cases, apply to the United States, Canada, Europe, the Far East, and other countries with free market economies (FME countries). A No New Orders scenario is presented only for the United States. These nuclear supply scenarios are described in Commercial Nuclear Power 1990: Prospects for the United States and the World (DOE/EIA-0438(90)). This report contains an analysis of the sensitivities of the nuclear fuel cycle projections to different levels and types of projected nuclear capacity, different enrichment tails assays, higher and lower capacity factors, changes in nuclear fuel burnup levels, and other exogenous assumptions. The projections for the United States generally extend through the year 2020, and the FME projections, which include the United States, are provided through 2010. The report also presents annual projections of spent nuclear fuel discharges and inventories of spent fuel. Appendix D includes domestic spent fuel projections through the year 2030 for the Lower and Upper Reference cases and through 2040, the last year in which spent fuel is discharged, for the No New Orders case. These disaggregated projections are provided at the request of the Department of Energy's Office of Civilian Radioactive Waste Management.

Not Available

1990-10-26T23:59:59.000Z

116

Nuclear Fuels Storage and Transportation Planning Project (NFST...  

Office of Environmental Management (EM)

Nuclear Fuels Storage and Transportation Planning Project (NFST) Program Status Nuclear Fuels Storage and Transportation Planning Project (NFST) Program Status Presentation made by...

117

2008 DOE Spent Nuclear Fuel and High Level Waste Inventory  

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

Management >> National Spent Nuclear Fuel INL Logo Search 2008 DOE Spent Nuclear Fuel and High Level Waste Inventory Content Goes Here Skip Navigation Links Home Newsroom About INL...

118

Used Nuclear Fuel Loading and Structural Performance Under Normal...  

Office of Environmental Management (EM)

Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan Used Nuclear Fuel Loading...

119

Fuel handling apparatus for a nuclear reactor  

DOE Patents (OSTI)

Fuel handling apparatus for transporting fuel elements into and out of a nuclear reactor and transporting them within the reactor vessel extends through a penetration in the side of the reactor vessel. A lateral transport device carries the fuel elements laterally within the vessel and through the opening in the side of the vessel, and a reversible lifting device raises and lowers the fuel elements. In the preferred embodiment, the lifting device is supported by a pair of pivot arms.

Hawke, Basil C. (Solana Beach, CA)

1987-01-01T23:59:59.000Z

120

Simulated nuclear reactor fuel assembly  

DOE Patents (OSTI)

An apparatus for electrically simulating a nuclear reactor fuel assembly. It includes a heater assembly having a top end and a bottom end and a plurality of concentric heater tubes having electrical circuitry connected to a power source, and radially spaced from each other. An outer target tube and an inner target tube is concentric with the heater tubes and with each other, and the outer target tube surrounds and is radially spaced from the heater tubes. The inner target tube is surrounded by and radially spaced from the heater tubes and outer target tube. The top of the assembly is generally open to allow for the electrical power connection to the heater tubes, and the bottom of the assembly includes means for completing the electrical circuitry in the heater tubes to provide electrical resistance heating to simulate the power profile in a nuclear reactor. The embedded conductor elements in each heater tube is split into two halves for a substantial portion of its length and provided with electrical isolation such that each half of the conductor is joined at one end and is not joined at the other end.

Berta, V.T.

1993-04-06T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Alternative Fuels Data Center: Alternative Fuel Standard Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Standard Development to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Standard Development on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Standard Development on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Standard Development on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Standard Development on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Standard Development on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Standard Development on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Standard Development The state of Hawaii is responsible for facilitating the development of

122

Alternative Fuels Data Center: Alternative Fuel Economic Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Economic Development to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Economic Development on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Economic Development on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Economic Development on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Economic Development on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Economic Development on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Economic Development on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Economic Development To stimulate local economic development, landowners may apply to amend the

123

Fuel cycle options for optimized recycling of nuclear fuel  

E-Print Network (OSTI)

The accumulation of transuranic inventories in spent nuclear fuel depends on both deployment of advanced reactors that can be loaded with recycled transuranics (TRU), and on availability of the facilities that separate and ...

Aquien, Alexandre

2006-01-01T23:59:59.000Z

124

Alternative Fuels Data Center: Fuel-Efficient Tire Program Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel-Efficient Tire Fuel-Efficient Tire Program Development to someone by E-mail Share Alternative Fuels Data Center: Fuel-Efficient Tire Program Development on Facebook Tweet about Alternative Fuels Data Center: Fuel-Efficient Tire Program Development on Twitter Bookmark Alternative Fuels Data Center: Fuel-Efficient Tire Program Development on Google Bookmark Alternative Fuels Data Center: Fuel-Efficient Tire Program Development on Delicious Rank Alternative Fuels Data Center: Fuel-Efficient Tire Program Development on Digg Find More places to share Alternative Fuels Data Center: Fuel-Efficient Tire Program Development on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Fuel-Efficient Tire Program Development The California Energy Commission (CEC) must adopt and implement a

125

Walk the Line: The Development of Route Selection Standards for Spent Nuclear Fuel and High-level Radioactive Waste in the United States - 13519  

SciTech Connect

Although storage facilities for spent nuclear fuel (SNF) and high-level radioactive waste (HLRW) are widely dispersed throughout the United States, these materials are also relatively concentrated in terms of geographic area. That is, the impacts of storage occur in a very small geographic space. Once shipments begin to a national repository or centralized interim storage facility, the impacts of SNF and HLRW will become more geographically distributed, more publicly visible, and almost certainly more contentious. The selection of shipping routes will likely be a major source of controversy. This paper describes the development of procedures, regulations, and standards for the selection of routes used to ship spent nuclear fuel and high-level radioactive waste in the United States. The paper begins by reviewing the circumstances around the development of HM-164 routing guidelines. The paper discusses the significance of New York City versus the Department of Transportation and application of HM-164. The paper describes the methods used to implement those regulations. The paper will also describe the current HM-164 designated routes and will provide a summary data analysis of their characteristics. This analysis will reveal the relatively small spatial scale of the effects of HM 164. The paper will then describe subsequent developments that have affected route selection for these materials. These developments include the use of 'representative routes' found in the Department of Energy (DOE) 2008 Supplemental Environmental Impact Statement for the formerly proposed Yucca Mountain geologic repository. The paper will describe recommendations related to route selection found in the National Academy of Sciences 2006 report Going the Distance, as well as recommendations found in the 2012 Final Report of the Blue Ribbon Commission on America's Nuclear Future. The paper will examine recently promulgated federal regulations (HM-232) for selection of rail routes for hazardous materials transport. The paper concludes that while the HM 164 regime is sufficient for certain applications, it does not provide an adequate basis for a national plan to ship spent nuclear fuel and high-level radioactive waste to centralized storage and disposal facilities over a period of 30 to 50 years. (authors)

Dilger, Fred [Black Mountain Research, Henderson, NV 81012 (United States)] [Black Mountain Research, Henderson, NV 81012 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States)] [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge, CA 91330 (United States)] [Department of Sociology, California State University, Northridge, CA 91330 (United States)

2013-07-01T23:59:59.000Z

126

Gap Analysis to Support Extended Storage of Used Nuclear Fuel | Department  

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

Gap Analysis to Support Extended Storage of Used Nuclear Fuel Gap Analysis to Support Extended Storage of Used Nuclear Fuel Gap Analysis to Support Extended Storage of Used Nuclear Fuel The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development activities related to storage, transportation, and disposal of used nuclear fuel and high-level radioactive waste. 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 (UNF) and wastes generated by existing and future nuclear fuel cycles. The Storage and Transportation staff within the UFDC are responsible for addressing issues regarding the

127

LMFBR operation in the nuclear cycle without fuel reprocessing  

SciTech Connect

Substantiation is given to expediency of investigation of nuclear power (NP) development with fast reactors cooled by lead-bismuth alloy operating during extended time in the open nuclear fuel cycle with slightly enriched or depleted uranium make-up. 9 refs., 1 fig., 6 tabs.

Toshinsky, S.I. [Institute of Physics and Power Engineering, Kaluga (Russian Federation)

1997-12-01T23:59:59.000Z

128

HTR Fuel Development in Europe  

SciTech Connect

In the frame of the European Network HTR-TN and in the 5. EURATOM RTD Framework Programme (FP5) European programmes have been launched to consolidate advanced modular HTR technology in Europe. This paper gives an overall description and first results of this programme. The major tasks covered concern a complete recovery of the past experience on fuel irradiation behaviour in Europe, qualification of HTR fuel by irradiating of fuel elements in the HFR reactor, understanding of fuel behaviour with the development of a fuel particle code and finally a recover of the fuel fabrication capability. (authors)

Languille, Alain [CEA Cadarache, 13108 Saint-Paul-lez-Durance BP1 (France); Conrad, R. [CEC/JRC/IE Petten (Netherlands); Guillermier, P. [Framatome-ANP/ Lyon (France); Nabielek, H. [FZJ/Juelich (Germany); Bakker, K. [NRG/Petten (Netherlands); Abram, T. [BNFL UK (United Kingdom); Haas, D. [JRC/ITU/Karlsruhe (Germany)

2002-07-01T23:59:59.000Z

129

Development of Pillared M(IV) Phosphate Phosphonate Inorganic Organic Hybrid Ion Exchange Materials for Applications in Separations found in the Nuclear Fuel Cycle  

E-Print Network (OSTI)

This dissertation focuses on key intergroup and intragroup separations found in the back end of the nuclear fuel cycle, specifically americium from lanthanides and americium from other actinides, most importantly americium from curium. Our goal...

Burns, Jonathan

2012-10-02T23:59:59.000Z

130

Department of Energy Awards $15 Million for Nuclear Fuel Cycle Technology  

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

15 Million for Nuclear Fuel Cycle 15 Million for Nuclear Fuel Cycle Technology Research and Development Department of Energy Awards $15 Million for Nuclear Fuel Cycle Technology Research and Development August 1, 2008 - 2:40pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced it will award up to $15 million to 34 research organizations as part of the Department's Advanced Fuel Cycle Initiative (AFCI). AFCI is the Department's nuclear energy research and development program supporting the long-term goals and objectives of the United States' nuclear energy policy. These projects will provide necessary data and analyses to further U.S. nuclear fuel cycle technology development, meet the need for advanced nuclear energy production and help to close the nuclear fuel cycle

131

Software: Reactor Physics and Fuel Cycle Analysis - Nuclear Engineering  

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

Analysis > Analysis > Software Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Software Bookmark and Share An extensive powerful suite of computer codes developed and validated by the NE Division and its predecessor divisions at Argonne supports the development of fast reactors; many of these codes are also applicable to other reactor types. A brief description of these codes follows. Contact

132

Overview of the nuclear fuel cycle  

SciTech Connect

The use of nuclear reactors to provide electrical energy has shown considerable growth since the first nuclear plant started commercial operation in the mid 1950s. Although the main purpose of this paper is to review the fuel cycle capabilities in the United States, the introduction is a brief review of the types of nuclear reactors in use and the world-wide nuclear capacity.

Leuze, R.E.

1982-01-01T23:59:59.000Z

133

Alternative Fuels Data Center: Alternative Fuel Development and Deployment  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Development and Deployment Grants to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Development and Deployment Grants on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Development and Deployment Grants on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Development and Deployment Grants on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Development and Deployment Grants on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Development and Deployment Grants on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Development and Deployment Grants on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type

134

Thermodynamics of high-temperature nuclear fuel  

Science Journals Connector (OSTI)

A method for performing a thermodynamic analysis of the high-temperature nuclear fuel using the ASTA computer program is substantiated. Calculations of the chemical composition and pressure of the gas phase of...

I. A. Belov; A. S. Ivanov

135

Chemistry of nuclear fuel reprocessing: Current status  

Science Journals Connector (OSTI)

Current status on the chemical aspects of nuclear fuel reprocessing is presented with special emphasis on the Purex process which continues to be the process of choice for the last four decades. Better deconta...

D. D. Sood; S. K. Patil

1996-03-01T23:59:59.000Z

136

Transuranium Elements in the Nuclear Fuel Cycle  

Science Journals Connector (OSTI)

Transuranium elements, neptunium, plutonium, americium, and curium, are formed via neutron capture processes of actinides, and are mainly by-products of fuel irradiation during the operation of a nuclear react...

Thomas Fanghänel; Jean-Paul Glatz; Rudy J. M. Konings…

2010-01-01T23:59:59.000Z

137

A FRAMEWORK TO DEVELOP FLAW ACCEPTANCE CRITERIA FOR STRUCTURAL INTEGRITY ASSESSMENT OF MULTIPURPOSE CANISTERS FOR EXTENDED STORAGE OF USED NUCLEAR FUEL  

SciTech Connect

A multipurpose canister (MPC) made of austenitic stainless steel is loaded with used nuclear fuel assemblies and is part of the transfer cask system to move the fuel from the spent fuel pool to prepare for storage, and is part of the storage cask system for on-site dry storage. This weld-sealed canister is also expected to be part of the transportation package following storage. The canister may be subject to service-induced degradation especially if exposed to aggressive environments during possible very long-term storage period if the permanent repository is yet to be identified and readied. Stress corrosion cracking may be initiated on the canister surface in the welds or in the heat affected zone because the construction of MPC does not require heat treatment for stress relief. An acceptance criteria methodology is being developed for flaw disposition should the crack-like defects be detected by periodic Inservice Inspection. The external loading cases include thermal accident scenarios and cask drop conditions with the contribution from the welding residual stresses. The determination of acceptable flaw size is based on the procedure to evaluate flaw stability provided by American Petroleum Institute (API) 579 Fitness-for-Service (Second Edition). The material mechanical and fracture properties for base and weld metals and the stress analysis results are obtained from the open literature such as NUREG-1864. Subcritical crack growth from stress corrosion cracking (SCC), and its impact on inspection intervals and acceptance criteria, is not addressed.

Lam, P.; Sindelar, R.; Duncan, A.; Adams, T.

2014-04-07T23:59:59.000Z

138

Fuel availability in nuclear power.  

E-Print Network (OSTI)

?? Nuclear power is in focus of attention due to several factors these days and the expression “nuclear renaissance” is getting well known. However, concerned… (more)

Söderlund, Karl

2009-01-01T23:59:59.000Z

139

Fresh nuclear fuel measurements at Ukrainian nuclear power plants  

SciTech Connect

In 2005, the Provisions on Nuclear Material Measurement System was enacted in Ukraine as an important regulatory driver to support international obligations in nuclear safeguards and nonproliferation. It defines key provisions and requirements for material measurement and measurement control programs to ensure the quality and reliability of measurement data within the framework of the State MC&A System. Implementing the Provisions requires establishing a number of measurement techniques for both fresh and spent nuclear fuel for various types of Ukrainian reactors. Our first efforts focused on measurements of fresh nuclear fuel from a WWR-1000 power reactor.

Kuzminski, Jozef [Los Alamos National Laboratory; Ewing, Tom [ANL; Dickman, Debbie [PNNL; Gavrilyuk, Victor [UKRAINE; Drapey, Sergey [UKRAINE; Kirischuk, Vladimir [UKRAINE; Strilchuk, Nikolay [UKRAINE

2009-01-01T23:59:59.000Z

140

Fuel Cycle Research & Development Documents | Department of Energy  

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

Initiatives » Fuel Cycle Technologies » Fuel Cycle Research & Initiatives » Fuel Cycle Technologies » Fuel Cycle Research & Development » Fuel Cycle Research & Development Documents Fuel Cycle Research & Development Documents November 8, 2011 2011 Fuel Cycle Technologies Annual Review Meeting As the largest domestic source of low-carbon energy, nuclear power is making major contributions toward meeting our nation's current and future energy demands. The United States must continue to ensure improvements and access to this technology so we can meet our economic, environmental and energy security goals. We rely on nuclear energy because it provides a consistent, reliable and stable source of base load electricity with an excellent safety record in the United States. July 11, 2011 Nuclear Separations Technologies Workshop Report

Note: This page contains sample records for the topic "development nuclear fuels" 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

International Nuclear Fuel Cycle Fact Book. Revision 5  

SciTech Connect

This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

1985-01-01T23:59:59.000Z

142

International nuclear fuel cycle fact book. Revision 4  

SciTech Connect

This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-03-01T23:59:59.000Z

143

Honeywell developing fuel cell sensors  

Science Journals Connector (OSTI)

In the US, four development teams from Honeywell Sensing & Control are collaborating in a DOE project to develop sensors that provide better control in the demanding fuel cell environment.

2004-01-01T23:59:59.000Z

144

Alternative Fuels Data Center: Alternative Fuel Research, Development, and  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Research, Development, and Promotion to someone by E-mail Research, Development, and Promotion to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Research, Development, and Promotion on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Research, Development, and Promotion on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Research, Development, and Promotion on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Research, Development, and Promotion on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Research, Development, and Promotion on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Research, Development, and Promotion on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type

145

Alternative Fuels Data Center: Alternative Fuel Development Property Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Development Property Tax Exemption to someone by E-mail Development Property Tax Exemption to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Development Property Tax Exemption on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Development Property Tax Exemption on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Development Property Tax Exemption on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Development Property Tax Exemption on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Development Property Tax Exemption on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Development Property Tax Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type

146

U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel  

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

U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel Development U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel Development A significant effort is being placed on silicon carbide ceramic matrix composite (SiC CMC) nuclear fuel cladding by Light Water Reactor Sustainability (LWRS) Advanced Light Water Reactor Nuclear Fuels Pathway. The intent of this work is to invest in a high-risk, high-reward technology that can be introduced in a relatively short time. The LWRS goal is to demonstrate successful advanced fuels technology that suitable for commercial development to support nuclear relicensing. Ceramic matrix composites are an established non-nuclear technology that utilizes ceramic fibers embedded in a ceramic matrix. A thin interfacial layer between the

147

DOE Seeks to Invest up to $15 Million in Funding for Nuclear Fuel Cycle  

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

DOE Seeks to Invest up to $15 Million in Funding for Nuclear Fuel DOE Seeks to Invest up to $15 Million in Funding for Nuclear Fuel Cycle Technology Research and Development DOE Seeks to Invest up to $15 Million in Funding for Nuclear Fuel Cycle Technology Research and Development April 17, 2008 - 10:49am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today issued a Funding Opportunity Announcement (FOA) inviting universities, national laboratories, and industry to compete for up to $15 million to advance nuclear technologies closing the nuclear fuel cycle. These projects will provide necessary data and analyses to further U.S. nuclear fuel cycle technology development, as part of the Department's Advanced Fuel Cycle Initiative (AFCI), the domestic technology R&D component of the Global Nuclear Energy Partnership (GNEP). Studies resulting from this FOA will

148

DOE Seeks to Invest up to $15 Million in Funding for Nuclear Fuel Cycle  

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

Seeks to Invest up to $15 Million in Funding for Nuclear Fuel Seeks to Invest up to $15 Million in Funding for Nuclear Fuel Cycle Technology Research and Development DOE Seeks to Invest up to $15 Million in Funding for Nuclear Fuel Cycle Technology Research and Development April 17, 2008 - 10:49am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today issued a Funding Opportunity Announcement (FOA) inviting universities, national laboratories, and industry to compete for up to $15 million to advance nuclear technologies closing the nuclear fuel cycle. These projects will provide necessary data and analyses to further U.S. nuclear fuel cycle technology development, as part of the Department's Advanced Fuel Cycle Initiative (AFCI), the domestic technology R&D component of the Global Nuclear Energy Partnership (GNEP). Studies resulting from this FOA will

149

An overview of measurement methods for special nuclear material in spent nuclear fuel  

SciTech Connect

Summary results from a survey of nondestructive assay measurement methods applicable to the measurement of the special nuclear material content of spent nuclear fuel are described. The role of nuclear materials measurements in the domestic and international safeguarding of spent nuclear fuel in the United States' federal waste management system has yet to be determined. An understanding of the characteristics and capabilities of the potentially applicable measurement systems should provide valuable information to the developers of the safeguards approaches for the monitored retrievable storage and final disposal systems. The discussion focuses on the general characteristics of the identified direct and indirect measurement methods. 3 refs., 1 tab.

Moran, B.W.; Reich, W.J.

1989-07-01T23:59:59.000Z

150

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

151

Used Fuel Disposition Campaign Disposal Research and Development...  

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

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...

152

Global Nuclear Energy Partnership Fact Sheet - Develop Advanced Burner  

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

Develop Advanced Develop Advanced Burner Reactors Global Nuclear Energy Partnership Fact Sheet - Develop Advanced Burner Reactors GNEP will develop and demonstrate Advanced Burner Reactors (ABRs) that consume transuranic elements (plutonium and other long-lived radioactive material) while extracting their energy. The development of ABRs will allow us to build an improved nuclear fuel cycle that recycles used fuel. Accordingly, the U.S. will work with participating international partners on the design, development, and demonstration of ABRs as part of the GNEP. Global Nuclear Energy Partnership Fact Sheet - Develop Advanced Burner Reactors More Documents & Publications GNEP Element:Develop Advanced Burner Reactors Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear Waste

153

Characterization of Zr-Fe-Cu Alloys for an Inert Matrix Fuel for Nuclear Energy Applications  

E-Print Network (OSTI)

An ultra-high burnup metallic inert matrix nuclear fuel concept is being characterized and evaluated by Lawrence Livermore National Laboratory based on a metal matrix fuel concept originally developed at the Bochvar Institute in Russia. The concept...

Barnhart, Brian A.

2013-08-09T23:59:59.000Z

154

Survey of Dynamic Simulation Programs for Nuclear Fuel Reprocessing  

SciTech Connect

The absence of any industrial scale nuclear fuel reprocessing in the U.S. has precluded the necessary driver for developing the advanced simulation capability now prevalent in so many other industries. Modeling programs to simulate the dynamic behavior of nuclear fuel separations and processing were originally developed to support the US government’s mission of weapons production and defense fuel recovery. Consequently there has been little effort is the US devoted towards improving this specific process simulation capability during the last two or three decades. More recent work has been focused on elucidating chemical thermodynamics and developing better models of predicting equilibrium in actinide solvent extraction systems. These equilibrium models have been used to augment flowsheet development and testing primarily at laboratory scales. The development of more robust and complete process models has not kept pace with the vast improvements in computational power and user interface and is significantly behind simulation capability in other chemical processing and separation fields.

Troy J. Tranter; Daryl R. Haefner

2008-06-01T23:59:59.000Z

155

Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive  

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

Categorization of Used Nuclear Fuel Inventory in Support of a Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy The Office of Nuclear Energy has conducted a technical review and assessment of the total current inventory [~70,150 MTHM as of 2011] of domestic discharged used nuclear fuel (UNF) and estimated an amount to be considered for retention in support of research, development, demonstration, and national security interests. The study recognizes that: 1) access to some amount of UNF is needed to support RD&D; 2) the two principal options for addressing UNF management are geologic disposal and recycling, and 3) U.S. nuclear power plants will continue to discharge

156

A framework and methodology for nuclear fuel cycle transparency.  

SciTech Connect

A key objective to the global deployment of nuclear technology is maintaining transparency among nation-states and international communities. By providing an environment in which to exchange scientific and technological information regarding nuclear technology, the safe and legitimate use of nuclear material and technology can be assured. Many nations are considering closed or multiple-application nuclear fuel cycles and are subsequently developing advanced reactors in an effort to obtain some degree of energy self-sufficiency. Proliferation resistance features that prevent theft or diversion of nuclear material and reduce the likelihood of diversion from the civilian nuclear power fuel cycle are critical for a global nuclear future. IAEA Safeguards have been effective in minimizing opportunities for diversion; however, recent changes in the global political climate suggest implementation of additional technology and methods to ensure the prompt detection of proliferation. For a variety of reasons, nuclear facilities are becoming increasingly automated and will require minimum manual operation. This trend provides an opportunity to utilize the abundance of process information for monitoring proliferation risk, especially in future facilities. A framework that monitors process information continuously can lead to greater transparency of nuclear fuel cycle activities and can demonstrate the ability to resist proliferation associated with these activities. Additionally, a framework designed to monitor processes will ensure the legitimate use of nuclear material. This report describes recent efforts to develop a methodology capable of assessing proliferation risk in support of overall plant transparency. The framework may be tested at the candidate site located in Japan: the Fuel Handling Training Model designed for the Monju Fast Reactor at the International Cooperation and Development Training Center of the Japan Atomic Energy Agency.

McClellan, Yvonne; York, David L.; Inoue, Naoko (Japan Atomic Energy Agency, Ibaraki, Japan); Love, Tracia L.; Rochau, Gary Eugene

2006-02-01T23:59:59.000Z

157

Characterization plan for Hanford spent nuclear fuel  

SciTech Connect

Reprocessing of spent nuclear fuel (SNF) at the Hanford Site Plutonium-Uranium Extraction Plant (PUREX) was terminated in 1972. Since that time a significant quantity of N Reactor and Single-Pass Reactor SNF has been stored in the 100 Area K-East (KE) and K-West (KW) reactor basins. Approximately 80% of all US Department of Energy (DOE)-owned SNF resides at Hanford, the largest portion of which is in the water-filled KE and KW reactor basins. The basins were not designed for long-term storage of the SNF and it has become a priority to move the SNF to a more suitable location. As part of the project plan, SNF inventories will be chemically and physically characterized to provide information that will be used to resolve safety and technical issues for development of an environmentally benign and efficient extended interim storage and final disposition strategy for this defense production-reactor SNF.

Abrefah, J.; Thornton, T.A.; Thomas, L.E.; Berting, F.M.; Marschman, S.C.

1994-12-01T23:59:59.000Z

158

Nuclear Fuel Cycle Reasoner: PNNL FY12 Report  

SciTech Connect

Building on previous internal investments and leveraging ongoing advancements in semantic technologies, PNNL implemented a formal reasoning framework and applied it to a specific challenge in nuclear nonproliferation. The Semantic Nonproliferation Analysis Platform (SNAP) was developed as a preliminary graphical user interface to demonstrate the potential power of the underlying semantic technologies to analyze and explore facts and relationships relating to the nuclear fuel cycle (NFC). In developing this proof of concept prototype, the utility and relevancy of semantic technologies to the Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D) has been better understood.

Hohimer, Ryan E.; Pomiak, Yekaterina G.; Neorr, Peter A.; Gastelum, Zoe N.; Strasburg, Jana D.

2013-05-03T23:59:59.000Z

159

Nuclear Fuel Facts: Uranium | Department of Energy  

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

Uranium Management and Uranium Management and Policy » Nuclear Fuel Facts: Uranium Nuclear Fuel Facts: Uranium Nuclear Fuel Facts: Uranium Uranium is a silvery-white metallic chemical element in the periodic table, with atomic number 92. It is assigned the chemical symbol U. A uranium atom has 92 protons and 92 electrons, of which 6 are valence electrons. Uranium has the highest atomic weight (19 kg m) of all naturally occurring elements. Uranium occurs naturally in low concentrations in soil, rock and water, and is commercially extracted from uranium-bearing minerals such as uraninite. Uranium ore can be mined from open pits or underground excavations. The ore can then be crushed and treated at a mill to separate the valuable uranium from the ore. Uranium may also be dissolved directly from the ore deposits

160

International Nuclear Fuel Cycle Fact Book  

SciTech Connect

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

Leigh, I.W.

1992-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Double-clad nuclear fuel safety rod  

DOE Patents (OSTI)

A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

McCarthy, William H. (Los Altos, CA); Atcheson, Donald B. (Cupertino, CA); Vaidyanathan, Swaminathan (San Jose, CA)

1984-01-01T23:59:59.000Z

162

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000 F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics. 5 figs.

Heubeck, N.B.

1998-09-08T23:59:59.000Z

163

Nuclear Fuel Cycle Reasoner: PNNL FY13 Report  

SciTech Connect

In Fiscal Year 2012 (FY12) PNNL implemented a formal reasoning framework and applied it to a specific challenge in nuclear nonproliferation. The Semantic Nonproliferation Analysis Platform (SNAP) was developed as a preliminary graphical user interface to demonstrate the potential power of the underlying semantic technologies to analyze and explore facts and relationships relating to the nuclear fuel cycle (NFC). In Fiscal Year 2013 (FY13) the SNAP demonstration was enhanced with respect to query and navigation usability issues.

