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Note: This page contains sample records for the topic "fuel cycle options" from the National Library of EnergyBeta (NLEBeta).
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1

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

2

Pilot Application to Nuclear Fuel Cycle Options | Department of Energy  

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

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

3

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.

4

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

5

Nuclear Fuel Cycle Options Evaluation to Inform R&D Planning  

SciTech Connect (OSTI)

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

6

New Fuel Cycle and Fuel Management Options in Heavy Liquid Metal-Cooled Reactors  

Science Journals Connector (OSTI)

Technical Paper / Advances in Nuclear Fuel Management - Fuel Management of Reactors Other Than Light Water Reactors

Ehud Greenspan; Pavel Hejzlar; Hiroshi Sekimoto; Georgy Toshinsky; David Wade

7

Fuels options conference  

SciTech Connect (OSTI)

The proceedings of the Fuels Options Conference held May 9-10, 1995 in Atlanta, Georgia are presented. Twenty-three papers were presented at the conference that dealt with fuels outlook; unconventional fuels; fuel specification, purchasing, and contracting; and waste fuels applications. A separate abstract was prepared for each paper for inclusion in the Energy Science and Technology Database.

NONE

1995-09-01T23:59:59.000Z

8

Fuel option for gas turbine  

SciTech Connect (OSTI)

Growth in electricity demand is an average of 10% per year. Energy, emission, and economy are importance of critical concerns for generating systems. Therefore, combined cycle power plant is preferred to Electricity Generating Authority of Thailand (EGAT) new power generating capacity. The various option of available fuel for gas turbine are natural gas, liquid fuel and coal fuel. Particularly with the tremendous price increases in imported and domestic fuel supplies, natural gas is an attractive low cost alternative for power generation. EGAT has researched using heavy fuel instead of natural gas since the year 1991. The problems of various corrosion characteristics have been found. In addition, fuel treatment for gas turbine are needed, and along with it, the environmental consideration are options that provide the limitation of environmental regulation.

Tantayakom, S. [Electricity Generating Authority of Thailand, Nonthaburi (Thailand). Chemical and Analysis Dept.

1995-12-31T23:59:59.000Z

9

Fuel Cell Financing Options  

Broader source: Energy.gov [DOE]

Presented at the Clean Energy States Alliance and U.S. Department of Energy Webinar: Financing Fuel Cell Installations, August 30, 2011.

10

Uncertainty Analyses of Advanced Fuel Cycles  

SciTech Connect (OSTI)

The Department of Energy is developing technology, experimental protocols, computational methods, systems analysis software, and many other capabilities in order to advance the nuclear power infrastructure through the Advanced Fuel Cycle Initiative (AFDI). Our project, is intended to facilitate will-informed decision making for the selection of fuel cycle options and facilities for development.

Laurence F. Miller; J. Preston; G. Sweder; T. Anderson; S. Janson; M. Humberstone; J. MConn; J. Clark

2008-12-12T23:59:59.000Z

11

Comparative analyses of spent nuclear fuel transport modal options: Transport options under existing site constraints  

SciTech Connect (OSTI)

The movement of nuclear waste can be accomplished by various transport modal options involving different types of vehicles, transport casks, transport routes, and intermediate intermodal transfer facilities. A series of systems studies are required to evaluate modal/intermodal spent fuel transportation options in a consistent fashion. This report provides total life-cycle cost and life-cycle dose estimates for a series of transport modal options under existing site constraints. 14 refs., 7 figs., 28 tabs.

Brentlinger, L.A.; Hofmann, P.L.; Peterson, R.W.

1989-08-01T23:59:59.000Z

12

Fuel Cycle CrossCut Group  

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

CrossCut Group CrossCut Group 1 NERAC Briefing: Assessment of Dose of Closed vs Open Gen-IV Fuel Cycles David Wade NERAC Meeting September 30, 2002 Fuel Cycle CrossCut Group 2 Public Dose and Worker Dose Comparison of Open vs Closed Fuel Cycles * Gen-IV fuel cycle options are meant to address all stated Gen-IV Goals - Dose to workers and to the public is one of the numerous elements to be evaluated by Gen-IV R&D - The Fuel Cycle Crosscut Group was assigned to take an early look at dose implication tradeoffs of open and closed fuel cycles * FCCG Interpretation of Assignment: - Collect already-existing evaluations and prepare a briefing on what is currently known Fuel Cycle CrossCut Group 3 Approach * Look at Actual Historical Doses Based on Operational Experience - Data compiled by the United Nations Scientific Committee on the Effects of Atomic

13

Fuel Cycle Research and Development Program  

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

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

14

VISION - Verifiable Fuel Cycle Simulation of Nuclear Fuel Cycle Dynamics  

SciTech Connect (OSTI)

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

15

Fuel cycle cost uncertainty from nuclear fuel cycle comparison  

SciTech Connect (OSTI)

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

16

IFR fuel cycle  

SciTech Connect (OSTI)

The next major milestone of the IFR program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase, which includes completion of facility modifications and installation and cold checkout of process equipment. This paper reviews the development of the electrorefining pyroprocess, the design and construction of the facility for the hot demonstration, the design and fabrication of the equipment, and the schedule and initial plan for its operation.

Battles, J.E.; Miller, W.E. [Argonne National Lab., IL (United States); Lineberry, M.J.; Phipps, R.D. [Argonne National Lab., Idaho Falls, ID (United States)

1992-04-01T23:59:59.000Z

17

CANDU fuel cycle flexibility  

SciTech Connect (OSTI)

High neutron economy, on-power refuelling, and a simple bundle design provide a high degree of flexibility that enables CANDU (CANada Deuterium Uranium; registered trademark) reactors to be fuelled with a wide variety of fuel types. Near-term applications include the use of slightly enriched uranium (SEU), and recovered uranium (RU) from reprocessed spent Light Water Reactor (LWR) fuel. Plutonium and other actinides arising from various sources, including spent LWR fuel, can be accommodated, and weapons-origin plutonium could be destroyed by burning in CANDU. In the DUPIC fuel cycle, a dry processing method would convert spent Pressurized Water Reactor (PWR) fuel to CANDU fuel. The thorium cycle remains of strategic interest in CANDU to ensure long-term resource availability, and would be of specific interest to those countries possessing large thorium reserves, but limited uranium resources.

Torgerson, D.F.; Boczar, P.G. [Chalk River Lab., Ontario (Canada); Dastur, A.R. [AECL CANDU, Mississauga, Ontario (Canada)

1994-12-31T23:59:59.000Z

18

USCEA fuel cycle '93  

SciTech Connect (OSTI)

The US Council for Energy Awareness sponsored the Fuel Cycle '93 conference in Dallas, Texas, on March 21-24, 1993. Over 250 participants attended, numerous papers were presented, and several panel discussions were held. The focus of most industry participants remains the formation of USEC and the pending US-Russian HEU agreement. Following are brief summaries of two key papers and the Fuel Market Issues panel discussion.

Not Available

1993-04-01T23:59:59.000Z

19

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect (OSTI)

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

Carter, J.

2011-01-03T23:59:59.000Z

20

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect (OSTI)

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

Jones, R.; Carter, J.

2010-10-13T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

Fuel Cycle Research & Development | Department of Energy  

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

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

22

Fuel Cycle Subcommittee  

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

Report to NEAC Report to NEAC Fuel Cycle Subcommittee Meeting of April 23, 2013 Washington D.C. June 13, 2013 Burton Richter (Chair), Margaret Chu, Darleane Hoffman, Raymond Juzaitis, Sekazi K Mtingwa, Ronald P Omberg, Joy L Rempe, Dominique Warin 2 I Introduction and Summary The Fuel Cycle Subcommittee of NEAC met in Washington on April 23, 2013. The meeting focused on issues relating to the NE advanced reactor program (sections II, III, and IV), and on storage and transportation issues (section V) related to a possible interim storage program that is the first step in moving toward a new permanent repository as recommended by the Blue Ribbon Commission (BRC) and discussed in the recent response by DOE to Congress on the BRC report 1 . The agenda is given in

23

Combating global warming via non-fossil fuel energy options  

Science Journals Connector (OSTI)

Non-fossil fuel energy options can help reduce or eliminate the emissions of greenhouse gases and are needed to combat climate change. Three distinct ways in which non-fossil fuel options can be used in society are examined here: the capture/production of non-fossil fuel energy sources, their conversion into appropriate energy carriers and increased efficiency throughout the life cycle. Non-fossil fuel energy sources are insufficient to avoid global warming in that they are not necessarily readily utilisable in their natural forms. Hydrogen energy systems are needed to facilitate the use of non-fossil fuels by converting them to two main classes of energy carriers: hydrogen (and hydrogen-derived fuels) and electricity. High efficiency is needed to allow the greatest benefits to be attained from energy options in terms of climate change and other factors. A case study is considered involving the production of hydrogen from non-fossil energy sources via thermochemical water decomposition. Thermochemical water decomposition provides a realistic future non-fossil fuel energy option, which can be driven by non-fossil energy sources (particularly nuclear or solar energy) and help combat global warming.

Marc A. Rosen

2009-01-01T23:59:59.000Z

24

Nuclear fuel cycle information workshop  

SciTech Connect (OSTI)

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

25

Alternative Fuels Data Center: Equipment Options for E85 Fueling Systems  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

Equipment Options for Equipment Options for E85 Fueling Systems to someone by E-mail Share Alternative Fuels Data Center: Equipment Options for E85 Fueling Systems on Facebook Tweet about Alternative Fuels Data Center: Equipment Options for E85 Fueling Systems on Twitter Bookmark Alternative Fuels Data Center: Equipment Options for E85 Fueling Systems on Google Bookmark Alternative Fuels Data Center: Equipment Options for E85 Fueling Systems on Delicious Rank Alternative Fuels Data Center: Equipment Options for E85 Fueling Systems on Digg Find More places to share Alternative Fuels Data Center: Equipment Options for E85 Fueling Systems on AddThis.com... More in this section... Ethanol Basics Benefits & Considerations Stations Locations Infrastructure Development Business Case Equipment Options

26

FUEL CELL/MICRO-TURBINE COMBINED CYCLE  

SciTech Connect (OSTI)

A wide variety of conceptual design studies have been conducted that describe ultra-high efficiency fossil power plant cycles. The most promising of these ultra-high efficiency cycles incorporate high temperature fuel cells with a gas turbine. Combining fuel cells with a gas turbine increases overall cycle efficiency while reducing per kilowatt emissions. This study has demonstrated that the unique approach taken to combining a fuel cell and gas turbine has both technical and economic merit. The approach used in this study eliminates most of the gas turbine integration problems associated with hybrid fuel cell turbine systems. By using a micro-turbine, and a non-pressurized fuel cell the total system size (kW) and complexity has been reduced substantially from those presented in other studies, while maintaining over 70% efficiency. The reduced system size can be particularly attractive in the deregulated electrical generation/distribution environment where the market may not demand multi-megawatt central stations systems. The small size also opens up the niche markets to this high efficiency, low emission electrical generation option.

Larry J. Chaney; Mike R. Tharp; Tom W. Wolf; Tim A. Fuller; Joe J. Hartvigson

1999-12-01T23:59:59.000Z

27

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

28

Sensitivity analysis and optimization of the nuclear fuel cycle  

SciTech Connect (OSTI)

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

29

Rethinking the light water reactor fuel cycle  

E-Print Network [OSTI]

The once through nuclear fuel cycle adopted by the majority of countries with operating commercial power reactors imposes a number of concerns. The radioactive waste created in the once through nuclear fuel cycle has to ...

Shwageraus, Evgeni, 1973-

2004-01-01T23:59:59.000Z

30

Development Plan for the Fuel Cycle Simulator  

SciTech Connect (OSTI)

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

31

Benefits and concerns of a closed nuclear fuel cycle  

SciTech Connect (OSTI)

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

32

VISION: Verifiable Fuel Cycle Simulation Model  

SciTech Connect (OSTI)

The nuclear fuel cycle is a very complex system that includes considerable dynamic complexity as well as detail complexity. In the nuclear power realm, there are experts and considerable research and development in nuclear fuel development, separations technology, reactor physics and waste management. What is lacking is an overall understanding of the entire nuclear fuel cycle and how the deployment of new fuel cycle technologies affects the overall performance of the fuel cycle. The Advanced Fuel Cycle Initiative’s systems analysis group is developing a dynamic simulation model, VISION, to capture the relationships, timing and delays in and among the fuel cycle components to help develop an understanding of how the overall fuel cycle works and can transition as technologies are changed. This paper is an overview of the philosophy and development strategy behind VISION. The paper includes some descriptions of the model and some examples of how to use VISION.

Jacob J. Jacobson; Abdellatif M. Yacout; Gretchen E. Matthern; Steven J. Piet; David E. Shropshire

2009-04-01T23:59:59.000Z

33

Coupling fuel cycles with repositories: how repository institutional choices may impact fuel cycle design  

SciTech Connect (OSTI)

The historical repository siting strategy in the United States has been a top-down approach driven by federal government decision making but it has been a failure. This policy has led to dispatching fuel cycle facilities in different states. The U.S. government is now considering an alternative repository siting strategy based on voluntary agreements with state governments. If that occurs, state governments become key decision makers. They have different priorities. Those priorities may change the characteristics of the repository and the fuel cycle. State government priorities, when considering hosting a repository, are safety, financial incentives and jobs. It follows that states will demand that a repository be the center of the back end of the fuel cycle as a condition of hosting it. For example, states will push for collocation of transportation services, safeguards training, and navy/private SNF (Spent Nuclear Fuel) inspection at the repository site. Such activities would more than double local employment relative to what was planned for the Yucca Mountain-type repository. States may demand (1) the right to take future title of the SNF so if recycle became economic the reprocessing plant would be built at the repository site and (2) the right of a certain fraction of the repository capacity for foreign SNF. That would open the future option of leasing of fuel to foreign utilities with disposal of the SNF in the repository but with the state-government condition that the front-end fuel-cycle enrichment and fuel fabrication facilities be located in that state.

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave., Room 24-207A Cambridge, MA 02139 (United States); Miller, W.F. [Texas A.M. University System, MS 3133 College Station, TX 77843-3133 (United States)

2013-07-01T23:59:59.000Z

34

Advanced Fuel Cycle Economic Sensitivity Analysis  

SciTech Connect (OSTI)

A fuel cycle economic analysis was performed on four fuel cycles to provide a baseline for initial cost comparison using the Gen IV Economic Modeling Work Group G4 ECON spreadsheet model, Decision Programming Language software, the 2006 Advanced Fuel Cycle Cost Basis report, industry cost data, international papers, the nuclear power related cost study from MIT, Harvard, and the University of Chicago. The analysis developed and compared the fuel cycle cost component of the total cost of energy for a wide range of fuel cycles including: once through, thermal with fast recycle, continuous fast recycle, and thermal recycle.

David Shropshire; Kent Williams; J.D. Smith; Brent Boore

2006-12-01T23:59:59.000Z

35

Nuclear Fuel Cycle Integrated System Analysis  

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

36

Life cycle assessment of base-load heat sources for district heating system options  

SciTech Connect (OSTI)

Purpose There has been an increased interest in utilizing renewable energy sources in district heating systems. District heating systems are centralized systems that provide heat for residential and commercial buildings in a community. While various renewable and conventional energy sources can be used in such systems, many stakeholders are interested in choosing the feasible option with the least environmental impacts. This paper evaluates and compares environmental burdens of alternative energy source options for the base load of a district heating center in Vancouver, British Columbia (BC) using the life cycle assessment method. The considered energy sources include natural gas, wood pellet, sewer heat, and ground heat. Methods The life cycle stages considered in the LCA model cover all stages from fuel production, fuel transmission/transportation, construction, operation, and finally demolition of the district heating system. The impact categories were analyzed based on the IMPACT 2002+ method. Results and discussion On a life-cycle basis, the global warming effect of renewable energy options were at least 200 kgeqCO2 less than that of the natural gas option per MWh of heat produced by the base load system. It was concluded that less than 25% of the upstream global warming impact associated with the wood pellet energy source option was due to transportation activities and about 50% of that was resulted from wood pellet production processes. In comparison with other energy options, the wood pellets option has higher impacts on respiratory of inorganics, terrestrial ecotoxicity, acidification, and nutrification categories. Among renewable options, the global warming impact of heat pump options in the studied case in Vancouver, BC, were lower than the wood pellet option due to BC's low carbon electricity generation profile. Ozone layer depletion and mineral extraction were the highest for the heat pump options due to extensive construction required for these options. Conclusions Natural gas utilization as the primary heat source for district heat production implies environmental complications beyond just the global warming impacts. Diffusing renewable energy sources for generating the base load district heat would reduce human toxicity, ecosystem quality degradation, global warming, and resource depletion compared to the case of natural gas. Reducing fossil fuel dependency in various stages of wood pellet production can remarkably reduce the upstream global warming impact of using wood pellets for district heat generation.

Ghafghazi, Saeed [University of British Columbia, Vancouver; Sowlati, T. [University of British Columbia, Vancouver; Sokhansanj, Shahabaddine [ORNL; Melin, Staffan [Delta Research Corporation

2011-03-01T23:59:59.000Z

37

Nuclear Fuel Cycle | Department of Energy  

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

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

38

Advanced Fuel Cycles Activities in IAEA  

SciTech Connect (OSTI)

Considerable scientific and technical progress in many areas of Partitioning and Transmutation (P and T) has been recognized as probable answers to ever-growing issues threatening sustainability, environmental protection and non-proliferation. These recent global developments such as Russian initiative on Global Nuclear Infrastructure-International Fuel Centre and the US initiative on Global Nuclear Energy Partnership (GNEP) have made advanced fuel cycles as one of the decisive influencing factor for the future growth of nuclear energy. International Atomic Energy Agency has initiated the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) with overall objective of bringing together technology holders and technology users to consider jointly the international and national actions required achieving desired innovations in nuclear reactors and fuel cycles. One of the interesting common features of these initiatives (INPRO, GNEP and GNI-IFC) is closed fast reactor fuel cycles and proliferation resistance. Any fuel cycle that integrate P and T into it is also known as 'Advanced Fuel Cycle' (AFC) that could achieve reduction of plutonium and Minor Actinide (MA) elements (namely Am, Np, Cm, etc.). In this regard, some Member States are also evaluating alternative concepts involving the use of thorium fuel cycle, inert-matrix fuel or coated particle fuel. Development of 'fast reactors with closed fuel cycles' would be the most essential step for implementation of P and T. The scale of realization of any AFC depends on the maturity of the development of all these elemental technologies such as recycling MA, Pu as well as reprocessed uranium. In accordance with the objectives of the Agency, the programme B entitled 'Nuclear Fuel cycle technologies and materials' initiated several activities aiming to strengthen the capabilities of interested Member States for policy making, strategic planning, technology development and implementation of safe, reliable, economically efficient, proliferation resistant, environmentally sound and secure nuclear fuel cycle programmes. The paper describes some on-going IAEA activities in the area of: MA-fuel and target, thorium fuel cycle, coated particle fuel, MA-property database, inert matrix fuels, liquid metal cooled fast reactor fuels and fuel cycles, management of reprocessed uranium and proliferation resistance in fuel cycle. (authors)

Nawada, H.P.; Ganguly, C. [Nuclear Fuel Cycle and Materials Section, Division of Nuclear Fuel Cycle and Waste Technology, Department of Nuclear Energy, International Atomic Energy Agency, Vienna (Austria)

2007-07-01T23:59:59.000Z

39

Performance improvement options for the supercritical carbon dioxide brayton cycle.  

SciTech Connect (OSTI)

The supercritical carbon dioxide (S-CO{sub 2}) Brayton cycle is under development at Argonne National Laboratory as an advanced power conversion technology for Sodium-Cooled Fast Reactors (SFRs) as well as other Generation IV advanced reactors as an alternative to the traditional Rankine steam cycle. For SFRs, the S-CO{sub 2} Brayton cycle eliminates the need to consider sodium-water reactions in the licensing and safety evaluation, reduces the capital cost of the SFR plant, and increases the SFR plant efficiency. Even though the S-CO{sub 2} cycle has been under development for some time and optimal sets of operating parameters have been determined, those earlier development and optimization studies have largely been directed at applications to other systems such as gas-cooled reactors which have higher operating temperatures than SFRs. In addition, little analysis has been carried out to investigate cycle configurations deviating from the selected 'recompression' S-CO{sub 2} cycle configuration. In this work, several possible ways to improve S-CO{sub 2} cycle performance for SFR applications have been identified and analyzed. One set of options incorporates optimization approaches investigated previously, such as variations in the maximum and minimum cycle pressure and minimum cycle temperature, as well as a tradeoff between the component sizes and the cycle performance. In addition, the present investigation also covers options which have received little or no attention in the previous studies. Specific options include a 'multiple-recompression' cycle configuration, intercooling and reheating, as well as liquid-phase CO{sub 2} compression (pumping) either by CO{sub 2} condensation or by a direct transition from the supercritical to the liquid phase. Some of the options considered did not improve the cycle efficiency as could be anticipated beforehand. Those options include: a double recompression cycle, intercooling between the compressor stages, and reheating between the turbine stages. Analyses carried out as part of the current investigation confirm the possibilities of improving the cycle efficiency that have been identified in previous investigations. The options in this group include: increasing the heat exchanger and turbomachinery sizes, raising of the cycle high end pressure (although the improvement potential of this option is very limited), and optimization of the low end temperature and/or pressure to operate as close to the (pseudo) critical point as possible. Analyses carried out for the present investigation show that significant cycle performance improvement can sometimes be realized if the cycle operates below the critical temperature at its low end. Such operation, however, requires the availability of a heat sink with a temperature lower than 30 C for which applicability of this configuration is dependent upon the climate conditions where the plant is constructed (i.e., potential performance improvements are site specific). Overall, it is shown that the S-CO{sub 2} Brayton cycle efficiency can potentially be increased to 45 %, if a low temperature heat sink is available and incorporation of larger components (e.g.., heat exchangers or turbomachinery) having greater component efficiencies does not significantly increase the overall plant cost.

Moisseytsev, A.; Sienicki, J. J.; Nuclear Engineering Division

2008-07-17T23:59:59.000Z

40

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...

Note: This page contains sample records for the topic "fuel cycle options" 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

Physics challenges for advanced fuel cycle assessment  

SciTech Connect (OSTI)

Advanced fuel cycles and associated optimized reactor designs will require substantial improvements in key research area to meet new and more challenging requirements. The present paper reviews challenges and issues in the field of reactor and fuel cycle physics. Typical examples are discussed with, in some cases, original results.

Giuseppe Palmiotti; Massimo Salvatores; Gerardo Aliberti

2014-06-01T23:59:59.000Z

42

VISION: Verifiable Fuel Cycle Simulation Model  

SciTech Connect (OSTI)

The nuclear fuel cycle consists of a set of complex components that work together in unison. In order 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. The Advanced Fuel Cycle Initiative’s systems analysis group 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.

Jacob Jacobson; A. M. Yacout; Gretchen Matthern; Steven Piet; David Shropshire; Tyler Schweitzer

2010-11-01T23:59:59.000Z

43

Nuclear Fuel Cycle | Department of Energy  

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

44

NETL - Petroleum-Based Fuels Life Cycle Greenhouse Gas Analysis...  

Open Energy Info (EERE)

- Petroleum-Based Fuels Life Cycle Greenhouse Gas Analysis 2005 Baseline Model Jump to: navigation, search Tool Summary LAUNCH TOOL Name: NETL - Petroleum-Based Fuels Life Cycle...

45

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,...

46

Full Fuel-Cycle Comparison of Forklift Propulsion Systems | Department...  

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

Full Fuel-Cycle Comparison of Forklift Propulsion Systems Full Fuel-Cycle Comparison of Forklift Propulsion Systems This report examines forklift propulsion systems and addresses...

47

Selection of Isotopes and Elements for Fuel Cycle Analysis  

SciTech Connect (OSTI)

Fuel cycle system analysis simulations examine how the selection among fuel cycle options for reactors, fuel, separation, and waste management impact uranium ore utilization, waste masses and volumes, radiotoxicity, heat to geologic repositories, isotope-dependent proliferation resistance measures, and so forth. Previously, such simulations have tended to track only a few actinide and fission product isotopes, those that have been identified as important to a few criteria from the standpoint of recycled material or waste, taken as a whole. After accounting for such isotopes, the residual mass is often characterized as “fission product other” or “actinide other”. However, detailed assessment of separation and waste management options now require identification of key isotopes and residual mass for Group 1A/2A elements (Rb, Cs, Sr, Ba), inert gases (Kr, Xe), halogens (Br, I), lanthanides, transition metals, transuranic (TRU), uranium, actinide decay products. The paper explains the rationale for a list of 81 isotopes and chemical elements to better support separation and waste management assessment in dynamic system analysis models such as Verifiable Fuel Cycle Simulation (VISION)

Steven J. Piet

2009-04-01T23:59:59.000Z

48

Cost-effective fuel cycle closure  

SciTech Connect (OSTI)

The U.S. government is moving toward meeting its obligation to accept spent fuel from commercial light water reactors (LWRs) in 1998 by providing an interim storage facility. Site work and analysis of the deep, geologic repository at Yucca Mountain will continue at a reduced level of effort. This provides the time required to reevaluate the use of spent-fuel recycling instead of direct disposal. A preliminary assessment of this option is presented in this paper.

Ehrman, C.S. [Burns & Roe, Inc., Oradell, NJ (United States); Boardman, C.E. [General Electric Company, San Jose, CA (United States)

1995-12-31T23:59:59.000Z

49

Physics of fusion-fuel cycles  

SciTech Connect (OSTI)

The evaluation of nuclear fusion fuels for a magnetic fusion economy must take into account the various technological impacts of the various fusion fuel cycles as well as the relative reactivity and the required ..beta..'s and temperatures necessary for economic steady-state burns. This paper will review some of the physics of the various fusion fuel cycles (D-T, catalyzed D-D, D-/sup 3/He, D-/sup 6/Li, and the exotic fuels: /sup 3/He/sup 3/He and the proton-based fuels such as P-/sup 6/Li, P-/sup 9/Be, and P-/sup 11/B) including such items as: (1) tritium inventory, burnup, and recycle, (2) neutrons, (3) condensable fuels and ashes, (4) direct electrical recovery prospects, (5) fissile breeding, etc. The advantages as well as the disadvantages of the different fusion fuel cycles will be discussed. The optimum fuel cycle from an overall standpoint of viability and potential technological considerations appears to be catalyzed D-D, which could also support smaller relatively clean, lean-D, rich-/sup 3/He satellite reactors as well as fission reactors.

McNally, J.R. Jr.

1981-01-01T23:59:59.000Z

50

IFR fuel cycle--pyroprocess development  

SciTech Connect (OSTI)

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

51

IFR fuel cycle--pyroprocess development  

SciTech Connect (OSTI)

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

52

Fuel Cycle Technology Documents | Department of Energy  

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

Technology Technology Documents Fuel Cycle Technology Documents January 11, 2013 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. October 30, 2012 2012 Fuel Cycle Technologies Annual Review Meeting Transaction Report The United States must continue to ensure improvements and access to this technology so we can meet our economic, environmental and energy security

53

International Atomic Energy Agency (IAEA) activities on spent fuel management options  

SciTech Connect (OSTI)

Many countries have in the past several decades opted for storage of spent fuel for undefined periods of time. They have adopted the 'wait and see' strategy for spent fuel management. A relatively small number of countries have adopted reprocessing and use of MOX fuel as part of their strategy in spent fuel management. From the 10, 000 tonnes of heavy metal that is removed annually from nuclear reactors throughout the world, only approximately 30 % is currently being reprocessed. Continuous re-evaluation of world energy resources, announcement of the Global Nuclear Energy Partnership (GNEP) and the Russian initiative to form international nuclear centers, including reprocessing, are changing the stage for future development of nuclear energy. World energy demand is expected to more than double by 2050, and expansion of nuclear energy is a key to meeting this demand while reducing pollution and greenhouse gases. Since its foundation, the International Atomic Energy Agency (IAEA) has served as an interface between countries in exchanging information on the peaceful development of nuclear energy and at the same time guarding against proliferation of materials that could be used for nuclear weapons. The IAEA's Department of Nuclear Energy has been generating technical documents, holding meetings and conferences, and supporting technical cooperation projects to facilitate this exchange of information. This paper focuses on the current status of IAEA activities in the field of spent fuel management being carried out by the Division of Nuclear Fuel Cycle and Waste Technology. Information on those activities could be found on the web site link www.iaea.org/OurWork/ST/NE/NEFW/nfcms. To date, the IAEA has given priority in its spent fuel management activities to supporting Member States in their efforts to deal with growing accumulations of spent power reactor fuel. There is technical consensus that the present technologies for spent fuel storage, wet and dry, provide adequate protection to people and environment. As storage durations grow, the IAEA has expanded its work related to the implications of extended storage periods. Operation and maintenance of containers for storage and transport have also been investigated related to long term storage periods. In addition, as international interest in reprocessing of spent fuel increases, the IAEA continues to serve as a crossroads for sharing the latest developments in spent fuel treatment options. A Coordinated Research Project is currently addressing spent fuel performance assessment and research to evaluate long term effects of storage on spent fuel. The effect of increased burnup and mixed oxide fuels on spent fuel management is also the focus of interest as it follows the trend in optimizing the use of nuclear fuel. Implications of damaged fuel on storage and transport as well as burnup credit in spent fuel applications are areas that the IAEA is also investigating. Since spent fuel management considerations require social stability and institutional control, those aspects are taken into account in most IAEA activities. Data requirements and records management as storage durations extend were also investigated as well as the potential for regional spent fuel storage facilities. Spent fuel management activities continue to be coordinated with others in the IAEA to ensure compliance and consistency with efforts in the Department of Safety and Security and the Department of Safeguards, as well as with activities related to geologic disposal. Either disposal of radioactive waste or spent fuel will be an ultimate consideration in all spent fuel management options. Updated information on spent fuel treatment options that include fuel reprocessing as well as transmutation of minor actinides are investigated to optimize the use of nuclear fuel and minimize impact on environment. Tools for spent fuel management economics are also investigated to facilitate assessment of industrial applicability for these options. Most IAEA spent fuel management activities will ultimately be reported in o

Lovasic, Z.; Danker, W. [International Atomic Energy Agency (IAEA) Vienna (Austria)

2007-07-01T23:59:59.000Z

54

Fuel-Cycle Analysis of Hydrogen-Powered Fuel-Cell Systems with...  

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

Fuel-Cycle Analysis of Hydrogen-Powered Fuel-Cell Systems with the GREET Model Fuel-Cycle Analysis of Hydrogen-Powered Fuel-Cell Systems with the GREET Model This presentation by...

55

International Nuclear Fuel Cycle Fact Book  

SciTech Connect (OSTI)

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

56

The integral fast reactor fuel cycle  

SciTech Connect (OSTI)

The liquid-metal reactor (LMR) has the potential to extend the uranium resource by a factor of 50 to 100 over current commercial light water reactors (LWRs). In the integral fast reactor (IFR) development program, the entire reactor system - reactor, fuel cycle, and waste process - is being developed and optimized at the same time as a single integral entity. A key feature of the IFR concept is the metallic fuel. The lead irradiation tests on the new U-Pu-Zr metallic fuel in the Experimental Breeder Reactor II have surpassed 185000 MWd/t burnup, and its high burnup capability has now been fully demonstrated. The metallic fuel also allows a radically improved fuel cycle technology. Pyroprocessing, which utilizes high temperatures and molten salt and molten metal solvents, can be advantageously utilized for processing metal fuels because the product is metal suitable for fabrication into new fuel elements. Direct production of a metal product avoids expensive and cumbersome chemical conversion steps that would result from use of the conventional Purex solvent extraction process. The key step in the IFR process is electrorefining, which provides for recovery of the valuable fuel constituents, uranium and plutonium, and for removal of fission products. A notable feature of the IFR process is that the actinide elements accompany plutonium through the process. This results in a major advantage in the high-level waste management.

Chang, Y.I. (Argonne National Lab., IL (United States))

1990-01-01T23:59:59.000Z

57

Analysis of fuel options for the breakeven core configuration of the Advanced Recycling Reactor  

SciTech Connect (OSTI)

A trade-off study is performed to determine the impacts of various fuel forms on the core design and core physics characteristics of the sodium-cooled Toshiba- Westinghouse Advanced Recycling Reactor (ARR). The fuel forms include oxide, nitride, and metallic forms of U and Th. The ARR core configuration is redesigned with driver and blanket regions in order to achieve breakeven fissile breeding performance with the various fuel types. State-of-the-art core physics tools are used for the analyses. In addition, a quasi-static reactivity balance approach is used for a preliminary comparison of the inherent safety performances of the various fuel options. Thorium-fueled cores exhibit lower breeding ratios and require larger blankets compared to the U-fueled cores, which is detrimental to core compactness and increases reprocessing and manufacturing requirements. The Th cores also exhibit higher reactivity swings through each cycle, which penalizes reactivity control and increases the number of control rods required. On the other hand, using Th leads to drastic reductions in void and coolant expansion coefficients of reactivity, with the potential for enhancing inherent core safety. Among the U-fueled ARR cores, metallic and nitride fuels result in higher breeding ratios due to their higher heavy metal densities. On the other hand, oxide fuels provide a softer spectrum, which increases the Doppler effect and reduces the positive sodium void worth. A lower fuel temperature is obtained with the metallic and nitride fuels due to their higher thermal conductivities and compatibility with sodium bonds. This is especially beneficial from an inherent safety point of view since it facilitates the reactor cool-down during loss of power removal transients. The advantages in terms of inherent safety of nitride and metallic fuels are maintained when using Th fuel. However, there is a lower relative increase in heavy metal density and in breeding ratio going from oxide to metallic or nitride Th fuels relative to the U counterpart fuels. (authors)

Stauff, N.E.; Klim, T.K.; Taiwo, T.A. [Argonne National Laboratory, Argonne, IL (United States); Fiorina, C. [Politecnico di Milano, Milan (Italy); Franceschini, F. [Westinghouse Electric Company LLC., Cranberry Township, Pennsylvania (United States)

2013-07-01T23:59:59.000Z

58

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

59

Nuclear reactors and the nuclear fuel cycle  

SciTech Connect (OSTI)

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

60

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

SciTech Connect (OSTI)

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

Note: This page contains sample records for the topic "fuel cycle options" 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

System Losses Study - FIT (Fuel-cycle Integration and Tradeoffs)  

SciTech Connect (OSTI)

This team aimed to understand the broad implications of changes of operating performance and parameters of a fuel cycle component on the entire system. In particular, this report documents the study of the impact of changing the loss of fission products into recycled fuel and the loss of actinides into waste. When the effort started in spring 2009, an over-simplified statement of the objective was “the number of nines” – how would the cost of separation, fuel fabrication, and waste management change as the number of nines of separation efficiency changed. The intent was to determine the optimum “losses” of TRU into waste for the single system that had been the focus of the Global Nuclear Energy Program (GNEP), namely sustained recycle in burner fast reactors, fed by transuranic (TRU) material recovered from used LWR UOX-51 fuel. That objective proved to be neither possible (insufficient details or attention to the former GNEP options, change in national waste management strategy from a Yucca Mountain focus) nor appropriate given the 2009-2010 change to a science-based program considering a wider range of options. Indeed, the definition of “losses” itself changed from the loss of TRU into waste to a generic definition that a “loss” is any material that ends up where it is undesired. All streams from either separation or fuel fabrication are products; fuel feed streams must lead to fuels with tolerable impurities and waste streams must meet waste acceptance criteria (WAC) for one or more disposal sites. And, these losses are linked in the sense that as the loss of TRU into waste is reduced, often the loss or carryover of waste into TRU or uranium is increased. The effort has provided a mechanism for connecting these three Campaigns at a technical level that had not previously occurred – asking smarter and smarter questions, sometimes answering them, discussing assumptions, identifying R&D needs, and gaining new insights. The FIT model has been a forcing function, helping the team in this endeavor. Models don’t like “TBD” as an input, forcing us to make assumptions and see if they matter. A major addition in FY 2010 was exploratory analysis of “modified open fuel” cycles, employing “minimum fuel treatment” as opposed to full aqueous or electrochemical separation treatment. This increased complexity in our analysis and analytical tool development because equilibrium conditions do not appear sustainable in minimum fuel treatment cases, as was assumed in FY 2009 work with conventional aqueous and electrochemical separation. It is no longer reasonable to assume an equilibrium situation exists in all cases.

Steven J. Piet; Nick R. Soelberg; Samuel E. Bays; Robert S. Cherry; Denia Djokic; Candido Pereira; Layne F. Pincock; Eric L. Shaber; Melissa C. Teague; Gregory M. Teske; Kurt G. Vedros

2010-09-01T23:59:59.000Z

62

FUEL CYCLE TECHNOLOGIES QUALITY ASSURANCE PROGRAM DOCUMENT  

Broader source: Energy.gov [DOE]

This Quality Assurance Program Document (QAPD) is the top-level quality policy and requirements document for the Fuel Cycle Technologies (FCT) program. The quality assurance (QA) requirements specified herein apply to Participants that manage and/or perform work within FCT Program.

63

Evaluation and Adaptation of 5-Cycle Fuel Economy Testing and...  

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

Adaptation of 5-Cycle Fuel Economy Testing and Calculations for HEVs and PHEVs Evaluation and Adaptation of 5-Cycle Fuel Economy Testing and Calculations for HEVs and PHEVs 2012...

64

Concept for a small, colocated fuel cycle facility for oxide breeder fuels  

SciTech Connect (OSTI)

As part of a United States Department of Energy (USDOE) program to examine innovative liquid-metal reactor (LMR) system designs over the past three years, the Oak Ridge National Laboratory (ORNL) and the Westinghouse Hanford Company (WHC) collaborated on studies of mixed oxide fuel cycle options. A principal effort was an advanced concept for a small integrated fuel cycle colocated with a 1300-MW(e) reactor station. The study provided a scoping design and a basis on which to proceed with implementation of such a facility if future plans so dictate. The facility integrated reprocessing, waste management, and refabrication functions in a single facility of nominal 35-t/year capacity utilizing the latest technology developed in fabrication programs at WHC and in reprocessing at ORNL. The concept was based on many years of work at both sites and extensive design studies of prior years.

Burch, W.D.; Stradley, J.G.; Lerch, R.E.

1987-01-01T23:59:59.000Z

65

Fuel Cycle Scenario Definition, Evaluation, and Trade-offs  

SciTech Connect (OSTI)

This report aims to clarify many of the issues being discussed within the AFCI program, including Inert Matrix Fuel (IMF) versus Mixed Oxide (MOX) fuel, single-pass versus multi-pass recycling, thermal versus fast reactors, potential need for transmutation of technetium and iodine, and the value of separating cesium and strontium. It documents most of the work produced by INL, ANL, and SNL personnel under their Simulation, Evaluation, and Trade Study (SETS) work packages during FY2005 and the first half of FY2006. This report represents the first attempt to calculate a full range of metrics, covering all four AFCI program objectives - waste management, proliferation resistance, energy recovery, and systematic management/economics/safety - using a combination of "static" calculations and a system dynamic model, DYMOND. In many cases, we examine the same issue both dynamically and statically to determine the robustness of the observations. All analyses are for the U.S. reactor fleet. This is a technical report, not aimed at a policy-level audience. A wide range of options are studied to provide the technical basis for identifying the most attractive options and potential improvements. Option improvement could be vital to accomplish before the AFCI program publishes definitive cost estimates. Information from this report will be extracted and summarized in future policy-level reports. Many dynamic simulations of deploying those options are included. There are few "control knobs" for flying or piloting the fuel cycle system into the future, even though it is dark (uncertain) and controls are sluggish with slow time response: what types of reactors are built, what types of fuels are used, and the capacity of separation and fabrication plants. Piloting responsibilities are distributed among utilities, government, and regulators, compounding the challenge of making the entire system work and respond to changing circumstances. We identify four approaches that would increase our ability to pilot the fuel cycle system: (1) have a recycle strategy that could be implemented before the 2030-2050 approximate period when current reactors retire so that replacement reactors fit into the strategy, (2) establish an option such as multi-pass blended-core IMF as a downward plutonium control knob and accumulate waste management benefits early, (3) establish fast reactors with flexible conversion ratio as a future control knob that slowly becomes available if/when fast reactors are added to the fleet, and (4) expand exploration of blended assemblies and cores, which appear to have advantages and agility. Initial results suggest multi-pass full-core MOX appears to be a less effective way than multi-pass blended core IMF to manage the fuel cycle system because it requires higher TRU throughput while more slowly accruing waste management benefits. Single-pass recycle approaches for LWRs (we did not study the VHTR) do not meet AFCI program objectives and could be considered a "dead end". Fast reactors appear to be effective options but a significant number of fast reactors must be deployed before the benefit of such strategies can be observed.

Steven J. Piet; Gretchen E. Matthern; Jacob J. Jacobson; Christopher T. Laws; Lee C. Cadwallader; Abdellatif M. Yacout; Robert N. Hill; J. D. Smith; Andrew S. Goldmann; George Bailey

2006-08-01T23:59:59.000Z

66

World nuclear fuel cycle requirements 1990  

SciTech Connect (OSTI)

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

67

Kinetics of pyroprocesses in ATW fuel cycles  

SciTech Connect (OSTI)

Accelerator-driven transmutation of waste (ATW) combines the technologies of accelerators and reactors to treat the nuclear waste problem. An ATW system uses a high-current accelerator to generate spallation neutrons to initiate the transmutation of actinides and select fission products in a subcritical nuclear assembly surrounding the target volume. For high burnup and efficient operation, an ATW system requires simple, reliable, and efficient fuel preparation and cleanup procedures to periodically remove {open_quotes}neutron poisons.{close_quotes} We have identified several fuel cycles based on pyroprocessing.

Li, Ning; Hu, Y.C.; Park, B.G. [Los Alamos National Lab., NM (United States)

1997-12-01T23:59:59.000Z

68

Integrating ALWR and ALMR fuel cycles  

SciTech Connect (OSTI)

Recent progress in the design of the Advanced Liquid Metal Reactor (ALMR) and in the development of the pyro-metallurgical processing system (Actinide Recycle System) have the potential to allow the back end of the Light Water Reactor (LWR) fuel cycle to be closed in an economically viable and environmentally preferable way. The design and development progress that makes closing the ALWR fuel cycle (removing the fissionable and fertile material for re-use prior to disposal) the most cost effective and environmentally sound approach are presented. Key factors addressed include: resource extension, a reduction in the risk and cost of waste disposal, and the added proliferation resistance associated with the pyro-metallurgical processing system.

Boardman, C.E.; Wadekamper, D.C. [General Electric Co., San Jose, CA (United States). Nuclear Energy Div.; Ehrman, C.S.; Hess, C.; Ocker, M. [Burns and Roe Co., Oradall, NJ (United States); Thompson, M. [Thompson (Marion), Fremont, CA (United States)

1996-08-01T23:59:59.000Z

69

Overview of the nuclear fuel cycle  

SciTech Connect (OSTI)

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

70

Safeguarding and Protecting the Nuclear Fuel Cycle  

SciTech Connect (OSTI)

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

71

Financing Strategies For A Nuclear Fuel Cycle Facility  

SciTech Connect (OSTI)

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

72

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

SciTech Connect (OSTI)

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

73

Fuel Cycle Research & Development Documents | Department of Energy  

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

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

74

USED FUEL RAIL SHOCK AND VIBRATION TESTING OPTIONS ANALYSIS  

SciTech Connect (OSTI)

The objective of the rail shock and vibration tests is to complete the framework needed to quantify loads of fuel assembly components that are necessary to guide materials research and establish a technical basis for review organizations such as the U.S. Nuclear Regulatory Commission (NRC). A significant body of experimental and numerical modeling data exists to quantify loads and failure limits applicable to normal conditions of transport (NCT) rail transport, but the data are based on assumptions that can only be verified through experimental testing. The test options presented in this report represent possible paths for acquiring the data that are needed to confirm the assumptions of previous work, validate modeling methods that will be needed for evaluating transported fuel on a case-by-case basis, and inform material test campaigns on the anticipated range of fuel loading. The ultimate goal of this testing is to close all of the existing knowledge gaps related to the loading of used fuel under NCT conditions and inform the experiments and analysis program on specific endpoints for their research. The options include tests that would use an actual railcar, surrogate assemblies, and real or simulated rail transportation casks. The railcar carrying the cradle, cask, and surrogate fuel assembly payload would be moved in a train operating over rail track modified or selected to impart shock and vibration forces that occur during normal rail transportation. Computer modeling would be used to help design surrogates that may be needed for a rail cask, a cask’s internal basket, and a transport cradle. The objective of the design of surrogate components would be to provide a test platform that effectively simulates responses to rail shock and vibration loads that would be exhibited by state-of-the-art rail cask, basket, and/or cradle structures. The computer models would also be used to help determine the placement of instrumentation (accelerometers and strain gauges) on the surrogate fuel assemblies, cask and cradle structures, and the railcar so that forces and deflections that would result in the greatest potential for damage to high burnup and long-cooled UNF can be determined. For purposes of this report we consider testing on controlled track when we have control of the track and speed to facilitate modeling.

Ross, Steven B.; Best, Ralph E.; Klymyshyn, Nicholas A.; Jensen, Philip J.; Maheras, Steven J.

2014-09-29T23:59:59.000Z

75

Indirect-fired gas turbine dual fuel cell power cycle  

DOE Patents [OSTI]

A fuel cell and gas turbine combined cycle system which includes dual fuel cell cycles combined with a gas turbine cycle wherein a solid oxide fuel cell cycle operated at a pressure of between 6 to 15 atms tops the turbine cycle and is used to produce CO.sub.2 for a molten carbonate fuel cell cycle which bottoms the turbine and is operated at essentially atmospheric pressure. A high pressure combustor is used to combust the excess fuel from the topping fuel cell cycle to further heat the pressurized gas driving the turbine. A low pressure combustor is used to combust the excess fuel from the bottoming fuel cell to reheat the gas stream passing out of the turbine which is used to preheat the pressurized air stream entering the topping fuel cell before passing into the bottoming fuel cell cathode. The CO.sub.2 generated in the solid oxide fuel cell cycle cascades through the system to the molten carbonate fuel cell cycle cathode.

Micheli, Paul L. (Sacramento, CA); Williams, Mark C. (Morgantown, WV); Sudhoff, Frederick A. (Morgantown, WV)

1996-01-01T23:59:59.000Z

76

Fuel cell systems for first lunar outpost -- Reactant storage options  

SciTech Connect (OSTI)

A Lunar Surface Power Working Group was formed to review candidate systems for providing power to the First Lunar Outpost habitat. The working group met for five days in the fall of 1992 and concluded that the most attractive candidate included a photovoltaic unit, a fuel cell, a regenerator to recycle the reactants, and storage of oxygen and hydrogen gases. Most of the volume (97%) and weight (64%) are taken up by the reactants and their storage tanks. The large volume is difficult to accommodate, and therefore, the working group explored ways of reducing the volume. An alternative approach to providing separate high pressure storage tanks is to use two of the descent stage propellant storage tanks, which would have to be wrapped with graphite fibers to increase their pressure capability. This saves 90% of the volume required for storage of fuel cell reactants. Another approach is to use the descent storage propellant tanks for storage of the fuel cell reactants as cryogenic liquids, but this requires a gas liquefaction system, increases the solar array by 40%, and increases the heat rejection rate by 170% compared with storage of reactants as high pressure gases. For a high power system (>20 kW) the larger energy storage requirement would probably favor the cryogenic storage option.

Nelson, P.A. [Argonne National Lab., IL (United States). Chemical Technology Div.

1995-06-01T23:59:59.000Z

77

Microsoft Word - Fuel Cycle Subcomm report final v2.docx  

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

of the Fuel Cycle of the Fuel Cycle Subcommittee of NEAC June 15, 2011 Washington, D.C. Members: Burton Richter (Chairman) Darleane Hoffman Raymond Juzaitis Sekazi Mtingwa Ron Omberg Joy Rempe Dominique Warin Fuel Cycle Subcommittee Report 6/15/2011 2 I. Introduction and Summary The Fuel Cycle subcommittee of NEAC met April 25-26 in Albuquerque, New Mexico. The main topics of discussion were the Used Nuclear Fuel (UNF) disposal program, the System Study Program's methodology that is to be used to set priorities for R&D on advanced fuel cycles, and the University Programs. In addition to these, we were briefed on the budget, but have no comments other than a hope for a good outcome and restrict ourselves to general advice until more is known. A current complication in the design of the Fuel Cycle R&D FCRD program is the Blue

78

DOE Hydrogen Analysis Repository: Life Cycle Assessment of Hydrogen Fuel  

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

Life Cycle Assessment of Hydrogen Fuel Cell and Gasoline Vehicles Life Cycle Assessment of Hydrogen Fuel Cell and Gasoline Vehicles Project Summary Full Title: Life Cycle Assessment of Hydrogen Fuel Cell and Gasoline Vehicles Project ID: 143 Principal Investigator: Ibrahim Dincer Brief Description: Examines the social, environmental and economic impacts of hydrogen fuel cell and gasoline vehicles. Purpose This project aims to investigate fuel cell vehicles through environmental impact, life cycle assessment, sustainability, and thermodynamic analyses. The project will assist in the development of highly qualified personnel in such areas as system analysis, modeling, methodology development, and applications. Performer Principal Investigator: Ibrahim Dincer Organization: University of Ontario Institute of Technology

79

Fuel Cycle Science & Technology | Nuclear Science | ORNL  

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

80

Fuel economy goals for future powertrain and engine options  

Science Journals Connector (OSTI)

Efficiency goals represent one of the key factors governing powertrain choice. These goals are specified for three novel developments in automotive technology which would enable them to compete on this single basis with the conventional four-speed manual or automatic transmission (with torque converter lock-up) coupled with a fixed displacement spark-ignition engine. The fuel consumption figures of continuously variable ratio and infinitely variable ratio automobile transmissions are presented using a simulation model of a vehicle in both urban (EPA cycle) and constant-speed operation. A powertrain utilising a variable displacement engine is also simulated.

D.B. Gilmore

1988-01-01T23:59:59.000Z

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


81

The IAEA international conference on fast reactors and related fuel cycles: highlights and main outcomes  

SciTech Connect (OSTI)

The 'International Conference on Fast Reactors and Related Fuel Cycles', which is regularly held every four years, represents the main international event dealing with fast reactors technology and related fuel cycles options. Main topics of the conference were new fast reactor concepts, design and simulation capabilities, safety of fast reactors, fast reactor fuels and innovative fuel cycles, analysis of past experience, fast reactor knowledge management. Particular emphasis was put on safety aspects, considering the current need of developing and harmonizing safety standards for fast reactors at the international level, taking also into account the lessons learned from the accident occurred at the Fukushima- Daiichi nuclear power plant in March 2011. Main advances in the several key areas of technological development were presented through 208 oral presentations during 41 technical sessions which shows the importance taken by fast reactors in the future of nuclear energy.

Monti, S.; Toti, A. [International Atomic Energy Agency - IAEA, Wagramer Strasse 5, PO Box 100, A-1400 Vienna (Austria)

2013-07-01T23:59:59.000Z

82

Grouped actinide separation in advanced nuclear fuel cycles  

SciTech Connect (OSTI)

Aiming at cleaner waste streams (containing only the short-lived fission products) a partitioning and transmutation (P-T) scheme can significantly reduce the quantities of long-lived radionuclides consigned to waste. Many issues and options are being discussed and studied at present in view of selecting the optimal route. The choice is between individual treatment of the relevant elements and a grouped treatment of all actinides together. In the European Collaborative Project ACSEPT (Actinide recycling by Separation and Transmutation), grouped separation options derived from an aqueous extraction or from a dry pyroprocessing route were extensively investigated. Successful demonstration tests for both systems have been carried out in the frame of this project. The aqueous process called GANEX (Grouped Actinide Extraction) is composed of 2 cycles, a first one to recover the major part of U followed by a co-extraction of Np, Pu, Am, and Cm altogether. The pyro-reprocessing primarily applicable to metallic fuels such as the U-Pu-Zr alloy originally developed by the Argonne National Laboratory (US) in the mid 1980s, has also been applied to the METAPHIX fuels containing up to 5% of minor actinides and 5% of lanthanides (e.g. U{sub 60}Pu{sub 20}-Zr{sub 10}Am{sub 2}Nd{sub 3.5}Y{sub 0.5}Ce{sub 0.5}Gd{sub 0.5}). A grouped actinide separation has been successfully carried out by electrorefining on solid Al cathodes. At present the recovery of the actinides from the alloy formed with Al upon electrodeposition is under investigation, because an efficient P-T cycle requires multiple re-fabrication and re-irradiation. (authors)

Glatz, J.P.; Malmbeck, R.; Ougier, M.; Soucek, P. [Joint Research Center - Institute for Transuranium Elements, P.O. Box 2340, D-76125 Karlsruhe (Germany); Murakamin, T.; Tsukada, T.; Koyama, T. [Central Research Institute of Electric Power Industry (CRIEPI), Komaeshi, Tokyo 201-8511 (Japan)

2013-07-01T23:59:59.000Z

83

Comprehensive Fuel Cycle - Community Perspective - 13093  

SciTech Connect (OSTI)

Should a five-county region surrounding the Department of Energy's Savannah River Site ('SRS') use its assets to help provide solutions to closing the nation's nuclear fuel cycle? That question has been the focus of a local ad hoc multi-disciplinary community task force (Tier I) that has been at work in recent months outlining issues and identifying unanswered questions to determine if assuming a leadership role in closing the nuclear fuel cycle is in the community's interest. If so, what are the terms and conditions under which we the community would agree to participate? Our starting point was the President's Blue Ribbon Commission on America's Nuclear Future ('Commission') which made a total of eight (8) recommendations in its final report. There are several recommendations that are directly relevant to the Tier I group and potential efforts of the Region. These are the 'consent-based approach', the creation of an independent nuclear waste management entity funded from the existing nuclear waste fee; the 'prompt efforts to develop one or more consolidated storage facilities', and 'continued U.S. innovation in nuclear energy technology and for workforce development'. (authors)

McLeod, Richard V. [Savannah River Community Reuse Organization, P.O. Box 696, Aiken, SC 29802 (United States)] [Savannah River Community Reuse Organization, P.O. Box 696, Aiken, SC 29802 (United States); Frazier, Timothy A. [Dickstein Shapiro LLP, 1825 Eye Street NW, Washington, DC, 20006-5403 (United States)] [Dickstein Shapiro LLP, 1825 Eye Street NW, Washington, DC, 20006-5403 (United States)

2013-07-01T23:59:59.000Z

84

(Coordinated research on fuel cycle cost)  

SciTech Connect (OSTI)

The Department of Energy (DOE) and the Commission of the European Communities (CEC) have been exploring the possibility of parallel studies on the externals costs of employing fuel cycles to deliver energy services. These studies are of particular importance following the activities of the US National Energy Strategy (NES), where the potential discrepancies between market prices and the social costs of energy services were raised as significant policy concerns. To respond to these concerns, Oak Ridge National Laboratory (ORNL) and Resources for the Future (RFF) have begun a collaborative effort for the DOE to investigate the external costs, or externalities, generated by cradle to grave fuel cycle activities. Upon initiating this project, the CEC expressed an interest to the DOE that Europe should conduct a parallel study and that the two studies should be highly coordinated for consistency in the results. This series of meetings with members of the CEC was undertaken to resolve some issues implied by pursuing parallel, coordinated studies; issues that were previously defined by the August meetings. In addition, it was an opportunity for some members of the US research team and the DOE sponsor to meet with their European counterparts for the study, as well as persons in charge of research areas that ultimately would play a key role in the European study.

Cantor, R.A.; Shelton, R.B.; Krupnick, A.J.

1990-11-05T23:59:59.000Z

85

Refiner options for converting and utilizing heavy fuel oil  

SciTech Connect (OSTI)

Ongoing advances in established technologies, together with recent commercial applications of residue fluid catalytic cracking (RFCC), automated residue demetallization, solvent deasphalting and gasification of pitch and coke, have markedly enhanced options for processing and economically using residues. Key long-term driving forces for processing strategies are: the need for flexibility to handle heavy, high-metals crude oils, and the economic benefit of being able to convert low-value residues to high-value light transportation fuels, hydrogen and electric power. Narrowing light/heavy crude oil price differentials and relatively low crude oil price levels since the early 1990s until the first quarter of 1996 have slowed the addition of new bottom-of-the-barrel conversion projects over the past two years. At the same time, world crude oil demand has increased at an annual average rate of nearly one million barrels/day (MMbpd) since 1985. Some major producer/refining companies forecast this rate of increase to continue well into the next decade. The inevitable net result will be the increased production of heavier crude oils. The authors project that this will be accompanied by flat or declining markets for heavy fuel oil and a resultant need for additional residue conversion/utilization capacity. The paper discusses technology application and status, economic observations, and technology outlook.

Dickenson, R.L.; Biasca, F.E.; Schulman, B.L.; Johnson, H.E. [SFA Pacific, Inc., Mountain View, CA (United States)

1997-02-01T23:59:59.000Z

86

Associate Deputy Assistant Secretary, Office of Fuel Cycle Technologies  

Broader source: Energy.gov [DOE]

The Associate Deputy Assistant Secretary for Fuel Cycle Technologies, Office of Nuclear Energy (NE) will provide leadership and expertise in supporting the management of national programs that...

87

Why reconsider the thorium fuel cycle?  