Hohimer, Ryan E.; Strasburg, Jana D.

2013-09-30T23:59:59.000Z

164

Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels -- Final Report under the International Nuclear Energy Research Initiative (I-NERI)  

SciTech Connect

The objective of this INERI project was to develop improved fuel behavior models for gas reactor coated-particle fuels and to explore improved coated-particle fuel designs that could be used reliably at very high burnups and potentially in gas-cooled fast reactors. Project participants included the Idaho National Engineering Laboratory (INEEL), Centre Étude Atomique (CEA), and the Massachusetts Institute of Technology (MIT). To accomplish the project objectives, work was organized into five tasks.

David Petti; Philippe Martin; Mayeul Phélip; Ronald Ballinger; Petti does not have NT account

2004-12-01T23:59:59.000Z

165

International nuclear fuel cycle fact book. [Contains glossary  

SciTech Connect

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is a consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

Leigh, I.W.; Lakey, L.T.; Schneider, K.J.; Silviera, D.J.

1987-01-01T23:59:59.000Z

166

Michigan Nuclear Profile - All Fuels  

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

total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,947",13.2,"29,625",26.6 "Coal","11,531",38.7,"65,604",58.8 "Hydro and Pumped...

167

Minnesota Nuclear Profile - All Fuels  

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

total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,594",10.8,"13,478",25.1 "Coal","4,789",32.5,"28,083",52.3 "Hydro and Pumped...

168

Wisconsin Nuclear Profile - All Fuels  

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

total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,584",8.9,"13,281",20.7 "Coal","8,063",45.2,"40,169",62.5 "Hydro and Pumped...

169

Washington Nuclear Profile - All Fuels  

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

total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,097",3.6,"9,241",8.9 "Coal","1,340",4.4,"8,527",8.2 "Hydro and Pumped...

170

Virginia Nuclear Profile - All Fuels  

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

total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,501",14.5,"26,572",36.4 "Coal","5,868",24.3,"25,459",34.9 "Hydro and Pumped...

171

Nuclear fuel cycle facility accident analysis handbook  

SciTech Connect

The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

NONE

1998-03-01T23:59:59.000Z

172

A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles  

E-Print Network (OSTI)

Nuclear   Fuel”,   Nuclear  Engineering  and  Technology,  in   Engineering  -­?  Nuclear  Engineering   and  the  in  Engineering  -­?  Nuclear  Engineering   and  the  

Djokic, Denia

2013-01-01T23:59:59.000Z

173

Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay  

SciTech Connect

In nuclear resonance fluorescence (NRF) measurements, resonances are excited by an external photon beam leading to the emission of gamma rays with specific energies that are characteristic of the emitting isotope. NRF promises the unique capability of directly quantifying a specific isotope without the need for unfolding the combined responses of several fissile isotopes as is required in other measurement techniques. We have analyzed the potential of NRF as a non-destructive analysis technique for quantitative measurements of Pu isotopes in spent nuclear fuel (SNF). Given the low concentrations of 239Pu in SNF and its small integrated NRF cross sections, the main challenge in achieving precise and accurate measurements lies in accruing sufficient counting statistics in a reasonable measurement time. Using analytical modeling, and simulations with the radiation transport code MCNPX that has been experimentally tested recently, the backscatter and transmission methods were quantitatively studied for differing photon sources and radiation detector types. Resonant photon count rates and measurement times were estimated for a range of photon source and detection parameters, which were used to determine photon source and gamma-ray detector requirements. The results indicate that systems based on a bremsstrahlung source and present detector technology are not practical for high-precision measurements of 239Pu in SNF. Measurements that achieve the desired uncertainties within hour-long measurements will either require stronger resonances, which may be expressed by other Pu isotopes, or require quasi-monoenergetic photon sources with intensities that are approximately two orders of magnitude higher than those currently being designed or proposed.This work is part of a larger effort sponsored by the Next Generation Safeguards Initiative to develop an integrated instrument, comprised of individual NDA techniques with complementary features, that is fully capable of determining Pu mass in spent fuel assemblies.

Quiter, Brian; Ludewigt, Bernhard; Ambers, Scott

2011-06-30T23:59:59.000Z

174

Nuclear Fuels Storage & Transportation Planning Project Documents |  

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

Fuel Cycle Technologies » Nuclear Fuels Storage & Fuel Cycle Technologies » Nuclear Fuels Storage & Transportation Planning Project » Nuclear Fuels Storage & Transportation Planning Project Documents Nuclear Fuels Storage & Transportation Planning Project Documents September 30, 2013 Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. February 22, 2013 Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal This report provides findings from a set of social science studies

175

JPRS report, nuclear developments  

SciTech Connect

This report contains articles concerning the nuclear developments of the following countries: (1) China; (2) Japan, North Korea, South Korea, Taiwan; (3) Bulgaria, Czechoslovakia, Yugoslavia; (4) Argentina, Brazil, Panama; (5) India, Iran, Pakistan, Israel, Afghanistan; (6) Soviet Union; (7) France, Germany, Turkey, Belgium, Canada, Netherlands, Switzerland, United Kingdom; and (8) South Africa.

NONE

1991-03-19T23:59:59.000Z

176

Seawater Enhances the Corrosion of Nuclear Fuel Rods | Photosynthetic...  

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

Seawater Enhances the Corrosion of Nuclear Fuel Rods April 19, 2012 Seawater Enhances the Corrosion of Nuclear Fuel Rods PARC Post Doc Anne-Marie Carey is featured in DOE Frontiers...

177

Strategy for the Management and Disposal of Used Nuclear Fuel...  

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

Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level...

178

Plasma processing of spent nuclear fuel by two-frequency ion cyclotron resonance heating  

SciTech Connect

A previously developed method for analyzing the plasma processing of spent nuclear fuel is generalized to a plasma containing multicharged fuel ions. In such a plasma, ion cyclotron resonance heating of nuclear ash ions should be carried out in two monochromatic RF fields of different frequencies, provided that the fraction of {xi} multicharged ions is small, {xi} {<=} 0.1, a condition that substantially restricts the productivity of systems for processing spent nuclear fuel. Ways of overcoming this difficulty are discussed.

Timofeev, A. V. [Russian Research Centre Kurchatov Institute, Nuclear Fusion Institute (Russian Federation)

2009-11-15T23:59:59.000Z

179

Environmental Impact of the Nuclear Fuel Cycle: Fate of Actinides  

SciTech Connect

The resurgence of nuclear power as a strategy for reducing greenhouse gas (GHG) emissions has, in parallel, revived interest in the environmental impact of actinides. Just as GHG emissions are the main environmental impact of the combustion of fossil fuels, the fate of actinides, consumed and produced by nuclear reactions, determines whether nuclear power is viewed as an environmentally “friendly” source of energy. In this article, we summarize the sources of actinides in the nuclear fuel cycle, how actinides are separated by chemical processing, the development of actinide-bearing materials, and the behavior of actinides in the environment. At each stage, actinides present a unique and complicated behavior because of the 5f electronic configurations.

Ewing, Rodney C.; Runde, W.; Albrecht-Schmitt, Thomas E.

2010-01-01T23:59:59.000Z

180

Synergistic smart fuel for in-pile nuclear reactor measurements  

SciTech Connect

The thermo-acoustic fuel rod sensor developed in this research has demonstrated a novel technique for monitoring the temperature within the core of a nuclear reactor or the temperature of the surrounding heat-transfer fluid. It uses the heat from the nuclear fuel to generate sustained acoustic oscillations whose frequency will be indicative of the temperature. Converting a nuclear fuel rod into this type of thermo-acoustic sensor simply requires the insertion of a porous material (stack). This sensor has demonstrated a synergy with the elevated temperatures that exist within the nuclear reactor using materials that have only minimal susceptibility to high-energy particle fluxes. When the sensor is in operation, the sound waves radiated from the fuel rod resonator will propagate through the surrounding cooling fluid. The frequency of these oscillations is directly correlated with an effective temperature within the fuel rod resonator. This device is self-powered and is operational even in case of total loss of power of the reactor.

Smith, J.A.; Kotter, D.K. [Idaho National Laboratories, Idaho Falls (United States); Ali, R.A.; Garrett, S.L. [Penn State University, University Park, State College, PA 16801 (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Verifiable Fuel Cycle Simulation Model (VISION): A Tool for Analyzing Nuclear Fuel Cycle Futures  

SciTech Connect

The nuclear fuel cycle consists of a set of complex components that are intended to work together. To support the nuclear renaissance, it is necessary to understand the impacts of changes and timing of events in any part of the fuel cycle system such as how the system would respond to each technological change, a series of which moves the fuel cycle from where it is to a postulated future state. The system analysis working group of the United States research program on advanced fuel cycles (formerly called the Advanced Fuel Cycle Initiative) is developing a dynamic simulation model, VISION, to capture the relationships, timing, and changes in and among the fuel cycle components to help develop an understanding of how the overall fuel cycle works. This paper is an overview of the philosophy and development strategy behind VISION. The paper includes some descriptions of the model components and some examples of how to use VISION. For example, VISION users can now change yearly the selection of separation or reactor technologies, the performance characteristics of those technologies, and/or the routing of material among separation and reactor types - with the model still operating on a PC in <5 min.

Jacob J. Jacobson; Steven J. Piet; Gretchen E. Matthern; David E. Shropshire; Robert F. Jeffers; A. M. Yacout; Tyler Schweitzer

2010-11-01T23:59:59.000Z

182

Comparative analysis of LWR and FBR spent fuels for nuclear forensics evaluation  

SciTech Connect

Some interesting issues are attributed to nuclide compositions of spent fuels from thermal reactors as well as fast reactors such as a potential to reuse as recycled fuel, and a possible capability to be manage as a fuel for destructive devices. In addition, analysis on nuclear forensics which is related to spent fuel compositions becomes one of the interesting topics to evaluate the origin and the composition of spent fuels from the spent fuel foot-prints. Spent fuel compositions of different fuel types give some typical spent fuel foot prints and can be estimated the origin of source of those spent fuel compositions. Some technics or methods have been developing based on some science and technological capability including experimental and modeling or theoretical aspects of analyses. Some foot-print of nuclear forensics will identify the typical information of spent fuel compositions such as enrichment information, burnup or irradiation time, reactor types as well as the cooling time which is related to the age of spent fuels. This paper intends to evaluate the typical spent fuel compositions of light water (LWR) and fast breeder reactors (FBR) from the view point of some foot prints of nuclear forensics. An established depletion code of ORIGEN is adopted to analyze LWR spent fuel (SF) for several burnup constants and decay times. For analyzing some spent fuel compositions of FBR, some coupling codes such as SLAROM code, JOINT and CITATION codes including JFS-3-J-3.2R as nuclear data library have been adopted. Enriched U-235 fuel composition of oxide type is used for fresh fuel of LWR and a mixed oxide fuel (MOX) for FBR fresh fuel. Those MOX fuels of FBR come from the spent fuels of LWR. Some typical spent fuels from both LWR and FBR will be compared to distinguish some typical foot-prints of SF based on nuclear forensic analysis.

Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki [Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 Nuclear Physics and Bio (Indonesia); Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 (Japan); Nuclear Physics and Bio Physics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia)

2012-06-06T23:59:59.000Z

183

OECD/NEA Ongoing activities related to the nuclear fuel cycle  

SciTech Connect

As part of its role in encouraging international collaboration, the OECD Nuclear Energy Agency is coordinating a series of projects related to the Nuclear Fuel Cycle. The Nuclear Science Committee (NSC) Working Party on Scientific Issues of the Nuclear Fuel Cycle (WPFC) comprises five different expert groups covering all aspects of the fuel cycle from front to back-end. Activities related to fuels, materials, physics, separation chemistry, and fuel cycles scenarios are being undertaken. By publishing state-of-the-art reports and organizing workshops, the groups are able to disseminate recent research advancements to the international community. Current activities mainly focus on advanced nuclear systems, and experts are working on analyzing results and establishing challenges associated to the adoption of new materials and fuels. By comparing different codes, the Expert Group on Advanced Fuel Cycle Scenarios is aiming at gaining further understanding of the scientific issues and specific national needs associated with the implementation of advanced fuel cycles. At the back end of the fuel cycle, separation technologies (aqueous and pyrochemical processing) are being assessed. Current and future activities comprise studies on minor actinides separation and post Fukushima studies. Regular workshops are also organized to discuss recent developments on Partitioning and Transmutation. In addition, the Nuclear Development Committee (NDC) focuses on the analysis of the economics of nuclear power across the fuel cycle in the context of changes of electricity markets, social acceptance and technological advances and assesses the availability of the nuclear fuel and infrastructure required for the deployment of existing and future nuclear power. The Expert Group on the Economics of the Back End of the Nuclear Fuel Cycle (EBENFC), in particular, is looking at assessing economic and financial issues related to the long term management of spent nuclear fuel. (authors)

Cornet, S.M. [OECD Nuclear Energy Agency, 12 Boulevard des Iles, 92130 Issy-les-Moulineaux (France); McCarthy, K. [Idaho Nat. Lab. - P.O. Box 1625, Idaho Falls, ID 83415-3860 (United States); Chauvin, N. [CEA Saclay, Nuclear Energy Division, 91191 Gif/Yvette (France)

2013-07-01T23:59:59.000Z

184

Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Performance of  

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

Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Performance of Geologic Disposal Systems Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Performance of Geologic Disposal Systems Development and implementation of future advanced fuel cycles including those that recycle fuel materials, use advanced fuels different from current fuels, or partition and transmute actinide radionuclides, will impact the waste management system. The Used Fuel Disposition Campaign can reasonably conclude that advanced fuel cycles, in combination with partitioning and transmutation, which remove actinides, will not materially alter the performance, the spread in dose results around the mean, the modeling effort to include significant features, events, and processes

185

Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Performance of  

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

Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Performance of Geologic Disposal Systems Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Performance of Geologic Disposal Systems Development and implementation of future advanced fuel cycles including those that recycle fuel materials, use advanced fuels different from current fuels, or partition and transmute actinide radionuclides, will impact the waste management system. The Used Fuel Disposition Campaign can reasonably conclude that advanced fuel cycles, in combination with partitioning and transmutation, which remove actinides, will not materially alter the performance, the spread in dose results around the mean, the modeling effort to include significant features, events, and processes

186

Overview of Fuel Cell Electric Bus Development  

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

Overview of Fuel Cell Electric Bus Development Leslie Eudy, National Renewable Energy Laboratory September 12, 2013 2 Why Fuel Cells for Transit Buses? * Reduce transit bus...

187

Texas Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,966",4.6,"41,335",10.0 "Coal","22,335",20.6,"150,173",36.5 "Hydro and Pumped Storage",689,0.6,"1,262",0.3 "Natural Gas","69,291",64.0,"186,882",45.4 "Other1",477,0.4,"3,630",0.9 "Other Renewable1","10,295",9.5,"27,705",6.7 "Petroleum",204,0.2,708,0.2 "Total","108,258",100.0,"411,695",100.0

188

Pennsylvania Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","9,540",20.9,"77,828",33.9 "Coal","18,481",40.6,"110,369",48.0 "Hydro and Pumped Storage","2,268",5.0,"1,624",0.7 "Natural Gas","9,415",20.7,"33,718",14.7 "Other1",100,0.2,"1,396",0.6 "Other Renewable1","1,237",2.7,"4,245",1.8 "Petroleum","4,534",9.9,571,0.2 "Total","45,575",100.0,"229,752",100.0

189

California Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,390",6.5,"32,201",15.8 "Coal",374,0.6,"2,100",1.0 "Hydro and Pumped Storage","13,954",20.7,"33,260",16.3 "Natural Gas","41,370",61.4,"107,522",52.7 "Other1",220,0.3,"2,534",1.2 "Other Renewable1","6,319",9.4,"25,450",12.5 "Petroleum",701,1.0,"1,059",0.5 "Total","67,328",100.0,"204,126",100.0

190

Arizona Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (nw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",3937,14.9,"31,200",27.9 "Coal","6,233",23.6,"43,644",39.1 "Hydro and Pumped Storage","2,937",11.1,"6,831",6.1 "Natural Gas","13,012",49.3,"29,676",26.6 "Other1","-","-",15,"*" "Other Renewable1",181,0.7,319,0.3 "Petroleum",93,0.4,66,0.1 "Total","26,392",100.0,"111,751",100.0

191

Louisiana Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,142",8.0,"18,639",18.1 "Coal","3,417",12.8,"23,924",23.3 "Hydro and Pumped Storage",192,0.7,"1,109",1.1 "Natural Gas","19,574",73.2,"51,344",49.9 "Other1",213,0.8,"2,120",2.1 "Other Renewable1",325,1.2,"2,468",2.4 "Petroleum",881,3.3,"3,281",3.2 "Total","26,744",100.0,"102,885",100.0

192

Illinois Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","11,441",25.9,"96,190",47.8 "Coal","15,551",35.2,"93,611",46.5 "Hydro and Pumped Storage",34,0.1,119,0.1 "Natural Gas","13,771",31.2,"5,724",2.8 "Other1",145,0.3,461,0.2 "Other Renewable1","2,078",4.7,"5,138",2.6 "Petroleum","1,106",2.5,110,0.1 "Total","44,127",100.0,"201,352",100.0

193

Alabama Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","5,043",15.6,"37,941",24.9 "Coal","11,441",35.3,"63,050",41.4 "Hydro and Pumped Storage","3,272",10.1,"8,704",5.7 "Natural Gas","11,936",36.8,"39,235",25.8 "Other1",100,0.3,643,0.4 "Other Renewable1",583,1.8,"2,377",1.6 "Petroleum",43,0.1,200,0.1 "Total","32,417",100.0,"152,151",100.0

194

Florida Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (nw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,924",6.6,"23,936",10.4 "Coal","9,975",16.9,"59,897",26.1 "Hydro and Pumped Storage",55,0.1,177,0.1 "Natural Gas","31,563",53.4,"128,634",56.1 "Other1",544,0.9,"2,842",1.2 "Other Renewable1","1,053",1.8,"4,487",2.0 "Petroleum","12,033",20.3,"9,122",4.0 "Total","59,147",100.0,"229,096",100.0

195

Arkansas Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,835",11.5,"15,023",24.6 "Coal","4,535",28.4,"28,152",46.2 "Hydro and Pumped Storage","1,369",8.6,"3,658",6.0 "Natural Gas","7,894",49.4,"12,469",20.4 "Other1","-","-",28,"*" "Other Renewable1",326,2.0,"1,624",2.7 "Petroleum",22,0.1,45,0.1 "Total","15,981",100.0,"61,000",100.0

196

Missouri Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,190",5.5,"8,996",9.7 "Coal","12,070",55.5,"75,047",81.3 "Hydro and Pumped Storage","1,221",5.6,"2,427",2.6 "Natural Gas","5,579",25.7,"4,690",5.1 "Other1","-","-",39,"*" "Other Renewable1",466,2.1,988,1.1 "Petroleum","1,212",5.6,126,0.1 "Total","21,739",100.0,"92,313",100.0

197

Massachusetts Nuclear Profile - All Fuels  

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

total electric power industry, smmer capacity and net generation, by energy source, 2010" total electric power industry, smmer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",685,5.0,"5,918",13.8 "Coal","1,669",12.2,"8,306",19.4 "Hydro and Pumped Storage","1,942",14.2,659,1.5 "Natural Gas","6,063",44.3,"25,582",59.8 "Other1",3,"*",771,1.8 "Other Renewable1",304,2.2,"1,274",3.0 "Petroleum","3,031",22.1,296,0.7 "Total","13,697",100.0,"42,805",100.0

198

Georgia Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,061",11.1,"33,512",24.4 "Coal","13,230",36.1,"73,298",53.3 "Hydro and Pumped Storage","3,851",10.5,"3,044",2.2 "Natural Gas","12,668",34.6,"23,884",17.4 "Other1","-","-",18,"*" "Other Renewable1",637,1.7,"3,181",2.3 "Petroleum","2,189",6.0,641,0.5 "Total","36,636",100.0,"137,577",100.0

199

Tennessee Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,401",15.9,"27,739",33.7 "Coal","8,805",41.1,"43,670",53.0 "Hydro and Pumped Storage","4,277",20.0,"7,416",9.0 "Natural Gas","4,655",21.7,"2,302",2.8 "Other1","-","-",16,"*" "Other Renewable1",222,1.0,988,1.2 "Petroleum",58,0.3,217,0.3 "Total","21,417",100.0,"82,349",100.0

200

Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites |  

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

Evaluation of Removing Used Nuclear Fuel From Shutdown Evaluation of Removing Used Nuclear Fuel From Shutdown Sites Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America's Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. Shutdown sites are defined as those commercial nuclear power reactor sites where the

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to obtain the most current and comprehensive results.


201

Development of alkaline fuel cells.  

SciTech Connect

This project focuses on the development and demonstration of anion exchange membrane (AEM) fuel cells for portable power applications. Novel polymeric anion exchange membranes and ionomers with high chemical stabilities were prepared characterized by researchers at Sandia National Laboratories. Durable, non-precious metal catalysts were prepared by Dr. Plamen Atanassov's research group at the University of New Mexico by utilizing an aerosol-based process to prepare templated nano-structures. Dr. Andy Herring's group at the Colorado School of Mines combined all of these materials to fabricate and test membrane electrode assemblies for single cell testing in a methanol-fueled alkaline system. The highest power density achieved in this study was 54 mW/cm2 which was 90% of the project target and the highest reported power density for a direct methanol alkaline fuel cell.

Hibbs, Michael R.; Jenkins, Janelle E.; Alam, Todd Michael; Janarthanan, Rajeswari [Colorado School of Mines, Golden, CO; Horan, James L. [Colorado School of Mines, Golden, CO; Caire, Benjamin R. [Colorado School of Mines, Golden, CO; Ziegler, Zachary C. [Colorado School of Mines, Golden, CO; Herring, Andrew M. [Colorado School of Mines, Golden, CO; Yang, Yuan [Colorado School of Mines, Golden, CO; Zuo, Xiaobing [Argonne National Laboratory, Argonne, IL; Robson, Michael H. [University of New Mexico, Albuquerque, NM; Artyushkova, Kateryna [University of New Mexico, Albuquerque, NM; Patterson, Wendy [University of New Mexico, Albuquerque, NM; Atanassov, Plamen Borissov [University of New Mexico, Albuquerque, NM

2013-09-01T23:59:59.000Z

202

Stainless steel-zirconium waste forms from the treatment of spent nuclear fuel  

Science Journals Connector (OSTI)

Stainless steel-zirconium waste-form alloys have been developed for the disposal of metallic wastes recovered from spent nuclear fuel using the electrometallurgical process developed by Argonne National Laborator...

S. M. McDeavitt; D. P. Abraham; J. Y. Park; D. D. Keiser

1997-07-01T23:59:59.000Z

203

Overview of Fuel Cell Electric Bus Development | Department of...  

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

Fuel Cell Electric Bus Development Overview of Fuel Cell Electric Bus Development Presentation slides from the Fuel Cell Technologies Office webinar ""Fuel Cell Buses"" held...

204

Testing to evaluate the suitability of waste forms developed for electrometallurgically treated spent sodium-bonded nuclear fuel for disposal in the Yucca Mountain reporsitory.  

SciTech Connect

The results of laboratory testing and modeling activities conducted to support the development of waste forms to immobilize wastes generated during the electrometallurgical treatment of spent sodium-bonded nuclear fuel and their qualification for disposal in the federal high-level radioactive waste repository are summarized in this report. Tests and analyses were conducted to address issues related to the chemical, physical, and radiological properties of the waste forms relevant to qualification. These include the effects of composition and thermal treatments on the phase stability, radiation effects, and methods for monitoring product consistency. Other tests were conducted to characterize the degradation and radionuclide release behaviors of the ceramic waste form (CWF) used to immobilize waste salt and the metallic waste form (MWF) used to immobilize metallic wastes and to develop models for calculating the release of radionuclides over long times under repository-relevant conditions. Most radionuclides are contained in the binder glass phase of the CWF and in the intermetallic phase of the MWF. The release of radionuclides from the CWF is controlled by the dissolution rate of the binder glass, which can be tracked using the same degradation model that is used for high-level radioactive waste (HLW) glass. Model parameters measured for the aqueous dissolution of the binder glass are used to model the release of radionuclides from a CWF under all water-contact conditions. The release of radionuclides from the MWF is element-specific, but the release of U occurs the fastest under most test conditions. The fastest released constituent was used to represent all radionuclides in model development. An empirical aqueous degradation model was developed to describe the dependence of the radionuclide release rate from a MWF on time, pH, temperature, and the Cl{sup -} concentration. The models for radionuclide release from the CWF and MWF are both bounded by the HLW glass degradation model developed for use in repository licensing, and HLW glass can be used as a surrogate for both CWF and MWF in performance assessment calculations. Test results indicate that the radionuclide release from CWF and MWF is adequately described by other relevant performance assessment models, such as the models for the solution chemistries in breached waste packages, dissolved concentration limits, and the formation of radionuclide-bearing colloids.

Ebert, W. E.

2006-01-31T23:59:59.000Z

205

Status of Transuranic Bearing Metallic Fuel Development  

SciTech Connect

This paper summarizes the status of the metallic fuel development under the Advanced Fuel Cycle Initiative (AFCI). The metallic fuel development program includes fuel fabrication, characterization, advanced cladding research, irradiation testing and post-irradiation examination (PIE). The focus of this paper is on the recent irradiation experiments conducted in the Advanced Test Reactor and some PIE results from these tests.

Steve Hayes; Bruce Hilton; Heather MacLean; Debbie Utterbeck; Jon Carmack; Kemal Pasamehmetoglu

2009-09-01T23:59:59.000Z

206

Nuclear Fuels Storage & Transportation Planning Project | Department of  

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

Nuclear Fuels Storage & Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel assemblies [412.3 metric ton heavy metal (MTHM)] and 3 canisters of greater-than-class-C (GTCC) low-level radioactive waste. Photo courtesy of Connecticut Yankee (http://www.connyankee.com/html/fuel_storage.html). Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel

207

Mechanical Properties of Nuclear Fuel Surrogates using Picosecond Laser Ultrasonics  

SciTech Connect

Detailed understanding between microstructure evolution and mechanical properties is important for designing new high burnup nuclear fuels. In this presentation we discuss the use of picosecond ultrasonics to measure localize changes in mechanical properties of fuel surrogates. We develop measurement techniques that can be applied to investigate heterogeneous elastic properties caused by localize changes in chemistry, grain microstructure caused by recrystallization, and mechanical properties of small samples prepared using focused ion beam sample preparation. Emphasis is placed on understanding the relationship between microstructure and mechanical properties

David Hurley; Marat Khafizov; Farhad Farzbod; Eric Burgett

2013-05-01T23:59:59.000Z

208

Assessment of National Nuclear Fuel Cycle for Transmutations of High Level Nuclear Waste  

Science Journals Connector (OSTI)

The advanced fuel cycle initiative (AFCI) has been investigated for the safe processing of the spent nuclear fuels (SNFs), which has focused mainly ... of the SNFs considering the characteristics of the nuclear m...

Taeho Woo

2012-01-01T23:59:59.000Z

209

Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels  

SciTech Connect

Enhancing performance of fuel cladding and duct alloys is a key means of increasing fuel burnup. This project will address the failure of fuel cladding via three-dimensional cracking models. Researchers will develop a simulation code for the failure of the fuel cladding and validate the code through experiments. The objective is to develop an algorithm to determine the failure of fuel cladding in the form of three-dimensional cracking due to prolonged exposure under varying conditions of pressure, temperature, chemical environment, and irradiation. This project encompasses the following tasks: 1. Simulate 3D crack initiation and growth under instantaneous and/or fatigue loads using a new variant of the material point method (MPM); 2. Simulate debonding of the materials in the crack path using cohesive elements, considering normal and shear traction separation laws; 3. Determine the crack propagation path, considering damage of the materials incorporated in the cohesive elements to allow the energy release rate to be minimized; 4. Simulate the three-dimensional fatigue crack growth as a function of loading histories; 5. Verify the simulation code by comparing results to theoretical and numerical studies available in the literature; 6. Conduct experiments to observe the crack path and surface profile in unused fuel cladding and validate against simulation results; and 7. Expand the adaptive mesh refinement infrastructure parallel processing environment to allow adaptive mesh refinement at the 3D crack fronts and adaptive mesh merging in the wake of cracks. Fuel cladding is made of materials such as stainless steels and ferritic steels with added alloying elements, which increase stability and durability under irradiation. As fuel cladding is subjected to water, chemicals, fission gas, pressure, high temperatures, and irradiation while in service, understanding performance is essential. In the fast fuel used in advanced burner reactors, simulations of the nuclear fuels are critical to understand the burnup, and thus the fuel efficiency.

Lu, Hongbing; Bukkapatnam, Satish; Harimkar, Sandip; Singh, Raman; Bardenhagen, Scott

2014-01-09T23:59:59.000Z

210

Nuclear fuel reprocessing and the problems of safeguarding against the spread of nuclear weapons  

SciTech Connect

In 1977, the executive branch reversed its long-standing support for nuclear fuel reprocessing, primarily because of the rick of spreading nuclear weapons. GAO reviewed safeguards technology designed to reduce such risks in Federal reprocessing facilities and found that concerns are warranted. Material in sufficient quantities to construct a nuclear weapon could be diverted and go undetected for a long time. Effective international control and safeguards over the production, storage, and use of separated plutonium are lacking. The United States should increase its efforts to: develop and ensure the use of effective safeguards for reprocessing facilities; and establish, in conjunction with major nuclear fuel users, suppliers, and reprocessors, an international system to control the storage and use of excess plutonium.

Staats, E.B.

1980-03-18T23:59:59.000Z

211

Neutronics of accelerator-driven subcritical fission for burning transuranics in used nuclear fuel  

SciTech Connect

We report the development of a conceptual design for accelerator-driven subcritical fission in a molten salt core (ADSMS). ADSMS is capable of destroying all of the transuranics at the same rate and proportion as they are produced in a conventional nuclear power plant. The ADSMS core is fueled solely by transuranics extracted from used nuclear fuel and reduces its radiotoxicity by a factor 10,000. ADSMS offers a way to close the nuclear fuel cycle so that the full energy potential in the fertile fuels uranium and thorium can be recovered.

Sattarov, A.; Assadi, S.; Badgley, K.; Baty, A.; Comeaux, J.; Gerity, J.; Kellams, J.; Mcintyre, P.; Pogue, N.; Sooby, E.; Tsvetkov, P.; Rosaire, G. [Texas A and M University, College Station, TX 77845 (United States); Mann, T. [Argone National Laboratory, Argone, IL (United States)

2013-04-19T23:59:59.000Z

212

Proceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads  

SciTech Connect

The Global conference is a forum for the discussion of the scientific, technical, social and regulatory aspects of the nuclear fuel cycle. Relevant topics include global utilization of nuclear energy, current fuel cycle technologies, advanced reactors, advanced fuel cycles, nuclear nonproliferation and public acceptance.

NONE

2013-07-01T23:59:59.000Z

213

The Role of Friction Stir Welding in Nuclear Fuel Plate Fabrication  

SciTech Connect

The friction bonding process combines desirable attributes of both friction stir welding and friction stir processing. The development of the process is spurred on by the need to fabricate thin, high density, reduced enrichment fuel plates for nuclear research reactors. The work seeks to convert research and test reactors currently operating on highly enriched uranium fuel to operate on low enriched uranium fuel without significant loss in reactor performance, safety characteristics, or significant increase in cost. In doing so, the threat of global nuclear material proliferation will be reduced. Feasibility studies performed on the process show that this is a viable option for mass production of plate-type nuclear fuel. Adapting the friction stir weld process for nuclear fuel fabrication has resulted in the development of several unique ideas and observations. Preliminary results of this adaptation and process model development are discussed.

D Burkes; P Medvedev; M Chapple; A Amritkar; P Wells; I Charit

2009-02-01T23:59:59.000Z

214

Nuclear knowledge development in Armenia  

Science Journals Connector (OSTI)

Armenia has rather a rich history of nuclear knowledge development. During the last several decades, depending upon circumstances related to the Armenian Nuclear Power Plant main milestones â?? construction, putting into operation, shutdown and restarting â?? nuclear knowledge has had its ups and downs. Though it has a high level of development, there is still a need to preserve accumulated nuclear knowledge through appropriate processes.

A.A. Gevorgyan

2008-01-01T23:59:59.000Z

215

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

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

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

216

RADIATION DOSE ASPECTS IN THE HANDLING OF EMERGING NUCLEAR FUELS  

Science Journals Connector (OSTI)

......Prot. (2008) 28:161. 15 NUREG. Standard review plan for the review of an application for a Mixed Oxide (MOX) fuel...fabrication facility. (2000) NUREG-1718, US Nuclear Regulatory Commission. 16 IAEA. Safety of uranium fuel fabrication......

G. Nicolaou

2014-02-01T23:59:59.000Z

217

Fuel assembly transfer basket for pool type nuclear reactor vessels  

DOE Patents (OSTI)

A fuel assembly transfer basket for a pool type, liquid metal cooled nuclear reactor having a side access loading and unloading port for receiving and relinquishing fuel assemblies during transfer.

Fanning, Alan W. (San Jose, CA); Ramsour, Nicholas L. (San Jose, CA)

1991-01-01T23:59:59.000Z

218

Microsoft Word - spent nuclear fuel report.doc  

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

Management of Spent Nuclear Fuel Management of Spent Nuclear Fuel at the Savannah River Site DOE/IG-0727 May 2006 REPORT ON MANAGEMENT OF SPENT NUCLEAR FUEL AT THE SAVANNAH RIVER SITE TABLE OF CONTENTS Spent Nuclear Fuel Management Details of Finding 1 Recommendations 2 Comments 3 Appendices 1. Objective, Scope, and Methodology 4 2. Prior Audit Reports 5 3. Management Comments 6 SPENT NUCLEAR FUEL MANGEMENT Page 1 Details of Finding H-Canyon The Department of Energy's (Department) spent nuclear fuel Operations program at the Savannah River Site (Site) will likely require Extended H-Canyon to be maintained at least two years beyond defined operational needs. The Department committed to maintain H-Canyon operational readiness to provide a disposal path for

219

EIS-0279: Spent Nuclear Fuel Management, Aiken, South Carolina | Department  

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

79: Spent Nuclear Fuel Management, Aiken, South Carolina 79: Spent Nuclear Fuel Management, Aiken, South Carolina EIS-0279: Spent Nuclear Fuel Management, Aiken, South Carolina SUMMARY The proposed DOE action considered in this environmental impact statement (EIS) is to implement appropriate processes for the safe and efficient management of spent nuclear fuel and targets at the Savannah River Site (SRS) in Aiken County, South Carolina, including placing these materials in forms suitable for ultimate disposition. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 5, 2013 EIS-0279: Amended Record of Decision Spent Nuclear Fuel Management at the Savannah River Site April 1, 2013 EIS-0279-SA-01: Supplement Analysis Savannah River Site Spent Nuclear Fuel Management (DOE/EIS-0279-SA-01 and

220

Nuclear reactor fuel rod attachment system  

DOE Patents (OSTI)

A reusable system for removably attaching a nuclear reactor fuel rod (12) to a support member (14). A locking cap (22) is secured to the fuel rod (12) and a locking strip (24) is fastened to the support member (14). The locking cap (22) has two opposing fingers (24a and 24b) shaped to form a socket having a body portion (26). The locking strip has an extension (36) shaped to rigidly attach to the socket's body portion (26). The locking cap's fingers are resiliently deflectable. For attachment, the locking cap (22) is longitudinally pushed onto the locking strip (24) causing the extension (36) to temporarily deflect open the fingers (24a and 24b) to engage the socket's body portion (26). For removal, the process is reversed.

Christiansen, David W. (Kennewick, WA)

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Report of the Fuel Cycle Subcommittee of the Nuclear Energy Advisory  

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

Fuel Cycle Subcommittee of the Nuclear Energy Fuel Cycle Subcommittee of the Nuclear Energy Advisory Committee Report of the Fuel Cycle Subcommittee of the Nuclear Energy Advisory Committee The Fuel Cycle Subcommittee (FCSC) of NEAC met in Washington, August 17- 19, 2010. DOE's new science-based approach to all matters related to nuclear energy is being implemented. The general approach was outlined to NEAC in the briefing on the NE Roadmap. There are many new directions being considered, and this meeting of the FCSC was to brief the Subcommittee on new directions in nuclear energy that might go beyond our present 4.5% enriched LWRs. The goal is to develop new concepts that have advantages over present systems in some combination of cost, passive safety, proliferation resistance, sustainability, and used fuel disposition.

222

Report of the Fuel Cycle Subcommittee of the Nuclear Energy Advisory  

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

of the Fuel Cycle Subcommittee of the Nuclear Energy of the Fuel Cycle Subcommittee of the Nuclear Energy Advisory Committee Report of the Fuel Cycle Subcommittee of the Nuclear Energy Advisory Committee The Fuel Cycle Subcommittee (FCSC) of NEAC met in Washington, August 17- 19, 2010. DOE's new science-based approach to all matters related to nuclear energy is being implemented. The general approach was outlined to NEAC in the briefing on the NE Roadmap. There are many new directions being considered, and this meeting of the FCSC was to brief the Subcommittee on new directions in nuclear energy that might go beyond our present 4.5% enriched LWRs. The goal is to develop new concepts that have advantages over present systems in some combination of cost, passive safety, proliferation resistance, sustainability, and used fuel disposition.

223

DOE SPENT NUCLEAR FUEL DISPOSAL CONTAINER  

SciTech Connect

The DOE Spent Nuclear Fuel Disposal Container (SNF DC) supports the confinement and isolation of waste within the Engineered Barrier System of the Mined Geologic Disposal System (MGDS). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the access mains, and emplaced in emplacement drifts. The DOE Spent Nuclear Fuel Disposal Container provides long term confinement of DOE SNF waste, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The DOE SNF Disposal Containers provide containment of waste for a designated period of time, and limit radionuclide release thereafter. The disposal containers maintain the waste in a designated configuration, withstand maximum handling and rockfall loads, limit the individual waste canister temperatures after emplacement. The disposal containers also limit the introduction of moderator into the disposal container during the criticality control period, resist corrosion in the expected repository environment, and provide complete or limited containment of waste in the event of an accident. Multiple disposal container designs may be needed to accommodate the expected range of DOE Spent Nuclear Fuel. The disposal container will include outer and inner barrier walls and outer and inner barrier lids. Exterior labels will identify the disposal container and contents. Differing metal barriers will support the design philosophy of defense in depth. The use of materials with different failure mechanisms prevents a single mode failure from breaching the waste package. The corrosion-resistant inner barrier and inner barrier lid will be constructed of a high-nickel alloy and the corrosion-allowance outer barrier and outer barrier lid will be made of carbon steel. The DOE Spent Nuclear Fuel Disposal Containers interface with the emplacement drift environment by transferring heat from the waste to the external environment and by protecting the DOE waste canisters and their contents from damage/degradation by the external environment. The disposal containers also interface with the SNF by limiting access of moderator and oxidizing agents to the waste. The disposal containers interface with the Ex-Container System's emplacement drift disposal container supports. The disposal containers interface with the Canister Transfer System, Waste Emplacement System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and remediation of the disposal container.

F. Habashi

1998-06-26T23:59:59.000Z

224

Used Nuclear Fuel Loading and Structural Performance Under Normal...  

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

deterministic evaluations of moderate-to-high burnup used nuclear fuel (UNF) mechanical performance under normal conditions of storage (NCS) and normal conditions of...

225

Development of Fuel-Flexible Combustion Systems Utilizing Opportunity...  

Office of Environmental Management (EM)

Fuel-Flexible Combustion Systems Utilizing Opportunity Fuels in Gas Turbines - Fact Sheet, May 2014 Development of Fuel-Flexible Combustion Systems Utilizing Opportunity Fuels in...

226

Heavy Liquid Metal Reactor Development - Nuclear Engineering Division  

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

> Heavy Liquid Metal Reactor Development > Heavy Liquid Metal Reactor Development Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Nuclear Data Program Advanced Reactor Development Overview Advanced Fast Reactor (AFR) Heavy Liquid Metal Reactor Development Generation IV Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Advanced Reactor Development and Technology Heavy Liquid Metal Reactor Development Bookmark and Share STAR-LM: Simplified, Modular, Small Reactor Featuring Flow-thru Fuel Cartridge STAR-LM: Simplified, Modular, Small Reactor Featuring Flow-thru Fuel Cartridge. Click on image to view larger image. Argonne has traditionally been the foremost institute in the US for

227

Conditioning of spent nuclear fuel for permanent disposal  

SciTech Connect

A compact, efficient method for conditioning spent nuclear fuel is under development. This method, known as pyrochemical processing, or pyroprocessing, provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the US Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (> 99.9%) separation of transuranics. The resultant waste forms from the pyroprocess are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and that avoid the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.

Laidler, J.J. [Argonne National Lab., IL (United States). Chemical Technology Div.

1994-12-31T23:59:59.000Z

228

Conditioning of spent nuclear fuel for permanent disposal  

SciTech Connect

A compact, efficient method for conditioning spent nuclear fuel is under development This method, known as pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United States Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (99.9%) separation of transuranics. The resultant waste forms from the pyroprocess are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and preclude the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.

Laidler, J.J.

1994-10-01T23:59:59.000Z

229

Nuclear Power and its Development  

Science Journals Connector (OSTI)

... make the effect on the coal industry the deciding factor in determining the development of nuclear power. The implications of technological change have been ignored, as has the effect of development ... been ignored, as has the effect of development on the cost of electricity supplied by nuclear power-stations, which Sir Christopher Hinton stressed very strongly in his Axel Ax:son Johnson ...

1959-08-08T23:59:59.000Z

230

Risk and Responsibility Sharing in Nuclear Spent Fuel Management  

E-Print Network (OSTI)

With the Nuclear Waste Policy Act of 1982, the responsibility of American utilities in the long-term management of spent nuclear fuel was limited to the payment of a fee. This narrow involvement did not result in faster ...

De Roo, Guillaume

231

Fuel Cycle Research and Development Program  

Office of Environmental Management (EM)

29, 2009 Fuel Cycle Research and Development DM 195665 5 Identify the governing phenomenology Identify the governing phenomenology Develop a first-principle based model of the...

232

Systems and Components Development Expertise [Nuclear Waste Management  

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

Systems and Components Systems and Components Development Expertise Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Systems and Components Development Expertise Bookmark and Share Electrorefiner The electrorefiner: an apparatus used for electrometallurgical treatment of spent nuclear fuel to facilitate storage and ultimate disposal. Click on

233

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

234

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

235

Development of Technology for Immobilization of Waste Salt from Electrorefining Spent Nuclear Fuel in Zeolite-A for Eventual Disposition in a Ceramic Waste Form  

SciTech Connect

The results of process development for the blending of waste salt from the electrorefining of spent fuel with zeolite-A are presented. This blending is a key step in the ceramic waste process being used for treatment of EBR-II spent fuel and is accomplished using a high-temperature v-blender. A labscale system was used with non-radioactive surrogate salts to determine optimal particle size distributions and time at temperature. An engineering-scale system was then installed in the Hot Fuel Examination Facility hot cell and used to demonstrate blending of actual electrorefiner salt with zeolite. In those tests, it was shown that the results are still favorable with actinide-loaded salt and that batch size of this v-blender could be increased to a level consistent with efficient production operations for EBR-II spent fuel treatment. One technical challenge that remains for this technology is to mitigate the problem of material retention in the v-blender due to formation of caked patches of salt/zeolite on the inner v-blender walls.

Michael F. Simpson; Prateek Sachdev

2008-04-01T23:59:59.000Z

236

Fuel cycle analysis of once-through nuclear systems.  

SciTech Connect

Once-through fuel cycle systems are commercially used for the generation of nuclear power, with little exception. The bulk of these once-through systems have been water-cooled reactors (light-water and heavy water reactors, LWRs and HWRs). Some gas-cooled reactors are used in the United Kingdom. The commercial power systems that are exceptions use limited recycle (currently one recycle) of transuranic elements, primarily plutonium, as done in Europe and nearing deployment in Japan. For most of these once-through fuel cycles, the ultimate storage of the used (spent) nuclear fuel (UNF, SNF) will be in a geologic repository. Besides the commercial nuclear plants, new once-through concepts are being proposed for various objectives under international advanced nuclear fuel cycle studies and by industrial and venture capital groups. Some of the objectives for these systems include: (1) Long life core for remote use or foreign export and to support proliferation risk reduction goals - In these systems the intent is to achieve very long core-life with no refueling and limited or no access to the fuel. Most of these systems are fast spectrum systems and have been designed with the intent to improve plant economics, minimize nuclear waste, enhance system safety, and reduce proliferation risk. Some of these designs are being developed under Generation IV International Forum activities and have generally not used fuel blankets and have limited the fissile content of the fuel to less than 20% for the purpose on meeting international nonproliferation objectives. In general, the systems attempt to use transuranic elements (TRU) produced in current commercial nuclear power plants as this is seen as a way to minimize the amount of the problematic radio-nuclides that have to be stored in a repository. In this case, however, the reprocessing of the commercial LWR UNF to produce the initial fuel will be necessary. For this reason, some of the systems plan to use low enriched uranium (LEU) fuels. Examples of systems in this class include the small modular reactors being considered internationally; e.g. 4S [Tsuboi 2009], Hyperion Power Module [Deal 2010], ARC-100 [Wade 2010], and SSTAR [Smith 2008]. (2) Systems for Resource Utilization - In recent years, interest has developed in the use of advanced nuclear designs for the effective utilization of fuel resources. Systems under this class have generally utilized the breed and burn concept in which fissile material is bred and used in situ in the reactor core. Due to the favorable breeding that is possible with fast neutrons, these systems have tended to be fast spectrum systems. In the once-through concepts (as opposed to the traditional multirecycle approach typically considered for fast reactors), an ignition (or starter) zone contains driver fuel which is fissile material. This zone is designed to last a long time period to allow the breeding of sufficient fissile material in the adjoining blanket zone. The blanket zone is initially made of fertile depleted uranium fuel. This zone could also be made of fertile thorium fuel or recovered uranium from fuel reprocessing or natural uranium. However, given the bulk of depleted uranium and the potentially large inventory of recovered uranium, it is unlikely that the use of thorium is required in the near term in the U.S. Following the breeding of plutonium or fissile U-233 in the blanket, this zone or assembly then carries a larger fraction of the power generation in the reactor. These systems tend to also have a long cycle length (or core life) and they could be with or without fuel shuffling. When fuel is shuffled, the incoming fuel is generally depleted uranium (or thorium) fuel. In any case, fuel is burned once and then discharged. Examples of systems in this class include the CANDLE concept [Sekimoto 2001], the traveling wave reactor (TWR) concept of TerraPower [Ellis 2010], the ultra-long life fast reactor (ULFR) by ANL [Kim 2010], and the BNL fast mixed spectrum reactor (FMSR) concept [Fisher 1979]. (3) Thermal systems for resource extensio

Kim, T. K.; Taiwo, T. A.; Nuclear Engineering Division

2010-08-10T23:59:59.000Z

237

Development Plan for the Fuel Cycle Simulator  

SciTech Connect

The Fuel Cycle Simulator (FCS) project was initiated late in FY-10 as the activity to develop a next generation fuel cycle dynamic analysis tool for achieving the Systems Analysis Campaign 'Grand Challenge.' This challenge, as documented in the Campaign Implementation Plan, is to: 'Develop a fuel cycle simulator as part of a suite of tools to support decision-making, communication, and education, that synthesizes and visually explains the multiple attributes of potential fuel cycles.'

Brent Dixon

2011-09-01T23:59:59.000Z

238

Report, Long-Term Nuclear Technology Research and Development Plan |  

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

Report, Long-Term Nuclear Technology Research and Development Plan Report, Long-Term Nuclear Technology Research and Development Plan Report, Long-Term Nuclear Technology Research and Development Plan This document constitutes the first edition of a long-term research and development (R&D) plan for nuclear technology in the United States. The federally-sponsored nuclear technology programs of the United States are almost exclusively the province of the U.S. Department of Energy (DOE). The nuclear energy areas in DOE include, but are not limited to, R&D related to power reactors and the responsibility for the waste management system for final disposition of the spent fuel resulting from nuclear power reactors. Although a major use of nuclear technology is to supply energy for electricity production, the DOE has far broader roles regarding nuclear

239

Nuclear Fuel Cycle Options Evaluation to Inform R&D Planning  

SciTech Connect

An Evaluation and Screening (E&S) of nuclear fuel cycle options has been conducted in fulfilment of a Charter specified for the study by the U.S. Department of Energy (DOE) Office of Nuclear Energy. The E&S study used an objective and independently reviewed evaluation process to provide information about the potential benefits and challenges that could strengthen the basis and provide guidance for the research and development(R&D) activities undertaken by the DOE Fuel Cycle Technologies Program Office. Using the nine evaluation criteria specified in the Charter and associated evaluation metrics and processes developed during the E&S study, a screening was conducted of 40 nuclear fuel cycle evaluation groups to provide answers to the questions: (1) Which nuclear fuel cycle system options have the potential for substantial beneficial improvements in nuclear fuel cycle performance, and what aspects of the options make these improvements possible? (2)Which nuclear material management approaches can favorably impact the performance of fuel cycle options? (3)Where would R&D investment be needed to support the set of promising fuel cycle system options and nuclear material management approaches identified above, and what are the technical objectives of associated technologies?

R. Wigeland; T. Taiwo; M. Todosow; H. Ludewig; W. Halsey; J. Gehin; R. Jubin; J. Buelt; S. Stockinger; K. Jenni; B. Oakley

2014-04-01T23:59:59.000Z

240

Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels  

SciTech Connect

Advanced fast reactor systems being developed under the DOE's Advanced Fuel Cycle Initiative are designed to destroy TRU isotopes generated in existing and future nuclear energy systems. Over the past 40 years, multiple experiments and demonstrations have been completed using U-Zr, U-Pu-Zr, U-Mo and other metal alloys. As a result, multiple empirical and semi-empirical relationships have been established to develop empirical performance modeling codes. many mechamistic questions about fission as mobility, bubble coalescience, and gas release have been answered through industrial experience, reearch, and empirical understanding. The advent of modern computational materials science, however, opens new doors of development such that physics-based multi-scale models may be developed to enable a new generation of predictive fuel performance codes that are not limited by empiricism.

McDeavitt, Sean; Shao, Lin; Tsvetkov, Pavel; Wirth, Brian; Kennedy, Rory

2014-04-07T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program  

SciTech Connect

The current state of the art in nuclear fuel cycle (NFC) modeling is an eclectic mixture of codes with various levels of applicability, flexibility, and availability. In support of the advanced fuel cycle systems analyses, especially those by the Advanced Fuel Cycle Initiative (AFCI), Unviery of Cincinnati in collaboration with Idaho State University carried out a detailed review of the existing codes describing various aspects of the nuclear fuel cycle and identified the research and development needs required for a comprehensive model of the global nuclear energy infrastructure and the associated nuclear fuel cycles. Relevant information obtained on the NFC codes was compiled into a relational database that allows easy access to various codes' properties. Additionally, the research analyzed the gaps in the NFC computer codes with respect to their potential integration into programs that perform comprehensive NFC analysis.

Adrian Miron; Joshua Valentine; John Christenson; Majd Hawwari; Santosh Bhatt; Mary Lou Dunzik-Gougar: Michael Lineberry

2009-10-01T23:59:59.000Z

242

Coupon Surveillance For Corrosion Monitoring In Nuclear Fuel Basin  

SciTech Connect

Aluminum and stainless steel coupons were put into a nuclear fuel basin to monitor the effect of water chemistry on the corrosion of fuel cladding. These coupons have been monitored for over ten years. The corrosion and pitting data is being used to model the kinetics and estimate the damage that is occurring to the fuel cladding.

Mickalonis, J. I.; Murphy, T. R.; Deible, R.

2012-10-01T23:59:59.000Z

243

Pyroprocessing oxide spent nuclear fuels for efficient disposal  

SciTech Connect

Pyrochemical processing as a means for conditioning spent nuclear fuels for disposal offers significant advantages over the direct disposal option. The advantages include reduction in high-level waste volume; conversion of most of the high-level waste to a low-level waste in which nearly all the transuranics (TRU) have been removed; and incorporation of the TRUs into a stable, highly radioactive waste form suitable for interim storage, ultimate destruction, or repository disposal. The lithium process has been under development at Argonne National Laboratory for use in pyrochemical conditioning of spent fuel for disposal. All of the process steps have been demonstrated in small-scale (0.5-kg simulated spent fuel) experiments. Engineering-scale (20-kg simulated spent fuel) demonstration of the process is underway, and small-scale experiments have been conducted with actual spent fuel from a light water reactor (LWR). The lithium process is simple, operates at relatively low temperatures, and can achieve high decontamination factors for the TRU elements. Ordinary materials, such as carbon steel, can be used for process containment.

McPheeters, C.C.; Pierce, R.D.; Mulcahey, T.P. [Argonne National Lab., IL (United States). Chemical Technology Div.

1994-12-31T23:59:59.000Z

244

World nuclear capacity and fuel cycle requirements, November 1993  

SciTech Connect

This analysis report presents the current status and projections of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. Long-term projections of US nuclear capacity, generation, fuel cycle requirements, and spent fuel discharges for three different scenarios through 2030 are provided in support of the Department of Energy`s activities pertaining to the Nuclear Waste Policy Act of 1982 (as amended in 1987). The projections of uranium requirements also support the Energy Information Administration`s annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment.

Not Available

1993-11-30T23:59:59.000Z

245

New Hampshire Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,247",29.8,"10,910",49.2 "Coal",546,13.1,"3,083",13.9 "Hydro and Pumped Storage",489,11.7,"1,478",6.7 "Natural Gas","1,215",29.1,"5,365",24.2 "Other1","-","-",57,0.3 "Other Renewable1",182,4.4,"1,232",5.6 "Petroleum",501,12.0,72,0.3 "Total","4,180",100.0,"22,196",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

246

New Jersey Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,108",22.3,"32,771",49.9 "Coal","2,036",11.1,"6,418",9.8 "Hydro and Pumped Storage",404,2.2,-176,-0.3 "Natural Gas","10,244",55.6,"24,902",37.9 "Other1",56,0.3,682,1.0 "Other Renewable1",226,1.2,850,1.3 "Petroleum","1,351",7.3,235,0.4 "Total","18,424",100.0,"65,682",100.0 "1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable."

247

Development of a fuel-tolerant diesel for alternative fuels  

Science Journals Connector (OSTI)

There is a growing requirement for engines operating on a wider range of fuels than when fuel supplies were more stable. The diesel engine, with its high compression ratio and absence of part-load throttling, offers high efficiency. Some widely available alternative fuels, in particular alcohol from biomass, present problems because of their low cetane number. The authors report the development of a diesel engine using a combustion system incorporating a high-energy, multi-strike spark to promote smooth combustion. Results obtained with this engine using ethanol are presented to illustrate its ability to handle fuels of very low cetane numbers.

A.W.E. Henham; R.A. Johns; S. Newnham

1991-01-01T23:59:59.000Z

248

Benefits and concerns of a closed nuclear fuel cycle  

SciTech Connect

Nuclear power can play an important role in our energy future, contributing to increasing electricity demand while at the same time decreasing carbon dioxide emissions. However, the nuclear fuel cycle in the United States today is unsustainable. As stated in the 1982 Nuclear Waste Policy Act, the U.S. Department of Energy is responsible for disposing of spent nuclear fuel generated by commercial nuclear power plants operating in a “once-through” fuel cycle in the deep geologic repository located at Yucca Mountain. However, unyielding political opposition to the site has hindered the commissioning process to the extant that the current administration has recently declared the unsuitability of the Yucca Mountain site. In light of this the DOE is exploring other options, including closing the fuel cycle through recycling and reprocessing of spent nuclear fuel. The possibility of closing the fuel cycle is receiving special attention because of its ability to minimize the final high level waste (HLW) package as well as recover additional energy value from the original fuel. The technology is, however, still very controversial because of the increased cost and proliferation risk it can present. To lend perspective on the closed fuel cycle alternative, this presents the arguments for and against closing the fuel cycle with respect to sustainability, proliferation risk, commercial viability, waste management, and energy security.