SciTech Connect (OSTI)

In this paper we have endeavored to present the available technical information on the potential use of Th in nuclear fuel cycle (FC) applications as compared to U without subjective evaluations. Where helpful, we have compared the technical attributes of Th-232 as a fertile isotope and U-233 as a fissile isotope with other similar isotopes (i.e., U-238, and U-235 and Pu-239, respectively). In addition, we have summarized (a) experience gained to-date with fabricating and reprocessing of Th-232/U-233 fuels, (b) factors concerning Th fuel irradiation in both test reactors and power reactors, and (c) differences in the backend of the FC with emphasis on repository risks. As might be expected, many technical aspects of Th vs. U have not changed since the sixties. However, there are some factors elaborated in this paper that have changed. Changes potentially encouraging Th use are: (a) the ability to recover large amounts of Th as a byproduct with small attendant costs and environmental impacts, (b) the potential to produce fewer minor actinides (MA) and less Pu during power production, and (c) increased concerns about proliferation which might be somewhat mitigated by the high radioactivity and amenability to isotopic dilution of U-233. Changes challenging Th utilization are: (a) obtaining sufficient experience handling Th/U-233 fuels, (b) the existence of large inventories of depleted U and continuing discovery of large U resources, and (c) recognition that the extent to which U-233 might mitigate proliferation concerns is not as large as originally hoped.

Krahn, S.; Croff, A.; Ault, T.; Wymer, R. [Vanderbilt University: 2301 Vanderbilt Place/PMB 351831, Nashville, TN, 37235 (United States)

2013-07-01T23:59:59.000Z

88

2012 Fuel Cycle MPACT Working Group  

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

Site Site Hydrogen Research Center 301 Gateway Drive Aiken, SC 29803 Accommodations Country Inn & Suites Aiken 3270 Whiskey Road Aiken, SC 29803 (803) 649-4024 RESERVATIONS: The cut-off date for guest room block reservations is Wednesday, February 22, 2012. We have a block of rooms reserved at this hotel at the government per diem rate of $86.00 per night. Please reference DOE -NE Fuel Cycle MPACT Working Group Meeting when making your reservations to the get the government rate. Reservations will be by individual call-in, per your institutional protocol. Here is a listing of other hotels that offer government room rates. Please note that we do not have rooms reserved at the list locations, only Country Inn & Suites in Aiken. Maps Maps to SRNL from Columbia, Aiken, and Augusta

89

Software Requirements Specification Verifiable Fuel Cycle Simulation (VISION) Model  

SciTech Connect (OSTI)

The purpose of this Software Requirements Specification (SRS) is to define the top-level requirements for a Verifiable Fuel Cycle Simulation Model (VISION) of the Advanced Fuel Cycle (AFC). This simulation model is intended to serve a broad systems analysis and study tool applicable to work conducted as part of the AFCI (including costs estimates) and Generation IV reactor development studies.

D. E. Shropshire; W. H. West

2005-11-01T23:59:59.000Z

90

Economic prospects of the Integral Fast Reactor (IFR) fuel cycle  

SciTech Connect (OSTI)

The IFR fuel cycle based on pyroprocessing involves only few operational steps and the batch-oriented process equipment systems are compact. This results in major cost reductions in all of three areas of reprocessing, fabrication, and waste treatment. This document discusses the economic aspects of this fuel cycle.

Chang, Y.I.; Till, C.E.

1991-01-01T23:59:59.000Z

91

2013 Fuel Cycle Technologies Annual Review MeetingTransactions Report  

SciTech Connect (OSTI)

The Fuel Cycle Technologies (FCT) program of the Department of Energy (DOE) Office of Nuclear Energy (NE) is charged with identifying promising sustainable fuel cycles and developing strategies for effective disposition of used fuel and high-level nuclear waste, enabling policymakers to make informed decisions about these critical issues. Sustainable fuel cycles will improve uranium resource utilization, maximize energy generation while minimizing waste, improve safety, and limit proliferation risk. To achieve its mission, FCT has initiated numerous activities in each of the technical campaign areas, of which this report provides a sample.

Not Listed

2013-11-01T23:59:59.000Z

92

FULL FUEL CYCLE ASSESSMENT WELL TO WHEELS ENERGY INPUTS,  

E-Print Network [OSTI]

, greenhouse gas (GHG) emissions, criteria pollutant emissions, air toxics emissions, and multimedia impacts on a full fuel cycle basis for alternative-fueled vehicles is important when assessing the overall control, and assumptions regarding feedstock sources and fuel production conversion efficiency

93

Nuclear fuel cycle facility accident analysis handbook  

SciTech Connect (OSTI)

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

94

Fuel Cycle System Analysis Implications of Sodium-Cooled Metal-Fueled Fast Reactor Transuranic Conversion Ratio  

SciTech Connect (OSTI)

If advanced fuel cycles are to include a large number of fast reactors (FRs), what should be the transuranic (TRU) conversion ratio (CR)? The nuclear energy era started with the assumption that they should be breeder reactors (CR > 1), but the full range of possible CRs eventually received attention. For example, during the recent U.S. Global Nuclear Energy Partnership program, the proposal was burner reactors (CR < 1). Yet, more recently, Massachusetts Institute of Technology's "Future of the Nuclear Fuel Cycle" proposed CR [approximately] 1. Meanwhile, the French company EDF remains focused on breeders. At least one of the reasons for the differences of approach is different fuel cycle objectives. To clarify matters, this paper analyzes the impact of TRU CR on many parameters relevant to fuel cycle systems and therefore spans a broad range of topic areas. The analyses are based on a FR physics parameter scan of TRU CR from 0 to [approximately]1.8 in a sodium-cooled metal-fueled FR (SMFR), in which the fuel from uranium-oxide-fueled light water reactors (LWRs) is recycled directly to FRs and FRs displace LWRs in the fleet. In this instance, the FRs are sodium cooled and metal fueled. Generally, it is assumed that all TRU elements are recycled, which maximizes uranium ore utilization for a given TRU CR and waste radiotoxicity reduction and is consistent with the assumption of used metal fuel separated by electrochemical means. In these analyses, the fuel burnup was constrained by imposing a neutron fluence limit to fuel cladding to the same constant value. This paper first presents static, time-independent measures of performance for the LWR [right arrow] FR fuel cycle, including mass, heat, gamma emission, radiotoxicity, and the two figures of merit for materials for weapon attractiveness developed by C. Bathke et al. No new fuel cycle will achieve a static equilibrium in the foreseeable future. Therefore, additional analyses are shown with dynamic, time-dependent measures of performance including uranium usage, TRU inventory, and radiotoxicity to evaluate the complex impacts of transition from the current uranium-fueled LWR system, and other more realistic impacts that may not be intuited from the time-independent steady-state conditions of the end-state fuel cycle. These analyses were performed using the Verifiable Fuel Cycle Simulation Model VISION. Compared with static calculations, dynamic results paint a different picture of option space and the urgency of starting a FR fleet. For example, in a static analysis, there is a sharp increase in uranium utilization as CR exceeds 1.0 (burner versus breeder). However, in dynamic analyses that examine uranium use over the next 1 to 2 centuries, behavior as CR crosses the 1.0 threshold is smooth, and other parameters such as the time required outside of reactors to recycle fuel become important. Overall, we find that there is no unambiguously superior value of TRU CR; preferences depend on the relative importance of different fuel cycle system objectives.

Steven J. Piet; Edward A. Hoffman; Samuel E. Bays; Gretchen E. Matthern; Jacob J. Jacobson; Ryan Clement; David W. Gerts

2013-03-01T23:59:59.000Z

95

Technology Insights and Perspectives for Nuclear Fuel Cycle Concepts  

SciTech Connect (OSTI)

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

96

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

E-Print Network [OSTI]

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

Gonzalez, Vanessa L

2012-06-07T23:59:59.000Z

97

The Northeast heating fuel market: Assessment and options  

SciTech Connect (OSTI)

In response to a Presidential request, this study examines how the distillate fuel oil market (and related energy markets) in the Northeast behaved in the winter of 1999-2000, explains the role played by residential, commercial, industrial, and electricity generation sector consumers in distillate fuel oil markets and describes how that role is influenced by the structure of tie energy markets in the Northeast. In addition, this report explores the potential for nonresidential users to move away from distillate fuel oil and how this might impact future prices, and discusses conversion of distillate fuel oil users to other fuels over the next 5 years. Because the President's and Secretary's request focused on converting factories and other large-volume users of mostly high-sulfur distillate fuel oil to other fuels, transportation sector use of low-sulfur distillate fuel oil is not examined here.

None

2000-07-01T23:59:59.000Z

98

High efficiency carbonate fuel cell/turbine hybrid power cycle  

SciTech Connect (OSTI)

The hybrid power cycle studies were conducted to identify a high efficiency, economically competitive system. A hybrid power cycle which generates power at an LHV efficiency > 70% was identified that includes an atmospheric pressure direct carbonate fuel cell, a gas turbine, and a steam cycle. In this cycle, natural gas fuel is mixed with recycled fuel cell anode exhaust, providing water for reforming fuel. The mixed gas then flows to a direct carbonate fuel cell which generates about 70% of the power. The portion of the anode exhaust which is not recycled is burned and heat transferred through a heat exchanger (HX) to the compressed air from a gas turbine. The heated compressed air is then heated further in the gas turbine burner and expands through the turbine generating 15% of the power. Half the exhaust from the turbine provides air for the anode exhaust burner. All of the turbine exhaust eventually flows through the fuel cell cathodes providing the O2 and CO2 needed in the electrochemical reaction. Exhaust from the cathodes flows to a steam system (heat recovery steam generator, staged steam turbine generating 15% of the cycle power). Simulation of a 200 MW plant with a hybrid power cycle had an LHV efficiency of 72.6%. Power output and efficiency are insensitive to ambient temperature, compared to a gas turbine combined cycle; NOx emissions are 75% lower. Estimated cost of electricity for 200 MW is 46 mills/kWh, which is competitive with combined cycle where fuel cost is > $5.8/MMBTU. Key requirement is HX; in the 200 MW plant studies, a HX operating at 1094 C using high temperature HX technology currently under development by METC for coal gassifiers was assumed. A study of a near term (20 MW) high efficiency direct carbonate fuel cell/turbine hybrid power cycle has also been completed.

Steinfeld, G.; Maru, H.C. [Energy Research Corp., Danbury, CT (United States); Sanderson, R.A. [Sanderson (Robert) and Associates, Wethersfield, CT (United States)

1996-07-01T23:59:59.000Z

99

Life Cycle Assessment of Automobile/Fuel Options  

Science Journals Connector (OSTI)

Assuming that the demand response is proportional to price, this experience suggests that a further tripling of price would be required to induce drivers to choose a vehicle mix that averaged 4.7 L/100 km (50 mpg). ...

Heather L. MacLean; Lester B. Lave

2003-10-22T23:59:59.000Z

100

Nuclear Fuel Cycle and Waste Management Technologies - Nuclear Engineering  

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

Note: This page contains sample records for the topic "fuel cycle options" 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

FULL FUEL CYCLE ASSESSMENT TANK TO WHEELS EMISSIONS  

E-Print Network [OSTI]

FULL FUEL CYCLE ASSESSMENT TANK TO WHEELS EMISSIONS AND ENERGY CONSUMPTION Prepared For: California to Tank, Criteria Pollutants, Multi-media impacts, EMFAC #12;#12;vii Table of Contents Acknowledgements

102

Drive Cycle Analysis, Measurement of Emissions and Fuel Consumption...  

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

Drive Cycle Analysis, Measurement of Emissions and Fuel Consumption of a PHEV School Bus Preprint Robb Barnitt and Jeff Gonder To be presented at the SAE 2011 World Congress...

103

Summary and recommendations: Total fuel cycle assessment workshop  

SciTech Connect (OSTI)

This report summarizes the activities of the Total Fuel Cycle Assessment Workshop held in Austin, Texas, during October 6--7, 1994. It also contains the proceedings from that workshop.

NONE

1995-08-01T23:59:59.000Z

104

Summary of Off-Normal Events in US Fuel Cycle Facilities for AFCI Applications  

SciTech Connect (OSTI)

This report is a collection and review of system operation and failure experiences for facilities comprising the fission reactor fuel cycle, with the exception of reactor operations. This report includes mines, mills, conversion plants, enrichment plants, fuel fabrication plants, transportation of fuel materials between these centers, and waste storage facilities. Some of the facilities discussed are no longer operating; others continue to produce fuel for the commercial fission power plant industry. Some of the facilities discussed have been part of the military’s nuclear effort; these are included when the processes used are similar to those used for commercial nuclear power. When reading compilations of incidents and accidents, after repeated entries it is natural to form an opinion that there exists nothing but accidents. For this reason, production or throughput values are described when available. These adverse operating experiences are compiled to support the design and decisions needed for the Advanced Fuel Cycle Initiative (AFCI). The AFCI is to weigh options for a new fission reactor fuel cycle that is efficient, safe, and productive for US energy security.

L. C. Cadwallader; S. J. Piet; S. O. Sheetz; D. H. McGuire; W. B. Boore

2005-09-01T23:59:59.000Z

105

Life Cycle Regulation of Transportation Fuels: Uncertainty and its Policy Implications  

E-Print Network [OSTI]

radiative forcing from bio- fuel and gasoline GHG emissions,directly to additional bio- fuel feedstocks. The averagelife cycle GHGs from bio- fuels highlights the limitations

Plevin, Richard Jay

2010-01-01T23:59:59.000Z

106

Overview of Options to Integrate Stationary Power Generation from Fuel Cells with  

E-Print Network [OSTI]

;3 Alternate Fuel Infrastructure Lessons Learned Project ·Project with NREL ·Workshop held in April 2008 Municipalities and Local government agencies Fire and Rescue facilities Policy stations Data centers Universities1 Overview of Options to Integrate Stationary Power Generation from Fuel Cells with Hydrogen Demand

107

International Nuclear Fuel Cycle Fact Book. Revision 5  

SciTech Connect (OSTI)

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

108

International nuclear fuel cycle fact book. Revision 4  

SciTech Connect (OSTI)

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

109

Fuel Cycle Comparison for Distributed Power Technologies  

Fuel Cell Technologies Publication and Product Library (EERE)

This report examines backup power and prime power systems and addresses the potential energy and environmental effects of substituting fuel cells for existing combustion technologies based on microtur

110

Wood energy fuel cycle optimization in beech and spruce forests  

Science Journals Connector (OSTI)

A novel synergistic approach to reducing emissions from residential wood combustion (RWC) is presented. Wood energy fuel cycle optimization (FCO) aims to provide cleaner burning fuels through optimization of forestry and renewable energy management practices. In this work, beech and spruce forests of average and high quality were modelled and analysed to determine the volume of fuel wood and its associated bark fraction produced during typical forestry cycles. Two separate fuel wood bark production regimes were observed for beech trees, while only one production regime was observed for spruce. The single tree and stand models were combined with existing thinning parameters to replicate existing management practices. Utilizing estimates of initial seedling numbers and existing thinning patterns a dynamic model was formed that responded to changes in thinning practices. By varying the thinning parameters, this model enabled optimization of the forestry practices for the reduction of bark impurities in the fuel wood supply chain. Beech forestry cycles responded well to fuel cycle optimization with volume reductions of bark from fuel wood of between ~10% and ~20% for average and high quality forest stands. Spruce, on the other hand, was fairly insensitive to FCO with bark reductions of 0–5%. The responsiveness of beech to FCO further supports its status as the preferred RWC fuel in Switzerland. FCO could easily be extended beyond Switzerland and applied across continental Europe and North America.

Nickolas K Meyer; Marco Mina

2012-01-01T23:59:59.000Z

111

CO2 Offset Options: Comparative Assessment of Terrestial Sinks vs. Natural Gas Combined Cycle  

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

W. South (south@energyresources.com; 202-785-8833) W. South (south@energyresources.com; 202-785-8833) Energy Resources International, Inc. 1015 18 th Street, N.W., Suite 650 Washington, DC 20036 CO 2 Offset Options: Comparative Assessment of Terrestial Sinks vs. Natural Gas Combined Cycle 1 Abstract This study compares the economic value of two CO 2 mitigation actions: terrestrial reforestation to sequester CO 2 emitted from coal-fired power generation versus natural gas combined cycle (NGCC) power generation to avoid (minimize) CO 2 release. The same quantity of carbon offset was assumed for both actions. Tree stock growth, carbon absorption/release cycles, and replanting were considered to maintain the quantity of carbon offset via reforestation. The study identified important parameters with both CO 2 mitigation options that should be considered when examining alternative strategies.

112

Fuel Cycle Research and Development Presentation Title  

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

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

113

World nuclear capacity and fuel cycle requirements, November 1993  

SciTech Connect (OSTI)

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

114

2012 Fuel Cycle Technologies Annual Review Meeting Transaction Report |  

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

Fuel Cycle Technologies Annual Review Meeting Transaction Fuel Cycle Technologies Annual Review Meeting Transaction Report 2012 Fuel Cycle Technologies Annual Review Meeting Transaction Report 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. In order to continue or expand the role for nuclear power in our long- term energy platform, the United States must: Continually improve the safety and security of nuclear energy and its associated technologies worldwide. Develop solutions for the transportation, storage, and long-term disposal of used nuclear fuel and associated wastes.

115

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:

116

Fuel cycle comparison of distributed power generation technologies.  

SciTech Connect (OSTI)

The fuel-cycle energy use and greenhouse gas (GHG) emissions associated with the application of fuel cells to distributed power generation were evaluated and compared with the combustion technologies of microturbines and internal combustion engines, as well as the various technologies associated with grid-electricity generation in the United States and California. The results were primarily impacted by the net electrical efficiency of the power generation technologies and the type of employed fuels. The energy use and GHG emissions associated with the electric power generation represented the majority of the total energy use of the fuel cycle and emissions for all generation pathways. Fuel cell technologies exhibited lower GHG emissions than those associated with the U.S. grid electricity and other combustion technologies. The higher-efficiency fuel cells, such as the solid oxide fuel cell (SOFC) and molten carbonate fuel cell (MCFC), exhibited lower energy requirements than those for combustion generators. The dependence of all natural-gas-based technologies on petroleum oil was lower than that of internal combustion engines using petroleum fuels. Most fuel cell technologies approaching or exceeding the DOE target efficiency of 40% offered significant reduction in energy use and GHG emissions.

Elgowainy, A.; Wang, M. Q.; Energy Systems

2008-12-08T23:59:59.000Z

117

SAFEGUARDS EXPERIENCE ON THE DUPIC FUEL CYCLE PROCESS  

SciTech Connect (OSTI)

Safeguards have been applied to the R and D process for directly fabricating CANDU fuel with PWR spent fuel material. Safeguards issues to be resolved were identified in the areas such as international cooperation on handling foreign origin nuclear material, technology development of operator's measurement system of the bulk handling process of spent fuel material, and a built-in C/S system for independent verification of material flow. The fuel cycle concept (Direct Use of PWR spent fuel in CANDU, DUPIC) was developed in consideration of reutilization of over-flowing spent fuel resources at PWR sites and a reduction of generated high level wastes. All those safeguards issues have been finally resolved, and the first batch of PWR spent fuel material was successfully introduced in the DUPIC lab facility and has been in use for routine process development.

J. HONG; H. KIM; ET AL

2001-02-01T23:59:59.000Z

118

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

119

The Decline of Fuel Taxes and New Transportation Funding Options  

E-Print Network [OSTI]

). Regardless of the original intent, fuel taxes expanded on the paradigm shift introduced by tolling by creating a system that effectively correlated vehicle usage to tax collected, all while driving down collection costs. In 1932, a federal gas tax of 1... cent was introduced (Tax Foundation, 2012). However, unlike state fuel taxes, which were earmarked for road projects, the federal gas tax was credited to the federal government’s general fund, where congressional lawmakers could divert this revenue...

Manning, Kevin M.

2012-12-14T23:59:59.000Z

120

New developments and prospects on COSI, the simulation software for fuel cycle analysis  

SciTech Connect (OSTI)

COSI, software developed by the Nuclear Energy Direction of the CEA, is a code simulating a pool of nuclear power plants with its associated fuel cycle facilities. This code has been designed to study various short, medium and long term options for the introduction of various types of nuclear reactors and for the use of associated nuclear materials. In the frame of the French Act for waste management, scenario studies are carried out with COSI, to compare different options of evolution of the French reactor fleet and options of partitioning and transmutation of plutonium and minor actinides. Those studies aim in particular at evaluating the sustainability of Sodium cooled Fast Reactors (SFR) deployment and the possibility to transmute minor actinides. The COSI6 version is a completely renewed software released in 2006. COSI6 is now coupled with the last version of CESAR (CESAR5.3 based on JEFF3.1.1 nuclear data) allowing the calculations on irradiated fuel with 200 fission products and 100 heavy nuclides. A new release is planned in 2013, including in particular the coupling with a recommended database of reactors. An exercise of validation of COSI6, carried out on the French PWR historic nuclear fleet, has been performed. During this exercise quantities like cumulative natural uranium consumption, or cumulative depleted uranium, or UOX/MOX spent fuel storage, or stocks of reprocessed uranium, or plutonium content in fresh MOX fuel, or the annual production of high level waste, have been computed by COSI6 and compared to industrial data. The results have allowed us to validate the essential phases of the fuel cycle computation, and reinforces the credibility of the results provided by the code.

Eschbach, R.; Meyer, M.; Coquelet-Pascal, C.; Tiphine, M.; Krivtchik, G.; Cany, C. [Atomic Energy and Alternative Energies Commission - CEA, CEA-Cadarache, DEN, DER, SPRC, F-13108 Saint-Paul-lez-Durance (France)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

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

SciTech Connect (OSTI)

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

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

1998-10-01T23:59:59.000Z

122

Reactor Physics and Fuel Cycle Analysis - Nuclear Engineering Division  

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

123

2011 Fuel Cycle Technologies Annual Review Meeting | Department of Energy  

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

1 Fuel Cycle Technologies Annual Review Meeting 1 Fuel Cycle Technologies Annual Review Meeting 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. To support nuclear energy's continued and expanded role in our energy platform, therefore, the United States must continually improve its knowledge, technology, and policy in order to:

124

International nuclear fuel cycle fact book. [Contains glossary  

SciTech Connect (OSTI)

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

125

International Nuclear Fuel Cycle Fact Book. Revision 12  

SciTech Connect (OSTI)

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

126

Software Platform Evaluation - Verifiable Fuel Cycle Simulation (VISION) Model  

SciTech Connect (OSTI)

The purpose of this Software Platform Evaluation (SPE) is to document the top-level evaluation of potential software platforms on which to construct a simulation model that satisfies the requirements for a Verifiable Fuel Cycle Simulation Model (VISION) of the Advanced Fuel Cycle (AFC). See the Software Requirements Specification for Verifiable Fuel Cycle Simulation (VISION) Model (INEEL/EXT-05-02643, Rev. 0) for a discussion of the objective and scope of the VISION model. VISION is intended to serve as a broad systems analysis and study tool applicable to work conducted as part of the AFCI (including costs estimates) and Generation IV reactor development studies. This document will serve as a guide for selecting the most appropriate software platform for VISION. This is a “living document” that will be modified over the course of the execution of this work.

J. J. Jacobson; D. E. Shropshire; W. B. West

2005-11-01T23:59:59.000Z

127

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

128

Fossil fuel combined cycle power generation method  

DOE Patents [OSTI]

A method for converting fuel energy to electricity includes the steps of converting a higher molecular weight gas into at least one mixed gas stream of lower average molecular weight including at least a first lower molecular weight gas and a second gas, the first and second gases being different gases, wherein the first lower molecular weight gas comprises H.sub.2 and the second gas comprises CO. The mixed gas is supplied to at least one turbine to produce electricity. The mixed gas stream is divided after the turbine into a first gas stream mainly comprising H.sub.2 and a second gas stream mainly comprising CO. The first and second gas streams are then electrochemically oxidized in separate fuel cells to produce electricity. A nuclear reactor can be used to supply at least a portion of the heat the required for the chemical conversion process.

Labinov, Solomon D [Knoxville, TN; Armstrong, Timothy R [Clinton, TN; Judkins, Roddie R [Knoxville, TN

2008-10-21T23:59:59.000Z

129

Fuel Life-Cycle Analysis of Hydrogen vs. Conventional Transportation Fuels.  

E-Print Network [OSTI]

??Fuel life-cycle analyses were performed to compare the affects of hydrogen on annual U.S. light-duty transportation emissions in future year 2030. Five scenarios were developed… (more)

DeGolyer, Jessica Suzanne

2008-01-01T23:59:59.000Z

130

Description of Transmutation Library for Fuel Cycle System Analyses  

SciTech Connect (OSTI)

This report documents the Transmutation Library that is used in Fuel Cycle System Analyses. This version replaces the 2008 version.[Piet2008] The Transmutation Library has the following objectives: • Assemble past and future transmutation cases for system analyses. • For each case, assemble descriptive information such as where the case was documented, the purpose of the calculation, the codes used, source of feed material, transmutation parameters, and the name of files that contain raw or source data. • Group chemical elements so that masses in separation and waste processes as calculated in dynamic simulations or spreadsheets reflect current thinking of those processes. For example, the CsSr waste form option actually includes all Group 1A and 2A elements. • Provide mass fractions at input (charge) and output (discharge) for each case. • Eliminate the need for either “fission product other” or “actinide other” while conserving mass. Assessments of waste and separation cannot use “fission product other” or “actinide other” as their chemical behavior is undefined. • Catalog other isotope-specific information in one place, e.g., heat and dose conversion factors for individual isotopes. • Describe the correlations for how input and output compositions change as a function of UOX burnup (for LWR UOX fuel) or fast reactor (FR) transuranic (TRU) conversion ratio (CR) for either FR-metal or FR-oxide. This document therefore includes the following sections: • Explanation of the data set information, i.e., the data that describes each case. In no case are all of the data presented in the Library included in previous documents. In assembling the Library, we return to raw data files to extract the case and isotopic data, into the specified format. • Explanation of which isotopes and elements are tracked. For example, the transition metals are tracked via the following: two Zr isotopes, Zr-other, Tc99, Tc-other, two Mo-Ru-Rh-Pd isotopes, Mo-Ru-Rh-Pd-other, four other specific TM isotopes, and TM-other. Mo-Ru-Rh-Pd are separated because their content constrains the loading of waste in glass, so we have to know the mass of those elements independent of others. • Rules for collapsing long lists of isotopes (~1000) to the 81 items in the library. For each tracked isotope, we define which short-lived isotopes’ mass (at t=0) is included with the mass of the tracked isotope at t=0, which short-lived radioactive progeny must be accounted for when the tracked isotope decays, and to which of the other 80 items the mass of the tracked isotope goes when it decays. • Explanation of where raw data files can be found on the fuel cycle data portal. • Explanation of generic cross section sets • Explanation of isotope-specific parameters such as heat and dose conversion factors • Explanation of the LWR UOX burnup and FR TRU CR correlations.

Steven J. Piet; Samuel E. Bays; Edward A. Hoffman

2010-08-01T23:59:59.000Z

131

Environmental Aspects of Advanced Nuclear Fuel Cycles: Parametric Modeling and Preliminary Analysis  

E-Print Network [OSTI]

........................................................... 10 2 Simplified schematic of the once-through open fuel cycle .................................. 12 3 Simplified schematic of the plutonium-burning fuel cycle .................................. 13 4 Simplified schematic of the actinide... ..................................................... 23 7 Material flow for the plutonium-burning fuel cycle, year 0 ................................. 24 8 Material flow for the plutonium-burning fuel cycle, year 40 ............................... 25 9 Material flow for the actinide-burning fuel...

Yancey, Kristina D.

2010-07-14T23:59:59.000Z

132

Life-cycle analysis of alternative aviation fuels in GREET  

SciTech Connect (OSTI)

The Greenhouse gases, Regulated Emissions, and Energy use in Transportation (GREET) model, developed at Argonne National Laboratory, has been expanded to include well-to-wake (WTWa) analysis of aviation fuels and aircraft. This report documents the key WTWa stages and assumptions for fuels that represent alternatives to petroleum jet fuel. The aviation module in GREET consists of three spreadsheets that present detailed characterizations of well-to-pump and pump-to-wake parameters and WTWa results. By using the expanded GREET version (GREET1{_}2011), we estimate WTWa results for energy use (total, fossil, and petroleum energy) and greenhouse gas (GHG) emissions (carbon dioxide, methane, and nitrous oxide) for (1) each unit of energy (lower heating value) consumed by the aircraft or (2) each unit of distance traveled/ payload carried by the aircraft. The fuel pathways considered in this analysis include petroleum-based jet fuel from conventional and unconventional sources (i.e., oil sands); Fisher-Tropsch (FT) jet fuel from natural gas, coal, and biomass; bio-jet fuel from fast pyrolysis of cellulosic biomass; and bio-jet fuel from vegetable and algal oils, which falls under the American Society for Testing and Materials category of hydroprocessed esters and fatty acids. For aircraft operation, we considered six passenger aircraft classes and four freight aircraft classes in this analysis. Our analysis revealed that, depending on the feedstock source, the fuel conversion technology, and the allocation or displacement credit methodology applied to co-products, alternative bio-jet fuel pathways have the potential to reduce life-cycle GHG emissions by 55-85 percent compared with conventional (petroleum-based) jet fuel. Although producing FT jet fuel from fossil feedstock sources - such as natural gas and coal - could greatly reduce dependence on crude oil, production from such sources (especially coal) produces greater WTWa GHG emissions compared with petroleum jet fuel production unless carbon management practices, such as carbon capture and storage, are used.