Widder, Sarah H.

2010-11-17T23:59:59.000Z

249

Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay  

E-Print Network (OSTI)

Security of the National Nuclear Security Administration, USof Energys National Nuclear Security Administration (NNSA)

Quiter, Brian

2012-01-01T23:59:59.000Z

250

Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel  

SciTech Connect

Part of the Department of Energy (DOE) spent nuclear fuel (SNF) inventory may require some type of treatment to meet acceptance criteria at various disposition sites. The current focus for much of this spent nuclear fuel is the electrometallurgical treatment process under development at Argonne National Laboratory. Potential flowsheets for this treatment process are presented. Deployment of the process for the treatment of the spent nuclear fuel requires evaluation to determine the spent nuclear fuel program need for treatment and compatibility of the spent nuclear fuel with the process. The evaluation of need includes considerations of cost, technical feasibility, process material disposition, and schedule to treat a proposed fuel. A siting evaluation methodology has been developed to account for these variables. A work breakdown structure is proposed to gather life-cycle cost information to allow evaluation of alternative siting strategies on a similar basis. The evaluation methodology, while created specifically for the electrometallurgical evaluation, has been written such that it could be applied to any potential treatment process that is a disposition option for spent nuclear fuel. Future work to complete the evaluation of the process for electrometallurgical treatment is discussed.

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

1998-07-01T23:59:59.000Z

251

THERMODYNAMIC MODEL FOR URANIUM DIOXIDE BASED NUCLEAR FUEL  

SciTech Connect

Many projects involving nuclear fuel rest on a quantitative understanding of the co-existing phases at various stages of burnup. Since the many fission products have considerably different abilities to chemically associate with oxygen, and the oxygen-to-metal molar ratio is slowly changing, the chemical potential of oxygen is a function of burnup. Concurrently, well-recognized small fractions of new phases such as inert gas, noble metals, zirconates, etc. also develop. To further complicate matters, the dominant UO2 fuel phase may be non-stoichiometric and most of the minor phases themselves have a variable composition dependent on temperature and possible contact with the coolant in the event of a sheathing breach. A thermodynamic fuel model to predict the phases in partially burned CANDU (CANada Deuterium Uranium) nuclear fuel containing many major fission products has been under development. The building blocks of the model are the standard Gibbs energies of formation of the many possible compounds expressed as a function of temperature. To these data are added mixing terms associated with the appearance of the component species in particular phases. In operational terms, the treatment rests on the ability to minimize the Gibbs energy in a multicomponent system, in our case using the algorithms developed by Eriksson. The model is capable of handling non-stoichiometry in the UO2 fluorite phase, dilute solution behaviour of significant solute oxides, noble metal inclusions, a second metal solid solution U(Pd-Rh-Ru)3, zirconate, molybdate, and uranate solutions as well as other minor solid phases, and volatile gaseous species.

Thompson, Dr. William T. [Royal Military College of Canada; Lewis, Dr. Brian J [Royal Military College of Canada; Corcoran, E. C. [Royal Military College of Canada; Kaye, Dr. Matthew H. [Royal Military College of Canada; White, S. J. [Royal Military College of Canada; Akbari, F. [Atomic Energy of Canada Limited, Chalk River Laboratories; Higgs, Jamie D. [Atomic Energy of Canada Limited, Point Lepreau; Thompson, D. M. [Praxair Inc.; Besmann, Theodore M [ORNL; Vogel, S. C. [Los Alamos National Laboratory (LANL)

2007-01-01T23:59:59.000Z

252

What to Expect When Readying to Move Spent Nuclear Fuel from...  

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

What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power Plants What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power...

253

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

3.4 Fuel Cells Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - 3.4 Fuel Cells Fuel Cells technical plan section of the Fuel Cell...

254

Methods for making a porous nuclear fuel element  

SciTech Connect

Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

Youchison, Dennis L; Williams, Brian E; Benander, Robert E

2014-12-30T23:59:59.000Z

255

Nuclear fuel corrosion over millennia interpreted using geologic data  

SciTech Connect

Corrosion of nuclear fuel over the 10,000 year regulatory period in a geologic repository will be a function of physical characteristics (e.g., crystallinity, crystal sizes, crystal forms) and chemical characteristics (e.g., crystal composition, compositional variability, accessory phases). Natural uraninite (nominally UO{sub 2+x}) which has undergone long-term corrosion can be studied to infer the long-term behavior of nuclear fuel. Previously, uraninite from the Nopal I deposit, Pena Blanca district, Chihuahua, Mexico, has been shown to constitute an outstanding analog material for comparison with nuclear fuel. Similarities between Nopal I uraninite and nuclear fuel have been shown to include bulk composition, general crystal structure, and total trace element content. Data presented here suggest that, as a bulk material, Nopal I uraninite compares favorably with irradiated nuclear fuel. Nevertheless, some fine-scale differences are noted between Nopal I uraninite and irradiated nuclear fuel with respect to both internal structures and compositions. These observations suggest that whereas the long-term responses of the two materials to oxidative alteration in a geologic repository may be similar, the detailed mechanisms of initial oxidant penetration and the short-term oxidative alternation of Nopal I uraninite and irradiated nuclear fuel are likely to be different.

Pearcy, E.C.; Manaktala, H.K. [Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses

1994-12-31T23:59:59.000Z

256

Fuel Fabrication Capability Research and Development Plan  

SciTech Connect

The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors. Therefore, the overriding motivation behind the FFC R&D program described in this plan is to foster closer integration between fuel design and fabrication to reduce programmatic risk. These motivating factors are all interrelated, and progress addressing one will aid understanding of the others. The FFC R&D needs fall into two principal categories, 1) baseline process optimization, to refine the existing fabrication technologies, and 2) manufacturing process alternatives, to evaluate new fabrication technologies that could provide improvements in quality, repeatability, material utilization, or cost. The FFC R&D Plan examines efforts currently under way in regard to coupon, foil, plate, and fuel element manufacturing, and provides recommendations for a number of R&D topics that are of high priority but not currently funded (i.e., knowledge gaps). The plan ties all FFC R&D efforts into a unified vision that supports the overall Convert Program schedule in general, and the fabrication schedule leading up to the MP-1 and FSP-1 irradiation experiments specifically. The fabrication technology decision gates and down-selection logic and schedules are tied to the schedule for fabricating the MP-1 fuel plates, which will provide the necessary data to make a final fuel fabrication process down-selection. Because of the short turnaround between MP-1 and the follow-on FSP-1 and MP-2 experiments, the suite of specimen types that will be available for MP-1 will be the same as those available for FSP-1 and MP-2. Therefore, the only opportunity to explore parameter space and alternative processing is between now and 2016 when the candidate processes are down-selected in preparation for the MP-1, FSP-1, and MP-2 plate manufacturing campaigns. A number of key risks identified by the FFC are discussed in this plan, with recommended mitigating actions for those activities within FFC, and identification of risks that are impacted by activities in other areas of the Convert Program. The R&D Plan does not include discussion of FFC initiatives related to production-scale manufacturing of fuel (e.g., establishment of the Pilot Line Production Facility), rather, the goal of this plan is to document the R&D activities needed ultimately to enable high-quality and cost-effective production of the fuel by the commercial fuel fabricator. The intent is for this R&D Plan to be a living document that will be reviewed and updated on a regular basis (e.g., annually) to ensure that FFC R&D activities remain properly aligned to the needs of the Convert Program. This version of the R&D Plan represents the first annual review and revision.

Senor, David J.; Burkes, Douglas

2014-04-17T23:59:59.000Z

257

Pyroprocessing of fast flux test facility nuclear fuel  

SciTech Connect

Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electro-refined uranium products exceeded 99%. (authors)

Westphal, B.R.; Wurth, L.A.; Fredrickson, G.L.; Galbreth, G.G.; Vaden, D.; Elliott, M.D.; Price, J.C.; Honeyfield, E.M.; Patterson, M.N. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415 (United States)

2013-07-01T23:59:59.000Z

258

Sustainability Considerations in Spent Light-water Nuclear Fuel Retrievability  

SciTech Connect

This paper examines long-term cost differences between two competing Light Water Reactor (LWR) fuels: Uranium Oxide (UOX) and Mixed Uranium Oxide-Plutonium Oxide (MOX). Since these costs are calculated on a life-cycle basis, expected savings from lower future MOX fuel prices can be used to value the option of substituting MOX for UOX, including the value of maintaining access to the used UOX fuel that could be reprocessed to make MOX. The two most influential cost drivers are the price of natural uranium and the cost of reprocessing. Significant and sustained reductions in reprocessing costs and/or sustained increases in uranium prices are required to give positive value to the retrievability of Spent Nuclear Fuel. While this option has positive economic value, it might not be exercised for 50 to 200 years. Therefore, there are many years for a program during which reprocessing technology can be researched, developed, demonstrated, and deployed. Further research is required to determine whether the cost of such a program would yield positive net present value and/or increases the sustainability of LWR energy systems.

Wood, Thomas W.; Rothwell, Geoffrey

2012-01-10T23:59:59.000Z

259

Issues related to EM management of DOE spent nuclear fuel  

SciTech Connect

This document is a summary of the important issues involved in managing spent nuclear fuel (SNF) owned by the Department of Energy (DOE). Issues related to civilian SNF activities are not discussed. DOE-owned SNF is stored primarily at the Hanford Site, Idaho National Engineering Laboratory (INEL), Savannah River Site (SRS), Oak Ridge National Laboratory (ORNL), and West Valley Demonstration Project. Smaller quantities of SNF are stored at Brookhaven National Laboratory, Sandia National Laboratories, and Los Alamos National Laboratory (LANL). There is a wide variety of fuel types, including both low and high enrichment fuels from weapons production, DOE reactors, research and development programs, naval programs, and universities. Most fuel is stored in pools associated with reactor or reprocessing facilities. Smaller quantities are in dry storage. Physical conditions of the fuel range from excellent to poor or severely damaged. An issue is defined as an important question that must be answered or decision that must be made on a topic or subject relevant to achieving the complimentary objectives of (a) storing SNF in compliance with applicable regulations and orders until it can be disposed, and (b) safely disposing of DOE`s SNF. The purpose of this document is to define the issues; no recommendations are made on resolutions. As DOE`s national SNF management program is implemented, a system of issues identification, documentation, tracking, and resolution will be implemented. This document is an initial effort at issues identification. The first section of this document is an overview of issues that are common to several or all DOE facilities that manage SNF. The common issues are organized according to specific aspects of spent fuel management. This is followed by discussions of management issues that apply specifically to individual DOE facilities. The last section provides literature references.

Abbott, D.G. [EG& G Idaho, Inc., Idaho Falls, ID (United States); Abashian, M.S.; Chakraborti, S.; Roberson, K.; Meloin, J.M. [IT Corp. (United States)

1993-07-01T23:59:59.000Z

260

Office of the Assistant General Counsel for Civilian Nuclear...  

Energy Savers (EERE)

(HLW) and Spent Nuclear Fuel (SNF) Management of Nuclear Materials and Non-HLW Nuclear Fuel Cycle Energy Research and Development Non-Proliferation Nuclear Regulatory Commission...

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


261

Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine Nuclear Fuel Qualification Program  

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

fficials from the U.S. Department of Energy’s (DOE) Office of Nuclear Energy today (April 8, 2010) participated in a ceremony in Ukraine to mark the insertion of Westinghouse-produced nuclear fuel into a nuclear power plant in Ukraine.

262

Land and Water Use, CO2 Emissions, and Worker Radiological Exposure Factors for the Nuclear Fuel Cycle  

SciTech Connect

The Department of Energy Office of Nuclear Energy’s Fuel Cycle Technologies program is preparing to evaluate several proposed nuclear fuel cycle options to help guide and prioritize Fuel Cycle Technology research and development. Metrics are being developed to assess performance against nine evaluation criteria that will be used to assess relevant impacts resulting from all phases of the fuel cycle. This report focuses on four specific environmental metrics. • land use • water use • CO2 emissions • radiological Dose to workers Impacts associated with the processes in the front-end of the nuclear fuel cycle, mining through enrichment and deconversion of DUF6 are summarized from FCRD-FCO-2012-000124, Revision 1. Impact estimates are developed within this report for the remaining phases of the nuclear fuel cycle. These phases include fuel fabrication, reactor construction and operations, fuel reprocessing, and storage, transport, and disposal of associated used fuel and radioactive wastes. Impact estimates for each of the phases of the nuclear fuel cycle are given as impact factors normalized per unit process throughput or output. These impact factors can then be re-scaled against the appropriate mass flows to provide estimates for a wide range of potential fuel cycles. A companion report, FCRD-FCO-2013-000213, applies the impact factors to estimate and provide a comparative evaluation of 40 fuel cycles under consideration relative to these four environmental metrics.

Brett W Carlsen; Brent W Dixon; Urairisa Pathanapirom; Eric Schneider; Bethany L. Smith; Timothy M. AUlt; Allen G. Croff; Steven L. Krahn

2013-08-01T23:59:59.000Z

263

Fuel Cell Development and Test Laboratory (Fact Sheet), NREL...  

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

Fuel Cell Development and Test Laboratory may include: * Fuel cell and fuel cell component manufacturers * Certification laboratories * Government agencies * Universities * Other...

264

Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites  

SciTech Connect

The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.

Maheras, Steven J. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Best, Ralph [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River National Laboratory, Aiken, SC (United States); McConnell, Paul [Sandia National Laboratories, Albuquerque, NM (United States)

2013-04-30T23:59:59.000Z

265

Nuclear Energy Research and Development Roadmap | Department...  

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

Energy Research and Development Roadmap Nuclear Energy Research and Development Roadmap NuclearEnergyRoadmapFinal.pdf More Documents & Publications Before the House Science and...

266

JPRS report supplement: Nuclear developments. Iraq -- Nuclear and missile proliferation  

SciTech Connect

This document contains articles from foreign periodicals from throughout the world, translated into English, that concern nuclear developments, specifically nuclear and missile proliferation in Iraq.

NONE

1990-09-14T23:59:59.000Z

267

Spent nuclear fuel characterization for a bounding reference assembly for the receiving basin for off-site fuel  

SciTech Connect

The Basis for Interim Operation (BIO) for the Receiving Basin for Off-Site Fuel (RBOF) facility at the Department of Energy (DOE) Savannah River Site (SRS) nuclear materials production complex, developed in accordance with draft DOE-STD-0019-93, required a hazard categorization for the safety analysis section as outlined in DOE-STD-1027-92. The RBOF facility was thus established as a Category-2 facility (having potential for significant on-site consequences from a radiological release) as defined in DOE 5480.23. Given the wide diversity of spent nuclear fuel stored in the RBOF facility, which made a detailed assessment of the total nuclear inventory virtually impossible, the categorization required a conservative calculation based on the concept of a hypothetical, bounding reference fuel assembly integrated over the total capacity of the facility. This scheme not only was simple but also precluded a potential delay in the completion of the BIO.

Kahook, S.D.; Garrett, R.L.; Canas, L.R.; Beckum, M.J. [Westinghouse Savannah River, Aiken, SC (United States)

1995-07-01T23:59:59.000Z

268

Thermoacoustic device for nuclear fuel monitoring and heat transfer enhancement  

Science Journals Connector (OSTI)

The Fukushima Dai’ichi nuclear disaster of 2011 exposed the need for self-powered sensors that could transmit the status of the fuel rods within the reactor and in spent fuel ponds that was not dependent upon availability of external electrical power for either sensing or telemetry. One possible solution is the use of a thermoacoustic standing wave engine incorporated within a fuel rod which is heated by the nuclear fuel. The engine’s resonance frequency is correlated to the fuel rod temperature and will be transmitted by sound radiation through the reactor's or storage pond’s surrounding water. In addition to acting as a passive temperature sensor the thermoacoustic device will serve to enhance heat transfer from the fuel to the surrounding heat transfer fluid. When activated the acoustically-driven streaming flow of the gas within the fuel rod will circulate gas away from the nuclear fuel and convectively enhance heat transfer to the surrounding coolant. We will present results for a thermoacousticresonator built into a Nitonic® 60 (stainless steel) fuel rod that can be substituted for conventional fuel rods in the Idaho National Laboratory’s Advanced Test Reactor. This laboratory version is heated electrically. [Work supported by the U.S. Department of Energy.

Randall A. Ali; Steven L. Garrett; James A. Smith; Dale K. Kotter

2012-01-01T23:59:59.000Z

269

Energy Return on Investment from Recycling Nuclear Fuel  

SciTech Connect

This report presents an evaluation of the Energy Return on Investment (EROI) from recycling an initial batch of 800 t/y of used nuclear fuel (UNF) through a Recycle Center under a number of different fuel cycle scenarios. The study assumed that apart from the original 800 t of UNF only depleted uranium was available as a feed. Therefore for each subsequent scenario only fuel that was derived from the previous fuel cycle scenario was considered. The scenarios represent a good cross section of the options available and the results contained in this paper and associated appendices will allow for other fuel cycle options to be considered.

None

2011-08-17T23:59:59.000Z

270

Ukraine Fuel Removal: Fact Sheet | National Nuclear Security Administration  

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

Ukraine Fuel Removal: Fact Sheet | National Nuclear Security Administration Ukraine Fuel Removal: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Ukraine Fuel Removal: Fact Sheet Fact Sheet Ukraine Fuel Removal: Fact Sheet Mar 26, 2012 For nearly two decades, the United States and Ukraine have cooperated on a

271

Nuclear Power Generation and Fuel Cycle Report 1997  

Gasoline and Diesel Fuel Update (EIA)

7) 7) Distribution Category UC-950 Nuclear Power Generation and Fuel Cycle Report 1997 September 1997 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or of any other organization. Contacts Energy Information Administration/ Nuclear Power Generation and Fuel Cycle Report 1997 ii The Nuclear Power Generation and Fuel Cycle Report is prepared by the U.S. Department of Energy's Energy Information Administration. Questions and comments concerning the contents of the report may be directed to:

272

Public Acceptability of and Preferences for Used Nuclear Fuel...  

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

Acceptance and Preferences for Used Nuclear Fuel Management in the U.S. Hank C. Jenkins-Smith Kuhika Gupta Center for Energy, Security & Society University of Oklahoma Energy...

273

Ukraine Fuel Removal: Fact Sheet | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Ukraine Fuel Removal: Fact Sheet | National Nuclear Security Administration Ukraine Fuel Removal: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Ukraine Fuel Removal: Fact Sheet Fact Sheet Ukraine Fuel Removal: Fact Sheet Mar 26, 2012 For nearly two decades, the United States and Ukraine have cooperated on a

274

Nuclear Power Generation and Fuel Cycle Report 1996  

Gasoline and Diesel Fuel Update (EIA)

6) 6) Distribution Category UC-950 Nuclear Power Generation and Fuel Cycle Report 1996 October 1996 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or of any other organization. Energy Information Administration/ Nuclear Power Generation and Fuel Cycle Report 1996 ii Contacts This report was prepared in the Office of Coal, Nuclear, report should be addressed to the following staff Electric and Alternate Fuels by the Analysis and Systems

275

Next-generation nuclear fuel withstands high-temperature accident...  

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

teri.ehresman@inl.gov Bill Cabage (ORNL), 865-574-4399, cabagewh@ornl.gov Next-generation nuclear fuel withstands high-temperature accident conditions IDAHO FALLS - A safer...

276

Overview of Fuel Cell Electric Bus Development  

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

Overview of Fuel Cell Overview of Fuel Cell Electric Bus Development Leslie Eudy, National Renewable Energy Laboratory September 12, 2013 2 Why Fuel Cells for Transit Buses? * Reduce transit bus emissions * Improve fuel efficiency * Improve vehicle performance * Consumer Acceptance * Transit industry is excellent test-bed for new technologies o Centrally fueled and maintained o Fixed routes with urban stop-go duty cycle o Professional operators and mechanics o Federal Capital Funding Support o High Visibility & High Impact 3 FCEB Development Timeline since 2000 California Air Resources Board Transit Rule Early demonstrations of single prototypes DOE begins funding NREL technology validation for FCEBs First multiple bus fleet demonstrations in California FTA initiates National Fuel Cell Bus Program and

277

Plutonium and Reprocessing of Spent Nuclear Fuel  

Science Journals Connector (OSTI)

...might spawn nuclear terrorism. Less than...reprocessing plant. The U.S. nuclear-energy...current fleet of power reactors (15...operational risk of transmutation...future of nuclear power is clarified...constructed plant increased...

Frank N. von Hippel

2001-09-28T23:59:59.000Z

278

Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF)  

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

GC-52 provides legal advice to DOE regarding the long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF). SNF is nuclear fuel that has been used as fuel in a reactor...

279

IFR fuel cycle--pyroprocess development  

SciTech Connect

The Integral Fast Reactor (IFR) fuel cycle is based on the use of a metallic fuel alloy, with nominal composition U-2OPu-lOZr. In its present state of development, this fuel system offers excellent high-burnup capabilities. Test fuel has been carried to burnups in excess of 20 atom % in EBR-II irradiations, and to peak burnups over 15 atom % in FFTF. The metallic fuel possesses physical characteristics, in particular very high thermal conductivity, that facilitate a high degree of passive inherent safety in the IFR design. The fuel has been shown to provide very large margins to failure in overpower transient events. Rapid overpower transient tests carried out in the TREAT reactor have shown the capability to withstand up to 400% overpower conditions before failing. An operational transient test conducted in EBR-II at a power ramp rate of 0.1% per second reached its termination point of 130% of normal power without any fuel failures. The IFR metallic fuel also exhibits superior compatibility with the liquid sodium coolant. Equally as important as the performance advantages offered by the use of metallic fuel is the fact that this fuel system permits the use of an innovative reprocessing method, known as ``pyroprocessing,`` featuring fused-salt electrorefining of the spent fuel. Development of the IFR pyroprocess has been underway at the Argonne National Laboratory for over five years, and great progress has been made toward establishing a commercially-viable process. Pyroprocessing offers a simple, compact means for closure of the fuel cycle, with anticipated significant savings in fuel cycle costs.

Laidler, J.J.; Miller, W.E.; Johnson, T.R.; Ackerman, J.P.; Battles, J.E.

1992-11-01T23:59:59.000Z

280

IFR fuel cycle--pyroprocess development  

SciTech Connect

The Integral Fast Reactor (IFR) fuel cycle is based on the use of a metallic fuel alloy, with nominal composition U-2OPu-lOZr. In its present state of development, this fuel system offers excellent high-burnup capabilities. Test fuel has been carried to burnups in excess of 20 atom % in EBR-II irradiations, and to peak burnups over 15 atom % in FFTF. The metallic fuel possesses physical characteristics, in particular very high thermal conductivity, that facilitate a high degree of passive inherent safety in the IFR design. The fuel has been shown to provide very large margins to failure in overpower transient events. Rapid overpower transient tests carried out in the TREAT reactor have shown the capability to withstand up to 400% overpower conditions before failing. An operational transient test conducted in EBR-II at a power ramp rate of 0.1% per second reached its termination point of 130% of normal power without any fuel failures. The IFR metallic fuel also exhibits superior compatibility with the liquid sodium coolant. Equally as important as the performance advantages offered by the use of metallic fuel is the fact that this fuel system permits the use of an innovative reprocessing method, known as pyroprocessing,'' featuring fused-salt electrorefining of the spent fuel. Development of the IFR pyroprocess has been underway at the Argonne National Laboratory for over five years, and great progress has been made toward establishing a commercially-viable process. Pyroprocessing offers a simple, compact means for closure of the fuel cycle, with anticipated significant savings in fuel cycle costs.

Laidler, J.J.; Miller, W.E.; Johnson, T.R.; Ackerman, J.P.; Battles, J.E.

1992-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Submersion Criticality Safety Analysis of Tungsten-Based Fuel for Nuclear Power and Propulsion Applications  

SciTech Connect

The Center for Space Nuclear Research (CSNR) is developing tungsten-encapsulated fuels for space nuclear applications. Aims to develop NTP fuels that are; Affordable Low impact on production and testing environment Producible on a large scale over suitable time period Higher-performance compared to previous graphite NTP fuel elements Space nuclear reactors remain subcritical before and during launch, and do not go critical until required by its mission. A properly designed reactor will remain subcritical in any launch abort scenario, where the reactor falls back to Earth and becomes submerged in terrestrial material. Submersion increases neutron reflection and thermalizes the neutrons, which typically increases the reactivity of the core. This effect is usually very significant for fast-spectrum reactors. This research provided a submersion criticality safety analysis for a representative tungsten/uranium oxide fueled reactor. Determine the submersion behavior of a reactor fueled by tungsten-based fuel. Considered fuel compositions with varying: Rhenium content (wt% rhenium in tungsten) Fuel loading fractions (UO2 vol%)

A.E. Craft; R. C. O'Brien; S. D. Howe; J. C. King

2014-07-01T23:59:59.000Z

282

Fuel Cycle Research and Development Presentation Title  

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

SiC Research for SiC Research for Accident Tolerant Fuels Shannon Bragg-Sitton Idaho National Laboratory Advanced LWR Fuels Technical Lead Advanced Fuels Campaign Advanced LWR Fuels Pathway Lead Light Water Reactor Sustainability Program August 2013 Outline  Overview of DOE SiC research  Severe accident modeling: MELCOR analysis w/SiC  Recent characterization test results - Oxidation kinetics - Irradiation studies - Fuel-clad interactions - Elastic property measurement - Thermal properties - Failure model analysis - Quench testing  Technology development - ASTM standards development - SiC/SiC joining technology 2 SiC Gap Analysis and Feasibility Study  SiC Gap Analysis / Feasibility - Milestone report issued July 30, 2013 - Incorporates results of work funded

283

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

2001-07-17T23:59:59.000Z

284

Mox fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion. characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

2001-05-15T23:59:59.000Z

285

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly. 38 figs.

Kantrowitz, M.L.; Rosenstein, R.G.

1998-10-13T23:59:59.000Z

286

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

1998-01-01T23:59:59.000Z

287

Nuclear Regulatory Commission's Integrated Strategy for Spent Fuel Management  

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

NRC's NRC's Integrated Strategy for NRC s Integrated Strategy for Spent Fuel Management Earl Easton 1 U.S. Nuclear Regulatory Commission May 25, 2010 Road to Yucca Mountain * 20+ years of preparation for the licensing i review * DOE application received in June 2008 and accepted for review in September 2008 * President Obama pursues alternatives to Yucca Mountain * DOE motion to withdraw in March 2010 2 * DOE motion to withdraw in March 2010 * Blue Ribbon Commission on America's Nuclear Future 2 Growing Spent Fuel Inventory Cumulative Used Nuclear Fuel Scenarios 50,000 100,000 150,000 200,000 250,000 Metric Tons 3 - 50,000 2010 2015 2020 2025 2030 2035 2040 2045 2050 Year Reference: Crozat, March 2010 Integrated Strategy * In response to the evolving national debate on spent fuel management strategy, NRC initiated a number of actions:

288

Review of Used Nuclear Fuel Storage and Transportation Technical Gap  

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

Analysis Analysis Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis While both wet and dry storage have been shown to be safe options for storing used nuclear fuel (UNF), the focus of the program is on dry storage of commercial UNF at reactor or centralized locations. This report focuses on the knowledge gaps concerning extended storage identified in numerous domestic and international investigations and provides the Used Fuel Disposition Campaign"s (UFDC) gap description, any alternate gap descriptions, the rankings by the various organizations, evaluation of the priority assignment, and UFDC-recommended action based on the comparison. Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis More Documents & Publications

289

Spent nuclear fuel discharges from US reactors 1992  

SciTech Connect

This report provides current statistical data on every fuel assembly irradiated in commercial nuclear reactors operating in the United States. It also provides data on the current inventories and storage capacities of those reactors to a wide audience, including Congress, Federal and State agencies, the nuclear and electric industries and the general public. It uses data from the mandatory, ``Nuclear Fuel Data`` survey, Form RW-859 for 1992 and historical data collected by the Energy Information Administration (EIA) on previous Form RW-859 surveys. The report was prepared by the EIA under a Memorandum of Understanding with the Office of Civilian Radioactive Waste Management.

Not Available

1994-05-05T23:59:59.000Z

290

Summary of Preliminary Criticality Analysis for Peach Bottom Fuel in the DOE Standardized Spent Nuclear Fuel Canister  

SciTech Connect

The Department of Energy's (DOE's) National Spent Nuclear Fuel Program is developing a standardized set of canisters for DOE spent nuclear fuel (SNF). These canisters will be used for DOE SNF handling, interim storage, transportation, and disposal in the national repository. Several fuels are being examined in conjunction with the DOE SNF canisters. This report summarizes the preliminary criticality safety analysis that addresses general fissile loading limits for Peach Bottom graphite fuel in the DOE SNF canister. The canister is considered both alone and inside the 5-HLW/DOE Long Spent Fuel Co-disposal Waste Package, and in intact and degraded conditions. Results are appropriate for a single DOE SNF canister. Specific facilities, equipment, canister internal structures, and scenarios for handling, storage, and transportation have not yet been defined and are not evaluated in this analysis. The analysis assumes that the DOE SNF canister is designed so that it maintains reasonable geometric integrity. Parameters important to the results are the canister outer diameter, inner diameter, and wall thickness. These parameters are assumed to have nominal dimensions of 45.7-cm (18.0-in.), 43.815-cm (17.25-in), and 0.953-cm (0.375-in.), respectively. Based on the analysis results, the recommended fissile loading for the DOE SNF canister is 13 Peach Bottom fuel elements if no internal steel is present, and 15 Peach Bottom fuel elements if credit is taken for internal steel.

Henrikson, D.J.

1999-09-01T23:59:59.000Z

291

Accelerator-driven subcritical fission in molten salt core: Closing the nuclear fuel cycle for green nuclear energy  

SciTech Connect

A technology for accelerator-driven subcritical fission in a molten salt core (ADSMS) is being developed as a basis for the destruction of the transuranics in used nuclear fuel. The molten salt fuel is a eutectic mixture of NaCl and the chlorides of the transuranics and fission products. The core is driven by proton beams from a strong-focusing cyclotron stack. This approach uniquely provides an intrinsically safe means to drive a core fueled only with transuranics, thereby eliminating competing breeding terms.

McIntyre, Peter; Assadi, Saeed; Badgley, Karie; Baker, William; Comeaux, Justin; Gerity, James; Kellams, Joshua; McInturff, Al; Pogue, Nathaniel; Sattarov, Akhdiyor; Sooby, Elizabeth; Tsvetkov, Pavel [Dept. of Physics, Texas A and M University, College Station, TX 77843 and Dept. of Nuclear Engineering, Texas A and M University, College Station, TX 77843 (United States); Phongikaroon, Supathorn; Simpson, Michael [Dept. of Chemical Engineering, University of Idaho, Idaho Falls ID 83402 (United States)

2013-04-19T23:59:59.000Z

292

Plutonium and Reprocessing of Spent Nuclear Fuel  

Science Journals Connector (OSTI)

...Repository for the Disposal of Spent Nuclear...Radioactive Waste at Yucca Mountain (YMP-0106...not committed funding to build...Repository for the Disposal of Spent Nuclear...Radioactive Waste at Yucca Mountain (YMP-0106, Yucca Mountain Project, North...

Frank N. von Hippel

2001-09-28T23:59:59.000Z

293

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W. (Oak Ridge, TN)

1998-01-01T23:59:59.000Z

294

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package. 6 figs.

Forsberg, C.W.

1998-11-03T23:59:59.000Z

295

Nuclear energy: Thorium fuel has risks  

Science Journals Connector (OSTI)

... thorium's use in declared nuclear activities, and greater vigilance is needed to protect against surreptitious activities involving this element. ...

Stephen F. Ashley; Geoffrey T. Parks; William J. Nuttall; Colin Boxall; Robin W. Grimes

2012-12-05T23:59:59.000Z

296

Porous nuclear fuel element with internal skeleton for high-temperature gas-cooled nuclear reactors  

DOE Patents (OSTI)

Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

Youchison, Dennis L.; Williams, Brian E.; Benander, Robert E.

2013-09-03T23:59:59.000Z

297

Porous nuclear fuel element for high-temperature gas-cooled nuclear reactors  

DOE Patents (OSTI)

Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

Youchison, Dennis L. (Albuquerque, NM); Williams, Brian E. (Pacoima, CA); Benander, Robert E. (Pacoima, CA)

2011-03-01T23:59:59.000Z

298

An evaluation of thermal modeling techniques utilized for nuclear fuel rods  

E-Print Network (OSTI)

like to thank my graduate advisor, Dr. K. L. Peddicord, for his technical advice and guidance throughout this project and my studies in Nuclear Engineering at Texas AgiM University. Thanks are also extended to Dr. Hassan and Dr. Caton for reviewing.... Burnup Fission Gas Rdease Fuel Tltermal Conductivity Fuel Cracking Fuel Creep Rate Fuel Relocadon Fuel VIrermal Expansion Fuel Rod Tltermal Power Fuel Telltpelanaes Fuel Stress es Fuel Strains Fission Rate Fuel-Cladding Gap Heat...

Simmons, Jeffrey Warren

2012-06-07T23:59:59.000Z

299

Prospects for and problems of using light-water supercritical-pressure coolant in nuclear reactors in order to increase the efficiency of the nuclear fuel cycle  

SciTech Connect

Trends in the development of the power sector of the Russian and world power industries both at present time and in the near future are analyzed. Trends in the rise of prices for reserves of fossil and nuclear fuels used for electricity production are compared. An analysis of the competitiveness of electricity production at nuclear power plants as compared to the competitiveness of electricity produced at coal-fired and natural-gas-fired thermal power plants is performed. The efficiency of the open nuclear fuel cycle and various versions of the closed nuclear fuel cycle is discussed. The requirements on light-water reactors under the scenario of dynamic development of the nuclear power industry in Russia are determined. Results of analyzing the efficiency of fuel utilization for various versions of vessel-type light-water reactors with supercritical coolant are given. Advantages and problems of reactors with supercritical-pressure water are listed.

Alekseev, P. N.; Semchenkov, Yu. M.; Sedov, A. A., E-mail: sedov@dhtp.kial.ru; Subbotin, S. A.; Chibinyaev, A. V. [Russian Research Centre Kurchatov Institute (Russian Federation)

2011-12-15T23:59:59.000Z

300

Multi-Detector Analysis System for Spent Nuclear Fuel Characterization  

SciTech Connect

The Spent Nuclear Fuel (SNF) Non-Destructive Analysis (NDA) program at INEEL is developing a system to characterize SNF for fissile mass, radiation source term, and fissile isotopic content. The system is based on the integration of the Fission Assay Tomography System (FATS) and the Gamma-Neutron Analysis Technique (GNAT) developed under programs supported by the DOE Office of Non-proliferation and National Security. Both FATS and GNAT were developed as separate systems to provide information on the location of special nuclear material in weapons configuration (FATS role), and to measure isotopic ratios of fissile material to determine if the material was from a weapon (GNAT role). FATS is capable of not only determining the presence and location of fissile material but also the quantity of fissile material present to within 50%. GNAT determines the ratios of the fissile and fissionable material by coincidence methods that allow the two prompt (immediately) produced fission fragments to be identified. Therefore, from the combination of FATS and GNAT, MDAS is able to measure the fissile material, radiation source term, and fissile isotopics content.

Reber, Edward Lawrence; Aryaeinejad, Rahmat; Cole, Jerald Donald; Drigert, Mark William; Jewell, James Keith; Egger, Ann Elizabeth; Cordes, Gail Adele

1999-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

Cover Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Cover Cover of the Fuel Cell Technologies Office Multi-Year Research, Development,...

302

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Appendix E: Acronyms Fuel Cell Technologies Office Multi-Year Research, Development, and...

303

Developing SAE Safety Standards for Hydrogen and Fuel Cell Vehicles...  

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

Developing SAE Safety Standards for Hydrogen and Fuel Cell Vehicles (FCVs) Developing SAE Safety Standards for Hydrogen and Fuel Cell Vehicles (FCVs) Presentation by Michael...

304

DEVELOPMENT OF A RENEWABLE HYDROGEN PRODUCITON AND FUEL CELL...  

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

DEVELOPMENT OF A RENEWABLE HYDROGEN PRODUCITON AND FUEL CELL EDUCATION PROGRAM DEVELOPMENT OF A RENEWABLE HYDROGEN PRODUCITON AND FUEL CELL EDUCATION PROGRAM 2009 DOE Hydrogen...

305

2010 Hydrogen and Fuel Cell Global Commercialization & Development...  

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

2010 Hydrogen and Fuel Cell Global Commercialization & Development Update 2010 Hydrogen and Fuel Cell Global Commercialization & Development Update This report outlines the role...

306

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan The...

307

Nuclear Systems Modeling, Simulation & Validation | Nuclear Science...  

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

Research Areas Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation...

308

TOWARDS BENCHMARK MEASUREMENTS FOR USED NUCLEAR FUEL ASSAY USING A LEAD SLOWING-DOWN SPECTROMETER  

E-Print Network (OSTI)

for spent fuel testing. The characterization of spent fuel is particularly important for nuclear safeguardsTOWARDS BENCHMARK MEASUREMENTS FOR USED NUCLEAR FUEL ASSAY USING A LEAD SLOWING-DOWN SPECTROMETER B) is considered as a possible option for non- destructive assay of fissile material in used nuclear fuel

Danon, Yaron

309

Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography  

E-Print Network (OSTI)

This paper explores the use of cosmic ray muons to image the contents of shielded containers and detect high-Z special nuclear materials inside them. Cosmic ray muons are a naturally occurring form of radiation, are highly penetrating and exhibit large scattering angles on high Z materials. Specifically, we investigated how radiographic and tomographic techniques can be effective for non-invasive nuclear waste characterization and for nuclear material accountancy of spent fuel inside dry storage containers. We show that the tracking of individual muons, as they enter and exit a structure, can potentially improve the accuracy and availability of data on nuclear waste and the contents of Dry Storage Containers (DSC) used for spent fuel storage at CANDU plants. This could be achieved in near real time, with the potential for unattended and remotely monitored operations. We show that the expected sensitivity, in the case of the DSC, exceeds the IAEA detection target for nuclear material accountancy.

Jonkmans, G; Jewett, C; Thompson, M

2012-01-01T23:59:59.000Z

310

Systems Analysis of an Advanced Nuclear Fuel Cycle Based on a Modified UREX+3c Process  

SciTech Connect

The research described in this report was performed under a grant from the U.S. Department of Energy (DOE) to describe and compare the merits of two advanced alternative nuclear fuel cycles -- named by this study as the “UREX+3c fuel cycle” and the “Alternative Fuel Cycle” (AFC). Both fuel cycles were assumed to support 100 1,000 MWe light water reactor (LWR) nuclear power plants operating over the period 2020 through 2100, and the fast reactors (FRs) necessary to burn the plutonium and minor actinides generated by the LWRs. Reprocessing in both fuel cycles is assumed to be based on the UREX+3c process reported in earlier work by the DOE. Conceptually, the UREX+3c process provides nearly complete separation of the various components of spent nuclear fuel in order to enable recycle of reusable nuclear materials, and the storage, conversion, transmutation and/or disposal of other recovered components. Output of the process contains substantially all of the plutonium, which is recovered as a 5:1 uranium/plutonium mixture, in order to discourage plutonium diversion. Mixed oxide (MOX) fuel for recycle in LWRs is made using this 5:1 U/Pu mixture plus appropriate makeup uranium. A second process output contains all of the recovered uranium except the uranium in the 5:1 U/Pu mixture. The several other process outputs are various waste streams, including a stream of minor actinides that are stored until they are consumed in future FRs. For this study, the UREX+3c fuel cycle is assumed to recycle only the 5:1 U/Pu mixture to be used in LWR MOX fuel and to use depleted uranium (tails) for the makeup uranium. This fuel cycle is assumed not to use the recovered uranium output stream but to discard it instead. On the other hand, the AFC is assumed to recycle both the 5:1 U/Pu mixture and all of the recovered uranium. In this case, the recovered uranium is reenriched with the level of enrichment being determined by the amount of recovered plutonium and the combined amount of the resulting MOX. The study considered two sub-cases within each of the two fuel cycles in which the uranium and plutonium from the first generation of MOX spent fuel (i) would not be recycled to produce a second generation of MOX for use in LWRs or (ii) would be recycled to produce a second generation of MOX fuel for use in LWRs. The study also investigated the effects of recycling MOX spent fuel multiple times in LWRs. The study assumed that both fuel cycles would store and then reprocess spent MOX fuel that is not recycled to produce a next generation of LWR MOX fuel and would use the recovered products to produce FR fuel. The study further assumed that FRs would begin to be brought on-line in 2043, eleven years after recycle begins in LWRs, when products from 5-year cooled spent MOX fuel would be available. Fuel for the FRs would be made using the uranium, plutonium, and minor actinides recovered from MOX. For the cases where LWR fuel was assumed to be recycled one time, the 1st generation of MOX spent fuel was used to provide nuclear materials for production of FR fuel. For the cases where the LWR fuel was assumed to be recycled two times, the 2nd generation of MOX spent fuel was used to provide nuclear materials for production of FR fuel. The number of FRs in operation was assumed to increase in successive years until the rate that actinides were recovered from permanently discharged spent MOX fuel equaled the rate the actinides were consumed by the operating fleet of FRs. To compare the two fuel cycles, the study analyzed recycle of nuclear fuel in LWRs and FRs and determined the radiological characteristics of irradiated nuclear fuel, nuclear waste products, and recycle nuclear fuels. It also developed a model to simulate the flows of nuclear materials that could occur in the two advanced nuclear fuel cycles over 81 years beginning in 2020 and ending in 2100. Simulations projected the flows of uranium, plutonium, and minor actinides as these nuclear fuel materials were produced and consumed in a fleet of 100 1,000 MWe LWRs and in FRs. The model als

E. R. Johnson; R. E. Best

2009-12-28T23:59:59.000Z

311

Roadmap to an Engineering-Scale Nuclear Fuel Performance & Safety Code  

SciTech Connect

Developing new fuels and qualifying them for large-scale deployment in power reactors is a lengthy and expensive process, typically spanning a period of two decades from concept to licensing. Nuclear fuel designers serve an indispensable role in the process, at the initial exploratory phase as well as in analysis of the testing results. In recent years fuel performance capabilities based on first principles have been playing more of a role in what has traditionally been an empirically dominated process. Nonetheless, nuclear fuel behavior is based on the interaction of multiple complex phenomena, and recent evolutionary approaches are being applied more on a phenomenon-by-phenomenon basis, targeting localized problems, as opposed to a systematic approach based on a fundamental understanding of all interacting parameters. Advanced nuclear fuels are generally more complex, and less understood, than the traditional fuels used in existing reactors (ceramic UO{sub 2} with burnable poisons and other minor additives). The added challenges are primarily caused by a less complete empirical database and, in the case of recycled fuel, the inherent variability in fuel compositions. It is clear that using the traditional approach to develop and qualify fuels over the entire range of variables pertinent to the U.S. Department of Energy (DOE) Office of Nuclear Energy on a timely basis with available funds would be very challenging, if not impossible. As a result the DOE Office of Nuclear Energy has launched the Nuclear Energy Advanced Modeling and Simulation (NEAMS) approach to revolutionize fuel development. This new approach is predicated upon transferring the recent advances in computational sciences and computer technologies into the fuel development program. The effort will couple computational science with recent advances in the fundamental understanding of physical phenomena through ab initio modeling and targeted phenomenological testing to leapfrog many fuel-development activities. Realizing the full benefits of this approach will likely take some time. However, it is important that the developmental activities for modeling and simulation be tightly coupled with the experimental activities to maximize feedback effects and accelerate both the experimental and analytical elements of the program toward a common objective. The close integration of modeling and simulation and experimental activities is key to developing a useful fuel performance simulation capability, providing a validated design and analysis tool, and understanding the uncertainties within the models and design process. The efforts of this project are integrally connected to the Transmutation Fuels Campaign (TFC), which maintains as a primary objective to formulate, fabricate, and qualify a transuranic-based fuel with added minor actinides for use in future fast reactors. Additional details of the TFC scope can be found in the Transmutation Fuels Campaign Execution Plan. This project is an integral component of the TFC modeling and simulation effort, and this multiyear plan borrowed liberally from the Transmutation Fuels Campaign Modeling and Simulation Roadmap. This document provides the multiyear staged development plan to develop a continuum-level Integrated Performance and Safety Code (IPSC) to predict the behavior of the fuel and cladding during normal reactor operations and anticipated transients up to the point of clad breach.

Turner, John A [ORNL; Clarno, Kevin T [ORNL; Hansen, Glen A [ORNL

2009-09-01T23:59:59.000Z

312

The Path to Sustainable Nuclear Energy. Basic and Applied Research Opportunities for Advanced Fuel Cycles  

SciTech Connect

The objective of this report is to identify new basic science that will be the foundation for advances in nuclear fuel-cycle technology in the near term, and for changing the nature of fuel cycles and of the nuclear energy industry in the long term. The goals are to enhance the development of nuclear energy, to maximize energy production in nuclear reactor parks, and to minimize radioactive wastes, other environmental impacts, and proliferation risks. The limitations of the once-through fuel cycle can be overcome by adopting a closed fuel cycle, in which the irradiated fuel is reprocessed and its components are separated into streams that are recycled into a reactor or disposed of in appropriate waste forms. The recycled fuel is irradiated in a reactor, where certain constituents are partially transmuted into heavier isotopes via neutron capture or into lighter isotopes via fission. Fast reactors are required to complete the transmutation of long-lived isotopes. Closed fuel cycles are encompassed by the Department of Energy?s Advanced Fuel Cycle Initiative (AFCI), to which basic scientific research can contribute. Two nuclear reactor system architectures can meet the AFCI objectives: a ?single-tier? system or a ?dual-tier? system. Both begin with light water reactors and incorporate fast reactors. The ?dual-tier? systems transmute some plutonium and neptunium in light water reactors and all remaining transuranic elements (TRUs) in a closed-cycle fast reactor. Basic science initiatives are needed in two broad areas: ? Near-term impacts that can enhance the development of either ?single-tier? or ?dual-tier? AFCI systems, primarily within the next 20 years, through basic research. Examples: Dissolution of spent fuel, separations of elements for TRU recycling and transmutation Design, synthesis, and testing of inert matrix nuclear fuels and non-oxide fuels Invention and development of accurate on-line monitoring systems for chemical and nuclear species in the nuclear fuel cycle Development of advanced tools for designing reactors with reduced margins and lower costs ? Long-term nuclear reactor development requires basic science breakthroughs: Understanding of materials behavior under extreme environmental conditions Creation of new, efficient, environmentally benign chemical separations methods Modeling and simulation to improve nuclear reaction cross-section data, design new materials and separation system, and propagate uncertainties within the fuel cycle Improvement of proliferation resistance by strengthening safeguards technologies and decreasing the attractiveness of nuclear materials A series of translational tools is proposed to advance the AFCI objectives and to bring the basic science concepts and processes promptly into the technological sphere. These tools have the potential to revolutionize the approach to nuclear engineering R&D by replacing lengthy experimental campaigns with a rigorous approach based on modeling, key fundamental experiments, and advanced simulations.

Finck, P.; Edelstein, N.; Allen, T.; Burns, C.; Chadwick, M.; Corradini, M.; Dixon, D.; Goff, M.; Laidler, J.; McCarthy, K.; Moyer, B.; Nash, K.; Navrotsky, A.; Oblozinsky, P.; Pasamehmetoglu, K.; Peterson, P.; Sackett, J.; Sickafus, K. E.; Tulenko, J.; Weber, W.; Morss, L.; Henry, G.

2005-09-01T23:59:59.000Z

313

Behavior of Spent Nuclear Fuel in Water Pool Storage  

Office of Scientific and Technical Information (OSTI)

Behavior of Spent Nuclear Behavior of Spent Nuclear Fuel in Water Pool Storage A. 0; Johnson, jr. , I ..: . Prepared Cor the Energy Research and Development Administration under Contract EY-76-C-06-1830 ---- Pat t i ~ < N ~ ~ r ~ t b w t ~ - ! I , ~ I ~ ~ ~ I . I I ~ ) ~ I I ~ ~ N O T I C E T€& - was prepad pnpn4. m w n t of w k spon-d by the Unitd S t . & ) C a u n m ~ (*WU ij*. M t e d $tam w the Wqy R e s e w & a d Ohrsropmcnt ~dmhirmlion, nor m y d thair ewhew,,nq Pny @fw a n t r ~ ~ t 0 ~ 1 , s ~ k m r i t r i l t t q r , ~ , m r tWf ernpfQw, r(tLltm any wartany, s x p r e s or kWld,= w w aAql -9 . o r r w p a m l ~ ~ t y for e~ o r uodruincvr of any infomutim, 9 F p d + d - , or repratants that -would nat 1 d - e privately owned rfghas. ,i PAQFIC NORTHWEST UBORATORY operated b ;"' SArnLLE ' fw the E M R m RESEARCH AND DEVELOPMENT ADMINISTRAT1QN Wk.Cwfraa rv-76c-ts-is38

314

Report of the Fuel Cycle Research and Development Subcommittee of the  

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

Report of the Fuel Cycle Research and Development Subcommittee of Report of the Fuel Cycle Research and Development Subcommittee of the Nuclear Energy Advisory Committee Report of the Fuel Cycle Research and Development Subcommittee of the Nuclear Energy Advisory Committee The Fuel Cycle (FC) Subcommittee of NEAC met February 7-8, 2012 in Washington (Drs. Hoffmann and Juzaitis were unable to attend). While the meeting was originally scheduled to occur after the submission of the President's FY 2013 budget, the submission was delayed a week; thus, we could have no discussion on balance in the NE program. The Agenda is attached as Appendix A. The main focus of the meeting was on accident tolerant fuels, an important post Fukushima issue, and on issues related to the report of the Blue Ribbon Commission on America's Nuclear Future (BRC) as related to the

315

A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation  

SciTech Connect

This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Lahti, Erik A.; Richmond, David J.

2012-08-01T23:59:59.000Z

316

International Nuclear Fuel Cycle Fact Book. Revision 12  

SciTech Connect

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

Leigh, I.W.

1992-05-01T23:59:59.000Z

317

Fuel cycle cost uncertainty from nuclear fuel cycle comparison  

SciTech Connect

This paper examined the uncertainty in fuel cycle cost (FCC) calculation by considering both model and parameter uncertainty. Four different fuel cycle options were compared in the analysis including the once-through cycle (OT), the DUPIC cycle, the MOX cycle and a closed fuel cycle with fast reactors (FR). The model uncertainty was addressed by using three different FCC modeling approaches with and without the time value of money consideration. The relative ratios of FCC in comparison to OT did not change much by using different modeling approaches. This observation was consistent with the results of the sensitivity study for the discount rate. Two different sets of data with uncertainty range of unit costs were used to address the parameter uncertainty of the FCC calculation. The sensitivity study showed that the dominating contributor to the total variance of FCC is the uranium price. In general, the FCC of OT was found to be the lowest followed by FR, MOX, and DUPIC. But depending on the uranium price, the FR cycle was found to have lower FCC over OT. The reprocessing cost was also found to have a major impact on FCC.

Li, J.; McNelis, D. [Institute for the Environment, University of North Carolina, Chapel Hill (United States); Yim, M.S. [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (Korea, Republic of)

2013-07-01T23:59:59.000Z

318

Double-clad nuclear-fuel safety rod  

DOE Patents (OSTI)

A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

McCarthy, W.H.; Atcheson, D.B.

1981-12-30T23:59:59.000Z

319

Apparatus for injection casting metallic nuclear energy fuel rods  

DOE Patents (OSTI)

Molds for making metallic nuclear fuel rods are provided which present reduced risks to the environment by reducing radioactive waste. In one embodiment, the mold is consumable with the fuel rod, and in another embodiment, part of the mold can be re-used. Several molds can be arranged together in a cascaded manner, if desired, or several long cavities can be integrated in a monolithic multiple cavity re-usable mold.

Seidel, Bobby R. (Idaho Falls, ID); Tracy, Donald B. (Firth, ID); Griffiths, Vernon (Butte, MT)

1991-01-01T23:59:59.000Z

320

Technology Insights and Perspectives for Nuclear Fuel Cycle Concepts  

SciTech Connect

The following report provides a rich resource of information for exploring fuel cycle characteristics. The most noteworthy trends can be traced back to the utilization efficiency of natural uranium resources. By definition, complete uranium utilization occurs only when all of the natural uranium resource can be introduced into the nuclear reactor long enough for all of it to undergo fission. Achieving near complete uranium utilization requires technologies that can achieve full recycle or at least nearly full recycle of the initial natural uranium consumed from the Earth. Greater than 99% of all natural uranium is fertile, and thus is not conducive to fission. This fact requires the fuel cycle to convert large quantities of non-fissile material into fissile transuranics. Step increases in waste benefits are closely related to the step increase in uranium utilization going from non-breeding fuel cycles to breeding fuel cycles. The amount of mass requiring a disposal path is tightly coupled to the quantity of actinides in the waste stream. Complete uranium utilization by definition means that zero (practically, near zero) actinide mass is present in the waste stream. Therefore, fuel cycles with complete (uranium and transuranic) recycle discharge predominately fission products with some actinide process losses. Fuel cycles without complete recycle discharge a much more massive waste stream because only a fraction of the initial actinide mass is burned prior to disposal. In a nuclear growth scenario, the relevant acceptable frequency for core damage events in nuclear reactors is inversely proportional to the number of reactors deployed in a fuel cycle. For ten times the reactors in a fleet, it should be expected that the fleet-average core damage frequency be decreased by a factor of ten. The relevant proliferation resistance of a fuel cycle system is enhanced with: decreasing reliance on domestic fuel cycle services, decreasing adaptability for technology misuse, enablement of material accountability, and decreasing material attractiveness.

S. Bays; S. Piet; N. Soelberg; M. Lineberry; B. Dixon

2010-09-01T23:59:59.000Z

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


321

Quantitative assessment of proposals on assurance of nuclear fuel supply  

SciTech Connect

The assurance of nuclear fuel supply has the potential to contribute to balancing peaceful use of nuclear power and nuclear nonproliferation. 5 proposals which provide the backup supply of the enrichment service in case of supply disruption, are investigated in this study. We investigated the 20 NPT countries which are non-nuclear-weapon states and possess operable commercial LWRs in October 2012 as potential participants for each proposal. As a result of literature researching, we have extracted factors that can be considered as important for a country to participate or not participate in the assurance of nuclear fuel supply. Then we have computed incentive and disincentive parameters for each country. The results show that the participation expectancy decreases in the order of IAEA Fuel Bank proposal, Russian LEU Reserve proposal, AFS proposal, WNA proposal and 6-Country proposal. The 'IAEA fuel bank proposal' would be triggered in case of the supply disruption which cannot be solved by the market mechanism and bilateral agreements.

Tanaka, T.; Kuno, Y.; Tanaka, S. [University of Tokyo, 7-3-1 Hongou, Bunkyou-ku, Tokyo 112-0005 (Japan)

2013-07-01T23:59:59.000Z

322

Spark Plasma Sintering of Fuel Cermets for Nuclear Reactor Applications  

SciTech Connect

The feasibility of the fabrication of tungsten based nuclear fuel cermets via Spark Plasma Sintering (SPS) is investigated in this work. CeO2 is used to simulate fuel loadings of UO2 or Mixed-Oxide (MOX) fuels within tungsten-based cermets due to the similar properties of these materials. This study shows that after a short time sintering, greater than 90 % density can be achieved, which is suitable to possess good strength as well as the ability to contain fission products. The mechanical properties and the densities of the samples are also investigated as functions of the applied pressures during the sintering.