Elgowainy, A.; Han, J.; Wang, M.; Carter, N.; Stratton, R.; Hileman, J.; Malwitz, A.; Balasubramanian, S. (Energy Systems)

2012-07-23T23:59:59.000Z

133

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

SciTech Connect (OSTI)

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

Williams, K.A.

1999-10-01T23:59:59.000Z

134

Changing Biomass, Fossil, and Nuclear Fuel Cycles for Sustainability  

SciTech Connect (OSTI)

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

135

13 - Generation IV reactor designs, operation and fuel cycle  

Science Journals Connector (OSTI)

Abstract: This chapter looks at Generation IV nuclear reactors, such as the very high-temperature reactor (VHTR), the supercritical water reactor (SCWR), the molten salt reactor (MSR), the sodium-cooled fast reactor (SFR), the lead-cooled fast reactor (LFR) and the gas-cooled fast reactor (GFR). Reactor designs and fuel cycles are also described.

N. Cerullo; G. Lomonaco

2012-01-01T23:59:59.000Z

136

LMFBR operation in the nuclear cycle without fuel reprocessing  

SciTech Connect (OSTI)

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

137

FULL FUEL CYCLE ASSESSMENT WELL TO TANK ENERGY INPUTS,  

E-Print Network [OSTI]

FULL FUEL CYCLE ASSESSMENT WELL TO TANK ENERGY INPUTS, EMISSIONS, AND WATER IMPACTS Prepared For be divided into two parts: · Well-to-Tank (WTT) Feedstock extraction, transport, storage, processing, distribution, transport, and storage · Tank-to-Wheels (TTW) Refueling, consumption and evaporation The full

138

Estimating Externalities of Hydro Fuel Cycles, Report 6  

SciTech Connect (OSTI)

There are three major objectives of this hydropower study: (1) to implement the methodological concepts that were developed in the background document (ORNL/RFF 1992) as a means of estimating the external costs and benefits of fuel cycles and, by so doing, to demonstrate their application to the hydroelectric fuel cycle (different fuel cycles have unique characteristics that need to be addressed in different ways); (2) to develop, given the time and resources, the best range of estimates of externalities associated with hydroelectric projects, using two benchmark projects at two reference sites in the US; and (3) to assess the state of the information that is available to support the estimation of externalities associated with the hydroelectric fuel cycle and, by so doing, to assist in identifying gaps in knowledge and in setting future research agendas. The main consideration in defining these objectives was a desire to have more information about externalities and a better method for estimating them. As set forth in the agreement between the US and the EC, the study is explicitly and intentionally not directed at any one audience. This study is about a methodology for estimating externalities. It is not about how to use estimates of externalities in a particular policy context.

Barnthouse, L.W.; Cada, G.F.; Cheng, M.-D.; Easterly, C.E.; Kroodsma, R.L.; Lee, R.; Shriner, D.S.; Tolbert, V.R.; Turner, R.S.

1994-12-01T23:59:59.000Z

139

Transmutation Dynamics: Impacts of Multi-Recycling on Fuel Cycle Performances  

SciTech Connect (OSTI)

From a physics standpoint, it is feasible to sustain continuous multi-recycle in either thermal or fast reactors. In Fiscal Year 2009, transmutaton work at INL provided important new insight, caveats, and tools on multi-recycle. Multi-recycle of MOX, even with all the transuranics, is possible provided continuous enrichment of the uranium phase to ~6.5% and also limitting the transuranic enrichment to slightly less than 8%. Multi-recycle of heterogeneous-IMF assemblies is possible with continuous enrichment of the UOX pins to ~4.95% and having =60 of the 264 fuel pins being inter-matrix. A new tool enables quick assessment of the impact of different cooling times on isotopic evolution. The effect of cooling time was found to be almost as controlling on higher mass actinide concentrations in fuel as the selection of thermal versus fast neutron spectra. A new dataset was built which provides on-the-fly estimates of gamma and neutron dose in MOX fuels as a function of the isotopic evolution. All studies this year focused on the impact of dynamic feedback due to choices made in option space. Both the equilibrium fuel cycle concentrations and the transient time to reach equilibrium for each isotope were evaluated over a range of reactor, reprocessing and cooling time combinations. New bounding cases and analysis methods for evaluating both reactor safety and radiation worker safety were established. This holistic collection of physics analyses and methods gives improved resolution of fuel cycle options, and impacts thereof, over that of previous ad-hoc and single-point analyses.

S. Bays; S. Piet; M. Pope; G. Youinou; A. Dumontier; D. Hawn

2009-09-01T23:59:59.000Z

140

Estimating Externalities of Natural Gas Fuel Cycles, Report 4  

SciTech Connect (OSTI)

This report describes methods for estimating the external costs (and possibly benefits) to human health and the environment that result from natural gas fuel cycles. Although the concept of externalities is far from simple or precise, it generally refers to effects on individuals' well being, that result from a production or market activity in which the individuals do not participate, or are not fully compensated. In the past two years, the methodological approach that this report describes has quickly become a worldwide standard for estimating externalities of fuel cycles. The approach is generally applicable to any fuel cycle in which a resource, such as coal, hydro, or biomass, is used to generate electric power. This particular report focuses on the production activities, pollution, and impacts when natural gas is used to generate electric power. In the 1990s, natural gas technologies have become, in many countries, the least expensive to build and operate. The scope of this report is on how to estimate the value of externalities--where value is defined as individuals' willingness to pay for beneficial effects, or to avoid undesirable ones. This report is about the methodologies to estimate these externalities, not about how to internalize them through regulations or other public policies. Notwithstanding this limit in scope, consideration of externalities can not be done without considering regulatory, insurance, and other considerations because these institutional factors affect whether costs (and benefits) are in fact external, or whether they are already somehow internalized within the electric power market. Although this report considers such factors to some extent, much analysis yet remains to assess the extent to which estimated costs are indeed external. This report is one of a series of reports on estimating the externalities of fuel cycles. The other reports are on the coal, oil, biomass, hydro, and nuclear fuel cycles, and on general methodology.

Barnthouse, L.W.; Cada, G.F.; Cheng, M.-D.; Easterly, C.E.; Kroodsma, R.L.; Lee, R.; Shriner, D.S.; Tolbert, V.R.; Turner, R.S.

1998-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

Moving toward multilateral mechanisms for the fuel cycle  

SciTech Connect (OSTI)

Multilateral mechanisms for the fuel cycle are seen as a potentially important way to create an industrial infrastructure that will support a renaissance and at the same time not contribute to the risk of nuclear proliferation. In this way, international nuclear fuel cycle centers for enrichment can help to provide an assurance of supply of nuclear fuel that will reduce the likelihood that individual states will pursue this sensitive technology, which can be used to produce nuclear material directly usable nuclear weapons. Multinational participation in such mechanisms can also potentially promote transparency, build confidence, and make the implementation of IAEA safeguards more effective or more efficient. At the same time, it is important to ensure that there is no dissemination of sensitive technology. The Russian Federation has taken a lead role in this area by establishing an International Uranium Enrichment Center (IUEC) for the provision of enrichment services at its uranium enrichment plant located at the Angarsk Electrolysis Chemical Complex (AECC). This paper describes how the IUEe is organized, who its members are, and the steps that it has taken both to provide an assured supply of nuclear fuel and to ensure protection of sensitive technology. It also describes the relationship between the IUEC and the IAEA and steps that remain to be taken to enhance its assurance of supply. Using the IUEC as a starting point for discussion, the paper also explores more generally the ways in which features of such fuel cycle centers with multinational participation can have an impact on safeguards arrangements, transparency, and confidence-building. Issues include possible lAEA safeguards arrangements or other links to the IAEA that might be established at such fuel cycle centers, impact of location in a nuclear weapon state, and the transition by the IAEA to State Level safeguards approaches.

Panasyuk,A.; Rosenthal,M.; Efremov, G. V.

2009-04-17T23:59:59.000Z

142

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

143

Determination of the proper operating range for the CAFCA IIB fuel cycle model  

E-Print Network [OSTI]

The fuel cycle simulation tool, CAFCA II was previously modified to produce the most recent version, CAFCA IIB. The code tracks the mass distribution of transuranics in the fuel cycle in one model and also projects costs ...

Warburton, Jamie (Jamie L.)

2007-01-01T23:59:59.000Z

144

The Adoption of Advanced Fuel Cycle Technology Under a Single Repository Policy  

SciTech Connect (OSTI)

Develops the tools to investiage the hypothesis that the savings in repository space associated with the implementation of advanced nuclear fuel cycles can result in sufficient cost savings to offset the higher costs of those fuel cycles.

Paul Wilson

2009-11-02T23:59:59.000Z

145

Fuel-Cycle Energy and Emissions Analysis with the GREET Model...  

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

Fuel-Cycle Energy and Emissions Analysis with the GREET Model Fuel-Cycle Energy and Emissions Analysis with the GREET Model 2009 DOE Hydrogen Program and Vehicle Technologies...

146

User Guide for VISION 3.4.7 (Verifiable Fuel Cycle Simulation) Model  

SciTech Connect (OSTI)

The purpose of this document is to provide a guide for using the current version of the Verifiable Fuel Cycle Simulation (VISION) model. This is a complex model with many parameters and options; the user is strongly encouraged to read this user guide before attempting to run the model. This model is an R&D work in progress and may contain errors and omissions. It is based upon numerous assumptions. This model is intended to assist in evaluating 'what if' scenarios and in comparing fuel, reactor, and fuel processing alternatives at a systems level. The model is not intended as a tool for process flow and design modeling of specific facilities nor for tracking individual units of fuel or other material through the system. The model is intended to examine the interactions among the components of a fuel system as a function of time varying system parameters; this model represents a dynamic rather than steady-state approximation of the nuclear fuel system. VISION models the nuclear cycle at the system level, not individual facilities, e.g., 'reactor types' not individual reactors and 'separation types' not individual separation plants. Natural uranium can be enriched, which produces enriched uranium, which goes into fuel fabrication, and depleted uranium (DU), which goes into storage. Fuel is transformed (transmuted) in reactors and then goes into a storage buffer. Used fuel can be pulled from storage into either separation or disposal. If sent to separations, fuel is transformed (partitioned) into fuel products, recovered uranium, and various categories of waste. Recycled material is stored until used by its assigned reactor type. VISION is comprised of several Microsoft Excel input files, a Powersim Studio core, and several Microsoft Excel output files. All must be co-located in the same folder on a PC to function. You must use Powersim Studio 8 or better. We have tested VISION with the Studio 8 Expert, Executive, and Education versions. The Expert and Education versions work with the number of reactor types of 3 or less. For more reactor types, the Executive version is currently required. The input files are Excel2003 format (xls). The output files are macro-enabled Excel2007 format (xlsm). VISION 3.4 was designed with more flexibility than previous versions, which were structured for only three reactor types - LWRs that can use only uranium oxide (UOX) fuel, LWRs that can use multiple fuel types (LWR MF), and fast reactors. One could not have, for example, two types of fast reactors concurrently. The new version allows 10 reactor types and any user-defined uranium-plutonium fuel is allowed. (Thorium-based fuels can be input but several features of the model would not work.) The user identifies (by year) the primary fuel to be used for each reactor type. The user can identify for each primary fuel a contingent fuel to use if the primary fuel is not available, e.g., a reactor designated as using mixed oxide fuel (MOX) would have UOX as the contingent fuel. Another example is that a fast reactor using recycled transuranic (TRU) material can be designated as either having or not having appropriately enriched uranium oxide as a contingent fuel. Because of the need to study evolution in recycling and separation strategies, the user can now select the recycling strategy and separation technology, by year.

Jacob J. Jacobson; Robert F. Jeffers; Gretchen E. Matthern; Steven J. Piet; Wendell D. Hintze

2011-07-01T23:59:59.000Z

147

Analysis of multi-recycle thorium fuel cycles in comparison with once-through fuel cycles.  

E-Print Network [OSTI]

??The purpose of this research is to develop a methodology for a thorium fuel recycling analysis that provides results for isotopics and radio-toxicity evaluation and… (more)

Huang, Lloyd Michael

2013-01-01T23:59:59.000Z

148

VISION User Guide - VISION (Verifiable Fuel Cycle Simulation) Model  

SciTech Connect (OSTI)

The purpose of this document is to provide a guide for using the current version of the Verifiable Fuel Cycle Simulation (VISION) model. This is a complex model with many parameters; the user is strongly encouraged to read this user guide before attempting to run the model. This model is an R&D work in progress and may contain errors and omissions. It is based upon numerous assumptions. This model is intended to assist in evaluating “what if” scenarios and in comparing fuel, reactor, and fuel processing alternatives at a systems level for U.S. nuclear power. The model is not intended as a tool for process flow and design modeling of specific facilities nor for tracking individual units of fuel or other material through the system. The model is intended to examine the interactions among the components of a fuel system as a function of time varying system parameters; this model represents a dynamic rather than steady-state approximation of the nuclear fuel system. VISION models the nuclear cycle at the system level, not individual facilities, e.g., “reactor types” not individual reactors and “separation types” not individual separation plants. Natural uranium can be enriched, which produces enriched uranium, which goes into fuel fabrication, and depleted uranium (DU), which goes into storage. Fuel is transformed (transmuted) in reactors and then goes into a storage buffer. Used fuel can be pulled from storage into either separation of disposal. If sent to separations, fuel is transformed (partitioned) into fuel products, recovered uranium, and various categories of waste. Recycled material is stored until used by its assigned reactor type. Note that recovered uranium is itself often partitioned: some RU flows with recycled transuranic elements, some flows with wastes, and the rest is designated RU. RU comes out of storage if needed to correct the U/TRU ratio in new recycled fuel. Neither RU nor DU are designated as wastes. VISION is comprised of several Microsoft Excel input files, a Powersim Studio core, and several Microsoft Excel output files. All must be co-located in the same folder on a PC to function. We use Microsoft Excel 2003 and have not tested VISION with Microsoft Excel 2007. The VISION team uses both Powersim Studio 2005 and 2009 and it should work with either.

Jacob J. Jacobson; Robert F. Jeffers; Gretchen E. Matthern; Steven J. Piet; Benjamin A. Baker; Joseph Grimm

2009-08-01T23:59:59.000Z

149

Fuel Cycle Utilizing Plutonium-238 as a“Heat Spike” for Proliferation Resistance  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel Cycle

W. R. Waltz; W. L. Godfrey; A. K. Williams

150

Fuel cycles and envisioned roles of fast neutron reactors and hybrids  

SciTech Connect (OSTI)

Future innovative nuclear fuel cycles will require insuring sustainability in terms of safe operation, optimal use of resources, radioactive waste minimization and reduced risk of proliferation. The present paper introduces some basic notions and fundamental fuel cycle strategies. The simulation approach needed to evaluate the impact of the different fuel cycle alternatives will also be shortly discussed.

Salvatores, Massimo [CEA-Cadarache, DEN-Dir, Bat. 101, St-Paul-Lez-Durance 13108 (France)

2012-06-19T23:59:59.000Z

151

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

SciTech Connect (OSTI)

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

152

Strengthening the nuclear-reactor fuel cycle against proliferation  

SciTech Connect (OSTI)

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

153

Fuel cycle analysis in a thorium fueled reactor using bidirectional fuel movement : correction to report MIT-2073-1, MITNE-51  

E-Print Network [OSTI]

This report corrects an error discovered in the code used in the study "Fuel Cycle Analysis in a Thorium Fueled Reactor Using Bidirectional Fuel Movement," MIT-2073-1, MITNE-51. The results of the correction show considerable ...

Stephen, James D.

1965-01-01T23:59:59.000Z

154

Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities  

SciTech Connect (OSTI)

Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a facility, DECON requires that contaminated components either be: (1) decontaminated to restricted or unrestricted release levels or (2) packaged and shipped to an authorized disposal site. This study considers unrestricted release only. The new decommissioning criteria of July 1997 are too recent for this study to include a cost analysis of the restricted release option, which is now allowed under these new criteria. The costs of decommissioning facility components are generally estimated to be in the range of $140 to $27,000, depending on the type of component, the type and amount of radioactive contamination, the remediation options chosen, and the quantity of radioactive waste generated from decommissioning operations. Estimated costs for decommissioning the example laboratories range from $130,000 to $205,000, assuming aggressive low-level waste (LLW) volume reduction. If only minimal LLW volume reduction is employed, decommissioning costs range from $150,000 to $270,000 for these laboratories. On the basis of estimated decommissioning costs for facility components, the costs of decommissioning typical non-fuel-cycle laboratory facilities are estimated to range from about $25,000 for the decommissioning of a small room containing one or two fume hoods to more than $1 million for the decommissioning of an industrial plant containing several laboratories in which radiochemicals and sealed radioactive sources are prepared. For the reference sites of this study, the basic decommissioning alternatives are: (1) site stabilization followed by long-term care and (2) removal of the waste or contaminated soil to an authorized disposal site. Cost estimates made for decommissioning three reference sites range from about $130,000 for the removal of a contaminated drain line and hold-up tank to more than $23 million for the removal of a tailings pile that contains radioactive residue from ore-processing operations in which tin slag is processed for the recovery of rare metals. Total occupational radiation doses generally range from 0.00007 person-rem to 13 person-rem for

MC Bierschbach; DR Haffner; KJ Schneider; SM Short

2002-12-01T23:59:59.000Z

155

Software: Reactor Physics and Fuel Cycle Analysis - Nuclear Engineering  

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

156

Health and environmental impacts of the hydroelectric fuel cycle  

Science Journals Connector (OSTI)

The impacts on health and the environment and the associated damage costs caused by the hydroelectric fuel cycle are assessed in this paper. To this purpose, a large hydroelectric project along the Nestos river in northern Greece has been selected as an example. A large number of impacts have been identified. Occupational accidents, impacts on agriculture and forests, noise produced during the operation of the plant, impacts on biodiversity due to the physical presence of the dams, and alterations to the local water balance are the most important of them. The results of the analysis show that the major contributors to the damage cost of the hydroelectric fuel cycle are impacts on biodiversity and fatal occupational accidents, especially those that occur during the construction phase of the project. Nonetheless hydroelectricity is an environmentally-friendly energy source that exhibits lower damage values compared to other electricity generating technologies.

I.G. Kollas; S. Mirasgedis

2002-01-01T23:59:59.000Z

157

Estimating Externalities of Coal Fuel Cycles, Report 3  

SciTech Connect (OSTI)

The agreement between the US DOE and the EC established the specific objectives of the study: (a) to develop a methodological framework that uses existing data and models to quantify the external costs and benefits of energy; (b) to demonstrate the application of the framework to estimate the externalities of the coal, biomass, oil, natural gas, hydro, nuclear, photovoltaic, and wind fuel cycles (by agreement with the EC, the US addressed the first six of these); and (c) to identify major gaps in the availability of information to quantify impacts, damages, benefits, and externalities of fuel cycles; and to suggest priorities for future research. The main consideration in defining these objectives was a desire to have more information about externalities, and a better method for estimating them.

Barnthouse, L.W.; Cada, G.F.; Cheng, M.-D.; Easterly, C.E.; Kroodsma, R.L.; Lee, R.; Shriner, D.S.; Tolbert, V.R.; Turner, R.S.

1994-09-01T23:59:59.000Z

158

Fuel Cycle Technologies Annual Review Meeting Transactions Report  

SciTech Connect (OSTI)

The Fuel Cycle Technologies (FCT) program supports the Department of Energy’s (DOE’s) mission to: “Enhance U.S. security and economic growth through transformative science, technology innovation, and market solutions to meet our energy, nuclear security, and environmental challenges.” Goal 1 of DOE’s Strategic Plan is to innovate energy technologies that enhance U.S. economic growth and job creation, energy security, and environmental quality. FCT does this by investing in advanced technologies that could transform the nuclear fuel cycle in the decades to come. Goal 2 of DOE’s Strategic Plan is to strengthen national security by strengthening key science, technology, and engineering capabilities. FCT does this by working closely with the National Nuclear Security Administration and the U.S Department of State to develop advanced technologies that support the Nation’s nuclear nonproliferation goals.

Lori Braase; W. Edgar May

2014-11-01T23:59:59.000Z

159

Full Fuel-Cycle Comparison of Forklift Propulsion Systems  

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

Full Fuel-Cycle Comparison Full Fuel-Cycle Comparison of Forklift Propulsion Systems ANL/ESD/08-3 Energy Systems Division Availability of This Report This report is available, at no cost, at http://www.osti.gov/bridge. It is also available on paper to the U.S. Department of Energy and its contractors, for a processing fee, from: U.S. Department of Energy Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 phone (865) 576-8401 fax (865) 576-5728 reports@adonis.osti.gov Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor UChicago Argonne, LLC, nor any of their employees or officers, makes any warranty, express

160

Generation-IV Roadmap Report of the Fuel Cycle Crosscut Group | Department  

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

Generation-IV Roadmap Report of the Fuel Cycle Crosscut Group Generation-IV Roadmap Report of the Fuel Cycle Crosscut Group Generation-IV Roadmap Report of the Fuel Cycle Crosscut Group The Charter of the Generation IV Roadmap Fuel Cycle Crosscut Group (FCCG) is to (1) examine the fuel cycle implications for alternative nuclear power scenarios in terms of Generation IV goals and (2) identify key fuel cycle issues associated with Generation IV goals. This included examination of "fuel resource inputs and waste outputs for the range of potential Generation IV fuel cycles, consistent with projected energy demand scenarios." This report summarizes the results of the studies. The membership of the FCCG comprised 8 US members and 7 members from Generation IV International Forum (GIF) countries including members from

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161

Development of a nuclear fuel cycle transparency framework.  

SciTech Connect (OSTI)

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

162

A Non-Proliferating Fuel Cycle: No Enrichment, Reprocessing or Accessible Spent Fuel - 12375  

SciTech Connect (OSTI)

Current fuel cycles offer a number of opportunities for access to plutonium, opportunities to create highly enriched uranium and access highly radioactive wastes to create nuclear weapons and 'dirty' bombs. The non-proliferating fuel cycle however eliminates or reduces such opportunities and access by eliminating the mining, milling and enrichment of uranium. The non-proliferating fuel cycle also reduces the production of plutonium per unit of energy created, eliminates reprocessing and the separation of plutonium from the spent fuel and the creation of a stream of high-level waste. It further simplifies the search for land based deep geologic repositories and interim storage sites for spent fuel in the USA by disposing of the spent fuel in deep sub-seabed sediments after storing the spent fuel at U.S. Navy Nuclear Shipyards that have the space and all of the necessary equipment and security already in place. The non-proliferating fuel cycle also reduces transportation risks by utilizing barges for the collection of spent fuel and transport to the Navy shipyards and specially designed ships to take the spent fuel to designated disposal sites at sea and to dispose of them there in deep sub-seabed sediments. Disposal in the sub-seabed sediments practically eliminates human intrusion. Potential disposal sites include Great Meteor East and Southern Nares Abyssal Plain. Such sites then could easily become international disposal sites since they occur in the open ocean. It also reduces the level of human exposure in case of failure because of the large physical and chemical dilution and the elimination of a major pathway to man-seawater is not potable. Of course, the recovery of uranium from sea water and the disposal of spent fuel in sub-seabed sediments must be proven on an industrial scale. All other technologies are already operating on an industrial scale. If externalities, such as reduced terrorist threats, environmental damage (including embedded emissions), long term care, reduced access to 'dirty' bomb materials, the social and political costs of siting new facilities and the psychological impact of no solution to the nuclear waste problem, were taken into account, the costs would be far lower than those of the present fuel cycle. (authors)

Parker, Frank L. [Vanderbilt University (United States)

2012-07-01T23:59:59.000Z

163

Nuclear Fuel Cycle Reasoner: PNNL FY13 Report  

SciTech Connect (OSTI)

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

Estimating Fuel Cycle Externalities: Analytical Methods and Issues, Report 2  

SciTech Connect (OSTI)

The activities that produce electric power typically range from extracting and transporting a fuel, to its conversion into electric power, and finally to the disposition of residual by-products. This chain of activities is called a fuel cycle. A fuel cycle has emissions and other effects that result in unintended consequences. When these consequences affect third parties (i.e., those other than the producers and consumers of the fuel-cycle activity) in a way that is not reflected in the price of electricity, they are termed ''hidden'' social costs or externalities. They are the economic value of environmental, health and any other impacts, that the price of electricity does not reflect. How do you estimate the externalities of fuel cycles? Our previous report describes a methodological framework for doing so--called the damage function approach. This approach consists of five steps: (1) characterize the most important fuel cycle activities and their discharges, where importance is based on the expected magnitude of their externalities, (2) estimate the changes in pollutant concentrations or other effects of those activities, by modeling the dispersion and transformation of each pollutant, (3) calculate the impacts on ecosystems, human health, and any other resources of value (such as man-made structures), (4) translate the estimates of impacts into economic terms to estimate damages and benefits, and (5) assess the extent to which these damages and benefits are externalities, not reflected in the price of electricity. Each step requires a different set of equations, models and analysis. Analysts generally believe this to be the best approach for estimating externalities, but it has hardly been used! The reason is that it requires considerable analysis and calculation, and to this point in time, the necessary equations and models have not been assembled. Equally important, the process of identifying and estimating externalities leads to a number of complex issues that also have not been fully addressed. This document contains two types of papers that seek to fill part of this void. Some of the papers describe analytical methods that can be applied to one of the five steps of the damage function approach. The other papers discuss some of the complex issues that arise in trying to estimate externalities. This report, the second in a series of eight reports, is part of a joint study by the U.S. Department of Energy (DOE) and the Commission of the European Communities (EC)* on the externalities of fuel cycles. Most of the papers in this report were originally written as working papers during the initial phases of this study. The papers provide descriptions of the (non-radiological) atmospheric dispersion modeling that the study uses; reviews much of the relevant literature on ecological and health effects, and on the economic valuation of those impacts; contains several papers on some of the more complex and contentious issues in estimating externalities; and describes a method for depicting the quality of scientific information that a study uses. The analytical methods and issues that this report discusses generally pertain to more than one of the fuel cycles, though not necessarily to all of them. The report is divided into six parts, each one focusing on a different subject area.

Barnthouse, L.W.; Cada, G.F.; Cheng, M.-D.; Easterly, C.E.; Kroodsma, R.L.; Lee, R.; Shriner, D.S.; Tolbert, V.R.; Turner, R.S.

1994-07-01T23:59:59.000Z

165

Assessment of bio-fuel options for solid oxide fuel cell applications.  

E-Print Network [OSTI]

??Rising concerns of inadequate petroleum supply, volatile crude oil price, and adverse environmental impacts from using fossil fuels have spurred the United States to promote… (more)

Lin, Jiefeng

2013-01-01T23:59:59.000Z

166

June 2011, Report of the Fuel Cycle Subcommittee of NEAC | Department of  

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

June 2011, Report of the Fuel Cycle Subcommittee of NEAC June 2011, Report of the Fuel Cycle Subcommittee of NEAC June 2011, Report of the Fuel Cycle Subcommittee of NEAC The Fuel Cycle subcommittee of NEAC met April 25-26 in Albuquerque, New Mexico. The main topics of discussion were the Used Nuclear Fuel (UNF) disposal program, the System Study Program's methodology that is to be used to set priorities for R&D on advanced fuel cycles, and the University Programs. In addition to these, we were briefed on the budget, but have no comments other than a hope for a good outcome and restrict ourselves to general advice until more is known. A current complication in the design of the Fuel Cycle R&D FCRD program is the Blue Ribbon Commission (BRC) which has been created to address the issues involved in long term disposal of used nuclear fuel (UNF) and any of

167

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

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

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

168

June 2011, Report of the Fuel Cycle Subcommittee of NEAC | Department of  

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

June 2011, Report of the Fuel Cycle Subcommittee of NEAC June 2011, Report of the Fuel Cycle Subcommittee of NEAC June 2011, Report of the Fuel Cycle Subcommittee of NEAC The Fuel Cycle subcommittee of NEAC met April 25-26 in Albuquerque, New Mexico. The main topics of discussion were the Used Nuclear Fuel (UNF) disposal program, the System Study Program's methodology that is to be used to set priorities for R&D on advanced fuel cycles, and the University Programs. In addition to these, we were briefed on the budget, but have no comments other than a hope for a good outcome and restrict ourselves to general advice until more is known. A current complication in the design of the Fuel Cycle R&D FCRD program is the Blue Ribbon Commission (BRC) which has been created to address the issues involved in long term disposal of used nuclear fuel (UNF) and any of

169

A framework and methodology for nuclear fuel cycle transparency.  

SciTech Connect (OSTI)

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

170

A Parametric Study of the DUPIC Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy  

SciTech Connect (OSTI)

For both pressurized water reactor (PWR) and Canada deuterium uranium (CANDU) tandem analysis, the Direct Use of spent PWR fuel In CANDU reactor (DUPIC) fuel cycle in a CANDU 6 reactor is studied using the DRAGON/DONJON chain of codes with the ENDF/B-V and ENDF/B-VI libraries. The reference feed material is a 17 x 17 French standard 900-MW(electric) PWR fuel. The PWR spent-fuel composition is obtained from two-dimensional DRAGON assembly transport and depletion calculations. After a number of years of cooling, this defines the initial fuel nuclide field in the CANDU unit cell calculations in DRAGON, where it is further depleted with the same neutron group structure. The resulting macroscopic cross sections are condensed and tabulated to be used in a full-core model of a CANDU 6 reactor to find an optimized channel fueling rate distribution on a time-average basis. Assuming equilibrium refueling conditions and a particular refueling sequence, instantaneous full-core diffusion calculations are finally performed with the DONJON code, from which both the channel power peaking factors and local parameter effects are estimated. A generic study of the DUPIC fuel cycle is carried out using the linear reactivity model for initial enrichments ranging from 3.2 to 4.5 wt% in a PWR. Because of the uneven power histories of the spent PWR assemblies, the spent PWR fuel composition is expected to differ from one assembly to the next. Uneven mixing of the powder during DUPIC fuel fabrication may lead to uncertainties in the composition of the fuel bundle and larger peaking factors in CANDU. A mixing method for reducing composition uncertainties is discussed.

Rozon, Daniel; Shen Wei [Institut de Genie Nucleaire (Canada)

2001-05-15T23:59:59.000Z

171

Overview of Options to Integrate Stationary Power Generation from Fuel Cells with Hydrogen Demand for the Transportation Sector  

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

Overview of Options to Integrate Stationary Overview of Options to Integrate Stationary Power Generation from Fuel Cells with Hydrogen Demand for the Transportation Sector Overview of Options to Integrate Stationary Overview of Options to Integrate Stationary Power Generation from Fuel Cells with Power Generation from Fuel Cells with Hydrogen Demand for the Transportation Hydrogen Demand for the Transportation Sector Sector Fred Joseck U.S. DOE Hydrogen Program Transportation and Stationary Power Integration Workshop (TSPI) Transportation and Stationary Power Transportation and Stationary Power Integration Workshop (TSPI) Integration Workshop (TSPI) Phoenix, Arizona October 27, 2008 2 Why Integration? * Move away from conventional thinking...fuel and power generation/supply separate * Make dramatic change, use economies of scale,

172

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

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

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

173

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

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

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

174

Life Cycle Assessment (LCA) of PET bottles and comparative LCA of three disposal options in Mauritius  

Science Journals Connector (OSTI)

Disposal of the increasing volume of used Polyethylene Terephthalate (PET) bottles has been a cause for concern for the Mauritian Government. To assist Government in decision-making, a study on PET bottles and its disposal was undertaken using the Life Cycle Assessment (LCA) tool. Three disposal scenarios, namely (100%) landfilling; (100%) incineration; and 50% landfilling and 50% incineration were compared. Sima Pro 5.1 software was used to analyse data and Eco-indicator 99 method was used for the impact assessment. The results showed that about 90% of the total environmental impact happened during the assembly and use phase of PET bottles. 100% incineration was found to be the most preferred option.

Rajendra Kumar Foolmaun; Toolseeram Ramjeawon

2008-01-01T23:59:59.000Z

175

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

SciTech Connect (OSTI)

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

176

Microsoft PowerPoint - 6_Rowe-Future Challenges for Global Fuel Cycle Material Accounting Final_Updated.pptx  

National Nuclear Security Administration (NNSA)

Future Challenges Future Challenges for Global Fuel Cycle Material Accounting Nathan Rowe Chris Pickett Oak Ridge National Laboratory Nuclear Materials Management & Safeguards System Users Annual Training Meeting May 20-23, 2013 St. Louis, Missouri 2 Future Challenges for Global Fuel Cycle Material Accounting Introduction * Changing Nuclear Fuel Cycle Activities * Nuclear Security Challenges * How to Respond? - Additional Protocol - State-Level Concept - Continuity of Knowledge * Conclusion 3 Future Challenges for Global Fuel Cycle Material Accounting Nuclear Fuel Cycle Source: International Atomic Energy Agency (IAEA), Nuclear Fuel Cycle Information System (NFCIS) web site IAEA Safeguards Begins Here 4 Future Challenges for Global Fuel Cycle Material Accounting Nuclear Weapons Cycle Conversion

177

Fuel cycle analysis of once-through nuclear systems.  

SciTech Connect (OSTI)

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

178

Fuel cycle modelling of open cycle thorium-fuelled nuclear energy systems  

Science Journals Connector (OSTI)

Abstract In this study, we have sought to determine the advantages, disadvantages, and viability of open cycle thorium–uranium-fuelled (Th–U-fuelled) nuclear energy systems. This has been done by assessing three such systems, each of which requires uranium enriched to ?20% 235U, in comparison to a reference uranium-fuelled (U-fuelled) system over various performance indicators, spanning material flows, waste composition, economics, and proliferation resistance. The values of these indicators were determined using the UK National Nuclear Laboratory’s fuel cycle modelling code ORION. This code required the results of lattice-physics calculations to model the neutronics of each nuclear energy system, and these were obtained using various nuclear reactor physics codes and burn-up routines. In summary, all three Th–U-fuelled nuclear energy systems required more separative work capacity than the equivalent benchmark U-fuelled system, with larger levelised fuel cycle costs and larger levelised cost of electricity. Although a reduction of ?6% in the required uranium ore per kWh was seen for one of the Th–U-fuelled systems compared to the reference U-fuelled system, the other two Th–U-fuelled systems required more uranium ore per kWh than the reference. Negligible advantages and disadvantages were observed for the amount and the properties of the spent nuclear fuel (SNF) generated by the systems considered. Two of the Th–U-fuelled systems showed some benefit in terms of proliferation resistance of the SNF generated. Overall, it appears that there is little merit in incorporating thorium into nuclear energy systems operating with open nuclear fuel cycles.

S.F. Ashley; B.A. Lindley; G.T. Parks; W.J. Nuttall; R. Gregg; K.W. Hesketh; U. Kannan; P.D. Krishnani; B. Singh; A. Thakur; M. Cowper; A. Talamo

2014-01-01T23:59:59.000Z

179

Environmental Impact of the Nuclear Fuel Cycle: Fate of Actinides  

SciTech Connect (OSTI)

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

Greenhouse Gas Emissions from the Nuclear Fuel Cycle  

SciTech Connect (OSTI)

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

Note: This page contains sample records for the topic "fuel cycle options" 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

Solar Thermochemical Fuels Production: Solar Fuels via Partial Redox Cycles with Heat Recovery  

SciTech Connect (OSTI)

HEATS Project: The University of Minnesota is developing a solar thermochemical reactor that will efficiently produce fuel from sunlight, using solar energy to produce heat to break chemical bonds. The University of Minnesota is envisioning producing the fuel by using partial redox cycles and ceria-based reactive materials. The team will achieve unprecedented solar-to-fuel conversion efficiencies of more than 10% (where current state-of-the-art efficiency is 1%) by combined efforts and innovations in material development, and reactor design with effective heat recovery mechanisms and demonstration. This new technology will allow for the effective use of vast domestic solar resources to produce precursors to synthetic fuels that could replace gasoline.

None

2011-12-19T23:59:59.000Z

182

PROTEUS - Simulation Toolset for Reactor Physics and Fuel Cycle Analysis  

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

Simulation Toolset for Simulation Toolset for Reactor Physics and Fuel Cycle Analysis PROTEUS Faster and more accurate neutronics calculations enable optimum reactor design... Argonne National Laboratory's powerful reactor physics toolset, PROTEUS, empowers users to create optimal reactor designs quickly, reliably and accurately. ...Reducing costs for designers of fast spectrum reactors. PROTEUS' long history of validation provides confidence in predictive simulations Argonne's simulation tools have more than 30 years of validation history against numerous experiments and measurements. The tools within PROTEUS work together, using the same interface files for easier integration of calculations. Multi-group Fast Reactor Cross Section Processing: MC 2 -3 No other fast spectrum multigroup generation tool

183

Life Cycle Analysis of wind–fuel cell integrated system  

Science Journals Connector (OSTI)

After ratification of the Kyoto Protocol, Canada’s Kyoto greenhouse gas (GHG) emission target is 571 Mt of CO2 equivalent emitted per year by 2010; however, if current emission trends continue, a figure of 809 Mt is projected by 2010 (Cote C. Basic of clean development mechanism—joint implementation and overview of CDM project cycle, 2003 regional workshop on CDM-JI, February 2003, Halifax). This underscores the need for additional reduction of 240 Mt. The Federal Government Action Plan 2000 aims to reduce this gap from 240 to 65 Mt (Cote C. Basic of clean development mechanism—joint implementation and overview of CDM project cycle, 2003 regional workshop on CDM-JI, February 2003, Halifax). In order to accomplish this goal, renewable energy use in all sectors will be required, and this type of energy is particularly applicable in power generation. Traditional power generation is a major source of greenhouse gas (GHG) emissions after industrial and transportation sectors (Environment Canada. Canada’s Greenhouse Gas Inventory 1990–1998. Final submission to the UNFCCC Secretariat, 2002 [Available from: http://www.ec.gc.ca/climate/resources_reportes-e.html]. Although wind energy, solar power and other forms of renewable energy are non-GHG emitting in their operation, there are GHG emissions in their different stages of life cycle (i.e. material extraction, manufacturing, construction and transportation, etc.). These emissions must be accounted for in order to assess accurately their capacity to reduce GHG emission and meet Kyoto targets. The current trend in electricity generation is towards integrated energy systems. One such proposed system is the wind–fuel cell integrated system for remote communities. This paper presents a detailed Life Cycle Analysis of the wind–fuel cell integrated system for application in Newfoundland and Labrador. The study confirms that wind–fuel integrated system is a zero emission system while in operation. There are significant emissions of \\{GHGs\\} during the production of the various components (wind turbine, fuel cell and electrolyzer). However, the global warming potential (GWP) of wind-integrated system is far lower (at least by two orders of magnitude) than the conventional diesel system, presently used in remote communities.

Faisal I. Khan; Kelly Hawboldt; M.T. Iqbal

2005-01-01T23:59:59.000Z

184

Nuclear Fuel Cycle Reasoner: PNNL FY12 Report  

SciTech Connect (OSTI)

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

185

Advanced Fuel Cycle Economic Tools, Algorithms, and Methodologies  

SciTech Connect (OSTI)

The Advanced Fuel Cycle Initiative (AFCI) Systems Analysis supports engineering economic analyses and trade-studies, and requires a requisite reference cost basis to support adequate analysis rigor. In this regard, the AFCI program has created a reference set of economic documentation. The documentation consists of the “Advanced Fuel Cycle (AFC) Cost Basis” report (Shropshire, et al. 2007), “AFCI Economic Analysis” report, and the “AFCI Economic Tools, Algorithms, and Methodologies Report.” Together, these documents provide the reference cost basis, cost modeling basis, and methodologies needed to support AFCI economic analysis. The application of the reference cost data in the cost and econometric systems analysis models will be supported by this report. These methodologies include: the energy/environment/economic evaluation of nuclear technology penetration in the energy market—domestic and internationally—and impacts on AFCI facility deployment, uranium resource modeling to inform the front-end fuel cycle costs, facility first-of-a-kind to nth-of-a-kind learning with application to deployment of AFCI facilities, cost tradeoffs to meet nuclear non-proliferation requirements, and international nuclear facility supply/demand analysis. The economic analysis will be performed using two cost models. VISION.ECON will be used to evaluate and compare costs under dynamic conditions, consistent with the cases and analysis performed by the AFCI Systems Analysis team. Generation IV Excel Calculations of Nuclear Systems (G4-ECONS) will provide static (snapshot-in-time) cost analysis and will provide a check on the dynamic results. In future analysis, additional AFCI measures may be developed to show the value of AFCI in closing the fuel cycle. Comparisons can show AFCI in terms of reduced global proliferation (e.g., reduction in enrichment), greater sustainability through preservation of a natural resource (e.g., reduction in uranium ore depletion), value from weaning the U.S. from energy imports (e.g., measures of energy self-sufficiency), and minimization of future high level waste (HLW) repositories world-wide.

David E. Shropshire

2009-05-01T23:59:59.000Z

186

Integrated Electrorefining Efficiency Test for Pyrochemical Fuel Cycle  

SciTech Connect (OSTI)

Pyrochemical processing plays an important role in the development of next generation nuclear reactors and closed nuclear fuel cycle technology. The Idaho National Laboratory (INL) has implemented a pyrochemical process for the treatment of sodium-bonded spent fuel from the Experimental Breeder Reactor-II (EBR-II). A successful demonstration of the technology was performed from 1996 to 1999 for the Department of Energy (DOE) [1]. Processing of the spent fuel and associated research and development activities have been integrated into DOE’s Advanced Fuel Cycle Initiatives (AFCI) program since 2003. Electrorefining can be considered to be the signature or central technology for pyrochemical processing. In order to assess the efficiencies involved in the electrorefining process, an integrated electrorefining efficiency test was performed in the Mk-IV electrorefiner. This paper summarizes the observations and results obtained from the test. EXPERIMENT AND RESULTS The primary goal of the integrated processing efficiency test is to demonstrate the integrated actinide dissolution and recovery efficiencies typical for the fixed operating parameters that have been applied to Mk-IV electrorefiner (ER) and cathode processor (CP) to treat spent EBR-II driver fuel during the last three years. The findings are of importance for scaling-up the pyroprocess to recover and recycle valuable actinides from spent nuclear fuel. The test was performed in the Mk-IV electrorefiner. The ER is located in the hot cell of the Fuel Conditioning Facility at the Materials and Fuels Complex. Descriptions of the major components of the ER and the process in general have been provided elsewhere [2]. Salt and cadmium levels were measured, and multiple samples were obtained prior to performing the integrated test to establish an ER baseline for assessing the test results. The test consisted of four electrorefining batches of spent driver fuel with approximately 50 kg heavy metal. Typically, three to four ER runs are required to complete a batch. Fig. 1 shows pictures of the cathodes produced by three electrorefining runs during the second batch. The cathode No.3 in the figure has clearly different morphology than that of the first two. The cathodes produced by the other three batches have the similar morphology as those pictured. The first and second cathodes are ordinary uranium dendrite, and the third and fourth cathode show typically high Zr content morphology [3]. The end-point for each batch was determined by weighing each anode basket and assuring a net residue mass being equal or less than 3.0 kg. The 3.0 kg residue included any un-dissolved fuel constituents and adhering salt. Previous operating experience has shown that uranium dissolution in excess of 99.7 wt% was achieved when using this established end-point. Cladding hull samples were taken from each basket after it was removed from the ER. The actinide dissolution efficiency will be evaluated when the analytical results become available. Cathode No. 1 Cathode No. 2 Cathode No. 3 Fig.1 Three cathodes produced through electrorefining the second batch of spent EBR-II driver fuel As a part of the integrated efficiency test, the cat

S. X. Li; T. A. Johnson; R. W. Benedict; D. Vaden; B. R. Westphal

2006-11-01T23:59:59.000Z

187

Hybrid Life-Cycle Assessment of Natural Gas Based Fuel Chains for Transportation  

Science Journals Connector (OSTI)

The end use is passenger transportation with a sub-compact car that has an internal combustion engine for the natural gas case and a fuel cell for the methanol and hydrogen cases. ... Then, trucks are used to transport the fuels to a fueling station in Geneva, Switzerland. ... In evaluating fuel/vehicle options with the potential to improve the greenness of cars [diesel (direct injection) and ethanol in internal combustion engines, battery-powered, gasoline hybrid elec., and hydrogen fuel cells], we find no option dominates the others on all dimensions. ...

Anders Hammer Strømman; Christian Solli; Edgar G. Hertwich

2006-03-17T23:59:59.000Z

188

Fuel-Cycle Fossil Energy Use and Greenhouse Gas Emissions of Fuel Ethanol Produced from U.S. Midwest Corn  

E-Print Network [OSTI]

#12;Fuel-Cycle Fossil Energy Use and Greenhouse Gas Emissions of Fuel Ethanol Produced from U essential to an informed choice about the corn-to-ethanol cycle are in need of updating, thanks to scientific and technological advances in both corn farming and ethanol production; and (2) generalized

Patzek, Tadeusz W.

189

Advanced fuel cycles and impacts On The Yucca Mountain Repository  

SciTech Connect (OSTI)

One of the goals identified for advanced fuel cycles, such as that proposed by the Global Nuclear Energy Partnership, is to reduce the volume of wastes that would ultimately have to be disposed in a geologic repository. Besides reducing volume, techniques that recycle the vast majority of actinides along with the removal of key fission products also reduce the inventory of radionuclides that must ultimately be disposed and the thermal output of the wastes. Advanced recycling techniques may also generate waste forms having different characteristics than those that have been considered for disposal in a repository at Yucca Mountain to-date. These all have a potential impact on several aspects of a repository, such as the proposed repository at Yucca Mountain, including surface and subsurface facility design, pre-closure and post-closure safety analyses, and ultimately licensing. These changes would all have to be performed in accordance with the requirements at 10 CFR 63 and approved by the U.S. Nuclear Regulatory Commission in a license amendment prior to the disposal of any wastes from an advanced fuel cycle. (authors)

Nutt, W.M.; Peters, M.T. [Argonne National Laboratory, Argonne, IL (United States); Swift, P.N. [Sandia National Laboratories, New Mexico, Albuquerque, NM (United States)

2007-07-01T23:59:59.000Z

190

NMSS handbook for decommissioning fuel cycle and materials licensees  

SciTech Connect (OSTI)

The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

Orlando, D.A.; Hogg, R.C.; Ramsey, K.M. [and others

1997-03-01T23:59:59.000Z

191

A Multi-Pollutant Framework for Evaluating CO2 Control Options for Fossil Fuel Power Plants  

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

Multi-Pollutant Framework for Evaluating CO Multi-Pollutant Framework for Evaluating CO 2 Control Options for Fossil Fuel Power Plants Edward S. Rubin (rubin@cmu.edu; 412-268-5897) Anand B. Rao (abr@andrew.cmu.edu; 412-268-5605) Michael B. Berkenpas (mikeb@cmu.edu; 412-268-1088) Carnegie Mellon University EPP Department, Baker Hall 128A Pittsburgh, PA 15213 Abstract As part of DOE/NETL's Carbon Sequestration Program, we are developing an integrated, multi-pollutant modeling framework to evaluate the costs and performance of alternative carbon capture and sequestration technologies for fossil-fueled power plants. The model calculates emissions, costs, and efficiency on a systematic basis at the level of an individual plant or facility. Both new and existing facilities can be modeled, including coal-based or natural gas-based combustion or gasification systems using air or oxygen.

192

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

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

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

193

NETL - Petroleum-Based Fuels Life Cycle Greenhouse Gas Analysis 2005  

Open Energy Info (EERE)

NETL - Petroleum-Based Fuels Life Cycle Greenhouse Gas Analysis 2005 NETL - Petroleum-Based Fuels Life Cycle Greenhouse Gas Analysis 2005 Baseline Model Jump to: navigation, search Tool Summary LAUNCH TOOL Name: NETL - Petroleum-Based Fuels Life Cycle Greenhouse Gas Analysis 2005 Baseline Model Agency/Company /Organization: National Energy Technology Laboratory Sector: Energy Topics: Baseline projection, GHG inventory Resource Type: Software/modeling tools Website: www.netl.doe.gov/energy-analyses/refshelf/results.asp?ptype=Models/Too References: NETL - Petroleum-Based Fuels Life Cycle Greenhouse Gas Analysis 2005 Baseline Model [1] NETL - Petroleum-Based Fuels Life Cycle Greenhouse Gas Analysis 2005 Baseline Model This model calculates the 2005 national average life cycle greenhouse gas emissions for petroleum-based fuels sold or distributed in the United

194

EARTHQUAKE CAUSED RELEASES FROM A NUCLEAR FUEL CYCLE FACILITY  

SciTech Connect (OSTI)

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

195

Life Cycle Regulation of Transportation Fuels: Uncertainty and its Policy Implications  

E-Print Network [OSTI]

Cycle Assessment 10(1), 68–76. NETL (2008). Development offossil carbon in the fuel (NETL, 2008). The upstream portionof the carbon in the fuel (NETL, 2008), which is directly

Plevin, Richard Jay

2010-01-01T23:59:59.000Z

196

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

197

Operation of CANDU power reactor in thorium self-sufficient fuel cycle  

Science Journals Connector (OSTI)

This paper presents the results of calculations for CANDU reactor operation in thorium fuel cycle. Calculations...233U and mode of operation in self-sufficient cycle. For the mode of accumulation of 233U it was a...

B. R. Bergelson; A. S. Gerasimov; G. V. Tikhomirov

2007-02-01T23:59:59.000Z

198

A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS.  

E-Print Network [OSTI]

?? A study was conducted to scope the relative merits of various thorium fuel cycles in CANDU reactors. It was determined that, due to the… (more)

Friedlander, Yonni

2011-01-01T23:59:59.000Z

199

Projections of Full-Fuel-Cycle Energy and Emissions Metrics  

E-Print Network [OSTI]

annual generation by fuel type. .of total annual generation by fuel type. Other Renewablesof annual estimates of total generation by fuel type and

Coughlin, Katie

2013-01-01T23:59:59.000Z

200

Effect of reduced enrichment on the fuel cycle for research reactors  

SciTech Connect (OSTI)

The new fuels developed by the RERTR Program and by other international programs for application in research reactors with reduced uranium enrichment (<20% EU) are discussed. It is shown that these fuels, combined with proper fuel-element design and fuel-management strategies, can provide at least the same core residence time as high-enrichment fuels in current use, and can frequently significantly extend it. The effect of enrichment reduction on other components of the research reactor fuel cycle, such as uranium and enrichment requirements, fuel fabrication, fuel shipment, and reprocessing are also briefly discussed with their economic implications. From a systematic comparison of HEU and LEU cores for the same reference research reactor, it is concluded that the new fuels have a potential for reducing the research reactor fuel cycle costs while reducing, at the same time, the uranium enrichment of the fuel.

Travelli, A.

1982-01-01T23:59:59.000Z

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


201

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

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

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

202

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

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

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

203

LEU fuel cycle analyses for the Belgian BR2 Research Reactor  

SciTech Connect (OSTI)

Equilibrium fuel cycle characteristics were calculated for reference HEU and two proposed LEU fuel cycles using an 11-group diffusion-theory neutron flux solution in hexagonal-Z geometry. The diffusion theory model was benchmarked with a detailed Monte Carlo core model. The two proposed LEU fuel designs increased the {sup 235}U loading 20% and the fuel meat volume 51%. The first LEU design used {sup 10}B as a burnable absorber. Either proposed LEU fuel element would provide equilibrium fuel cycle characteristics similar to those of the HEU fuel cycle. Irradiation rates of Co control followers and Ir disks in the center of the core were reduced 6 {plus minus} 1% in the LEU equilibrium core compared to reference HEU core. 11 refs., 4 figs., 5 tabs.

Deen, J.R.; Snelgrove, J.L.

1988-01-01T23:59:59.000Z

204

Full Fuel-Cycle Comparison of Forklift Propulsion Systems  

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

3 3 Full Fuel-Cycle Comparison of Forklift Propulsion Systems Energy Systems Division About Argonne National Laboratory Argonne is a U.S. Department of Energy laboratory managed by UChicago Argonne, LLC under contract DE-AC02-06CH11357. The Laboratory's main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne, see www.anl.gov. Availability of This Report This report is available, at no cost, at http://www.osti.gov/bridge. It is also available on paper to the U.S. Department of Energy and its contractors, for a processing fee, from: U.S. Department of Energy Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 phone (865) 576-8401

205

Dr. Hussein Khalil at Reactor and Fuel Cycle Technologies Subcommittee  

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

Blue Blue ribbon presentation by Dr. Hussein Khalil Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share Blue ribbon presentation by Hussein Khalil Hussein Khalil Dr. Hussein Khalil during the panel discussion Oct. 21, 2010 On October 12 Hussein Khalil, director of Argonne's Nuclear Engineering Division, participated in a Reactor and Fuel Cycle Technologies

206

Preliminary study: isotopic safeguards techniques (IST) LMFBR fuel cycles  

SciTech Connect (OSTI)

This memorandum presents the preliminary results of the effort to investigate the applicability of isotope correlation techniques (ICT), formulated for the LWR system, to the LMFBR fuel cycle. The detailed isotopic compositional changes with burnup developed for the CRBR was utilized as the reference case. This differs from the usual LMFBR design studies in that the core uranium is natural uranium rather than depleted. Nevertheless, the general isotopic behavior should not differ significantly and does allow an initial insight into the expected behavior of isotopic correlations for the LMFBR power systems such as: the U.K. PFR and reprocessing plant; the French Phenix and Superphenix; and the US reference conceptual design studies (CDS) of homogeneous and heterogeneous LMFBR systems as they are developed.

Persiani, P.J.; Kroc, T.K.

1980-06-01T23:59:59.000Z

207

OECD/NEA Ongoing activities related to the nuclear fuel cycle  

SciTech Connect (OSTI)

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

208

Hydraulic Hybrid and Conventional Parcel Delivery Vehicles' Measured Laboratory Fuel Economy on Targeted Drive Cycles  

SciTech Connect (OSTI)

This research project compares laboratory-measured fuel economy of a medium-duty diesel powered hydraulic hybrid vehicle drivetrain to both a conventional diesel drivetrain and a conventional gasoline drivetrain in a typical commercial parcel delivery application. Vehicles in this study included a model year 2012 Freightliner P100H hybrid compared to a 2012 conventional gasoline P100 and a 2012 conventional diesel parcel delivery van of similar specifications. Drive cycle analysis of 484 days of hybrid parcel delivery van commercial operation from multiple vehicles was used to select three standard laboratory drive cycles as well as to create a custom representative cycle. These four cycles encompass and bracket the range of real world in-use data observed in Baltimore United Parcel Service operations. The NY Composite cycle, the City Suburban Heavy Vehicle Cycle cycle, and the California Air Resources Board Heavy Heavy-Duty Diesel Truck (HHDDT) cycle as well as a custom Baltimore parcel delivery cycle were tested at the National Renewable Energy Laboratory's Renewable Fuels and Lubricants Laboratory. Fuel consumption was measured and analyzed for all three vehicles. Vehicle laboratory results are compared on the basis of fuel economy. The hydraulic hybrid parcel delivery van demonstrated 19%-52% better fuel economy than the conventional diesel parcel delivery van and 30%-56% better fuel economy than the conventional gasoline parcel delivery van on cycles other than the highway-oriented HHDDT cycle.

Lammert, M. P.; Burton, J.; Sindler, P.; Duran, A.

2014-10-01T23:59:59.000Z

209

Life-cycle cost analysis of energy efficiency design options for residential furnaces and boilers  

E-Print Network [OSTI]

energy conservation standard in terms of the Annual Fuel Utilization Efficiency (AFUE) descriptor at a minimum

Lutz, James; Lekov, Alex; Whitehead, Camilla Dunham; Chan, Peter; Meyers, Steve; McMahon, James

2004-01-01T23:59:59.000Z

210

Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems  

SciTech Connect (OSTI)

The Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems, prepared to support the U.S. Advanced Fuel Cycle Initiative (AFCI) systems analysis, provides a technology-oriented baseline system cost comparison between the open fuel cycle and closed fuel cycle systems. The intent is to understand their overall cost trends, cost sensitivities, and trade-offs. This analysis also improves the AFCI Program’s understanding of the cost drivers that will determine nuclear power’s cost competitiveness vis-a-vis other baseload generation systems. The common reactor-related costs consist of capital, operating, and decontamination and decommissioning costs. Fuel cycle costs include front-end (pre-irradiation) and back-end (post-iradiation) costs, as well as costs specifically associated with fuel recycling. This analysis reveals that there are large cost uncertainties associated with all the fuel cycle strategies, and that overall systems (reactor plus fuel cycle) using a closed fuel cycle are about 10% more expensive in terms of electricity generation cost than open cycle systems. The study concludes that further U.S. and joint international-based design studies are needed to reduce the cost uncertainties with respect to fast reactor, fuel separation and fabrication, and waste disposition. The results of this work can help provide insight to the cost-related factors and conditions needed to keep nuclear energy (including closed fuel cycles) economically competitive in the U.S. and worldwide. These results may be updated over time based on new cost information, revised assumptions, and feedback received from additional reviews.

D. E. Shropshire

2009-01-01T23:59:59.000Z

211

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development  

SciTech Connect (OSTI)

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions.

Till, C.E.; Chang, Y.I.

1993-01-01T23:59:59.000Z

212

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development  

SciTech Connect (OSTI)

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions.

Till, C.E.; Chang, Y.I.

1993-03-01T23:59:59.000Z

213

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development  

SciTech Connect (OSTI)

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions. 10 refs.

Till, C.E.; Chang, Y.I.