Yang Zhong; Robert C. O'Brien; Steven D. Howe; Nathan D. Jerred; Kristopher Schwinn; Laura Sudderth; Joshua Hundley

2011-11-01T23:59:59.000Z

323

Characterization of Nuclear Fuel using Multivariate Statistical Analysis  

SciTech Connect

Various combinations of reactor type and fuel composition have been characterized using principle components analysis (PCA) of the concentrations of 9 U and Pu isotopes in the 10 fuel as a function of burnup. The use of PCA allows the reduction of the 9-dimensional data (isotopic concentrations) into a 3-dimensional approximation, giving a visual representation of the changes in nuclear fuel composition with burnup. Real-world variation in the concentrations of {sup 234}U and {sup 236}U in the fresh (unirradiated) fuel was accounted for. The effects of reprocessing were also simulated. The results suggest that, 15 even after reprocessing, Pu isotopes can be used to determine both the type of reactor and the initial fuel composition with good discrimination. Finally, partial least squares discriminant analysis (PSLDA) was investigated as a substitute for PCA. Our results suggest that PLSDA is a better tool for this application where separation between known classes is most important.

Robel, M; Robel, M; Robel, M; Kristo, M J; Kristo, M J

2007-11-27T23:59:59.000Z

324

Sensitivity analysis and optimization of the nuclear fuel cycle  

SciTech Connect

A sensitivity study has been conducted to assess the robustness of the conclusions presented in the MIT Fuel Cycle Study. The Once Through Cycle (OTC) is considered as the base-line case, while advanced technologies with fuel recycling characterize the alternative fuel cycles. The options include limited recycling in LWRs and full recycling in fast reactors and in high conversion LWRs. Fast reactor technologies studied include both oxide and metal fueled reactors. The analysis allowed optimization of the fast reactor conversion ratio with respect to desired fuel cycle performance characteristics. The following parameters were found to significantly affect the performance of recycling technologies and their penetration over time: Capacity Factors of the fuel cycle facilities, Spent Fuel Cooling Time, Thermal Reprocessing Introduction Date, and in core and Out-of-core TRU Inventory Requirements for recycling technology. An optimization scheme of the nuclear fuel cycle is proposed. Optimization criteria and metrics of interest for different stakeholders in the fuel cycle (economics, waste management, environmental impact, etc.) are utilized for two different optimization techniques (linear and stochastic). Preliminary results covering single and multi-variable and single and multi-objective optimization demonstrate the viability of the optimization scheme. (authors)

Passerini, S.; Kazimi, M. S.; Shwageraus, E. [Massachusetts Inst. of Technology, Dept. of Nuclear Science and Engineering, 77 Massachusetts Avenue, Cambridge, MA 02138 (United States)

2012-07-01T23:59:59.000Z

325

Incorporation of a risk analysis approach for the nuclear fuel cycle advanced transparency framework.  

SciTech Connect

Proliferation resistance features that reduce the likelihood of diversion of nuclear materials from the civilian nuclear power fuel cycle are critical for a global nuclear future. A framework that monitors process information continuously can demonstrate the ability to resist proliferation by measuring and reducing diversion risk, thus ensuring the legitimate use of the nuclear fuel cycle. The automation of new nuclear facilities requiring minimal manual operation makes this possible by generating instantaneous system state data that can be used to track and measure the status of the process and material at any given time. Sandia National Laboratories (SNL) and the Japan Atomic Energy Agency (JAEA) are working in cooperation to develop an advanced transparency framework capable of assessing diversion risk in support of overall plant transparency. The ''diversion risk'' quantifies the probability and consequence of a host nation diverting nuclear materials from a civilian fuel cycle facility. This document introduces the details of the diversion risk quantification approach to be demonstrated in the fuel handling training model of the MONJU Fast Reactor.

Mendez, Carmen Margarita (Sociotecnia Solutions, LLC); York, David L.; Inoue, Naoko (Japan Atomic Energy Agency); Kitabata, Takuya (Japan Atomic Energy Agency); Vugrin, Eric D.; Vugrin, Kay White; Rochau, Gary Eugene; Cleary, Virginia D.

2007-05-01T23:59:59.000Z

326

E-Print Network 3.0 - alternative nuclear fuel Sample Search...  

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

Summary: of electricity from nuclear power plants is far less than any of the alternative energy technologies now contem... Processing of Nuclear Fuel, EGRN 430 ...

327

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Section 3.5 Manufacturing R&D Fuel Cell Technologies Office Multi-Year Research,...

328

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Section 3.7 Hydrogen Safety, Codes and Standards Fuel Cell Technologies Office Multi-Year...

329

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

1.0 Introduction Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Section 1.0 Introduction Introduction section of the Fuel Cell...

330

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Section 3.9 Market Transformation Fuel Cell Technologies Office Multi-Year Research,...

331

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

Executive Summary Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Executive Summary Executive Summary section of the Fuel Cell Technologies...

332

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

0 Technical Plan Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Section 3.0 Technical Plan Technical Plan section of the Fuel Cell...

333

New generation nuclear fuel structures: dense particles in selectively soluble matrix  

SciTech Connect

We have developed a technology for dispersing sub-millimeter sized fuel particles within a bulk matrix that can be selectively dissolved. This may enable the generation of advanced nuclear fuels with easy separation of actinides and fission products. The large kinetic energy of the fission products results in most of them escaping from the sub-millimeter sized fuel particles and depositing in the matrix during burning of the fuel in the reactor. After the fuel is used and allowed to cool for a period of time, the matrix can be dissolved and the fission products removed for disposal while the fuel particles are collected by filtration for recycle. The success of such an approach would meet a major goal of the GNEP program to provide advanced recycle technology for nuclear energy production. The benefits of such an approach include (1) greatly reduced cost of the actinide/fission product separation process, (2) ease of recycle of the fuel particles, and (3) a radiation barrier to prevent theft or diversion of the recycled fuel particles during the time they are re-fabricated into new fuel. In this study we describe a method to make surrogate nuclear fuels of micrometer scale W (shell)/Mo (core) or HfO2 particles embedded in an MgO matrix that allows easy separation of the fission products and their embedded particles. In brief, the method consists of physically mixing W-Mo or hafnia particles with an MgO precursor. Heating the mixture, in air or argon, without agitation, to a temperature is required for complete decomposition of the precursor. The resulting material was examined using chemical analysis, scanning electron microscopy, X-ray diffraction and micro X-ray computed tomography and found to consist of evenly dispersed particles in an MgO + matrix. We believe this methodology can be extended to actinides and other matrix materials.

Sickafus, Kurt E [Los Alamos National Laboratory; Devlin, David J [Los Alamos National Laboratory; Jarvinen, Gordon D [Los Alamos National Laboratory; Patterson, Brian M [Los Alamos National Laboratory; Pattillo, Steve G [Los Alamos National Laboratory; Valdez, James [Los Alamos National Laboratory; Phillips, Jonathan [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

334

MANAGEMENT OF SPENT NUCLEAR FUEL IN FINLAND: POLICY, PAST AND PRESENT PRACTICES, PLANS FOR THE FUTURE  

Science Journals Connector (OSTI)

In Finland, about 1700 tU of spent nuclear fuel has arisen from the operation of the four nuclear power units which were commissioned in late ... 1980’s. Initially the spent fuel management policy was based on se...

E. RUOKOLA

2006-01-01T23:59:59.000Z

335

Sizing particles of natural uranium and nuclear fuels using poly-allyl-diglycol carbonate autoradiography  

Science Journals Connector (OSTI)

......particles of natural uranium and nuclear fuels...low enriched, depleted and natural uranium and also aged...committed doses and cancer risks(4...Bristol, UK, sized uranium fragments found...nuclear fuels of depleted uranium (depUO2......

G. Hegyi; R. B. Richardson

2008-07-01T23:59:59.000Z

336

E-Print Network 3.0 - apex nuclear fuel Sample Search Results  

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

nuclear fuel Search Powered by Explorit Topic List Advanced Search Sample search results for: apex nuclear fuel Page: << < 1 2 3 4 5 > >> 1 FY 2010 Highlights Faculty and Summary:...

337

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste...  

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

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste Locations of Spent Nuclear Fuel and High-Level Radioactive Waste Map of the United States of America showing the...

338

Greenhouse Gas Emissions from the Nuclear Fuel Cycle  

SciTech Connect

Since greenhouse gases are a global concern, rather than a local concern as are some kinds of effluents, one must compare the entire lifecycle of nuclear power to alternative technologies for generating electricity. A recent critical analysis by Sovacool (2008) gives a clearer picture. "It should be noted that nuclear power is not directly emitting greenhouse gas emissions, but rather that lifecycle emissions occur through plant construction, operation, uranium mining and milling, and plant decommissioning." "[N]uclear energy is in no way 'carbon free' or 'emissions free,' even though it is much better (from purely a carbon-equivalent emissions standpoint) than coal, oil, and natural gas electricity generators, but worse than renewable and small scale distributed generators" (Sovacool 2008). According to Sovacool, at an estimated 66 g CO2 equivalent per kilowatt-hour (gCO2e/kWh), nuclear power emits 15 times less CO2 per unit electricity generated than unscrubbed coal generation (at 1050 gCO2e/kWh), but 7 times more than the best renewable, wind (at 9 gCO2e/kWh). The U.S. Nuclear Regulatory Commission (2009) has long recognized CO2 emissions in its regulations concerning the environmental impact of the nuclear fuel cycle. In Table S-3 of 10 CFR 51.51(b), NRC lists a 1000-MW(electric) nuclear plant as releasing as much CO2 as a 45-MW(e) coal plant. A large share of the carbon emissions from the nuclear fuel cycle is due to the energy consumption to enrich uranium by the gaseous diffusion process. A switch to either gas centrifugation or laser isotope separation would dramatically reduce the carbon emissions from the nuclear fuel cycle.

Strom, Daniel J.

2010-03-01T23:59:59.000Z

339

Microscopic Examination of a Corrosion Front in Spent Nuclear Fuel  

SciTech Connect

Spent uranium oxide nuclear fuel hosts a variety of trace chemical constituents, many of which must be sequestered from the biosphere during fuel storage and disposal. In this paper we present synchrotron x-ray absorption spectroscopy and microscopy findings that illuminate the resultant local chemistry of neptunium and plutonium within spent uranium oxide nuclear fuel before and after corrosive alteration in an air-saturated aqueous environment. We find the plutonium and neptunium in unaltered spent fuel to have a +4 oxidation state and an environment consistent with solid-solution in the UO{sub 2} matrix. During corrosion in an air-saturated aqueous environment, the uranium matrix is converted to uranyl U(VI)O{sub 2}{sup 2+} mineral assemblage that is depleted in plutonium and neptunium relative to the parent fuel. At the corrosion front interface between intact fuel and the uranyl-mineral corrosion layer, we find evidence of a thin ({approx}20 micrometer) layer that is enriched in plutonium and neptunium within a predominantly U{sup 4+} environment. Available data for the standard reduction potentials for NpO{sup 2+}/Np{sup 4+} and UO{sub 2}{sup 2+}/U{sup 4+} couples indicate that Np(IV) may not be effectively oxidized to Np(V) at the corrosion potentials of uranium dioxide spent nuclear fuel in air-saturated aqueous solutions. Neptunium is an important radionuclide in dose contribution according to performance assessment models of the proposed U. S. repository at Yucca Mountain, Nevada. A scientific understanding of how the UO{sub 2} matrix of spent nuclear fuel impacts the oxidative dissolution and reductive precipitation of neptunium is needed to predict its behavior at the fuel surface during aqueous corrosion. Neptunium would most likely be transported as aqueous Np(V) species, but for this to occur it must first be oxidized from the Np(IV) state found within the parent spent nuclear fuel [1]. In the immediate vicinity of the spent fuel's surface the redox and nucleation behavior is likely to promote/enhance nucleation of NpO{sub 2} and Np{sub 2}O{sub 5}. Alternatively, Np may be incorporated into uranyl (UO{sub 2}{sup 2+}) alteration phases [2]. In some cases, less-soluble elements such as plutonium will be enriched near the surface of the corroding fuel [3]. We have used focused synchrotron x-rays from the MRCAT beam line at the Advanced Photon Source (APS) at Argonne National Lab to examine a specimen of spent nuclear fuel that had been subject to 10 years of corrosion testing in an environment of humid air and dripping groundwater at 90 C [4]. We find evidence of a region, approximately 20 microns in thickness, enriched in plutonium and neptunium at the corrosion front that exists between the uranyl silicate alteration mineral rind and the unaltered uranium oxide fuel (Figures 1 and 2). The uranyl silicate is itself found to be depleted in these transuranic elements relative to their abundance relative to uranium in the parent fuel. This suggests a low mobility of these components owing to a resistance to oxidize further in the presence of a UO{sub 2}{sup 2+}/U{sup 4+} couple [5].

J.A> Fortner; A.J. Kropf; R.J. Finch; J.C. Cunnane

2006-06-20T23:59:59.000Z

340

Alternative Fuels Data Center: Hydrogen Research and Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Research and Research and Development to someone by E-mail Share Alternative Fuels Data Center: Hydrogen Research and Development on Facebook Tweet about Alternative Fuels Data Center: Hydrogen Research and Development on Twitter Bookmark Alternative Fuels Data Center: Hydrogen Research and Development on Google Bookmark Alternative Fuels Data Center: Hydrogen Research and Development on Delicious Rank Alternative Fuels Data Center: Hydrogen Research and Development on Digg Find More places to share Alternative Fuels Data Center: Hydrogen Research and Development on AddThis.com... More in this section... Hydrogen Basics Production & Distribution Research & Development Related Links Benefits & Considerations Stations Vehicles Laws & Incentives Hydrogen Research and Development

Note: This page contains sample records for the topic "development nuclear fuels" 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

Standard guide for drying behavior of spent nuclear fuel  

E-Print Network (OSTI)

1.1 This guide is organized to discuss the three major components of significance in the drying behavior of spent nuclear fuel: evaluating the need for drying, drying spent nuclear fuel, and confirmation of adequate dryness. 1.1.1 The guide addresses drying methods and their limitations in drying spent nuclear fuels that have been in storage at water pools. The guide discusses sources and forms of water that remain in SNF, its container, or both, after the drying process and discusses the importance and potential effects they may have on fuel integrity, and container materials. The effects of residual water are discussed mechanistically as a function of the container thermal and radiological environment to provide guidance on situations that may require extraordinary drying methods, specialized handling, or other treatments. 1.1.2 The basic issue in drying is to determine how dry the SNF must be in order to prevent issues with fuel retrievability, container pressurization, or container corrosion. Adequate d...

American Society for Testing and Materials. Philadelphia

2008-01-01T23:59:59.000Z

342

Changing Biomass, Fossil, and Nuclear Fuel Cycles for Sustainability  

SciTech Connect

The energy and chemical industries face two great sustainability challenges: the need to avoid climate change and the need to replace crude oil as the basis of our transport and chemical industries. These challenges can be met by changing and synergistically combining the fossil, biomass, and nuclear fuel cycles.

Forsberg, Charles W [ORNL

2007-01-01T23:59:59.000Z

343

Method of controlling crystallite size in nuclear-reactor fuels  

DOE Patents (OSTI)

Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.

Lloyd, Milton H. (Oak Ridge, TN); Collins, Jack L. (Knoxville, TN); Shell, Sam E. (Oak Ridge, TN)

1985-01-01T23:59:59.000Z

344

The Overlooked Back End of the Nuclear Fuel Cycle  

Science Journals Connector (OSTI)

...long-term plan for the disposal of nuclear waste...in new fuel and disposal of the subsequent...geologic repository at Yucca Mountain, Nevada, but the...repository for final disposal. To establish...constant source of funding is required to...

Allison M. Macfarlane

2011-09-02T23:59:59.000Z

345

Dry storage of spent nuclear fuel in UAE – Economic aspect  

Science Journals Connector (OSTI)

Abstract Cost analysis of dry storage of spent nuclear fuel (SNF) discharged from Barakah nuclear power plants in the UAE was performed using three variables: average fuel discharge rate (FD), discount rate (d), and cooling time in a spent fuel pool (Tcool). The costs of dry storage as an interim spent fuel storage option in the UAE were estimated and compared between the following two scenarios: Scenario 1 is ‘accelerated transfer of spent fuel to dry storage’ that SNF will be transferred to dry storage facilities as soon as spent fuel has been sufficiently cooled down in a pool for the dry storage; Scenario 2 is defined as ‘maximum use of spent fuel pool’ that SNF will be stored in a pool as long as possible till the amount of stored SNF in the pool reaches the capacity of the pools and, then, to be moved to dry storage. A sensitivity analysis on the costs was performed and multiple regression analysis was applied to the resulting net present values (NPVs) for Scenarios 1 and 2 and ?NPV that is difference in the net present values between the two scenarios. The results showed that \\{NPVs\\} and ?NPV could be approximately expressed by single equations with the three variables. Among the three variables, the discount rate had the largest effect on the \\{NPVs\\} of the dry storage costs. However, ?NPV was turned out to be equally sensitive to the discount rate and cooling period. Over the ranges of the variables, the additional cost for accelerated fuel transfer (Scenario 1) ranged from 86.4 to 212.9 million $. Calculated using the maximum difference (212.9 M$) between the two scenarios, the accelerated fuel transfer to dry storage could incur the additional electricity rate 8.0 × 10?5 USD/kWh, which is not considered to be significant, compared to the overall electricity generation cost.

Sara Al Saadi; Yongsun Yi

2015-01-01T23:59:59.000Z

346

Development of Solid Oxide Fuel Cells Utilizing Alternative Fuels.  

E-Print Network (OSTI)

??This dissertation is a summary of four solid oxide fuel cell (SOFC) research projects which addressed a number of SOFC technologies to use alternative fuels… (more)

Labarbera, Mark

2012-01-01T23:59:59.000Z

347

High-pressure coal fuel processor development  

SciTech Connect

Caterpillar shares DOE/METC interest in demonstrating the technology required to displace petroleum-based engine fuels with various forms of low cost coal. Current DOE/METC programs on mild gasification and coal-water-slurries are addressing two approaches to this end. Engine and fuel processor system concept studies by Caterpillar have identified a third, potentially promising, option. This option includes high-pressure fuel processing of run-of-the-mine coal and direct injection of the resulting low-Btu gas stream into an ignition assisted, high compression ratio diesel engine. The compactness and predicted efficiency of the system make it suitable for application to line-haul railroad locomotives. Two overall conclusions resulted from Task 1. First direct injected, ignition assisted Diesel cycle engine combustion systems can be suitably modified to efficiently utilize low-Btu gas fuels. Second, high pressure gasification of selected run-of-the-mine coals in batch-loaded fuel processors is feasible. These two findings, taken together, significantly reduce the perceived technical risk associated with the further development of the proposed coal gas fueled Diesel cycle power plant concept. The significant conclusions from Task 2 were: An engine concept, derived from a Caterpillar 3600 series engine, and a fuel processor concept, based on scaling up a removable-canister configuration from the test rig, appear feasible; and although the results of this concept study are encouraging, further, full-scale component research and development are required before attempting a full-scale integrated system demonstration effort.

Greenhalgh, M.L. (Caterpillar, Inc., Peoria, IL (United States))

1992-12-01T23:59:59.000Z

348

Nuclear Fuel in a Reactor Accident  

Science Journals Connector (OSTI)

...Three Mile Island: A report to the commissioners and to the public” (Nuclear Regulatory Commission, Washington, DC, 1980). 5...Podcast The contents of this podcast interview represent the opinion of the author and may go beyond the content of the published...

Peter C. Burns; Rodney C. Ewing; Alexandra Navrotsky

2012-03-09T23:59:59.000Z

349

Development of a Natural Gas-to-Hydrogen Fueling System  

E-Print Network (OSTI)

compressors Reliable & cost effective hydrogen fueling system #12;9 Accomplishments > Comprehensive subsystem> Development of a Natural Gas-to- Hydrogen Fueling System DOE Hydrogen & Fuel Cell Merit Review integrator, fuel processing subsystem ­ FuelMaker Corporation > Maker of high-quality high

350

Development of a Turnkey H2 Fueling  

E-Print Network (OSTI)

Feedstocks Storage NG Compression PSAPSARef.Ref. PTI, CATA, Penn State H2 Generator #12;5 © Air ProductsDevelopment of a Turnkey H2 Fueling Station David E. Guro Air Products and Chemicals, Inc. Allentown, PA U.S. D.O.E. - Hydrogen Program Annual Review May 2003 #12;2 © Air Products & Chemicals, Inc

351

Alternative Fuels Data Center: Electricity Research and Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Electricity Research Electricity Research and Development to someone by E-mail Share Alternative Fuels Data Center: Electricity Research and Development on Facebook Tweet about Alternative Fuels Data Center: Electricity Research and Development on Twitter Bookmark Alternative Fuels Data Center: Electricity Research and Development on Google Bookmark Alternative Fuels Data Center: Electricity Research and Development on Delicious Rank Alternative Fuels Data Center: Electricity Research and Development on Digg Find More places to share Alternative Fuels Data Center: Electricity Research and Development on AddThis.com... More in this section... Electricity Basics Production & Distribution Research & Development Related Links Benefits & Considerations Stations Vehicles Laws & Incentives

352

Alternative Fuels Data Center: Biomass Research and Development Initiative  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biomass Research and Biomass Research and Development Initiative to someone by E-mail Share Alternative Fuels Data Center: Biomass Research and Development Initiative on Facebook Tweet about Alternative Fuels Data Center: Biomass Research and Development Initiative on Twitter Bookmark Alternative Fuels Data Center: Biomass Research and Development Initiative on Google Bookmark Alternative Fuels Data Center: Biomass Research and Development Initiative on Delicious Rank Alternative Fuels Data Center: Biomass Research and Development Initiative on Digg Find More places to share Alternative Fuels Data Center: Biomass Research and Development Initiative on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biomass Research and Development Initiative

353

Alternative Fuels Data Center: Biomass and Biofuels Industry Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biomass and Biofuels Biomass and Biofuels Industry Development to someone by E-mail Share Alternative Fuels Data Center: Biomass and Biofuels Industry Development on Facebook Tweet about Alternative Fuels Data Center: Biomass and Biofuels Industry Development on Twitter Bookmark Alternative Fuels Data Center: Biomass and Biofuels Industry Development on Google Bookmark Alternative Fuels Data Center: Biomass and Biofuels Industry Development on Delicious Rank Alternative Fuels Data Center: Biomass and Biofuels Industry Development on Digg Find More places to share Alternative Fuels Data Center: Biomass and Biofuels Industry Development on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biomass and Biofuels Industry Development

354

Gamma Ray Mirrors for Direct Measurement of Spent Nuclear Fuel  

SciTech Connect

Direct measurement of the amount of Pu and U in spent nuclear fuel represents a challenge for the safeguards community. Ideally, the characteristic gamma-ray emission lines from different isotopes provide an observable suitable for this task. However, these lines are generally lost in the fierce flux of radiation emitted by the fuel. The rates are so high that detector dead times limit measurements to only very small solid angles of the fuel. Only through the use of carefully designed view ports and long dwell times are such measurements possible. Recent advances in multilayer grazing-incidence gamma-ray optics provide one possible means of overcoming this difficulty. With a proper optical and coating design, such optics can serve as a notch filter, passing only narrow regions of the overall spectrum to a fully shielded detector that does not view the spent fuel directly. We report on the design of a mirror system and a number of experimental measurements.

Pivovaroff, Dr. Michael J. [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Ziock, Klaus-Peter [ORNL] [ORNL; Harrison, Mark J [ORNL] [ORNL; Soufli, Regina [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL)

2014-01-01T23:59:59.000Z

355

High-pressure coal fuel processor development  

SciTech Connect

The objective of Subtask 1.1 Engine Feasibility was to conduct research needed to establish the technical feasibility of ignition and stable combustion of directly injected, 3,000 psi, low-Btu gas with glow plug ignition assist at diesel engine compression ratios. This objective was accomplished by designing, fabricating, testing and analyzing the combustion performance of synthesized low-Btu coal gas in a single-cylinder test engine combustion rig located at the Caterpillar Technical Center engine lab in Mossville, Illinois. The objective of Subtask 1.2 Fuel Processor Feasibility was to conduct research needed to establish the technical feasibility of air-blown, fixed-bed, high-pressure coal fuel processing at up to 3,000 psi operating pressure, incorporating in-bed sulfur and particulate capture. This objective was accomplished by designing, fabricating, testing and analyzing the performance of bench-scale processors located at Coal Technology Corporation (subcontractor) facilities in Bristol, Virginia. These two subtasks were carried out at widely separated locations and will be discussed in separate sections of this report. They were, however, independent in that the composition of the synthetic coal gas used to fuel the combustion rig was adjusted to reflect the range of exit gas compositions being produced on the fuel processor rig. Two major conclusions resulted from this task. First, direct injected, ignition assisted Diesel cycle engine combustion systems can be suitably modified to efficiently utilize these low-Btu gas fuels. Second, high pressure gasification of selected run-of-the-mine coals in batch-loaded fuel processors is feasible. These two findings, taken together, significantly reduce the perceived technical risks associated with the further development of the proposed coal gas fueled Diesel cycle power plant concept.

Greenhalgh, M.L.

1992-11-01T23:59:59.000Z

356

Safeguarding Nuclear Fuel Processing | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

Safeguarding Nuclear Safeguarding Nuclear Fuel Processing Laboratory Policy and Evaluation (LPE) LPE Home Staff M&O Contracts SC Laboratory Appraisal Process Laboratory Planning Process Work for Others in the Office of Science Laboratory Directed Research and Development (LDRD) DOE's Philosophy on LDRD Frequently Asked Questions Success Stories Brochures Additional Information LDRD Program Contacts Technology Transfer DOE National Laboratories Contact Information Laboratory Policy and Evaluation U.S. Department of Energy SC-32/Forrestal Building 1000 Independence Ave., SW Washington, DC 20585 P: (202) 586-5447 F: (202) 586-3119 Success Stories Safeguarding Nuclear Fuel Processing Print Text Size: A A A RSS Feeds FeedbackShare Page Idaho National Laboratory Develops International Nonproliferation

357

Microstructural Examination to Aid in Understanding Friction Bonding Fabrication Technique for Monolithic Nuclear Fuel  

SciTech Connect

Monolithic nuclear fuel is currently being developed for use in research reactors, and friction bonding (FB) is a technique being developed to help in this fuel’s fabrication. Since both FB and monolithic fuel are new concepts, research is needed to understand the impact of varying FB fabrication parameters on fuel plate characteristics. This thesis research provides insight into the FB process and its application to the monolithic fuel design by recognizing and understanding the microstructural effects of varying fabrication parameters (a) FB tool load, and (b) FB tool face alloy. These two fabrication parameters help drive material temperature during fabrication, and thus the material properties, bond strength, and possible formation of interface reaction layers. This study analyzed temperatures and tool loads measured during those FB processes and examined microstructural characteristics of materials and bonds in samples taken from the resulting fuel plates. This study shows that higher tool load increases aluminum plasticization and forging during FB, and that the tool face alloy helps determine the tool’s heat extraction efficacy. The study concludes that successful aluminum bonds can be attained in fuel plates using a wide range of FB tool loads. The range of tool loads yielding successful uranium-aluminum bonding was not established, but it was demonstrated that such bonding can be attained with FB tool load of 48,900 N (11,000 lbf) when using a FB tool faced with a tungsten alloy. This tool successfully performed FB, and with better results than tools faced with other materials. Results of this study correlate well with results reported for similar aluminum bonding techniques. This study’s results also provide support and validation for other nuclear fuel development studies and conclusions. Recommendations are offered for further research.

Karen L. Shropshire

2008-04-01T23:59:59.000Z

358

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel  

SciTech Connect

This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integrity of the dry-stored spent fuel from actual foreign experience. Countries covered in this survey are: Argentina, Canada, Federal Republic of Germany (before reunification with the former East Germany), former German Democratic Republic (former East Germany), France, India, Italy, Japan, South Korea, Spain, Switzerland, United Kingdom, and the former USSR (most of these former Republics are now in the Commonwealth of Independent States [CIS]). Industrial dry storage of Magnox fuels started in 1972 in the United Kingdom; Canada began industrial dry storage of CANDU fuels in 1980. The technology for safe storage is generally considered to be developed for time periods of 30 to 100 years for LWR fuel in inert gas and for some fuels in oxidizing gases at low temperatures. Because it will probably be decades before countries will have a repository for spent fuels and high-level wastes, the plans for expanded use of dry storage have increased significantly in recent years and are expected to continue to increase in the near future.

Schneider, K.J.; Mitchell, S.J.