1991-01-01T23:59:59.000Z

214

Generic Repository Concepts and Thermal Analysis for Advanced Fuel Cycles  

SciTech Connect (OSTI)

The current posture of the used nuclear fuel management program in the U.S. following termination of the Yucca Mountain Project, is to pursue research and development (R&D) of generic (i.e., non-site specific) technologies for storage, transportation and disposal. Disposal R&D is directed toward understanding and demonstrating the performance of reference geologic disposal concepts selected to represent the current state-of-the-art in geologic disposal. One of the principal constraints on waste packaging and emplacement in a geologic repository is management of the waste-generated heat. This paper describes the selection of reference disposal concepts, and thermal management strategies for waste from advanced fuel cycles. A geologic disposal concept for spent nuclear fuel (SNF) or high-level waste (HLW) consists of three components: waste inventory, geologic setting, and concept of operations. A set of reference geologic disposal concepts has been developed by the U.S. Department of Energy (DOE) Used Fuel Disposition Campaign, for crystalline rock, clay/shale, bedded salt, and deep borehole (crystalline basement) geologic settings. We performed thermal analysis of these concepts using waste inventory cases representing a range of advanced fuel cycles. Concepts of operation consisting of emplacement mode, repository layout, and engineered barrier descriptions, were selected based on international progress and previous experience in the U.S. repository program. All of the disposal concepts selected for this study use enclosed emplacement modes, whereby waste packages are in direct contact with encapsulating engineered or natural materials. The encapsulating materials (typically clay-based or rock salt) have low intrinsic permeability and plastic rheology that closes voids so that low permeability is maintained. Uniformly low permeability also contributes to chemically reducing conditions common in soft clay, shale, and salt formations. Enclosed modes are associated with temperature constraints that limit changes to the encapsulating materials, and they generally have less capacity to dissipate heat from the waste package and its immediate surroundings than open modes such as that proposed for a repository at Yucca Mountain, Nevada. Open emplacement modes can be ventilated for many years prior to permanent closure of the repository, limiting peak temperatures both before and after closure, and combining storage and disposal functions in the same facility. Open emplacement modes may be practically limited to unsaturated host formations, unless emplacement tunnels are effectively sealed everywhere prior to repository closure. Thermal analysis of disposal concepts and waste inventory cases has identified important relationships between waste package size and capacity, and the duration of surface decay storage needed to meet temperature constraints. For example, the choice of salt as the host medium expedites the schedule for geologic disposal by approximately 50 yr (other factors held constant) thereby reducing future reliance on surface decay storage. Rock salt has greater thermal conductivity and stability at higher temperatures than other media considered. Alternatively, the choice of salt permits the use of significantly larger waste packages for SNF. The following sections describe the selection of reference waste inventories, geologic settings, and concepts of operation, and summarize the results from the thermal analysis.

Hardin, Ernest [Sandia National Laboratories (SNL)] [Sandia National Laboratories (SNL); Blink, James [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Carter, Joe [Savannah River National Laboratory (SRNL)] [Savannah River National Laboratory (SRNL); Massimiliano, Fratoni [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Greenberg, Harris [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Howard, Rob L [ORNL] [ORNL

2011-01-01T23:59:59.000Z

215

Risk-based performance analysis for regional hybrid fuel with compressed natural gas option  

Science Journals Connector (OSTI)

Compressed natural gas is widely used for transportation due to its competitive price and less environmental impacts compared with traditional gasoline. With the recent push to implement electric vehicles, it became important to evaluate the current transportation fuelling status and identify best scenarios to move towards greener transportation. This paper presents analysis of hybrid transportation with compressed natural gas as a fuelling option to determine the most effective way to implement regional green transportation. Intelligent modelling and simulation techniques are proposed to model transportation and fuelling process and used as basis for performance modelling and analysis for different scenarios. Compressed natural gas is found to be a superior fuel to gasoline based on given scenario conditions and criteria for regional green hybrid transportation. The proposed scenarios are applied on case studies in Ontario to confirm the high value of compressed natural gas as viable fuelling scenarios.

Hossam A. Gabbar; Raymond Bedard

2012-01-01T23:59:59.000Z

216

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

SciTech Connect (OSTI)

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

217

Fuel-Cycle Analysis of Hydrogen-Powered Fuel-Cell Systems with the GREET Model  

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

Cycle Analysis of Hydrogen-Powered Cycle Analysis of Hydrogen-Powered Fuel-Cell Systems with the GREET Model Michael Wang Argonne National Laboratory June 10, 2008 Project ID # AN2 This presentation does not contain any proprietary, confidential, or otherwise restricted information 2 Overview * Project start date: Oct. 2002 * Project end date: Continuous * Percent complete: N/A * Inconsistent data, assumptions, and guidelines * Suite of models and tools * Unplanned studies and analyses * Total project funding from DOE: $2.04 million through FY08 * Funding received in FY07: $450k * Funding for FY08: $840k Budget * H2A team * PSAT team * NREL * Industry stakeholders Partners Timeline Barriers to Address 3 Objectives * Expand and update the GREET model for hydrogen production pathways and for applications of FCVs and other FC systems

218

Evaluation of Options for Permanent Geologic Disposal of Spent NuclearFuel and High-Level Radioactive Waste  

Broader source: Energy.gov [DOE]

[In Support of a Comprehensive National Nuclear Fuel Cycle Strategy, Volumes I and II (Appendices)] This study provides a technical basis for informing policy decisions regarding strategies for the management and permanent disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) in the United States requiring geologic isolation.

219

The Economic, repository and proliferation implications of advanced nuclear fuel cycle  

SciTech Connect (OSTI)

The goal of this project was to compare the effects of recycling actinides using fast burner reactors, with recycle that would be done using inert matrix fuel burned in conventional light water reactors. In the fast reactor option, actinides from both spent light water and fast reactor fuel would be recycled. In the inert matrix fuel option, actinides from spent light water fuel would be recycled, but the spent inert matrix fuel would not be reprocessed. The comparison was done over a limited 100-year time horizon. The economic, repository and proliferation implications of these options all hinge on the composition of isotopic byproducts of power production. We took the perspective that back-end economics would be affected by the cost of spent fuel reprocessing (whether conventional uranium dioxide fuel, or fast reactor fuel), fuel manufacture, and ultimate disposal of high level waste in a Yucca Mountain like geological repository. Central to understanding these costs was determining the overall amount of reprocessing needed to implement a fast burner, or inert matrix fuel, recycle program. The total quantity of high level waste requiring geological disposal (along with its thermal output), and the cost of reprocessing were also analyzed. A major advantage of the inert matrix fuel option is that it could in principle be implemented using the existing fleet of commercial power reactors. A central finding of this project was that recycling actinides using an inert matrix fuel could achieve reductions in overall actinide production that are nearly very close to those that could be achieved by recycling the actinides using a fast burner reactor.

Mark Deinert; K.B. Cady

2011-09-04T23:59:59.000Z

220

Preliminary LEU fuel cycle analyses for the Belgian BR2 reactor  

SciTech Connect (OSTI)

Fuel cycle calculations have been performed with reference HEU fuel and LEU fuel using Cd wires or boron as burnable absorbers. The /sup 235/U content in the LEU element has increased 20% to 480g compared to the reference HEU element. The number of fuel plates has remained unchanged while the fuel meat thickness has increased to 0.76 mm from 0.51 mm. The LEU meat density is 5.1 Mg U/m/sup 3/. The reference fuel cycle was a 31 element core operating at 56 MW with a 19.8 day cycle length and eight fresh elements loaded per cycle. Comparable fuel cycle characteristics can be achieved using the proposed LEU fuel element with either Cd wires or boron burnable absorbers. The neutron flux for E/sub n/ > 1 eV changes very little (<5%) in LEU relative to HEU cores. Thermal flux reductions are 5 to 10% in non-fueled positions, and 20 to 30% in fuel elements.

Deen, J.R.; Snelgrove, J.L.

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

Life cycle analysis of waste management options for EBI in Quebec  

E-Print Network [OSTI]

Quebec has issued a mandate requiring all waste management facilities to ban the landfilling of organic waste by 2020. EBI is considering Anaerobic Digestion as one of its alternative options, but is uncertain if it is the ...

Wilson, Jaclyn D

2014-01-01T23:59:59.000Z

222

Report of the Fuel Cycle Subcommittee of the Nuclear Energy Advisory  

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

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.

223

Report of the Fuel Cycle Research and Development Subcommittee of the  

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

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

224

Report of the Fuel Cycle Subcommittee of the Nuclear Energy Advisory  

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

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.

225

Evaluation of fuel cycle scenarios on MOX fuel recycling in PWRs and SFRs  

SciTech Connect (OSTI)

Prospects on advanced fuel cycle scenario are considered for achieving a progressive integration of Sodium Fast Reactor (SFR) technology within the current French Pressurized Water Reactor (PWR) nuclear fleet, in a view to benefit from fissile material multi-recycling capability. A step by step process is envisioned, and emphasis is put on its potential implementation through the nuclear mass inventory calculations with the COSAC code. The overall time scale is not optimized. The first step, already implemented in several countries, the plutonium coming from the reprocessing of used Light Water Reactor (LWR) fuels is recycled into a small number of LWRs. The second step is the progressive introduction of the first SFRs, in parallel with the continuation of step 1. This second step lets to prepare the optimized multi recycling of MOX fuel which is considered in step 3. Step 3 is characterized by the introduction of a greater number of SFR and MOX management between EPR reactors and SFRs. In the final step 4, all the fleet is formed with SFRs. This study assesses the viability of each step of the overall scenario. The switch from one step to the other one could result from different constrains related to issues such as resources, waste, experience feedback, public acceptance, country policy, etc.

Carlier, B.; Caron-Charles, M.; Van Den Durpel, L. [AREVA, 1 place Jean Millier, Paris La Defense (France); Senentz, G. [AREVA, 33 rue La Lafayette, 75009 Paris (France); Serpantie, J.P. [AREVA, 10 rue Juliette Recamier, Lyon (France)

2013-07-01T23:59:59.000Z

226

Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model - 13413  

SciTech Connect (OSTI)

This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system, and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity. (authors)

Djokic, Denia [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States)] [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, Steven J.; Pincock, Layne F.; Soelberg, Nick R. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)] [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

2013-07-01T23:59:59.000Z

227

GREET 1.0 -- Transportation fuel cycles model: Methodology and use  

SciTech Connect (OSTI)

This report documents the development and use of the Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation (GREET) model. The model, developed in a spreadsheet format, estimates the full fuel-cycle emissions and energy use associated with various transportation fuels for light-duty vehicles. The model calculates fuel-cycle emissions of five criteria pollutants (volatile organic compounds, Co, NOx, SOx, and particulate matter measuring 10 microns or less) and three greenhouse gases (carbon dioxide, methane, and nitrous oxide). The model also calculates the total fuel-cycle energy consumption, fossil fuel consumption, and petroleum consumption using various transportation fuels. The GREET model includes 17 fuel cycles: petroleum to conventional gasoline, reformulated gasoline, clean diesel, liquefied petroleum gas, and electricity via residual oil; natural gas to compressed natural gas, liquefied petroleum gas, methanol, hydrogen, and electricity; coal to electricity; uranium to electricity; renewable energy (hydropower, solar energy, and wind) to electricity; corn, woody biomass, and herbaceous biomass to ethanol; and landfill gases to methanol. This report presents fuel-cycle energy use and emissions for a 2000 model-year car powered by each of the fuels that are produced from the primary energy sources considered in the study.

Wang, M.Q.

1996-06-01T23:59:59.000Z

228

Reducing the Carbon Footprint of Commercial Refrigeration Systems Using Life Cycle Climate Performance Analysis: From System Design to Refrigerant Options  

SciTech Connect (OSTI)

In this paper, Life Cycle Climate Performance (LCCP) analysis is used to estimate lifetime direct and indirect carbon dioxide equivalent gas emissions of various refrigerant options and commercial refrigeration system designs, including the multiplex DX system with various hydrofluorocarbon (HFC) refrigerants, the HFC/R744 cascade system incorporating a medium-temperature R744 secondary loop, and the transcritical R744 booster system. The results of the LCCP analysis are presented, including the direct and indirect carbon dioxide equivalent emissions for each refrigeration system and refrigerant option. Based on the results of the LCCP analysis, recommendations are given for the selection of low GWP replacement refrigerants for use in existing commercial refrigeration systems, as well as for the selection of commercial refrigeration system designs with low carbon dioxide equivalent emissions, suitable for new installations.

Fricke, Brian A [ORNL] [ORNL; Abdelaziz, Omar [ORNL] [ORNL; Vineyard, Edward Allan [ORNL] [ORNL

2013-01-01T23:59:59.000Z

229

Projections of Full-Fuel-Cycle Energy and Emissions Metrics  

E-Print Network [OSTI]

Adam R. 2008. “Converting Oil Shale to Liquid Fuels: Energyshale gas, tight oil, oil shale, and tar (bitumen) sands. In

Coughlin, Katie

2013-01-01T23:59:59.000Z

230

Power Gas and Combined Cycles: Clean Power from Fossil Fuels  

Science Journals Connector (OSTI)

...gas has such a low heating value that it cannot...from residual fuel oil (the relatively...Oil Residual fuel oil with a low sulfur...stations in Maryland, Connecticut, and New York-has...low-sulfur residual fuel oil is growing and its price is rising. Residual...

William D. Metz

1973-01-05T23:59:59.000Z

231

Life-Cycle Analysis of Transportation Fuels and Vehicle Technologies  

E-Print Network [OSTI]

Camelina Algae Gasoline Diesel Jet Fuel Liquefied Petroleum Gas Naphtha Residual Oil Hydrogen Fischer Coke Nuclear Energy Hydrogen #12;GREET examines more than 80 vehicle/fuel systems Conventional Spark-Tropsch diesel 4 Dimethyl ether 4 Biodiesel Fuel Cell Vehicles 4 On-board hydroge

Bustamante, Fabián E.

232

Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors  

SciTech Connect (OSTI)

Two of the major barriers to the expansion of worldwide adoption of nuclear power are related to proliferation potential of the nuclear fuel cycle and issues associated with the final disposal of spent fuel. The Radkowsky Thorium Fuel (RTF) concept proposed by Professor A. Radkowsky offers a partial solution to these problems. The main idea of the concept is the utilization of the seed-blanket unit (SBU) fuel assembly geometry which is a direct replacement for a 'conventional' assembly in either a Russian pressurized water reactor (VVER-1000) or a Western pressurized water reactor (PWR). The seed-blanket fuel assembly consists of a fissile (U) zone, known as seed, and a fertile (Th) zone known as blanket. The separation of fissile and fertile allows separate fuel management schemes for the thorium part of the fuel (a subcritical 'blanket') and the 'driving' part of the core (a supercritical 'seed'). The design objective for the blanket is an efficient generation and in-situ fissioning of the U233 isotope, while the design objective for the seed is to supply neutrons to the blanket in a most economic way, i.e. with minimal investment of natural uranium. The introduction of thorium as a fertile component in the nuclear fuel cycle significantly reduces the quantity of plutonium production and modifies its isotopic composition, reducing the overall proliferation potential of the fuel cycle. Thorium based spent fuel also contains fewer higher actinides, hence reducing the long-term radioactivity of the spent fuel. The analyses show that the RTF core can satisfy the requirements of fuel cycle length, and the safety margins of conventional pressurized water reactors. The coefficients of reactivity are comparable to currently operating VVER's/PWR's. The major feature of the RTF cycle is related to the total amount of spent fuel discharged for each cycle from the reactor core. The fuel management scheme adopted for RTF core designs allows a significant decrease in the amount of discharged spent fuel, for a given energy production, compared with standard VVER/PWR. The total Pu production rate of RTF cycles is only 30 % of standard reactor. In addition, the isotopic compositions of the RTF's and standard reactor grade Pu are markedly different due to the very high burnup accumulated by the RTF spent fuel.

Todosow M.; Todosow M.; Raitses, G. (BNL) Galperin, A. (Ben Gurion University)

2009-07-12T23:59:59.000Z

233

A low-radioactive D-3He thermonuclear fuel cycle with 3He self-supply  

Science Journals Connector (OSTI)

The possibility of implementing a highly efficient low-radioactive thermonuclear fuel cycle using deuterium as the raw...3He reaction, with 3He obtained in the course of the reactor operation. It is shown that, u...

V. I. Khvesyuk; A. Yu. Chirkov

2001-08-01T23:59:59.000Z

234

Impacts of Renewable Generation on Fossil Fuel Unit Cycling: Costs and Emissions (Presentation)  

SciTech Connect (OSTI)

Prepared for the Clean Energy Regulatory Forum III, this presentation looks at the Western Wind and Solar Integration Study and reexamines the cost and emissions impacts of fossil fuel unit cycling.

Brinkman, G.; Lew, D.; Denholm, P.

2012-09-01T23:59:59.000Z

235

Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties  

E-Print Network [OSTI]

. The reactors and fuel cycle performance parameters may be strongly dependent on minor variations in the system's input data. Proven discrepancies in nuclear data evaluations could affect the validity of the system optimization metrics. This study first...

Cuvelier, Marie-Hermine

2012-07-16T23:59:59.000Z

236

Decision-making of biomass ethanol fuel policy based on life cycle 3E assessment  

Science Journals Connector (OSTI)

To evaluate the environmental, economic, energy performance of biomass ethanol fuel in China and to support the decision-making of biomass ethanol energy policy, an assessment method of life cycle 3E (economy, en...

Ru-bo Leng PhD; Du Dai; Xiao-jun Chen…

2005-10-01T23:59:59.000Z

237

Performance assessment modeling of high level nuclear wasteforms from the pyroprocess fuel cycle  

SciTech Connect (OSTI)

Several performance assessment (PA) analyses have been completed to estimate the release to the accessible environment of radionuclides from spent light water reactor (LWR) fuel emplaced in the proposed Yucca Mountain repository. Probabilistic methods were utilized based on the complexity of the repository system. Recent investigations have been conducted to identify the merits of a pyroprocess fuel cycle. This cycle utilizes high temperature molten salts and metals to partially separate actinides and fission products. In a closed liquid metal reactor (LMR) fuel cycle, this allows recycling of nearly all of the actinides. In a once-through cycle, this isolates the actinides for storage into a wasteform which can be specifically tailored for their retention. With appropriate front-end treatment, this Process can also be used to treat LWR spent fuel.

Nutt, W.M.; Hill, R.N. [Argonne National Lab., IL (United States); Bullen, D.B. [Ames Lab., IA (United States)

1995-06-01T23:59:59.000Z

238

Optimization strategies for sustainable fuel cycle of the BR2 Reactor  

SciTech Connect (OSTI)

The objective of the present study is to achieve a sustainable fuel cycle in a long term of reactor operation applying advanced in-core loading strategies. The optimization criteria concern mainly enhancement of nuclear safety by means of reactivity margins and minimization of the operational fuel cycle cost at a given (constant) power level and same or longer cycle length. An important goal is also to maintain the same or to improve the experimental performances. Current developments are focused on optimization of control rods localization; optimization of fresh and burnt fuel assemblies in-core distribution; optimization of azimuth and axial fuel burn up strategies, including fuel assembly rotating and flipping upside down. (authors)

Kalcheva, S.; Van Den Branden, G.; Koonen, E. [SCK-CEN, BR2 Reactor, Boeretang 200, Mol, 2400 (Belgium)

2013-07-01T23:59:59.000Z

239

Life Cycle Assessment of Natural Gas-Powered Personal Mobility Options  

Science Journals Connector (OSTI)

Both CCS processes use monoethanolamine (MEA) as the absorbent, and the LCI for the carbon capture processes for the respective fuel conversion plants were adapted from two U.S. DOE national laboratory reports in which detailed technology descriptions were provided for systems with and without CCS. ... In Handbook of Fuel Cells: Fundamentals, Technology, and Applications; Vielstich, W., Eds.; John Wiley & Sons: New York, 2010. ...

Qiang Dai; Christian M. Lastoskie

2014-08-02T23:59:59.000Z

240

Is a single fuel on the battlefield still a viable option. Research report, August 1992-April 1993  

SciTech Connect (OSTI)

The plan for petroleum support in CENTCOM was based on the single fuel on the battlefield concept. Under this concept, land based aircraft and ground vehicles and equipment would operate using a single fuel, Jet A-1. However, when the Persian Gulf War occurred, this plan was set aside. This paper investigates the reasons why the plan to use a single was not followed. Essentially, there were two reasons. One, Jet A-1, diesel fuel, and automotive gasoline were all readily available in Saudi Arabia. Two, some US units were not confident using Jet A-1 in lieu of diesel fuel. Units which used Jet A-1 did not experience any significant fuel-related problems. In fact, the Persian Gulf War further demonstrated that aviation and ground equipment can be operated using the same fuel. In addition, using the same fuel added flexibility and simplicity to petroleum support operations. Therefore, the single fuel on the battlefield concept remains a viable option and one which DOD should continue to strive to attain.

Garrett, R.K.

1993-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

Assessing Options for Electricity Generation from Biomass on a Life Cycle Basis: Environmental and Economic Evaluation  

Science Journals Connector (OSTI)

Co-firing biomass with coal is being increasingly seen in the EU ... direct emissions of pollutants generated during combustion of coal, including carbon dioxide, sulphur dioxide and ... cycle approach to evaluat...

Harish Kumar Jeswani; Haruna Gujba; Adisa Azapagic

2011-02-01T23:59:59.000Z

242

Projections of Full-Fuel-Cycle Energy and Emissions Metrics  

E-Print Network [OSTI]

Adam R. 2008. “Converting Oil Shale to Liquid Fuels: Energyshale gas, tight oil, oil shale, and tar (bitumen) sands. Inunconventional (tar sands or shale oil) being more energy

Coughlin, Katie

2013-01-01T23:59:59.000Z

243

Projections of Full-Fuel-Cycle Energy and Emissions Metrics  

E-Print Network [OSTI]

from Conventional Oil Production and Oil Sands. ” Environ.6 Forecasts of Canadian oil production published in 2006 andPetroleum Fuels The oil production chain is similar to

Coughlin, Katie

2013-01-01T23:59:59.000Z

244

Projections of Full-Fuel-Cycle Energy and Emissions Metrics  

E-Print Network [OSTI]

function of the FFC energy intensity parameters. The FFCand c as the energy intensity of fuel production, defined asrepresenting the energy intensity and material losses at

Coughlin, Katie

2013-01-01T23:59:59.000Z

245

Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel  

Broader source: Energy.gov [DOE]

The Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel report assesses the technical options for the safe and permanent disposal of high-level radioactive waste (HLW) and spent nuclear fuel (SNF) managed by the Department of Energy. Specifically, it considers whether DOE-managed HLW and SNF should be disposed of with commercial SNF and HLW in one geologic repository or whether there are advantages to developing separate geologic disposal pathways for some DOE-managed HLW and SNF. The report recommends that the Department begin implementation of a phased, adaptive, and consent-based strategy with development of a separate mined repository for some DOE-managed HLW and cooler DOE-managed SNF.

246

Fuel cycle cost, reactor physics and fuel manufacturing considerations for Erbia-bearing PWR fuel with > 5 wt% U-235 content  

SciTech Connect (OSTI)

The efforts to reduce fuel cycle cost have driven LWR fuel close to the licensed limit in fuel fissile content, 5.0 wt% U-235 enrichment, and the acceptable duty on current Zr-based cladding. An increase in the fuel enrichment beyond the 5 wt% limit, while certainly possible, entails costly investment in infrastructure and licensing. As a possible way to offset some of these costs, the addition of small amounts of Erbia to the UO{sub 2} powder with >5 wt% U-235 has been proposed, so that its initial reactivity is reduced to that of licensed fuel and most modifications to the existing facilities and equipment could be avoided. This paper discusses the potentialities of such a fuel on the US market from a vendor's perspective. An analysis of the in-core behavior and fuel cycle performance of a typical 4-loop PWR with 18 and 24-month operating cycles has been conducted, with the aim of quantifying the potential economic advantage and other operational benefits of this concept. Subsequently, the implications on fuel manufacturing and storage are discussed. While this concept has certainly good potential, a compelling case for its short-term introduction as PWR fuel for the US market could not be determined. (authors)

Franceschini, F.; Lahoda, E. J.; Kucukboyaci, V. N. [Westinghouse Electric Co. LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2012-07-01T23:59:59.000Z

247

Task report No. 3. Systems analysis of organic Rankine bottoming cycles. [Fuel cell power plant  

SciTech Connect (OSTI)

A model was developed that predicts the design performance and cost of a Fuel Cell/Rankine cycle powerplant. The Rankine cycle utilizes the rejected heat of an 11.3 MW phosphoric acid fuel cell powerplant. Improvements in the total plant heat rate and efficiency of up to 10% were attainalbe, using ammonia as the working fluid. The increase in total plant cost divided by the increase in total plant power ranged from $296/kW to $1069/kW for the cases run, and was a strong function of ambient temperature. The concept appears to be capable of producing substantial energy savings in large fuel cell powerplants, at reasonable costs. However, a much more detailed study that includes such factors as duty cycle, future cost of fuel and site meteorology needs to be done to prove the design for any potential site.

Bloomfield, D.; Fried, S.

1980-12-01T23:59:59.000Z

248

A comparative environmental analysis of fossil fuel electricity generation options for South Africa .  

E-Print Network [OSTI]

??The increased demand for electricity in South Africa is expected to exceed supply between 2004 and 2007. Electricity supply options in the country would be… (more)

Govender, Indran

2009-01-01T23:59:59.000Z

249

9 - Hybrid fuel cell gas turbine (FC/GT) combined cycle systems  

Science Journals Connector (OSTI)

Abstract: Hybrid fuel cell gas turbine systems consisting of high-temperature fuel cells (HTFCs) integrated into cycles with gas turbines can significantly increase fuel-to-electricity conversion efficiency and lower emissions of greenhouse gases and criteria pollutants from the electric power sector. In addition, the separated anode and cathode compartments of the fuel cell can enable CO2 separation and sequestration for some cycle configurations. Hybrid fuel cell gas turbine technology has the potential to operate on natural gas, digester gas, landfill gas, and coal and biomass syngas. HTFC technologies are emerging with high reliability and durability, which should enable them to be integrated with gas turbine technology to produce modern hybrid power systems. Advanced thermodynamic and dynamic simulation capabilities have been developed and demonstrated to enable future system integration and control.

J. Brouwer

2012-01-01T23:59:59.000Z

250

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

SciTech Connect (OSTI)

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

251

An integrated appraisal of energy recovery options in the United Kingdom using solid recovered fuel derived from municipal solid waste  

SciTech Connect (OSTI)

This paper reports an integrated appraisal of options for utilising solid recovered fuels (SRF) (derived from municipal solid waste, MSW) in energy intensive industries within the United Kingdom (UK). Four potential co-combustion scenarios have been identified following discussions with industry stakeholders. These scenarios have been evaluated using (a) an existing energy and mass flow framework model, (b) a semi-quantitative risk analysis, (c) an environmental assessment and (d) a financial assessment. A summary of results from these evaluations for the four different scenarios is presented. For the given ranges of assumptions; SRF co-combustion with coal in cement kilns was found to be the optimal scenario followed by co-combustion of SRF in coal-fired power plants. The biogenic fraction in SRF (ca. 70%) reduces greenhouse gas (GHG) emissions significantly ({approx}2500 g CO{sub 2} eqvt./kg DS SRF in co-fired cement kilns and {approx}1500 g CO{sub 2} eqvt./kg DS SRF in co-fired power plants). Potential reductions in electricity or heat production occurred through using a lower calorific value (CV) fuel. This could be compensated for by savings in fuel costs (from SRF having a gate fee) and grants aimed at reducing GHG emission to encourage the use of fuels with high biomass fractions. Total revenues generated from coal-fired power plants appear to be the highest ( Pounds 95/t SRF) from the four scenarios. However overall, cement kilns appear to be the best option due to the low technological risks, environmental emissions and fuel cost. Additionally, cement kiln operators have good experience of handling waste derived fuels. The scenarios involving co-combustion of SRF with MSW and biomass were less favourable due to higher environmental risks and technical issues.

Garg, A.; Smith, R. [Sustainable Systems Department, School of Applied Sciences, Cranfield University, Cranfield, Bedfordshire, MK43 0AL (United Kingdom); Hill, D. [DPH Environment and Energy Ltd., c/o Sustainable Systems Department, School of Applied Sciences, Cranfield University, Cranfield, Bedfordshire, MK43 0AL (United Kingdom); Longhurst, P.J.; Pollard, S.J.T. [Sustainable Systems Department, School of Applied Sciences, Cranfield University, Cranfield, Bedfordshire, MK43 0AL (United Kingdom); Simms, N.J. [Sustainable Systems Department, School of Applied Sciences, Cranfield University, Cranfield, Bedfordshire, MK43 0AL (United Kingdom)], E-mail: n.j.simms@cranfield.ac.uk

2009-08-15T23:59:59.000Z

252

Assessment of PNGV fuels infrastructure. Phase 1 report: Additional capital needs and fuel-cycle energy and emissions impacts  

SciTech Connect (OSTI)

This report presents the methodologies and results of Argonne`s assessment of additional capital needs and the fuel-cycle energy and emissions impacts of using six different fuels in the vehicles with tripled fuel economy (3X vehicles) that the Partnership for a New Generation of Vehicles is currently investigating. The six fuels included in this study are reformulated gasoline, low-sulfur diesel, methanol, ethanol, dimethyl ether, and hydrogen. Reformulated gasoline, methanol, and ethanol are assumed to be burned in spark-ignition, direct-injection engines. Diesel and dimethyl ether are assumed to be burned in compression-ignition, direct-injection engines. Hydrogen and methanol are assumed to be used in fuel-cell vehicles. The authors have analyzed fuels infrastructure impacts under a 3X vehicle low market share scenario and a high market share scenario. The assessment shows that if 3X vehicles are mass-introduced, a considerable amount of capital investment will be needed to build new fuel production plants and to establish distribution infrastructure for methanol, ethanol, dimethyl ether, and hydrogen. Capital needs for production facilities will far exceed those for distribution infrastructure. Among the four fuels, hydrogen will bear the largest capital needs. The fuel efficiency gain by 3X vehicles translates directly into reductions in total energy demand, fossil energy demand, and CO{sub 2} emissions. The combination of fuel substitution and fuel efficiency results in substantial petroleum displacement and large reductions in emissions of nitrogen oxide, carbon monoxide, volatile organic compounds, sulfur oxide, and particulate matter of size smaller than 10 microns.