1992-04-01T23:59:59.000Z

359

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel  

SciTech Connect

This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integrity of the dry-stored spent fuel from actual foreign experience. Countries covered in this survey are: Argentina, Canada, Federal Republic of Germany (before reunification with the former East Germany), former German Democratic Republic (former East Germany), France, India, Italy, Japan, South Korea, Spain, Switzerland, United Kingdom, and the former USSR (most of these former Republics are now in the Commonwealth of Independent States (CIS)). Industrial dry storage of Magnox fuels started in 1972 in the United Kingdom; Canada began industrial dry storage of CANDU fuels in 1980. The technology for safe storage is generally considered to be developed for time periods of 30 to 100 years for LWR fuel in inert gas and for some fuels in oxidizing gases at low temperatures. Because it will probably be decades before countries will have a repository for spent fuels and high-level wastes, the plans for expanded use of dry storage have increased significantly in recent years and are expected to continue to increase in the near future.

Schneider, K.J.; Mitchell, S.J.

1992-04-01T23:59:59.000Z

360

Alternative Fuels Data Center: Cellulosic Ethanol Research and Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Cellulosic Ethanol Cellulosic Ethanol Research and Development Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Cellulosic Ethanol Research and Development Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Cellulosic Ethanol Research and Development Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Cellulosic Ethanol Research and Development Tax Credit on Google Bookmark Alternative Fuels Data Center: Cellulosic Ethanol Research and Development Tax Credit on Delicious Rank Alternative Fuels Data Center: Cellulosic Ethanol Research and Development Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Cellulosic Ethanol Research and Development Tax Credit on AddThis.com... More in this section... Federal State

Note: This page contains sample records for the topic "development nuclear fuels" 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

Status of radioiodine control for nuclear fuel reprocessing plants  

SciTech Connect

This report summarizes the status of radioiodine control in a nuclear fuel reprocessing plant with respect to capture, fixation, and disposal. Where possible, we refer the reader to a number of survey documents which have been published in the last four years. We provide updates where necessary. Also discussed are factors which must be considered in developing criteria for iodine control. For capture from gas streams, silver mordenite and a silver nitrate impregnated silica (AC-6120) are considered state-of-the-art and are recommended. Three aqueous scrubbing processes have been demonstrated: Caustic scrubbing is simple but probably will not give an adequate iodine retention by itself. Mercurex (mercuric nitrate-nitric acid scrubbing) has a number of disadvantages including the use of toxic mercury. Iodox (hyperazeotropic nitric acid scrubbing) is effective but employs a very corrosive and hazardous material. Other technologies have been tested but require extensive development. The waste forms recommended for long-term storage or disposal are silver iodide, the iodates of barium, strontium, or calcium, and silver loaded sorbents, all fixed in cement. Copper iodide in bitumen (asphalt) is a possibility but requires testing. The selection of a specific form will be influenced by the capture process used.

Burger, L.L.; Scheele, R.D.

1983-07-01T23:59:59.000Z

362

Strategy for the Management and Disposal of Used Nuclear Fuel and  

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

Strategy for the Management and Disposal of Used Nuclear Fuel and Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste The Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste is a framework for moving toward a sustainable program to deploy an integrated system capable of transporting, storing, and disposing of used nuclear fuel and high-level radioactive waste from civilian nuclear power generation, defense, national security and other activities. Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste More Documents & Publications Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste

363

Strategy for the Management and Disposal of Used Nuclear Fuel and  

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

Strategy for the Management and Disposal of Used Nuclear Fuel and Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Issued on January 11, 2013, the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste is a framework for moving toward a sustainable program to deploy an integrated system capable of transporting, storing, and disposing of used nuclear fuel and high-level radioactive waste from civilian nuclear power generation, defense, national security and other activities. Strategy for the Management and Disposal of Used Nuclear Fuel and High Level Radioactive Waste.pdf More Documents & Publications Strategy for the Management and Disposal of Used Nuclear Fuel and

364

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

A. Alsaed

2005-07-28T23:59:59.000Z

365

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

J.K. Knudson

2003-10-02T23:59:59.000Z

366

Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced...  

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

Enhanced Nuclear Safeguards Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear Safeguards GNEP will help prevent misuse of civilian nuclear facilities for...

367

Nuclear-Renewable Hybrid System Economic Basis for Electricity, Fuel, and Hydrogen  

SciTech Connect

Concerns about climate change and altering the ocean chemistry are likely to limit the use of fossil fuels. That implies a transition to a low-carbon nuclear-renewable electricity grid. Historically variable electricity demand was met using fossil plants with low capital costs, high operating costs, and substantial greenhouse gas emissions. However, the most easily scalable very-low-emissions generating options, nuclear and non-dispatchable renewables (solar and wind), are capital-intensive technologies with low operating costs that should operate at full capacities to minimize costs. No combination of fully-utilized nuclear and renewables can meet the variable electricity demand. This implies large quantities of expensive excess generating capacity much of the time. In a free market this results in near-zero electricity prices at times of high nuclear renewables output and low electricity demand with electricity revenue collapse. Capital deployment efficiency—the economic benefit derived from energy systems capital investment at a societal level—strongly favors high utilization of these capital-intensive systems, especially if low-carbon nuclear renewables are to replace fossil fuels. Hybrid energy systems are one option for better utilization of these systems that consumes excess energy at times of low prices to make some useful product.The economic basis for development of hybrid energy systems is described for a low-carbon nuclear renewable world where much of the time there are massivequantities of excess energy available from the electric sector.Examples include (1) high-temperature electrolysis to generate hydrogen for non-fossil liquid fuels, direct use as a transport fuel, metal reduction, etc. and (2) biorefineries.Nuclear energy with its concentrated constant heat output may become the enabling technology for economically-viable low-carbon electricity grids because hybrid nuclear systems may provide an economic way to produce dispatachable variable electricity with economic base-load operation of the reactor.

Charles Forsberg; Steven Aumeier

2014-04-01T23:59:59.000Z

368

Cost Savings of Nuclear Power with Total Fuel Reprocessing  

SciTech Connect

The cost of fast reactor (FR) generated electricity with pyro-processing is estimated in this article. It compares favorably with other forms of energy and is shown to be less than that produced by light water reactors (LWR's). FR's use all the energy in natural uranium whereas LWR's utilize only 0.7% of it. Because of high radioactivity, pyro-processing is not open to weapon material diversion. This technology is ready now. Nuclear power has the same advantage as coal power in that it is not dependent upon a scarce foreign fuel and has the significant additional advantage of not contributing to global warming or air pollution. A jump start on new nuclear plants could rapidly allow electric furnaces to replace home heating oil furnaces and utilize high capacity batteries for hybrid automobiles: both would reduce US reliance on oil. If these were fast reactors fueled by reprocessed fuel, the spent fuel storage problem could also be solved. Costs are derived from assumptions on the LWR's and FR's five cost components: 1) Capital costs: LWR plants cost $106/MWe. FR's cost 25% more. Forty year amortization is used. 2) The annual O and M costs for both plants are 9% of the Capital Costs. 3) LWR fuel costs about 0.0035 $/kWh. Producing FR fuel from spent fuel by pyro-processing must be done in highly shielded hot cells which is costly. However, the five foot thick concrete walls have the advantage of prohibiting diversion. LWR spent fuel must be used as feedstock for the FR initial core load and first two reloads so this FR fuel costs more than LWR fuel. FR fuel costs much less for subsequent core reloads (< LWR fuel) if all spent fuel feedstock is from the fast reactor (i.e., Breeding Ratio =1). 4) Yucca Mountain storage of unprocessed LWR spent fuel is estimated as $360,000/MTHM. But this fuel can be processed to remove TRU for use as fast reactor fuel. The remaining fission products repository costs are only one fifth that of the original fuel. Storage of short half life fission products alone requires less storage time and long term integrity than LWR spent fuel (300 years storage versus 100,000 years.) 5) LWR decommissioning costs are estimated to be $0.3 x 10{sup 6}/MWe. The annual cost for a 40 year licensed plant would be 2.5 % of this or less if interest is taken into account. All plants will eventually have to replace those components which become radiation damaged. FR's should be designed to replace parts rather than decommission. The LWR costs are estimated to be 2.65 cents/kWh. FR costs are 2.99 cents/kWh for the first 7.5 years and 2.39 cents/kWh for the next 32.5 years. The average cost over forty years is 2.50 cents/kWh which is less than the LWR costs. These power costs are similar to coal power, are lower than gas, oil, and much lower than renewable power.(authors)

Solbrig, Charles W.; Benedict, Robert W. [Fuel Cycle Programs Division, Idaho National Laboratory, Idaho Falls, Idaho (United States)

2006-07-01T23:59:59.000Z

369

Light Water Reactors Technology Development - Nuclear Reactors  

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

Light Water Reactors Light Water Reactors About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

370

The DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification Program  

SciTech Connect

The Department of Energy has established the Advanced Gas Reactor Fuel Development and Qualification Program to address the following overall goals: Provide a baseline fuel qualification data set in support of the licensing and operation of the Next Generation Nuclear Plant (NGNP). Gas-reactor fuel performance demonstration and qualification comprise the longest duration research and development (R&D) task for the NGNP feasibility. The baseline fuel form is to be demonstrated and qualified for a peak fuel centerline temperature of 1250°C. Support near-term deployment of an NGNP by reducing market entry risks posed by technical uncertainties associated with fuel production and qualification. Utilize international collaboration mechanisms to extend the value of DOE resources. The Advanced Gas Reactor Fuel Development and Qualification Program consists of five elements: fuel manufacture, fuel and materials irradiations, postirradiation examination (PIE) and safety testing, fuel performance modeling, and fission product transport and source term evaluation. An underlying theme for the fuel development work is the need to develop a more complete fundamental understanding of the relationship between the fuel fabrication process, key fuel properties, the irradiation performance of the fuel, and the release and transport of fission products in the NGNP primary coolant system. Fuel performance modeling and analysis of the fission product behavior in the primary circuit are important aspects of this work. The performance models are considered essential for several reasons, including guidance for the plant designer in establishing the core design and operating limits, and demonstration to the licensing authority that the applicant has a thorough understanding of the in-service behavior of the fuel system. The fission product behavior task will also provide primary source term data needed for licensing. An overview of the program and recent progress will be presented.

David Petti; Hans Gougar; Gary Bell

2005-05-01T23:59:59.000Z

371

Sensor Development for PEM Fuel Cell Systems  

SciTech Connect

This document reports on the work done by Honeywell Sensing and Control to investigate the feasibility of modifying low cost Commercial Sensors for use inside a PEM Fuel Cell environment. Both stationary and automotive systems were considered. The target environment is hotter (100 C) than the typical commercial sensor maximum of 70 C. It is also far more humid (100% RH condensing) than the more typical 95% RH non-condensing at 40 C (4% RH maximum at 100 C). The work focused on four types of sensors, Temperature, Pressure, Air Flow and Relative Humidity. Initial design goals were established using a market research technique called Market Driven Product Definition (MDPD). A series of interviews were conducted with various users and system designers in their facilities. The interviewing team was trained in data taking and analysis per the MDPD process. The final result was a prioritized and weighted list of both requirements and desires for each sensor. Work proceeded on concept development for the 4 types of sensors. At the same time, users were developing the actual fuel cell systems and gaining knowledge and experience in the use of sensors and controls systems. This resulted in changes to requirements and desires that were not anticipated during the MDPD process. The concepts developed met all the predicted requirements. At the completion of concept development for the Pressure Sensor, it was determined that the Fuel Cell developers were happy with off-the-shelf automotive pressure sensors. Thus, there was no incentive to bring a new Fuel Cell Specific Pressure Sensor into production. Work was therefore suspended. After the experience with the Pressure Sensor, the requirements for a Temperature Sensor were reviewed and a similar situation applied. Commercially available temperature sensors were adequate and cost effective and so the program was not continued from the Concept into the Design Phase.

Steve Magee; Richard Gehman

2005-07-12T23:59:59.000Z

372

Measures of the Environmental Footprint of the Front End of the Nuclear Fuel Cycle  

SciTech Connect

Previous estimates of environmental impacts associated with the front end of the nuclear fuel cycle have focused primarily on energy consumption and CO2 emissions. Results have varied widely. Section 2 of this report provides a summary of historical estimates. This study revises existing empirical correlations and their underlying assumptions to fit to a more complete set of existing data. This study also addresses land transformation, water withdrawals, and occupational and public health impacts associated with the processes of the front end of the once-through nuclear fuel cycle. These processes include uranium mining, milling, refining, conversion, enrichment, and fuel fabrication. Metrics are developed to allow environmental impacts to be summed across the full set of front end processes, including transportation and disposition of the resulting depleted uranium.

Brett Carlsen; Emily Tavrides; Erich Schneider

2010-08-01T23:59:59.000Z

373

New York Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","5,271",13.4,"41,870",30.6 "Coal","2,781",7.1,"13,583",9.9 "Hydro and Pumped Storage","5,714",14.5,"24,942",18.2 "Natural Gas","17,407",44.2,"48,916",35.7 "Other1",45,0.1,832,0.6 "Other Renewable1","1,719",4.4,"4,815",3.5 "Petroleum","6,421",16.3,"2,005",1.5 "Total","39,357",100.0,"136,962",100.0

374

South Carolina Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","6,486",27.0,"51,988",49.9 "Coal","7,230",30.1,"37,671",36.2 "Hydro and Pumped Storage","4,006",16.7,"1,442",1.4 "Natural Gas","5,308",22.1,"10,927",10.5 "Other1","-","-",61,0.1 "Other Renewable1",284,1.2,"1,873",1.8 "Petroleum",670,2.8,191,0.2 "Total","23,982",100.0,"104,153",100.0

375

Nuclear reactor vessel fuel thermal insulating barrier  

DOE Patents (OSTI)

The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

Keegan, C. Patrick; Scobel, James H.; Wright, Richard F.

2013-03-19T23:59:59.000Z

376

North Carolina Nuclear Profile - All Fuels  

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

total electric power industry, summer capacity and net generation, by energy source, 2010" total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,958",17.9,"40,740",31.7 "Coal","12,766",46.1,"71,951",55.9 "Hydro and Pumped Storage","2,042",7.4,"4,757",3.7 "Natural Gas","6,742",24.4,"8,447",6.6 "Other1",50,0.2,407,0.3 "Other Renewable1",543,2.0,"2,083",1.6 "Petroleum",573,2.1,293,0.2 "Total","27,674",100.0,"128,678",100.0

377

EIS-0306: Treatment and Management of Sodium-Bonded Spent Nuclear Fuel |  

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

306: Treatment and Management of Sodium-Bonded Spent Nuclear 306: Treatment and Management of Sodium-Bonded Spent Nuclear Fuel EIS-0306: Treatment and Management of Sodium-Bonded Spent Nuclear Fuel Summary This EIS evaluates the potential environmental impacts of the proposed electrometallurgical treatment of DOE-owned sodium bonded spent nuclear fuel in the Fuel Conditioning Facility at Argonne National Laboratory-West (ANL-W). Public Comment Opportunities None available at this time. Documents Available for Download September 19, 2000 EIS-0306: Record of Decision Treatment and Management of Sodium-Bonded Spent Nuclear Fuel July 1, 2000 EIS-0306: Final Environmental Impact Statement Treatment and Management of Sodium-Bonded Spent Nuclear Fuel July 1, 1999 EIS-0306: Draft Environmental Impact Statement Treatment of Sodium-Bonded Spent Nuclear Fuel

378

U.S. Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification  

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

Commits $14 million to U.S. - Ukraine Nuclear Fuel Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification Project U.S. Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification Project March 15, 2007 - 10:55am Addthis KYIV, Ukraine - U.S. Department of Energy Deputy Secretary Clay Sell today announced that the United States will invest $14 million to provide 42 nuclear fuel assemblies to the South Ukraine Nuclear Power Plant under the U.S.-Ukraine Nuclear Fuel Qualification Project (UNFQP). In an agreement reached last week, Westinghouse Electric Company will manufacture nuclear fuel assemblies, which account for one-fourth of the fuel that powers a reactor for up to four years of operation. Deputy Secretary Sell is in Kyiv today to meet with top Ukrainian officials and U.S. business leaders to promote diversity of energy sources, greater energy efficiency,

379

MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY_  

SciTech Connect

Full-size/prototypic U10Mo monolithic fuel-foils and aluminum clad fuel plates are being developed at the Idaho National Laboratory’s (INL) Materials and Fuels Complex (MFC). These efforts are focused on realizing Low Enriched Uranium (LEU) high density monolithic fuel plates for use in High Performance Research and Test Reactors. The U10Mo fuel foils under development afford a fuel meat density of ~16 gU/cc and thus have the potential to facilitate LEU conversions without any significant reactor-performance penalty. An overview is provided of the ongoing monolithic UMo fuel development effort, including application of a zirconium barrier layer on fuel foils, fabrication scale-up efforts, and development of complex/graded fuel foils. Fuel plate clad bonding processes to be discussed include: Hot Isostatic Pressing (HIP) and Friction Bonding (FB).

G. A. Moore; F. J. Rice; N. E. Woolstenhulme; J-F. Jue; B. H. Park; S. E. Steffler; N. P. Hallinan; M. D. Chapple; M. C. Marshall; B. L. Mackowiak; C. R. Clark; B. H. Rabin

2009-11-01T23:59:59.000Z

380

Hydrogen Fuel Cell Development in Columbia (SC)  

SciTech Connect

This is an update to the final report filed after the extension of this program to May of 2011. The activities of the present program contributed to the goals and objectives of the Fuel Cell element of the Hydrogen, Fuel Cells and Infrastructure Technologies Program of the Department of Energy through five sub-projects. Three of these projects have focused on PEM cells, addressing the creation of carbon-based metal-free catalysts, the development of durable seals, and an effort to understand contaminant adsorption/reaction/transport/performance relationships at low contaminant levels in PEM cells. Two programs addressed barriers in SOFCs; an effort to create a new symmetrical and direct hydrocarbon fuel SOFC designs with greatly increased durability, efficiency, and ease of manufacturing, and an effort to create a multiphysics engineering durability model based on electrochemical impedance spectroscopy interpretations that associate the micro-details of how a fuel cell is made and their history of (individual) use with specific prognosis for long term performance, resulting in attendant reductions in design, manufacturing, and maintenance costs and increases in reliability and durability.

Reifsnider, Kenneth [University of South Carolina; Chen, Fanglin [University of South Carolina; Popov, Branko [University of South Carolina; Chao, Yuh [University of South Carolina; Xue, Xingjian [University of South Carolina

2012-09-15T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

EM Safely and Efficiently Manages Spent Nuclear Fuel | Department of Energy  

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

Services » Waste Management » Nuclear Materials & Waste » EM Services » Waste Management » Nuclear Materials & Waste » EM Safely and Efficiently Manages Spent Nuclear Fuel EM Safely and Efficiently Manages Spent Nuclear Fuel Dry storage casks at Idaho National Laboratory can safely house spent nuclear fuel for decades. Dry storage casks at Idaho National Laboratory can safely house spent nuclear fuel for decades. EM's mission is to safely and efficiently manage its spent nuclear fuel and prepare it for disposal in a geologic repository. Previously, the Office of Environmental Management's (EM) mission had included the safe and efficient management of its spent nuclear fuel (SNF) and preparation for its disposal in a geologic repository. However, in May 2009, the planned geologic repository at Yucca Mountain was cancelled. The

382

Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications  

SciTech Connect

The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle technologies that are cleaner, more efficient, less waste-intensive, and more proliferation resistant. The need for advanced fuel development is emphasized in on-going DOE-supported programs, e.g., Global Nuclear Energy Initiative (GNEI), Advanced Fuel Cycle Initiative (AFCI), and GEN-IV Technology Development. The Directorates of Energy & Environment (E&E) and Chemistry & Material Sciences (C&MS) at Lawrence Livermore National Laboratory (LLNL) are interested in advanced fuel research and manufacturing using its multi-disciplinary capability and facilities to support a design concept of a small, secure, transportable, and autonomous reactor (SSTAR). The E&E and C&MS Directorates co-sponsored this Laboratory Directed Research & Development (LDRD) Project on Mono-Uranium Nitride Fuel Development for SSTAR and Space Applications. In fact, three out of the six GEN-IV reactor concepts consider using the nitride-based fuel, as shown in Table 1. SSTAR is a liquid-metal cooled, fast reactor. It uses nitride fuel in a sealed reactor vessel that could be shipped to the user and returned to the supplier having never been opened in its long operating lifetime. This sealed reactor concept envisions no fuel refueling nor on-site storage of spent fuel, and as a result, can greatly enhance proliferation resistance. However, the requirement for a sealed, long-life core imposes great challenges to research and development of the nitride fuel and its cladding. Cladding is an important interface between the fuel and coolant and a barrier to prevent fission gas release during normal and accidental conditions. In fabricating the nitride fuel rods and assemblies, the cladding material should be selected based on its the coolant-side corrosion properties, the chemical/physical interaction with the nitride fuel, as well as their thermal and neutronic properties. The US NASA space reactor, the SP-100 was designed to use mono-uranium nitride fuel. Although the SP-100 reactor was not commissioned, tens of thousand of nitride fuel pellets were manufactured and lots of them, cladded in Nb-1-Zr had been irradiated in fast test reactors (FFTF and EBR-II) with good irradiation results. The Russian Naval submarines also use nitride fuel with stainless steel cladding (HT-9) in Pb-Bi coolant. Although the operating experience of the Russian submarine is not readily available, such combination of fuel, cladding and coolant has been proposed for a commercial-size liquid-metal cooled fast reactor (BREST-300). Uranium mono-nitride fuel is studied in this LDRD Project due to its favorable properties such as its high actinide density and high thermal conductivity. The thermal conductivity of mono-nitride is 10 times higher than that of oxide (23 W/m-K for UN vs. 2.3 W/m-K for UO{sub 2} at 1000 K) and its melting temperature is much higher than that of metal fuel (2630 C for UN vs. 1132 C for U metal). It also has relatively high actinide density, (13.51 gU/cm{sup 3} in UN vs. 9.66 gU/cm{sup 3} in UO{sub 2}) which is essential for a compact reactor core design. The objective of this LDRD Project is to: (1) Establish a manufacturing capability for uranium-based ceramic nuclear fuel, (2) Develop a computational capability to analyze nuclear fuel performance, (3) Develop a modified UN-based fuel that can support a compact long-life reactor core, and (4) Collaborate with the Nuclear Engineering Department of UC Berkeley on nitride fuel reprocessing and disposal in a geologic repository.

Choi, J; Ebbinghaus, B; Meiers, T; Ahn, J

2006-02-09T23:59:59.000Z

383

Security Science & Technology | Nuclear Science | ORNL  

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

Research Areas Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Border Security Comprehensive...

384

Development of alternate extractant systems for fast reactor fuel cycle  

SciTech Connect

Due to the limitations of TBP in processing of high burn-up, Pu-rich fast reactor fuels, there is a need to develop alternate extractants for fast reactor fuel processing. In this context, our Centre has been examining the suitability of alternate tri-alkyl phosphates. Third phase formation in the extraction of Th(IV) by TBP, tri-n-amyl phosphate (TAP) and tri-2-methyl-butyl phosphate (T2MBP) from nitric acid media has been investigated under various conditions to derive conclusions on their application for extraction of Pu at macro levels. The chemical and radiolytic degradation of tri-n-amyl-phosphate (TAP) diluted in normal paraffin hydrocarbon (NPH) in the presence of nitric acid has been investigated by the measurement of plutonium retention in organic phase. The potential application of room temperature ionic liquids (RTILs) for reprocessing of spent nuclear fuel has been explored. Extraction of uranium (VI) and palladium (II) from nitric acid medium by commercially available RTIL and tri-n-butyl phosphate solution in RTIL have been studied and the feasibility of electrodeposition of uranium as uranium oxide (UO{sub 2}) and palladium (II) as metallic palladium from the loaded organic phase have been demonstrated. This paper describes results of the above studies and discusses the suitability of the systems for fast reactor fuel reprocessing. (authors)

Vasudeva Rao, P.R.; Suresh, A.; Venkatesan, K.A.; Srinivasan, T.G.; Raj, Baldev [Indira Gandhi Centre for Atomic Research, Kalpakkam - 603 102 (India)

2007-07-01T23:59:59.000Z

385

Detachable connection for a nuclear reactor fuel assembly  

DOE Patents (OSTI)

A locking connection for releasably attaching a handling socket to the duct tube of a fuel assembly for a nuclear reactor. The connection comprises a load pad housing mechanically attached to the duct tube and a handling socket threadably secured within the housing. A retaining ring is interposed between the housing and the handling socket and is formed with a projection and depression engageable within a cavity and groove of the housing and handling socket, respectively, to form a detachable interlocked connection assembly.

Christiansen, David W. (Kennewick, WA); Karnesky, Richard A. (Richland, WA)

1986-01-01T23:59:59.000Z

386

Method for cleaning solution used in nuclear fuel reprocessing  

DOE Patents (OSTI)

Nuclear fuel processing solution consisting of tri-n-butyl phosphate and dodecane, with a complex of uranium, plutonium, or zirconium and with a solvent degradation product such as di-n-butyl phosphate therein, is contacted with an aqueous solution of a salt formed from hydrazine and either a dicarboxylic acid or a hydroxycarboxylic acid, thereby removing the aforesaid complex from the processing solution.

Tallent, O.K.; Crouse, D.J.; Mailen, J.C.

1980-12-17T23:59:59.000Z

387

Financing Strategies For A Nuclear Fuel Cycle Facility  

SciTech Connect

To help meet the nation’s energy needs, recycling of partially used nuclear fuel is required to close the nuclear fuel cycle, but implementing this step will require considerable investment. This report evaluates financing scenarios for integrating recycling facilities into the nuclear fuel cycle. A range of options from fully government owned to fully private owned were evaluated using DPL (Decision Programming Language 6.0), which can systematically optimize outcomes based on user-defined criteria (e.g., lowest lifecycle cost, lowest unit cost). This evaluation concludes that the lowest unit costs and lifetime costs are found for a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. However, this does not mean that the facilities should necessarily be constructed and operated by the government. The costs for hybrid combinations of public and private (commercial) financed options can compete under some circumstances with the costs of the government option. This analysis shows that commercial operations have potential to be economical, but there is presently no incentive for private industry involvement. The Nuclear Waste Policy Act (NWPA) currently establishes government ownership of partially used commercial nuclear fuel. In addition, the recently announced Global Nuclear Energy Partnership (GNEP) suggests fuels from several countries will be recycled in the United States as part of an international governmental agreement; this also assumes government ownership. Overwhelmingly, uncertainty in annual facility capacity led to the greatest variations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; and the annual operating costs, forgiveness of debt, and overnight costs dominate the costs computed for the government case. The uncertainty in operations, leading to lower than optimal processing rates (or annual plant throughput), is the most detrimental issue to achieving low unit costs. Conversely, lowering debt interest rates and the required return on investments can reduce costs for private industry.

David Shropshire; Sharon Chandler

2006-07-01T23:59:59.000Z

388

The Chemistry os Spent Nuclear Fuel From X-Ray Absorption Spectroscopy  

SciTech Connect

Present and future nuclear fuel cycles will require an understanding of the complex chemistry of trace fission products and transuranium actinides in spent nuclear fuel (SNF). Because of the unique analytical challenges presented by SNF to the materials scientist, many of its fundamental physical and chemical properties remain poorly understood, especially on the microscopic scale. Such an understanding of the chemical states of radionuclides in SNF would benefit development of technologies for fuel monitoring, fuel performance improvement and modeling, fuel reprocessing, and spent fuel storage and disposal. We have recently demonstrated the use of synchrotron x-ray absorption spectroscopy (XAS) to examine crystal chemical properties of actinides and fission products in extracted specimens of SNF. Information obtained includes oxidation state, chemical bond coordination, and quantitative elemental concentration and distribution. We have also used XAS in a scanning mode to obtain x-ray spectral micrographs with resolution approaching 1 micron. A brief overview of the technique will be presented, along with findings on uranium, plutonium, neptunium, technetium, and molybdenum in commercial PWR SNF specimens.