Wang, M.; Stork, K.; Vyas, A.; Mintz, M.; Singh, M.; Johnson, L.

1997-01-01T23:59:59.000Z

253

FULL FUEL CYCLE ASSESSMENT: WELL-TO-WHEELS ENERGY INPUTS,  

E-Print Network [OSTI]

California Electric Transportation Coalition California Fuel Cell Partnership California Invasive Plant Systems Inc Electric Power Research Institute Energy Independence Now Exxon Mobil Ferrellgas-Blue Rhino First Southwest Company Ford Motor Co. Friends of the Earth/Blue Water Network General Motors

254

Development of alternate extractant systems for fast reactor fuel cycle  

SciTech Connect (OSTI)

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

255

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

256

Thermo economic evaluation of oxy fuel combustion cycle in Kazeroon power plant considering enhanced oil recovery revenues  

Science Journals Connector (OSTI)

Oxy fuel combustion and conventional cycle (currently working cycle ... for enhanced oil recovery in the various oil price indices is conducted and indices net present ... models reveal that gross efficiency of t...

Ehsan Torabnejad; Ramin Haghighi-Khoshkhoo…

2014-03-01T23:59:59.000Z

257

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

SciTech Connect (OSTI)

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

258

Microsoft Word - Influence of Adv Fuel cycles on Uncertainty Final[1].docx  

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

Influence of Nuclear Fuel Influence of Nuclear Fuel Cycles on Uncertainty of Long-Term Performance of Geologic Disposal Systems Prepared for US Department of Energy Used Fuel Disposition Campaign R. P. Rechard Sandia National Laboratories M. Sutton, J.A. Blink H.R. Greenberg, M. Sharma Lawrence Livermore National Laboratory B.A. Robinson Los Alamos National Laboratory July 2012 FCRD-UFD-2012-000088 SAND2012-6383P Influence of Nuclear Fuel Cycles on Uncertainty of Geologic Disposal ii July 2012 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the US Department of Energy National Nuclear Security Administration under contract DE-AC04-94AL85000.

259

Recovery of Information from the Fast Flux Test Facility for the Advanced Fuel Cycle Initiative  

SciTech Connect (OSTI)

The Fast Flux Test Facility is the most recent Liquid Metal Reactor to operate in the United States. Information from the design, construction, and operation of this reactor was at risk as the facilities associated with the reactor are being shut down. The Advanced Fuel Cycle Initiative is a program managed by the Office of Nuclear Energy of the U.S. Department of Energy with a mission to develop new fuel cycle technologies to support both current and advanced reactors. Securing and preserving the knowledge gained from operation and testing in the Fast Flux Test Facility is an important part of the Knowledge Preservation activity in this program.

Nielsen, Deborah L.; Makenas, Bruce J.; Wootan, David W.; Butner, R. Scott; Omberg, Ronald P.

2009-09-30T23:59:59.000Z

260

Research on fuel supply rate of marine intercooled-cycle engine based on simulation experiment  

Science Journals Connector (OSTI)

The complete non-linear mathematical model and dynamic simulation model based on MATLAB/Simulink of intercooled-cycle gas turbine had been built according to the mechanism of thermodynamic system modelling method, taking the impacts into consideration such as rotational inertia, volume inertia and intercooler's thermal inertia. By analysing the existing problems of the modelling and simulation of the heat exchanger, the mathematical model and simulation model of the on-engine intercooler and off-engine intercooler were built using sub-lumped modelling method. Through the simulation study of fuel supply rate, the best fuel supply rate curve of the intercooled-cycle gas turbine was obtained.

Yu-Long Ying; Yun-Peng Cao; Shu-Ying Li

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

Life Cycle Inventory Energy Consumption and Emissions for Biodiesel versus Petroleum Diesel Fueled Construction Vehicles  

Science Journals Connector (OSTI)

Life Cycle Inventory Energy Consumption and Emissions for Biodiesel versus Petroleum Diesel Fueled Construction Vehicles ... In general, LCI emissions of HC and CO are lower if NSPS-compliant soyoil plants are used. ... The purpose of this study is to demonstrate a methodology for characterizing at high resolution the energy use and emissions of a plug-in parallel-hybrid diesel-electric school bus (PHSB) to support assessments of sensitivity to driving cycles and ... ...

Shih-Hao Pang; H. Christopher Frey; William J. Rasdorf

2009-07-16T23:59:59.000Z

262

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

SciTech Connect (OSTI)

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

263

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14  

SciTech Connect (OSTI)

The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

Schneider, K.J.

1982-09-01T23:59:59.000Z

264

Fuel-Cycle Analysis of Hydrogen-Powered Fuel-Cell Systems with the GREET Model  

Broader source: Energy.gov [DOE]

This presentation by Michael Wang of Argonne National Laboratory provides information about an analysis of hydrogen-powered fuel-cell systems.

265

The need for a characteristics-based approach to radioactive waste classification as informed by advanced nuclear fuel cycles using the fuel-cycle integration and tradeoffs (FIT) model  

SciTech Connect (OSTI)

This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. Because heat generation is generally the most important factor limiting geological repository areal loading, this analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. Waste streams generated in different fuel cycles and their possible classification based on the current U.S. framework and international standards are discussed. It is shown that the effects of separating waste streams are neglected under a source-based radioactive waste classification system. (authors)

Djokic, D. [Department of Nuclear Engineering, University of California, Berkeley, 3115B Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, S.; Pincock, L.; Soelberg, N. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

2013-07-01T23:59:59.000Z

266

Transportation Center Seminar... Life-Cycle Analysis of Transportation Fuels and Vehicle  

E-Print Network [OSTI]

with life-cycle analysis (LCA). In fact, LCA of transportation fuels and vehicle systems has a history of more than 30 years. Over this period, LCA methodologies have evolved and critical data have become readily available. This is especially true in the past ten years when LCA has been applied extensively

Bustamante, Fabián E.

267

Nuclear fuel cycle risk assessment: survey and computer compilation of risk-related literature. [Once-through Cycle and Plutonium Recycle  

SciTech Connect (OSTI)

The US Nuclear Regulatory Commission has initiated the Fuel Cycle Risk Assessment Program to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. Both the once-through cycle and plutonium recycle are being considered. A previous report generated by this program defines and describes fuel cycle facilities, or elements, considered in the program. This report, the second from the program, describes the survey and computer compilation of fuel cycle risk-related literature. Sources of available information on the design, safety, and risk associated with the defined set of fuel cycle elements were searched and documents obtained were catalogued and characterized with respect to fuel cycle elements and specific risk/safety information. Both US and foreign surveys were conducted. Battelle's computer-based BASIS information management system was used to facilitate the establishment of the literature compilation. A complete listing of the literature compilation and several useful indexes are included. Future updates of the literature compilation will be published periodically. 760 annotated citations are included.

Yates, K.R.; Schreiber, A.M.; Rudolph, A.W.

1982-10-01T23:59:59.000Z

268

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

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

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

269

Human capital needs - teaching, training and coordination for nuclear fuel cycle  

SciTech Connect (OSTI)

Human capital is the accumulation of competencies, knowledge, social and creativity skills and personality attributes, which are necessary to perform work so as to produce economic value. In the frame of the nuclear fuel cycle, this is of paramount importance that the right human capital exists and in Europe this is fostered by a series of integrated or directed projects. The teaching, training and coordination will be discussed in the frame of University curricula with examples from several programs, like e.g. the Master of Nuclear Engineering at Chalmers University, Sweden and two FP7 EURATOM Projects: CINCH - a project for cooperation in nuclear chemistry - and ASGARD - a research project on advanced or novel nuclear fuels and their reprocessing issues for generation IV reactors. The integration of the university curricula in the market needs but also the anchoring in the research and future fuel cycles will be also discussed, with examples from the ASGARD project. (authors)

Retegan, T.; Ekberg, C. [Department of Chemistry and Biological Engineering, Nuclear Chemistry, Chalmers University of Technology, Kemivaegen 4, 41296 Gothenburg (Sweden); John, J. [Department of Nuclear Chemistry, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Brehova 7, 115 19 Prague 1 (Czech Republic); Nordlund, A. [Nuclear Engineering, Chalmers University of Technology, Kemivaegen 4, 41296 Gothenburg (Sweden)

2013-07-01T23:59:59.000Z

270

Proliferation resistance of the fuel cycle for the Integral Fast Reactor  

SciTech Connect (OSTI)

Argonne National Laboratory has developed an electrorefining pyrochemical process for recovery and recycle of metal fuel discharged from the Integral Fast Reactor (FR). This inherently low decontamination process has an overall decontamination factor of only about 100 for the plutonium metal product. As a result, all of the fuel cycle operations must be conducted in heavily shielded cells containing a high-purity argon atmosphere. The FR fuel cycle possesses high resistance to clandestine diversion or overt, state- supported removal of plutonium for nuclear weapons production because of two main factors: the highly radioactive product, which is also contaminated with heat- and neutron-producing isotopes of plutonium and other actinide elements, and the difficulty of removing material from the FR facility through the limited number of cell transfer locks without detection.

Burris, L.

1993-09-01T23:59:59.000Z

271

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

SciTech Connect (OSTI)

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

272

Life-Cycle Water and Greenhouse Gas Implications of Alternative Fuel  

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

Life-Cycle Water and Greenhouse Gas Implications of Alternative Fuel Life-Cycle Water and Greenhouse Gas Implications of Alternative Fuel Production Speaker(s): Corinne Scown Date: January 31, 2012 - 12:00pm Location: 90-3122 Seminar Host/Point of Contact: Michael Sohn If the goal of science is to understand the structure and behavior of the physical and natural world, and the goal of engineering is to design, build, and manage systems that serve society's needs, then the study of civil infrastructure systems acts as a link between the two. Understanding the reliance of engineered systems on constrained natural resources, as well as their impact on human well-being and the environment, is key to building and maintaining infrastructure that is sustainable in the broader sense. This talk will explore the important role of life-cycle assessment and optimization in assessing such questions as: a.)

273

Cofiring: technological option in Romania for promoting cleaner fossil fuels usage.  

E-Print Network [OSTI]

??Co-firing refers to the simultaneous or alternative utilisation of two or more fuels in a combustion unit for the purpose of heat/power generation and it… (more)

Marin, Bogdan

2008-01-01T23:59:59.000Z

274

Implications of Plutonium isotopic separation on closed fuel cycles and repository design  

SciTech Connect (OSTI)

Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation. This would have large impacts on LWR closed fuel cycles and waste management. If Pu-240 is removed before recycling plutonium as mixed oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, Americium, and Curium. Pu-240 is a fertile material and thus can be replaced by U-238. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Eliminating fertile Pu-240 and Pu-242 reduces the plutonium content in MOX fuel and simplifies fabrication. Reducing production of Pu-241 reduces production of Am-241 - the primary heat generator in spent nuclear fuels after several decades. Reducing heat generating Am-241 would reduce repository cost and waste toxicity. Avoiding Am- 241 avoids its decay product Np-237, a nuclide that partly controls long-term oxidizing repository performance. Most of these benefits also apply to LWR plutonium recycled into fast reactors. There are benefits for plutonium isotopic separation in fast reactor fuel cycles (particularly removal of Pu-242) but the benefits are less. (author)

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave. Cambridge, MA 20129 (United States)

2013-07-01T23:59:59.000Z

275

An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle  

SciTech Connect (OSTI)

Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/ or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K. NNL

2011-01-13T23:59:59.000Z

276

An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle  

SciTech Connect (OSTI)

Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Boyer, B. D. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K., NNL

2010-11-24T23:59:59.000Z

277

Development and use of the GREET model to estimate fuel-cycle energy use and emissions of various transportation technologies and fuels  

SciTech Connect (OSTI)

This report documents the development and use of the Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation (GREET) model. The model, developed in a spreadsheet format, estimates the full fuel- cycle emissions and energy use associated with various transportation fuels for light-duty vehicles. The model calculates fuel-cycle emissions of five criteria pollutants (volatile organic compounds, carbon monoxide, nitrogen oxides, sulfur oxides, and particulate matter measuring 10 microns or less) and three greenhouse gases (carbon dioxide, methane, and nitrous oxide). The model also calculates the total fuel-cycle energy consumption, fossil fuel consumption, and petroleum consumption using various transportation fuels. The GREET model includes 17 fuel cycles: petroleum to conventional gasoline, reformulated gasoline, clean diesel, liquefied petroleum gas, and electricity via residual oil; natural gas to compressed natural gas, liquefied petroleum gas, methanol, hydrogen, and electricity; coal to electricity; uranium to electricity; renewable energy (hydrogen, solar energy, and wind) to electricity; corn, woody biomass, and herbaceous biomass to ethanol; and landfill gases to methanol. This report presents fuel-cycle energy use and emissions for a 2000 model-year car powered by each of the fuels that are produced from the primary energy sources considered in the study.

Wang, M.Q.

1996-03-01T23:59:59.000Z

278

Molten salt considerations for accelerator-driven subcritical fission to close the nuclear fuel cycle  

SciTech Connect (OSTI)

The host salt selection, molecular modeling, physical chemistry, and processing chemistry are presented here for an accelerator-driven subcritical fission in a molten salt core (ADSMS). The core is fueled solely with the transuranics (TRU) and long-lived fission products (LFP) from used nuclear fuel. The neutronics and salt composition are optimized to destroy the transuranics by fission and the long-lived fission products by transmutation. The cores are driven by proton beams from a strong-focusing cyclotron stack. One such ADSMS system can destroy the transuranics in the used nuclear fuel produced by a 1GWe conventional reactor. It uniquely provides a method to close the nuclear fuel cycle for green nuclear energy.

Sooby, Elizabeth; Baty, Austin; Gerity, James; McIntyre, Peter; Melconian, Karie; Pogue, Nathaniel; Sattarov, Akhdiyor [Department of Physics and Astronomy, Texas A and M University, 4242 TAMU, College Station TX 77843 (United States); Adams, Marvin; Tsevkov, Pavel [Nuclear Engineering, Texas A and M University, Spence St., College Station TX 77843 (United States); Phongikaroon, Supathorn [Center for Advanced Energy Studies, University of Idaho, 995 University Blvd, Idaho Falls, ID 83401 (United States); Simpson, Michael; Tripathy, Prabhat [Materials Fuels Complex, Idaho National Laboratory, Idaho Falls, ID 83415 (United States)

2013-04-19T23:59:59.000Z

279

Energy Return on Investment from Recycling Nuclear Fuel  

SciTech Connect (OSTI)

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

280

Comparative Analysis of the Production Costs and Life-Cycle GHG Emissions of FT-Liquid Fuels from Coal and  

E-Print Network [OSTI]

Coal and Natural Gas Figure S1 shows a graphical description of the life cycle of coal-to-liquids (CTL) and gas-to-liquids (GTL). Figure S1: Life Cycle of Coal-Based and Natural Gas-Based Fischer-Tropsch LiquidComparative Analysis of the Production Costs and Life- Cycle GHG Emissions of FT-Liquid Fuels from

Jaramillo, Paulina

Note: This page contains sample records for the topic "fuel cycle options" 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

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

SciTech Connect (OSTI)

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

282

Assessment of the environmental footprint of nuclear energy systems. Comparison between closed and open fuel cycles  

Science Journals Connector (OSTI)

Abstract Energy perspectives for the current century are dominated by the anticipated significant increase of energy needs. Particularly, electricity consumption is anticipated to increase by a factor higher than two before 2050. Energy choices are considered as structuring political choices that implies a long-standing and stable policy based on objective criteria. LCA (life cycle analysis) is a structured basis for deriving relevant indicators which can allow the comparison of a wide range of impacts of different energy sources. Among the energy-mix, nuclear power is anticipated to have very low GHG-emissions. However, its viability is severely addressed by the public opinion after the Fukushima accident. Therefore, a global LCA of the French nuclear fuel cycle was performed as a reference model. Results were compared in terms of impact with other energy sources. It emphasized that the French nuclear energy is one of the less impacting energy, comparable with renewable energy. In a second, part, the French scenario was compared with an equivalent open fuel cycle scenario. It demonstrates that an open fuel cycle would require about 16% more natural uranium, would have a bigger environmental footprint on the “non radioactive indicators” and would produce a higher volume of high level radioactive waste.

Ch. Poinssot; S. Bourg; N. Ouvrier; N. Combernoux; C. Rostaing; M. Vargas-Gonzalez; J. Bruno

2014-01-01T23:59:59.000Z

283

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

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

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

284

Fuel Cycle Research & Development Technical Monthly - June 2012  

SciTech Connect (OSTI)

Topics are: (1) MPACT Campaign - (a) Management and Integration - Coordination meetings between NE and NA-22, NA-24, and NA-82 were conducted the week of June 11th. Preparations are being made for the next MPACT working group meeting, scheduled for Aug 28-30 at Idaho Falls. In addition to covering accomplishments and discussing future plans, a site tour of INL facilities (MFC, EBR, ATR, INTEC) is being organized. (2) Accounting and Control Technologies - (a) Microcalorimetry - Now operating 256-pixel array at LANL. We are in the process of tuning detector parameters to improve and optimize performance. Preliminary measurements show approximate number of live pixels is similar to that observed previously at NIST. Continuing to study contribution to systematic error from uncertainties in tabulated gamma-ray energies. (b) Electrochemical Sensor - Testing of sensors fashioned from different precursor materials continued. SEM analysis of all used sensors has been or will be performed. (c) Lead Slowing Down Spectrometer - Ongoing perturbation calculations are providing information on the fundamental systematic error limits of LSDS. In order to achieve separating the contribution of Pu and 235U to the signal, there will need to be tight controls on systematic errors. Continuing to look into a He4 detector. Research into local construction of a He4 detector continued. We have started to apply the algorithm to test the LSDS using experimental data from previous RPI measurements. PNNL also developed a plan to address the lack of statistics in the MCNP modeling of the NGSI 64 assemblies. The ISU graduate student built and tested a fission chamber to gain experience with them. (d) Fast Neutron Imaging to Quantify Nuclear Materials - The imaging detector design was modified for each pixel to have an 8 x 8 pixel array. Quotations and purchasing process for components, including the new PSD scintillator are in progress. (e) Fast Neutron Multiplicity Analysis - The team submitted two papers to the upcoming INMM meeting that are related to the fast neutron multiplicity R&D effort. Progress was made on the project's main goal of designing a concept for a prototype fast-neutron multiplicity counter. We started laying out the outline for the final report. We have been working with our ORNL collaborators to develop a new digitizer system to support our experimental campaign planned for next year. (3) MPACT Analysis Tools - (a) Multi-isotope Process Monitor - Fuel characterization framework development continued during June. A report describing the methodologies is being completed. Kenneth Dayman, from University of Texas, spent a week at PNNL wrapping up his master's research and working on a journal submission covering that work. The target journal is the IEEE transactions on Nuclear Science; submission is planned for the end of July. A proposal to instrument H-Canyon is being prepared in conjunction with SRNL and the NNSA's NGSI program. The impact of gamma-ray spectrum counting statistics on the precision of relative radioisotope component intensities as reconstructed via Principal Component Regression (PCR) continued in June with Monte Carlo simulations of a two-component (i.e., two radioisotope) system. This work generalizes earlier studies in FY12 in which Poisson counting variations of only a single spectrum component were simulated. (b) Modeling and Simulation for Analysis of Safeguards Performance (Electrochemical) - Preliminary insights into safeguards challenges and the initial design for an electrochemical plant have been written up into an INMM paper and will be presented at the INMM Summer Meeting. Work is currently adding a new visualization capability for integrating materials accountancy with physical protection. (c) Material Control including Process Monitoring (Pattern Recognition, Sensors) - Fabrication of quartz chips continued at an external foundry. Awaiting delivery of the heat exchange manifold and chip holder. (d) MPACT System Integration and Technical Support - The initial report on cost-basis metrics for nucle

Miller, Michael C. [Los Alamos National Laboratory

2012-07-25T23:59:59.000Z

285

Hybrid combustion-premixed gasoline homogeneous charge ignited by injected diesel fuel-4-stroke cycle engines  

SciTech Connect (OSTI)

This paper describes the formation and testing of two hybrid combustion engines, wherein a premixed gasoline homogeneous charge was ignited by a small amount of injected diesel fuel under high compression ratio, by modifying open chamber and prechamber 4-stroke cycle diesel engines. It was found that the premixed gasoline was effective not only for decreasing the fuel consumption but also for reducing the smoke density both in the heavy and over-load regions. The effect of introducing a small amount N/sub 2/ gas for suppressing the diesel knock in the heavy load region also was examined.

Yonetani, H.; Okanishi, N.; Fukutani, I.; Watanabe, E.

1989-01-01T23:59:59.000Z

286

System Level Analysis of Hydrogen Storage Options - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

4 4 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Rajesh K. Ahluwalia (Primary Contact), T. Q. Hua, J-K Peng, Hee Seok Roh, and Romesh Kumar Argonne National Laboratory 9700 South Cass Avenue Argonne, IL 60439 Phone: (630) 252-5979 Email: walia@anl.gov DOE Manager HQ: Grace Ordaz Phone: (202) 586-8350 Email: Grace.Ordaz@ee.doe.gov Start Date: October 1, 2004 Projected End Date: September 30, 2014 Objective The overall objective of this effort is to support DOE with independent system level analyses of various H 2 storage approaches, to help to assess and down-select options, and to determine the feasibility of meeting DOE targets. Fiscal Year (FY) 2012 Objectives Model various developmental hydrogen storage systems. * Provide results to Hydrogen Storage Engineering Center *

287

ASSESSMENT OF POSSIBLE CYCLE LENGTHS FOR FULLY-CERAMIC MICRO-ENCAPSULATED FUEL-BASED LIGHT WATER REACTOR CONCEPTS  

SciTech Connect (OSTI)

The use of TRISO-particle-based dispersion fuel within SiC matrix and cladding materials has the potential to allow the design of extremely safe LWRs with failure-proof fuel. This paper examines the feasibility of LWR-like cycle length for such a low enriched uranium fuel with the imposed constraint of strictly retaining the original geometry of the fuel pins and assemblies. The motivation for retaining the original geometry is to provide the ability to incorporate the fuel 'as-is' into existing LWRs while retaining their thermal-hydraulic characteristics. The feasibility of using this fuel is assessed by looking at cycle lengths and fuel failure rates. Other considerations (e.g., safety parameters, etc.) were not considered at this stage of the study. The study includes the examination of different TRISO kernel diameters without changing the coating layer thicknesses. The study shows that a naive use of UO{sub 2} results in cycle lengths too short to be practical for existing LWR designs and operational demands. Increasing fissile inventory within the fuel compacts shows that acceptable cycle lengths can be achieved. In this study, starting with the recognized highest packing fraction practically achievable (44%), higher enrichment, larger fuel kernel sizes, and the use of higher density fuels have been evaluated. The models demonstrate cycle lengths comparable to those of ordinary LWRs. As expected, TRISO particles with extremely large kernels are shown to fail under all considered scenarios. In contrast, the designs that do not depart too drastically from those of the nominal NGNP HTR fuel TRISO particles are shown to perform satisfactorily and display a high rates of survival under all considered scenarios. Finally, it is recognized that relaxing the geometry constraint will result in satisfactory cycle lengths even using UO{sub 2}-loaded TRISO particles-based fuel with enrichment at or below 20 w/o.

R. Sonat Sen; Michael A. Pope; Abderrafi M. Ougouag; Kemal Pasamehmetoglu; Francesco Venneri

2012-04-01T23:59:59.000Z

288

Initial concepts on energetics and mass releases during nonnuclear explosive events in fuel cycle facilities  

SciTech Connect (OSTI)

Non-nuclear explosions are one of the initiating events (accidents) considered in the US Nuclear Regulatory Commission study of formal methods for estimating the airborne release of radionuclides from fuel cycle facilities. Methods currently available to estimate the energetics and mass airborne release from the four types of non-nuclear explosive events (fast and slow physical explosions and fast and slow chemical explosions) are reviewed. The likelihood that fast physical explosions will occur in fuel cycle facilities appears to be remote and this type of explosion is not considered. Methods to estimate the consequences of slow physical and fast chemical explosions are available. Methods to estimate the consequences of slow chemical explosions are less well defined.

Halverson, M.A.; Mishima, J.

1986-09-01T23:59:59.000Z

289

Microsoft PowerPoint - NEAC on Science Based Fuel Cycle R&D.PPT [Compatibility Mode]  

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

Advanced Advanced Fuel Cycle Initiative The Advanced Fuel Cycle Initiative Science Based Fuel Cycle y Research and Development Phillip Finck Idaho National Laboratory June 9, 2009 Former Programmatic Approach Incremental improvement of existing technologies to allow for short-term (~20 years) deployment, driven by better utilization of Yucca Mountain y ) p y , y - Specific choice of technologies and integrated system (dictated by time frame and Yucca Mountain characteristics) - Challenges were well identified - Engineering approaches were chosen to address these challenges - Fundamental challenges had also been identified (2006 workshops), but were marginally acted upon (e.g., modeling and simulation) The industrial approach resulted in very limited investment in the tools needed

290

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

SciTech Connect (OSTI)

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

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

1980-06-01T23:59:59.000Z

291

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

SciTech Connect (OSTI)

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

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

1997-05-01T23:59:59.000Z

292

Microsoft PowerPoint - NEAC Rpt of Fuel Cycle comm slides  

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

t t f th F l C l Report of the Fuel Cycle Research and Development p Subcommittee of NEAC B Ri h (Ch i ) Burton Richter (Chairman) Margaret Chu Darleane Hoffman Ray Juzaitis Ray Juzaitis Sekazi Mtingwa Ronald P. Omberg Joy L. Rempe Joy L. Rempe Dominique Warin June 12, 2012 Washington, D.C. Context for the Meeting Context for the Meeting * Fukushima - Increased fault tolerance for Fukushima Increased fault tolerance for reactor systems * Used Fuel Disposal - Response to BRC is being Used Fuel Disposal Response to BRC is being developed, but it is not ready. Nonetheless, there are many things that can be done * Review of some things that were already in the works (Systems Study; Separation & Waste Form * Budget was not available at time of meeting

293

Evaluation of Powertrain Options and Component Sizing for MD and HD Applications on Real World Drive Cycles  

Broader source: Energy.gov [DOE]

2011 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation

294

Environmental Impacts, Health and Safety Impacts, and Financial Costs of the Front End of the Nuclear Fuel Cycle  

SciTech Connect (OSTI)

FEFC processes, unlike many of the proposed fuel cycles and technologies under consideration, involve mature operational processes presently in use at a number of facilities worldwide. This report identifies significant impacts resulting from these current FEFC processes and activities. Impacts considered to be significant are those that may be helpful in differentiating between fuel cycle performance and for which the FEFC impact is not negligible relative to those from the remainder of the full fuel cycle. This report: • Defines ‘representative’ processes that typify impacts associated with each step of the FEFC, • Establishes a framework and architecture for rolling up impacts into normalized measures that can be scaled to quantify their contribution to the total impacts associated with various fuel cycles, and • Develops and documents the bases for estimates of the impacts and costs associated with each of the representative FEFC processes.

Brett W Carlsen; Urairisa Phathanapirom; Eric Schneider; John S. Collins; Roderick G. Eggert; Brett Jordan; Bethany L. Smith; Timothy M. Ault; Alan G. Croff; Steven L. Krahn; William G. Halsey; Mark Sutton; Clay E. Easterly; Ryan P. Manger; C. Wilson McGinn; Stephen E. Fisher; Brent W. Dixon; Latif Yacout

2013-07-01T23:59:59.000Z

295

Comparative Fuel Cycle Analysis of Critical and Subcritical Fast Reactor Transmutation Systems  

SciTech Connect (OSTI)

Fuel cycle analyses are performed to evaluate the impacts of further transmutation of spent nuclear fuel on high-level and low-level waste mass flows into repositories, on the composition and toxicity of the high-level waste, on the capacity of high-level waste repositories, and on the proliferation resistance of the high-level waste. Storage intact of light water reactor (LWR) spent nuclear fuel, a single recycle in a LWR of the plutonium as mixed-oxide fuel, and the repeated recycle of the transuranics in critical and subcritical fast reactors are compared with the focus on the waste management performance of these systems. Other considerations such as cost and technological challenges were beyond the scope of this study. The overall conclusion of the studies is that repeated recycling of the transuranics from spent nuclear fuel would significantly increase the capacity of high-level waste repositories per unit of nuclear energy produced, significantly increase the nuclear energy production per unit mass of uranium ore mined, significantly reduce the radiotoxicity of the waste streams per unit of nuclear energy produced, and significantly enhance the proliferation resistance of the material stored in high-level waste repositories.