F.A. Fortner; A.J. Kropf; J.C. Cunnane

2006-09-21T23:59:59.000Z

389

Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay  

E-Print Network (OSTI)

by the Next Generation Safeguards Initiative to develop anIn 2009, the Next Generation Safeguards Initiative (NGSI) ofcurrently unattainable safeguards capabilities, i.e. ,

Quiter, Brian

2012-01-01T23:59:59.000Z

390

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Health and Safety Aspects of Pro- posed Nuclear, Geothermal, and Fossil-FuelHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel

Nero, A.V.

2010-01-01T23:59:59.000Z

391

Summary, Long-Term Nuclear Technology Research and Development...  

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

Summary, Long-Term Nuclear Technology Research and Development Plan Summary, Long-Term Nuclear Technology Research and Development Plan In 1998, DOE established the Nuclear Energy...

392

SOURCE OF BURNUP VALUES FOR COMMERCIAL SPENT NUCLEAR FUEL ASSEMBLIES  

SciTech Connect

Waste packages are loaded with commercial spent nuclear fuel (SNF) that satisfies the minimum burnup requirements of a criticality loading curve. The burnup value assigned by the originating nuclear utility to each SNF assembly (assigned burnup) is used to load waste packages in compliance with a criticality loading curve. The burnup provided by a nuclear utility has uncertainties, so conservative calculation methods are used to characterize those uncertainties for incorporation into the criticality loading curves. Procedural safety controls ensure that the correct assembly is loaded into each waste package to prevent a misload that could create a condition affecting the safety margins. Probabilistic analyses show that procedural safety controls can minimize the chance of a misload but can not completely eliminate the possibility. Physical measurements of burnup with instrumentation in the surface facility are not necessary due to the conservative calculation methods used to produce the criticality loading curves. The reactor records assigned burnup of a commercial SNF assembly contains about two percent uncertainty, which is increased to five-percent to ensure conservatism. This five-percent uncertainty is accommodated by adjusting the criticality loading curve. Also, the record keeping methods of nuclear utilities are not uniform and the level of detail required by the NRC has varied over the last several decades. Thus, some SNF assemblies may have assigned burnups that are averages for a batch of assemblies with similar characteristics. Utilities typically have access to more detailed core-follow records that allow the batch average burnup to be changed to an assembly specific burnup. Alternatively, an additional safety margin is incorporated into the criticality loading curve to accommodate SNF assemblies with batch average burnups or greater uncertainties due to the methodology used by the nuclear utility. The utility records provide the assembly identifier, initial {sup 235}U enrichment, and time of discharge from the reactor as well as the assigned burnup, but the distribution. of burnup axially along the assembly length is not provided. The axial burnup profile is maintained within acceptable bounds by the operating conditions of the nuclear reactor and is calculated during preparations to reload a reactor, but the actual burnup profile is not measured. The axial burnup profile is important to the determination of the reactivity of a waste package, so a conservative evaluation of the calculated axial profiles for a large database of SNF has been performed. The product of the axial profile evaluation is a profile that is conservative. Thus, there is no need for physical measurement of the axial profile. The assembly identifier is legible on each SNF assembly and the utility records provide the associated characteristics of the assembly. The conservative methodologies used to determine the criticality loading curve for a waste package provide sufficient margin so that criticality safety is assured for preclosure operations even in the event of a misload. Consideration of misload effects for postclosure time periods is provided by the criticality Features, Events, and Processes (FEPs) analysis. The conservative approaches used to develop and apply the criticality loading curve are thus sufficiently robust that the utility assigned burnup is an adequate source of burnup values, and additional means of verification of assigned burnup through physical measurements are not needed.

BSC

2004-12-01T23:59:59.000Z

393

Nuclear Safety Research and Development Committee Charter  

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

This Nuclear Safety Research & Development (NSR&D) Committee Charter provides the membership, roles, and responsibilities of the NSR&D Committee.

394

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

395

Fuel Cell Development and Test Laboratory (Fact Sheet)  

SciTech Connect

This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Fuel Cell Development and Test Laboratory at the Energy Systems Integration Facility. NREL's state-of-the-art Fuel Cell Development and Test Laboratory in the Energy Systems Integration Facility (ESIF) supports NREL's fuel cell research and development projects through in-situ fuel cell testing. Current projects include various catalyst development projects, a system contaminant project, and the manufacturing project. Testing capabilities include but are not limited to single cell fuel cells and fuel cell stacks.

Not Available

2011-10-01T23:59:59.000Z

396

Update on US High Density Fuel Fabrication Development  

SciTech Connect

Second generation uranium molybdenum fuel has shown excellent in-reactor irradiation performance. This metallic fuel type is capable of being fabricated at much higher loadings than any presently used research reactor fuel. Due to the broad range of fuel types this alloy system encompasses—fuel powder to monolithic foil and binary fuel systems to multiple element additions—significant amounts of research and development have been conducted on the fabrication of these fuels. This paper presents an update of the US RERTR effort to develop fabrication techniques and the fabrication methods used for the RERTR-9A miniplate test.

C.R. Clark; G.A. Moore; J.F. Jue; B.H. Park; N.P. Hallinan; D.M. Wachs; D.E. Burkes

2007-03-01T23:59:59.000Z

397

Review Lecture: The Development and Practical Application of Fuel Cells  

Science Journals Connector (OSTI)

...Development and Practical Application of Fuel Cells F. T. Bacon T. M. Fry First, a definition is given of what a fuel cell is, and a description is given of...account of the early history of the hydrogen fuel cell. Next, the alkaline fuel cell is...

1973-01-01T23:59:59.000Z

398

Intelligent Energy, Boeing to develop fuel cell plane  

Science Journals Connector (OSTI)

UK-based PEM fuel cell producer Intelligent Energy has been selected by US aerospace giant Boeing as a partner to develop the world’s first fuel-cell-powered aeroplane for manned flight. Fuel cells will be used to replace auxiliary power units (APUs), improving fuel efficiency. Visit www.re-focus.net for the latest renewable energy industry news

2003-01-01T23:59:59.000Z

399

MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY  

SciTech Connect

Within the Reduced Enrichment for Research and Test Reactors (RERTR) program directed by the US Department of Energy (DOE), UMo fuel-foils are being developed in an effort to realize high density monolithic fuel plates for use in high-flux research and test reactors. Namely, targeted are reactors that are not amenable to Low Enriched Uranium (LEU) fuel conversion via utilization of high density dispersion-based fuels, i.e. 8-9 gU/cc. LEU conversion of reactors having a need for >8-9 gU/cc fuel density will only be possible by way of monolithic fuel forms. The UMo fuel foils under development afford fuel meat density of ~16 gU/cc and thus have the potential to facilitate LEU conversions without any significant reactor-performance penalty. Two primary challenges have been established with respect to UMo monolithic fuel development; namely, fuel element fabrication and in-reactor fuel element performance. Both issues are being addressed concurrently at the Idaho National Laboratory. An overview is provided of the ongoing monolithic UMo fuel development effort at the Idaho National Laboratory (INL); including development of complex/graded fuel foils. Fabrication processes to be discussed include: UMo alloying and casting, foil fabrication via hot rolling, fuel-clad interlayer application via co-rolling and thermal spray processes, clad bonding via Hot Isostatic Pressing (HIP) and Friction Bonding (FB), and fuel plate finishing.

Glenn A. Moore; Francine J. Rice; Nicolas E. Woolstenhulme; W. David SwanK; DeLon C. Haggard; Jan-Fong Jue; Blair H. Park; Steven E. Steffler; N. Pat Hallinan; Michael D. Chapple; Douglas E. Burkes

2008-10-01T23:59:59.000Z

400

Synergistic energy conversion processes using nuclear energy and fossil fuels  

Science Journals Connector (OSTI)

This paper reviews the methods of producing energy carriers, such as electricity, hydrocarbons and hydrogen, by utilising both nuclear energy and fossil fuels synergistically. There are many possibilities for new, innovative, synergistic processes, which combine chemical and nuclear systems for efficient, clean and economical production of energy carriers. Besides the individual processes by each form of energy to produce the energy carriers, the synergistic processes which use two primary energies to produce the energy carriers will become important with the features of resource saving, CO2 emission reduction and economic production, due to the higher conversion efficiency and low cost of nuclear heat. The synergistic processes will be indispensable to the 21st century, when efficient best-mixed supplies of available primary energies are crucial.

Masao Hori

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Foreign Research Reactor Spent Nuclear Fuel Acceptance Program  

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

Global Threat Reduction Initiative: Global Threat Reduction Initiative: U.S. Nuclear Remove Program Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance 2007 DOE TEC Meeting Chuck Messick DOE/NNSA/SRS 2 Contents * Program Objective and Policy * Program implementation status * Shipment Information * Operational Logistics * Lessons Learned * Conclusion 3 U.S. Nuclear Remove Program Objective * To play a key role in the Global Threat Reduction Remove Program supporting permanent threat reduction by accepting program eligible material. * Works in conjunction with the Global Threat Reduction Convert Program to accept program eligible material as an incentive to core conversion providing a disposition path for HEU and LEU during the life of the Acceptance Program. 4 Reasons for the Policy

402

SUPPLEMENT ANALYSIS OF FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL  

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

FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL TRANSPORTATION ALONG OTHER THAN~. PRESENTATIVE ROUTE FROM CONCORD NAVAL WEAPO~~ STATION TO IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LADORA TORY Introduction The Department of Energy is planning to transport foreign research reactor spent nuclear fuel by rail from the Concord Naval Weapons Station (CNWS), Concord, California, to the Idaho National Engineering and Environmental Laboratory (INEEL). The environmental analysis supporting the decision to transport, by rail or truck, foreign research reactor spent nuclear fuel from CNWS to the INEEL is contained in +he Final Environmental Impact Statement on a Proposed Nuclear Weapons Nonproliftration Policy Concerning Foreign Research Reactor

403

U.S. Spent Nuclear Fuel Data as of December 31, 2002  

Gasoline and Diesel Fuel Update (EIA)

Home > Nuclear > Spent Nuclear Fuel Home > Nuclear > Spent Nuclear Fuel Release Date: October 1, 2004 Next Release: Late 2010** Spent nuclear fuel data is collected by the Energy Information Administration (EIA) for the Office of Civilian Radioactive Waste Management (OCRWM). The spent nuclear fuel (SNF) data includes detailed characteristics of SNF generated by commercial U.S. nuclear power plants. From 1983 through 1995 this data was collected annually. Since 1996 this data has been collected every three years. The latest available detailed data covers all SNF discharged from commercial reactors before December 31, 2002, and is maintained in a data base by the EIA. Summary data tables from this data base may be found as indicated below. Table 1. Total U.S. Commercial Spent Nuclear Fuel Discharges, 1968 - 2002

404

A Novel Fuel/Reactor Cycle to Implement the 300 Years Nuclear Waste Policy Approach - 12377  

SciTech Connect

A thorium-based fuel cycle system can effectively burn the currently accumulated commercial used nuclear fuel and move to a sustainable equilibrium where the actinide levels in the high level waste are low enough to yield a radiotoxicity after 300 years lower than that of the equivalent uranium ore. The second step of the Westinghouse approach to solving the waste 'problem' has been completed. The thorium fuel cycle has indeed the potential of burning the legacy TRU and achieve the waste objective proposed. Initial evaluations have been started for the third step, development and selection of appropriate reactors. Indications are that the probability of show-stoppers is rather remote. It is, therefore, believed that development of the thorium cycle and associated technologies will provide a permanent solution to the waste management. Westinghouse is open to the widest collaboration to make this a reality. (authors)

Carelli, M.D.; Franceschini, F.; Lahoda, E.J. [Westinghouse Electric Company LLC., Cranberry Township, PA (United States); Petrovic, B. [Georgia Institute of Technology, Atlanta, GA (United States)

2012-07-01T23:59:59.000Z

405

The Overlooked Back End of the Nuclear Fuel Cycle  

Science Journals Connector (OSTI)

...working toward developing a geologic repository at Yucca Mountain, Nevada, but the Obama Administration pulled the license...10 Macfarlane A. , in Uncertainty Underground: Yucca Mountain and the Nation's High-Level Nuclear Waste , Macfarlane...

Allison M. Macfarlane

2011-09-02T23:59:59.000Z

406

Institutional Research & Development | National Nuclear Security  

National Nuclear Security Administration (NNSA)

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407

Fuel Cell Technologies Program Multi-Year Research, Development...  

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

deployment of hydrogen and fuel cell technologies. o Facilitate development of safe, high-performance materials for hydrogen service. o Develop appropriate test methodologies for...

408

EARTHQUAKE CAUSED RELEASES FROM A NUCLEAR FUEL CYCLE FACILITY  

SciTech Connect

The fuel cycle facility (FCF) at the Idaho National Laboratory is a nuclear facility which must be licensed in order to operate. A safety analysis is required for a license. This paper describes the analysis of the Design Basis Accident for this facility. This analysis involves a model of the transient behavior of the FCF inert atmosphere hot cell following an earthquake initiated breach of pipes passing through the cell boundary. The hot cell is used to process spent metallic nuclear fuel. Such breaches allow the introduction of air and subsequent burning of pyrophoric metals. The model predicts the pressure, temperature, volumetric releases, cell heat transfer, metal fuel combustion, heat generation rates, radiological releases and other quantities. The results show that releases from the cell are minimal and satisfactory for safety. This analysis method should be useful in other facilities that have potential for damage from an earthquake and could eliminate the need to back fit facilities with earthquake proof boundaries or lessen the cost of new facilities.

Charles W. Solbrig; Chad Pope; Jason Andrus

2014-08-01T23:59:59.000Z

409

General-purpose heat source project and space nuclear safety fuels program. Progress report, February 1980  

SciTech Connect

This formal monthly report covers the studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are: General-Purpose Heat Source Development and Space Nuclear Safety and Fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

Maraman, W.J. (comp.)

1980-05-01T23:59:59.000Z

410

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

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

Fuels Storage Fuels Storage and Transportation Planning Project (NFST) Program Status Jeff Williams Project Director National Transportation Stakeholders Forum Buffalo, New York May 2013 2  "With the appropriate authorizations from Congress, the Administration currently plans to implement a program over the next 10 years that:  Sites, designs and licenses, constructs and begins operations of a pilot interim storage facility by 2021 with an initial focus on accepting used nuclear fuel from shut-down reactor sites;  Advances toward the siting and licensing of a larger interim storage facility to be available by 2025 that will have sufficient capacity to provide flexibility in the waste management system and allows for acceptance of enough used

411

Materials Development & Fuel Processing Research for  

E-Print Network (OSTI)

tolerance/ catalyst deactivation Understanding reaction pathways Natural Gas Biofuel Diesel Jet Fuel

Azad, Abdul-Majeed

412

Development of Sensors for Automotive PEM-based Fuel Cells  

E-Print Network (OSTI)

organization #12;4 Sensors for Automotive PEM Fuel Cells - Motivation Sensor Performance and Cost ImprovementsDevelopment of Sensors for Automotive PEM-based Fuel Cells DOE Agreement DE-FC04-02AL67616 Brian FC Series 200 - 50 kW PEM #12;2 Development of Sensors for Automotive PEM-based Fuel Cells ­ Program

413

Spent nuclear fuel characterization for a bounding reference assembly for the receiving basin for off-site fuel  

SciTech Connect

A basis for interim operation 1 (BIO) for the receiving basin for off-site fuel (RBOF) facility at the U.S. Department of Energy`s (DOE) Savannah River site nuclear materials production complex has been developed in accordance to draft DOE-STD-0019-93 (Ref. 2). The latter document requires a hazard categorization per DOE-STD-1027-92 (Ref. 3) for the safety analysis portion of the BIO. This classification places the facility in one of three categories as defined in DOE 5480.23 (Ref. 4) per the total radioactivity, which can be released during an accident. The diversity of spent nuclear fuels stored in the RBOF made an exacting assessment of the total radioactive inventory virtually impossible. This restriction led to a conservative calculation based on the concept of a hypothetical bounding reference fuel assembly (RFA) integrated over the total capacity of the facility. The RFA is derived from a systematic ranking of the real assemblies (current and expected) according to a maximum burnup criterion. The indicated scheme is not only simple but precluded a potential delay in the completion of the BIO.

Kahook, S.D.; Garrett, R.L.; Canas, L.R. [Westinghouse Savannah River Company, Aiken, SC (United States)] [and others

1995-12-31T23:59:59.000Z

414

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

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

This environmental assessment (EA) will evaluate the potential environmental impacts of a DOE proposal to accept used nuclear fuel from the Federal Republic of Germany at DOE’s Savannah River Site (SRS) for processing and disposition. This used nuclear fuel is composed of kernels containing thorium and U.S.-origin highly enriched uranium (HEU) embedded in small graphite spheres that were irradiated in nuclear reactors used for research and development purposes.

415

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

4.0 Systems Analysis Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Section 4.0 Systems Analysis Systems Analysis section of the Fuel Cell...

416

Fuel Cell Technologies Office Multi-Year Research, Development...  

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

2.0 Program Benefits Fuel Cell Technologies Office Multi-Year Research, Development, and Demonstration Plan - Section 2.0 Program Benefits Program Benefits section of the Fuel Cell...

417

Sensitivity of economic performance of the nuclear fuel cycle to simulation modeling assumptions  

E-Print Network (OSTI)

Comparing different nuclear fuel cycles and assessing their implications require a fuel cycle simulation model as complete and realistic as possible. In this thesis, methodological implications of modeling choices are ...

Bonnet, Nicéphore

2007-01-01T23:59:59.000Z

418

An experiment to simulate the heat transfer properties of a dry, horizontal spent nuclear fuel assembly  

E-Print Network (OSTI)

Nuclear power reactors generate highly radioactive spent fuel assemblies. Initially, the spent fuel assemblies are stored for a period of several years in an on-site storage facility to allow the radioactivity levels of ...

Lovett, Phyllis Maria

1991-01-01T23:59:59.000Z

419

Alternative Fuels Data Center: Vehicle Research and Development Grants  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Vehicle Research and Vehicle Research and Development Grants to someone by E-mail Share Alternative Fuels Data Center: Vehicle Research and Development Grants on Facebook Tweet about Alternative Fuels Data Center: Vehicle Research and Development Grants on Twitter Bookmark Alternative Fuels Data Center: Vehicle Research and Development Grants on Google Bookmark Alternative Fuels Data Center: Vehicle Research and Development Grants on Delicious Rank Alternative Fuels Data Center: Vehicle Research and Development Grants on Digg Find More places to share Alternative Fuels Data Center: Vehicle Research and Development Grants on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Vehicle Research and Development Grants The Indiana Economic Development Corporation (IDEC) administers the Indiana

420

Dry Storage of Research Reactor Spent Nuclear Fuel - 13321  

SciTech Connect

Spent fuel from domestic and foreign research reactors is received and stored at the Savannah River Site's L Area Material Storage (L Basin) Facility. This DOE-owned fuel consists primarily of highly enriched uranium in metal, oxide or silicide form with aluminum cladding. Upon receipt, the fuel is unloaded and transferred to basin storage awaiting final disposition. Disposition alternatives include processing via the site's H Canyon facility for uranium recovery, or packaging and shipment of the spent fuel to a waste repository. A program has been developed to provide a phased approach for dry storage of the L Basin fuel. The initial phase of the dry storage program will demonstrate loading, drying, and storage of fuel in twelve instrumented canisters to assess fuel performance. After closure, the loaded canisters are transferred to pad-mounted concrete overpacks, similar to those used for dry storage of commercial fuel. Unlike commercial spent fuel, however, the DOE fuel has high enrichment, very low to high burnup, and low decay heat. The aluminum cladding presents unique challenges due to the presence of an oxide layer that forms on the cladding surface, and corrosion degradation resulting from prolonged wet storage. The removal of free and bound water is essential to the prevention of fuel corrosion and radiolytic generation of hydrogen. The demonstration will validate models predicting pressure, temperature, gas generation, and corrosion performance, provide an engineering scale demonstration of fuel handling, drying, leak testing, and canister backfill operations, and establish 'road-ready' storage of fuel that is suitable for offsite repository shipment or retrievable for onsite processing. Implementation of the Phase I demonstration can be completed within three years. Phases II and III, leading to the de-inventory of L Basin, would require an additional 750 canisters and 6-12 years to complete. Transfer of the fuel from basin storage to dry storage requires integration with current facility operations, and selection of equipment that will allow safe operation within the constraints of existing facility conditions. Examples of such constraints that are evaluated and addressed by the dry storage program include limited basin depth, varying fuel lengths up to 4 m, (13 ft), fissile loading limits, canister closure design, post-load drying and closure of the canisters, instrument selection and installation, and movement of the canisters to storage casks. The initial pilot phase restricts the fuels to shorter length fuels that can be loaded to the canister directly underwater; subsequent phases will require use of a shielded transfer system. Removal of the canister from the basin, followed by drying, inerting, closure of the canister, and transfer of the canister to the storage cask are completed with remotely operated equipment and appropriate shielding to reduce personnel radiation exposure. (authors)

Adams, T.M.; Dunsmuir, M.D.; Leduc, D.R.; Severynse, T.F.; Sindelar, R.L. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States); Moore, E.N. [Moore Nuclear Energy, LLC (United States)] [Moore Nuclear Energy, LLC (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "development nuclear fuels" 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

Prospects for nuclear power development in the Russian Federation and Central Asian countries  

Science Journals Connector (OSTI)

Currently, the Russian economy is based mainly on the export of fossil fuel resources and other raw materials. The contribution of nuclear power to the country's overall electricity production is about 16%, which is relatively low given its available potential, namely, advanced technologies, developed infrastructure, skilled personnel and scientists. It is now clear from the sharp increase in the price of fossil fuels that fossil-fuel-based power would be unable to support the sustainable development of Russian society in the long term. At the same time, nuclear power is capable of both meeting the country's energy needs and providing energy security.

Alexander N. Chebeskov; Vladimir S. Kagramanyan

2008-01-01T23:59:59.000Z

422

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

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

of Section 180(c) of the Nuclear of Section 180(c) of the Nuclear Waste Policy Act, as amended National Transportation Stakeholder's Forum Buffalo, NY May 15, 2013 Section 180(c) Mandate "The Secretary shall provide technical assistance and funds to States for training for public safety officials of appropriate units of local government and Indian tribes through whose jurisdiction the Secretary plans to transport spent nuclear fuel or high-level radioactive waste [to an NWPA-authorized facility]. * The training shall cover procedures for safe routine transportation of these materials and procedures for dealing with emergency response situations. * Covers all modes of transport 2 Section 180(c) - Background  DOE nearly implemented Section 180(c) in the mid-

423

Process for recovery of palladium from nuclear fuel reprocessing wastes  

DOE Patents (OSTI)

Palladium is selectively removed from spent nuclear fuel reprocessing waste by adding sugar to a strong nitric acid solution of the waste to partially denitrate the solution and cause formation of an insoluble palladium compound. The process includes the steps of: (a) adjusting the nitric acid content of the starting solution to about 10 M; (b) adding 50% sucrose solution in an amount sufficient to effect the precipitation of the palladium compound; (c) heating the solution at reflux temperature until precipitation is complete; and (d) centrifuging the solution to separate the precipitated palladium compound from the supernatant liquid.

Campbell, D.O.; Buxton, S.R.

1980-06-16T23:59:59.000Z

424

Welding fixture for nuclear fuel pin cladding assemblies  

DOE Patents (OSTI)

A welding fixture for locating a driver sleeve about the open end of a nuclear fuel pin cladding. The welding fixture includes a holder provided with an open cavity having shoulders for properly positioning the driver sleeve, the end cap, and a soft, high temperature resistant plastic protective sleeve that surrounds a portion of the end cap stem. Ejected contaminant particles spewed forth by closure of the cladding by pulsed magnetic welding techniques are captured within a contamination trap formed in the holder for ultimate removal and disposal of contaminating particles along with the holder.

Oakley, David J. (Richland, WA); Feld, Sam H. (West Richland, WA)

1986-01-01T23:59:59.000Z

425

Corrosion of Spent Nuclear Fuel: The Long-Term Assessment  

SciTech Connect

Spent nuclear fuel, essentially U{sub 2}, accounts for over 95% of the total radioactivity of all of the radioactive wastes in the United States that require disposal, disposition or remediation. The UO{sub 2} in SNF is not stable under oxiding conditions and may also be altered under reducing conditions. The alteration of SNF results in the formation of new uranium phases that can cause the release or retardation of actinide and fission product radionuclides. Over the long term, and depending on the extent to which the secondary uranium phases incorporate fission products and actinides, these alteration phases become the near-field source term.

Rodney C. Ewing

2004-10-07T23:59:59.000Z

426

Test protocol for aluminum based spent nuclear fuel  

SciTech Connect

Aluminum based spent nuclear fuel (Al-SNF) will be treated and then stored in a geological repository. A series of corrosion tests, including coupon, galvanic, and electrochemical, were performed to measure the effects of degradation on U-Al alloys, which simulated various Al-SNF forms. The test solutions were variants of a J-13 well water chemistry. As part of the degradation characteristics, the dissolution of uranium, which is the primary radionuclide, was measured. The degradation and dissolution were changed by the type of water chemistry and the temperature. The alloy composition and fabrication were not significant variables.

Mickalonis, J.I.; Wiersma, B.J.

1999-07-01T23:59:59.000Z

427

Strengthening the nuclear-reactor fuel cycle against proliferation  

SciTech Connect

Argonne National Laboratory (ANL) conducts several research programs that serve to reduce the risks of fissile-material diversion from the nuclear-reactor fuel cycle. The objectives are to provide economical and efficient neutron or power generation with the minimum of inherent risks, and to further minimize risks by utilizing sophisticated techniques to detect attempts at material diversion. This paper will discuss the Reduced Enrichment Research and Test Reactor (RERTR) Program, the Isotope Correlation Technique (ICT), and Proliferation-Resistant Closed-Cycle Reactors. The first two are sponsored by the DOE Office of Arms Control and Nonproliferation.

Travelli, A.; Snelgrove, J.; Persiani, P. [Argonne National Lab., IL (United States). Arms Control and Nonproliferation Program

1992-12-31T23:59:59.000Z

428

Closure mechanism and method for spent nuclear fuel canisters  

DOE Patents (OSTI)

A canister is provided for storing, transporting, and/or disposing of spent nuclear fuel. The canister includes a canister shell, a top shield plug disposed within the canister, and a leak-tight closure arrangement. The closure arrangement includes a shear ring which forms a containment boundary of the canister, and which is welded to the canister shell and top shield plug. An outer seal plate, forming an outer seal, is disposed above the shear ring and is welded to the shield plug and the canister.

Doman, Marvin J. (Monroeville, PA)

2004-11-23T23:59:59.000Z

429

Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel  

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

Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel Vitaly T. Gotovchikov a , Victor A. Seredenko a , Valentin V. Shatalov a , Vladimir N. Kaplenkov a , Alexander S. Shulgin a , Vladimir K. Saranchin a , Michail A. Borik a∗ , Charles W. Forsberg b , All-Russian Research Institute of Chemical Technology (ARRICT) 33, Kashirskoe ave., Moscow, Russia, 115409, E-mail: chem.conv@ru.net Oak Ridge National Laboratory (ORNL) Bethel Wall Road, P.O. Box 2008, MS-6165, Oak Ridge, TN, USA, 37831 Abstract - Induction cold crucible melters (ICCM) have the potential to be a very-low-cost high-throughput method for the production of DUO 2 for SNF casks. The proposed work would develop these melters for this specific application. If a

430

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels  

SciTech Connect

Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These include refractory alloys base on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as those based on silicon carbide (SiCf-SiC); carbon-carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor componets is necessary for improved efficiency. Improving thermal conductivity of the materials used in nuclear fuels and other temperature critical components can lower the center-line fuel temperature and thereby enhance durability and reduce the risk of premature failure.

Hui Zhang; Raman P. Singh

2008-11-30T23:59:59.000Z

431

Alternative Fuels Data Center: Support for Advance Biofuel Development  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Support for Advance Support for Advance Biofuel Development to someone by E-mail Share Alternative Fuels Data Center: Support for Advance Biofuel Development on Facebook Tweet about Alternative Fuels Data Center: Support for Advance Biofuel Development on Twitter Bookmark Alternative Fuels Data Center: Support for Advance Biofuel Development on Google Bookmark Alternative Fuels Data Center: Support for Advance Biofuel Development on Delicious Rank Alternative Fuels Data Center: Support for Advance Biofuel