Hoffman, Edward A.; Stacey, Weston M. [Georgia Institute of Technology (United States)

2003-10-15T23:59:59.000Z

296

Life-cycle assessment of diesel, natural gas and hydrogen fuel cell bus transportation systems  

Science Journals Connector (OSTI)

The Sustainable Transport Energy Programme (STEP) is an initiative of the Government of Western Australia, to explore hydrogen fuel cell technology as an alternative to the existing diesel and natural gas public transit infrastructure in Perth. This project includes three buses manufactured by DaimlerChrysler with Ballard fuel cell power sources operating in regular service alongside the existing natural gas and diesel bus fleets. The life-cycle assessment (LCA) of the fuel cell bus trial in Perth determines the overall environmental footprint and energy demand by studying all phases of the complete transportation system, including the hydrogen infrastructure, bus manufacturing, operation, and end-of-life disposal. The \\{LCAs\\} of the existing diesel and natural gas transportation systems are developed in parallel. The findings show that the trial is competitive with the diesel and natural gas bus systems in terms of global warming potential and eutrophication. Emissions that contribute to acidification and photochemical ozone are greater for the fuel cell buses. Scenario analysis quantifies the improvements that can be expected in future generations of fuel cell vehicles and shows that a reduction of greater than 50% is achievable in the greenhouse gas, photochemical ozone creation and primary energy demand impact categories.

Jamie Ally; Trevor Pryor

2007-01-01T23:59:59.000Z

297

Summary of national and international fuel cycle and radioactive waste management programs, 1984  

SciTech Connect (OSTI)

Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories.

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

1984-07-01T23:59:59.000Z

298

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

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

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-

299

Core materials development for the fuel cycle R&D program  

SciTech Connect (OSTI)

The Fuel Cycle Research and Development program is investigating methods of burning minor actinides in a transmutation fuel. One of the challenges of achieving this goal is to develop fuels capable of reaching extreme burnup levels (e.g. 40%). To achieve such high burnup levels fast reactor core materials (cladding and duct) must be able to withstand very high doses (>300 dpa design goal) while in contact with the coolant and the fuel. Thus, these materials must withstand radiation effects that promote low temperature embrittlement, radiation induced segregation, high temperature helium embrittlement, swelling, accelerated creep, corrosion with the coolant, and chemical interaction with the fuel (FCCI). To develop and qualify materials to a total fluence greater than 200 dpa requires development of advanced alloys and irradiations in fast reactors to test these alloys. Test specimens of ferritic/martensitic alloys (T91/HT-9) previously irradiated in the FFTF reactor up to 210 dpa at a temperature range of 350 750 C are presently being tested. This includes analysis of a duct made of HT-9 after irradiation to a total dose of 155 dpa at temperatures from 370 to 510 C. Compact tension, charpy and tensile specimens have been machined from this duct and mechanical testing as well as SANS and Mossbauer spectroscopy are currently being performed. Initial results from compression testing and Charpy testing reveal a strong increase in yield stress (400 MPa) and a large increase in DBTT (up to 230 C) for specimens irradiated at 383 C to a dose of 28 dpa. Less hardening and a smaller increase in DBTT was observed for specimens irradiated at higher temperatures up to 500 C. Advanced radiation tolerant materials are also being developed to enable the desired extreme fuel burnup levels. Specifically, coatings are being developed to minimize FCCI, and research is underway to fabricate large heats of radiation tolerant oxide dispersion steels with homogeneous oxide dispersions.

Toloczko, M [Pacific Northwest National Laboratory (PNNL); Maloy, S [Los Alamos National Laboratory (LANL); Cole, James I. [Idaho National Laboratory (INL); Byun, Thak Sang [ORNL

2011-01-01T23:59:59.000Z

300

Core Materials Development for the Fuel Cycle R&D Program  

SciTech Connect (OSTI)

The Fuel Cycle Research and Development program is investigating methods of burning minor actinides in a transmutation fuel. One of the challenges of achieving this goal is to develop fuels capable of reaching extreme burnup levels (e.g. 40%). To achieve such high burnup levels fast reactor core materials (cladding and duct) must be able to withstand very high doses (greater than 300 dpa design goal) while in contact with the coolant and the fuel. Thus, these materials must withstand radiation effects that promote low temperature embrittlement, radiation induced segregation, high temperature helium embrittlement, swelling, accelerated creep, corrosion with the coolant, and chemical interaction with the fuel (FCCI). To develop and qualify materials to a total fluence greater than 200 dpa requires development of advanced alloys and irradiations in fast reactors to test these alloys. Test specimens of ferritic/martensitic alloys (T91/HT-9) previously irradiated in the FFTF reactor up to 210 dpa at a temperature range of 350-750 C are presently being tested. This includes analysis of a duct made of HT-9 after irradiation to a total dose of 155 dpa at temperatures from 370 to 510 C. Compact tension, charpy and tensile specimens have been machined from this duct and mechanical testing as well as SANS and Mossbauer spectroscopy are currently being performed. Initial results from compression testing and Charpy testing reveal a strong increase in yield stress ({approx}400 MPa) and a large increase in DBTT (up to 230 C) for specimens irradiated at 383 C to a dose of 28 dpa. Less hardening and a smaller increase in DBTT was observed for specimens irradiated at higher temperatures up to 500 C. Advanced radiation tolerant materials are also being developed to enable the desired extreme fuel burnup levels. Specifically, coatings are being developed to minimize FCCI, and research is underway to fabricate large heats of radiation tolerant oxide dispersion steels with homogeneous oxide dispersions.

S. A. Maloy; M. Toloczko; J. Cole; T. S. Byun

2011-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

Contribution of Clinch River Breeder Reactor plant design and development to the LMFBR fuel cycle  

SciTech Connect (OSTI)

This paper describes how the CRBRP development and CRBRP focus of the LMFBR base technology program have led to advances in the state of the art in physics, thermal-hydraulics, structural analysis, core restraint, seismic analysis, and analysis of hypothetical core-disruptive accident energetics, all of which have been incorporated through disciplined engineering into the final CRBRP design. The total development in the US of fuels and materials, the analytical advances made on CRBRP design, and the incorporation of the latest experimental results into that design have put the US technology in general and the CRBRP design in particular at the forefront of technology. This has placed the US in a position to develop the most favorable LMFBR fuel cycle.

Riley, D.R.; Dickson, P.W.

1981-01-01T23:59:59.000Z

302

Comparison between two optimization strategies for solid oxide fuel cell–gas turbine hybrid cycles  

Science Journals Connector (OSTI)

This paper compares the performance characteristics of a combined power system with solid oxide fuel cell (SOFC) and gas turbine (GT) working under two thermodynamic optimization strategies. Expressions of the optimized power output and efficiency for both the subsystems and the SOFC-GT hybrid cycle are derived. Optimal performance characteristics are discussed and compared in detail through a parametric analysis to evaluate the impact of multi-irreversibilities that take into account on the system behaviour. It is found that there exist certain new optimum criteria for some important design and operating parameters. Engineers should find the methodologies developed in this paper useful in the optimal design and practical operation of complex hybrid fuel cell power plants.

Yingru Zhao; Nilay Shah; Nigel Brandon

2011-01-01T23:59:59.000Z

303

Life-cycle assessment of corn-based butanol as a potential transportation fuel.  

SciTech Connect (OSTI)

Butanol produced from bio-sources (such as corn) could have attractive properties as a transportation fuel. Production of butanol through a fermentation process called acetone-butanol-ethanol (ABE) has been the focus of increasing research and development efforts. Advances in ABE process development in recent years have led to drastic increases in ABE productivity and yields, making butanol production worthy of evaluation for use in motor vehicles. Consequently, chemical/fuel industries have announced their intention to produce butanol from bio-based materials. The purpose of this study is to estimate the potential life-cycle energy and emission effects associated with using bio-butanol as a transportation fuel. The study employs a well-to-wheels analysis tool--the Greenhouse Gases, Regulated Emissions and Energy Use in Transportation (GREET) model developed at Argonne National Laboratory--and the Aspen Plus{reg_sign} model developed by AspenTech. The study describes the butanol production from corn, including grain processing, fermentation, gas stripping, distillation, and adsorption for products separation. The Aspen{reg_sign} results that we obtained for the corn-to-butanol production process provide the basis for GREET modeling to estimate life-cycle energy use and greenhouse gas emissions. The GREET model was expanded to simulate the bio-butanol life cycle, from agricultural chemical production to butanol use in motor vehicles. We then compared the results for bio-butanol with those of conventional gasoline. We also analyzed the bio-acetone that is coproduced with bio-butanol as an alternative to petroleum-based acetone. Our study shows that, while the use of corn-based butanol achieves energy benefits and reduces greenhouse gas emissions, the results are affected by the methods used to treat the acetone that is co-produced in butanol plants.

Wu, M.; Wang, M.; Liu, J.; Huo, H.; Energy Systems

2007-12-31T23:59:59.000Z

304

Cyclus fuel cycle simulation capabilities with the CYDER disposal system model  

SciTech Connect (OSTI)

An algorithm and supporting database for rapid thermal repository loading calculation was implemented in CYDER. This algorithm employs a Specific Temperature Change (STC) method and has resulted from combining detailed spent nuclear fuel composition data with a detailed thermal repository performance analysis tool from Lawrence Livermore National Laboratory (LLNL), Argonne National Laboratory (ANL), and the Used Fuel Disposition (UFD) campaign. By abstraction of and benchmarking against these detailed thermal models, CYDER captures the dominant physics of thermal phenomena affecting repository capacity in various geologic media and as a function of spent fuel composition. Abstraction based on detailed computational thermal repository performance calculations with the LLNL semi-analytic model has resulted in implementation of the STC estimation algorithm and a supporting reference dataset. This method is capable of rapid estimation of temperature increase near emplacement tunnels as a function of waste composition, limiting radius, waste package spacing, near field thermal conductivity and near field thermal diffusivity. The sensitivity analyses and validation efforts conducted in this work demonstrate the capability of the CYDER tool to provide repository capacity and performance metrics in the context of dynamic fuel cycle.

Huff, K.D. [Argonne National Laboratory, 9700 S. Cass Ave., Lemont, IL 60439 (United States); University of Wisconsin, 1500 Engineering Drive, Madison, WI 53706 (United States)

2013-07-01T23:59:59.000Z

305

Dynamic Systems Analysis Report for Nuclear Fuel Recycle  

SciTech Connect (OSTI)

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

306

Measures of the environmental footprint of the front end of the nuclear fuel cycle  

SciTech Connect (OSTI)

Previous estimates of environmental impacts associated with the front end of the nuclear fuel cycle (FEFC) have focused primarily on energy consumption and CO2 emissions. Results have varied widely. This work builds upon reports from operating facilities and other primary data sources to build a database of front end environmental impacts. This work also addresses land transformation and water withdrawals associated with the processes of the FEFC. These processes include uranium extraction, conversion, enrichment, fuel fabrication, depleted uranium disposition, and transportation. To allow summing the impacts across processes, all impacts were normalized per tonne of natural uranium mined as well as per MWh(e) of electricity produced, a more conventional unit for measuring environmental impacts that facilitates comparison with other studies. This conversion was based on mass balances and process efficiencies associated with the current once-through LWR fuel cycle. Total energy input is calculated at 8.7 x 10- 3 GJ(e)/MWh(e) of electricity and 5.9 x 10- 3 GJ(t)/MWh(e) of thermal energy. It is dominated by the energy required for uranium extraction, conversion to fluoride compound for subsequent enrichment, and enrichment. An estimate of the carbon footprint is made from the direct energy consumption at 1.7 kg CO2/MWh(e). Water use is likewise dominated by requirements of uranium extraction, totaling 154 L/MWh(e). Land use is calculated at 8 x 10- 3 m2/MWh(e), over 90% of which is due to uranium extraction. Quantified impacts are limited to those resulting from activities performed within the FEFC process facilities (i.e. within the plant gates). Energy embodied in material inputs such as process chemicals and fuel cladding is identified but not explicitly quantified in this study. Inclusion of indirect energy associated with embodied energy as well as construction and decommissioning of facilities could increase the FEFC energy intensity estimate by a factor of up to 2.

E. Schneider; B. Carlsen; E. Tavrides; C. van der Hoeven; U. Phathanapirom

2013-11-01T23:59:59.000Z

307

Energy analysis of the coal fuel cycle in an Appalachian coal county  

SciTech Connect (OSTI)

Preliminary results from an energy analysis of the coal fuel cycle in an Appalachian coal county have provided a systematic assessment of hidden energy subsidies in extraction, transport, processing, and combustion. Current results indicate that the system operates at an annual energy deficit of approximately 350 x 10/sup 10/ kcal. A major loss is depletion of the coal resource base by use of inefficient mining techniques. Although of smaller magnitude, reductions in work force and community productivity from occupational accidents, disease, and road maintenance requirements for transport also appear to be significant. Further assessment is needed to verify assumptions and characterize additional data bases. 39 references.

Watson, A.P.

1984-03-01T23:59:59.000Z

308

Life cycle study of coal-based dimethyl ether as vehicle fuel for urban bus in China  

Science Journals Connector (OSTI)

With life cycle assessment (LCA) methodology, a life cycle model of coal-based dimethyl ether (CBDME) as a vehicle fuel is established for China. Its life cycle from well to wheel are divided into three phases. They are feedstock extraction, fuel production and fuel consumption in vehicle. The primary energy consumption (PEC) and global warming potential (GWP) of CBDME pathway are analyzed and compared with coal-based diesel (CBD) as a latent rival to replace conventional petroleum-based diesel (CPBD). This study demonstrates that the LCA methodology is very suitable and effective for the choice of vehicle fuels. One result is that the greenhouse gases (GHGs) emission of coal-based vehicle fuel pathways is usually concentrated on fuel production stage. The percentages of CBDME and CBD pathways both exceed 60%. The application of carbon capture and storage (CCS) is helpful for coal-based vehicle fuel pathways to improve their global warming effect dramatically. Compared with CBD pathway, CBDME pathway consumes less PEC and emits less \\{GHGs\\} emission as well. Even though the CCS and CH4-fired generation are used, the advantages of CBDME are still kept. For saving petroleum energy and reducing global warming effect, CBDME has greater potential than CBD to substitute CPBD under current fuel synthesis technologies. If the hurdles such as the maturity of engine and vehicle technologies, corresponding regulations and standards and infrastructures are reliably solved, CBDME will have better prospect in China.

Liang Zhang; Zhen Huang

2007-01-01T23:59:59.000Z

309

Pyroprocessing of oxidized sodium-bonded fast reactor fuel - An experimental study of treatment options for degraded EBR-II fuel  

SciTech Connect (OSTI)

An experimental study was conducted to assess pyrochemical treatment options for degraded EBR-II fuel. As oxidized material, the degraded fuel would need to be converted back to metal to enable electrorefining within an existing electro-metallurgical treatment process. A lithium-based electrolytic reduction process was studied to assess the efficacy of converting oxide materials to metal with a particular focus on the impact of zirconium oxide and sodium oxide on this process. Bench-scale electrolytic reduction experiments were performed in LiCl-Li{sub 2}O at 650 C. degrees with combinations of manganese oxide (used as a surrogate for uranium oxide), zirconium oxide, and sodium oxide. In the absence of zirconium or sodium oxide, the electrolytic reduction of MnO showed nearly complete conversion to metal. The electrolytic reduction of a blend of MnO-ZrO{sub 2} in LiCl - 1 wt% Li{sub 2}O showed substantial reduction of manganese, but only 8.5% of the zirconium was found in the metal phase. The electrolytic reduction of the same blend of MnO-ZrO{sub 2} in LiCl - 1 wt% Li{sub 2}O - 6.2 wt% Na{sub 2}O showed substantial reduction of manganese, but zirconium reduction was even less at 2.4%. This study concluded that ZrO{sub 2} cannot be substantially reduced to metal in an electrolytic reduction system with LiCl - 1 wt% Li{sub 2}O at 650 C. degrees due to the perceived preferential formation of lithium zirconate. This study also identified a possible interference that sodium oxide may have on the same system by introducing a parasitic and cyclic reaction of dissolved sodium metal between oxidation at the anode and reduction at the cathode. When applied to oxidized sodium-bonded EBR-II fuel (e.g., U-10Zr), the prescribed electrolytic reduction system would not be expected to substantially reduce zirconium oxide, and the accumulation of sodium in the electrolyte could interfere with the reduction of uranium oxide, or at least render it less efficient.

Hermann, S.D.; Gese, N.J. [Separations Department, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Wurth, L.A. [Zinc Air Inc., 5314-A US Hwy 2 West, Columbia Falls, MT 59912 (United States)

2013-07-01T23:59:59.000Z

310

Improving the actinides recycling in closed fuel cycles, a major step towards nuclear energy sustainability  

SciTech Connect (OSTI)

Increasing the sustainability of nuclear energy is a longstanding road that requires a stepwise approach to successively tackle the following 3 objectives. First of all, optimize the consumption of natural resource to preserve them for future generations and hence guarantee the energetic independence of the countries (no uranium ore is needed anymore). The current twice-through cycle of Pu implemented by France, UK, Japan and soon China is a first step in this direction and already allows the development and optimization of the relevant industrial processes. It also allows a major improvement regarding the conditioning of the ultimate waste in a durable and robust nuclear glass. Secondly, the recycling of americium could be an interesting option for the future with the deployment of FR fleet to save the repository resource and optimize its use by allowing a denser disposal. It would limit the burden towards the future generations and the need for additional repositories before several centuries. Thirdly, the recycling of the whole minor actinides inventory could be an interesting option for the far-future for strongly decreasing the waste long-term toxicity, down to a few centuries. It would bring the waste issue back within the human history, which should promote its acceptance by the social opinion.

Poinssot, C.; Grandjean, S.; Masson, M. [RadioChemistry and Processes Department, CEA Marcoule, 30207 Bagnols sur Ceze (France); Bouillis, B.; Warin, D. [Innovation and Industrial Support Direction, CEA Saclay, F-91191 Gif-sur-Yvette (France)

2013-07-01T23:59:59.000Z

311

Investigation of the recoverable degradation of PEM fuel cell operated under drive cycle and different humidities  

Science Journals Connector (OSTI)

Abstract Recoverable degradation of a proton exchange membrane fuel cell (PEMFC) under different relative humidities (RHs) after a whole night rest was investigated. A single cell was operated under drive cycle to simulate the working conditions of fuel cell vehicle. It was found that the cell performance decreased after 5 h operation and recovered mostly after one night rest at higher humidities, i.e. 100%, 75% and 50% RH for both cathode and anode sides; while continuous decrease took place at lower humidity, 35%RH. Polarization curve, electrochemical impedance spectroscopy (EIS), cyclic voltammetry (CV) and linear sweep voltammetry (LSV) were conducted before and after every 5 h drive cycle for investigating the mechanism of the recoverable degradation. It was found that water content, current density and thermal management might be the main contributions to the performance degradation, by impacting the membrane conductivity, internal resistance, electrode kinetics, and catalyst utilization. A good understanding of voltage recovery phenomenon after several hours rest and its effect on durability will be helpful in improving the reliability and durability of PEMFC.

Feijie Wang; Daijun Yang; Bing Li; Hao Zhang; Chuanpu Hao; Fengrui Chang; Jianxin Ma

2014-01-01T23:59:59.000Z

312

FURTHER ASSESSMENTS OF THE ATTRACTIVENESS OF MATERIALS IN ADVANCED NUCLEAR FUEL CYCLES FROM A SAFEGUARDS PERSPECTIVE  

SciTech Connect (OSTI)

This paper summarizes the results of an extension to an earlier study [ ] that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the PUREX, UREX+, and COEX reprocessing schemes. This study focuses on the materials associated with the UREX, COEX, THOREX, and PYROX reprocessing schemes. This study also examines what is required to render plutonium as “unattractive.” Furthermore, combining the results of this study with those from the earlier study permits a comparison of the uranium and thorium based fuel cycles on the basis of the attractiveness of the SNM associated with each fuel cycle. Both studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of “attractiveness levels” that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities [ ]. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed.

Bathke, C. G.; Jarvinen, G. D.; Wallace, R. K.; Ireland, J. R.; Johnson, M. W.; Sleaford, Brad W.; Ebbinghaus, B. B.; Bradley, Keith S.; Collins, Brian A.; Smith, Brian W.; Prichard, Andrew W.

2008-10-01T23:59:59.000Z

313

Investigation of dynamic driving cycle effect on the degradation of proton exchange membrane fuel cell by segmented cell technology  

Science Journals Connector (OSTI)

Abstract Durability is one of the most important limiting factors for the commercialization of proton exchange membrane fuel cell (PEMFC). Fuel cells are more vulnerable to degradation under operating conditions as dynamic load cycle or start up/shut down. The purpose of this study is to evaluate influences of driving cycles on the durability of fuel cells through analyzing the degradation mechanism of a segmented cell in real time. This study demonstrates that the performance of the fuel cell significantly decreases after 200 cycles. The segmented cell technology is used to measure the local current density distribution, which shows that the current density at the exit region and the inlet region declines much faster than the other parts. Meanwhile, electro-chemical impedance spectroscopy (EIS) reveals that after 200 cycles the ohmic resistance of fuel cell increases, especially at the cathode, and electro-chemical surface area (ESA) decreases from 392 to 307 cm2 mg?1. Furthermore, scanning electron microscopy (SEM) images of the membrane–electrode assembly (MEA) in cross-section demonstrate crackle flaw on the surface of the catalyst layer and the delamination of the electrodes from the membrane. Transmission electron microscope (TEM) results also show that the Pt particle size increases distinctly after driving cycles.

R. Lin; F. Xiong; W.C. Tang; L. Técher; J.M. Zhang; J.X. Ma

2014-01-01T23:59:59.000Z

314

Study of feasible and sustainable multilateral approach on nuclear fuel cycle  

SciTech Connect (OSTI)

Despite the Fukushima accident it is undeniable that nuclear power remains one of the most important methods to handle global growth of economic/energy consumption and issues with greenhouse gases. If the demand for nuclear power increases, the demand for not only the generation of power but also for refining uranium (U), conversion, enrichment, re-conversion, and fuel manufacturing should increase. In addition, concerns for the proliferation of 'Sensitive Nuclear Technologies' (SNT) should also increase. We propose a demand-side approach, where nuclear fuel cycle (NFC) activities would be implemented among multiple states. With this approach, NFC services, in particular those using SNTs, are multilaterally executed and controlled, thereby preventing unnecessary proliferation of SNTs, and enabling safe and appropriate control of nuclear technologies and nuclear materials. This proposal would implement nuclear safety and security at an international level and solve transport issues for nuclear fuels. This proposal is based on 3 types of cooperation for each element of NFC: type A: cooperation for 3S only, services received; Type B: cooperation for 3S, MNA (Multilateral Nuclear Activities) without transfer of ownership to MNA; and Type C cooperation for 3S, MNA holding ownership rights. States involved in the 3 types of activity should be referred to as partner states, host states, and site states respectively. The feasibility of the proposal is discussed for the Asian region.

Kuno, Y.; Tazaki, M. [University of Tokyo, Tokyo (Japan); Japan Atomic Energy Agency - JAEA, 4-49 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1184 (Japan); Akiba, M.; Takashima, R.; Izumi, Y.; Tanaka, S. [University of Tokyo, Tokyo (Japan)

2013-07-01T23:59:59.000Z

315

NUCLEAR MATERIAL ATTRACTIVENESS: AN ASSESSMENT OF MATERIAL ASSOCIATED WITH A CLOSED FUEL CYCLE  

SciTech Connect (OSTI)

This paper examines the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the various processing steps required for a closed fuel cycle. This paper combines the results from earlier studies that examined the attractiveness of SNM associated with the processing of spent light water reactor (LWR) fuel by various reprocessing schemes and the recycle of plutonium as a mixed oxide (MOX) fuel in LWR with new results for the final, repeated burning of SNM in fast-spectrum reactors: fast reactors and accelerator driven systems (ADS). The results of this paper suggest that all reprocessing products evaluated so far need to be rigorously safeguarded and provided moderate to high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of "attractiveness levels" that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, or undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed.

Bathke, C. G.; Ebbinghaus, B.; Sleaford, Brad W.; Wallace, R. K.; Collins, Brian A.; Hase, Kevin R.; Robel, Martin; Jarvinen, G. D.; Bradley, Keith S.; Ireland, J. R.; Johnson, M. W.; Prichard, Andrew W.; Smith, Brian W.

2010-06-11T23:59:59.000Z

316

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities, Sections 15-19  

SciTech Connect (OSTI)

Information is presented under the following section headings: fuel reprocessing; spent fuel and high-level and transuranic waste storage; spent fuel and high-level and transuranic waste disposal; low-level and intermediate-level waste disposal; and, transportation of radioactive materials in the nuclear fuel cycle. In each of the first three sections a description is given on the mainline process, effluent processing and waste management systems, plant layout, and alternative process schemes. Safety information and a summary are also included in each. The section on transport of radioactive materials includes information on the transportation of uranium ore, uranium ore concentrate, UF/sub 6/, PuO/sub 2/ powder, unirradiated uranium and mixed-oxide fuel assemblies, spent fuel, solidified high-level waste, contact-handled transuranic waste, remote-handled transuranic waste, and low and intermediate level nontransuranic waste. A glossary is included. (JGB)

Schneider, K.J.

1982-09-01T23:59:59.000Z

317

Life Cycle Analysis of the Production of Aviation Fuels Using the CE-CERT Process  

E-Print Network [OSTI]

2 Jet fuel and crude oil price history. From IATA website:oil discovery and fuel production………………………. ……..4 Figure.2: Jet fuel and crude oil price history……………………………. …………

Hu, Sangran

2012-01-01T23:59:59.000Z

318

Advantages of Irradiated DUPIC Fuels from the Perspective of Environmental Impact  

SciTech Connect (OSTI)

This study compares some properties of irradiated Direct Use of Spent Pressurized Water Reactor (PWR) Fuel In Canada Deuterium Uranium reactor (CANDU) (DUPIC ) fuels with properties of other fuel cycles. The properties include the radiotoxicity, decay heat, activity, and actinide content embedded in various spent fuels or high-level wastes, which could be measures of the effectiveness of waste management. From radiotoxicity analysis of fuel cycles, the toxicity of the DUPIC option based on 1 GW(electric).yr is much smaller than those of other fuel cycle options such as the PWR once-through mode, mixed oxide fuel recycling mode, and CANDU once-through mode. The analysis shows that the value is just about half the order of magnitude of other fuel cycles until decayed to a level below the toxicity of initial ore. This means that the DUPIC option could have an indirect benefit on the environmental effects of long-term spent-fuel disposal. From total activity analysis of various fuel cycle options, the activity per metric ton heavy metal of spent fuel is the lowest in natural uranium CANDU fuel, but in the case of activity based on 1 GW(electric).yr, the DUPIC option has the smallest activity. In the meanwhile, from the activity analysis of {sup 99}Tc and {sup 237}Np, which are important to the long-term transport in geologic media, the DUPIC option was being contained in only about half of those other options. In conclusion, compared to other fuel cycle cases, the irradiated DUPIC fuels would have good properties from the perspective of environmental effects.

Ko, Won Il; Kim, Ho Dong; Yang, Myung Seung [Korea Atomic Energy Research Institute (Korea, Republic of)

2002-05-15T23:59:59.000Z

319

Update of the Used Fuel Disposition Campaign Implementation Plan |  

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

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

320

Assessment of potential life-cycle energy and greenhouse gas emission effects from using corn-based butanol as a transportation fuel.  

SciTech Connect (OSTI)

Since advances in the ABE (acetone-butanol-ethanol) fermentation process in recent years have led to significant increases in its productivity and yields, the production of butanol and its use in motor vehicles have become an option worth evaluating. This study estimates the potential life-cycle energy and emission effects associated with using bio-butanol as a transportation fuel. It employs a well-to-wheels (WTW) analysis tool: the Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation (GREET) model. The estimates of life-cycle energy use and greenhouse gas (GHG) emissions are based on an Aspen Plus(reg. sign) simulation for a corn-to-butanol production process, which describes grain processing, fermentation, and product separation. Bio-butanol-related WTW activities include corn farming, corn transportation, butanol production, butanol transportation, and vehicle operation. In this study, we also analyzed the bio-acetone that is coproduced with bio-butanol as an alternative to petroleum-based acetone. We then compared the results for bio-butanol with those of conventional gasoline. Our study shows that driving vehicles fueled with corn-based butanol produced by the current ABE fermentation process could result in substantial fossil energy savings (39%-56%) and avoid large percentage of the GHG emission burden, yielding a 32%-48% reduction relative to using conventional gasoline. On energy basis, a bushel of corn produces less liquid fuel from the ABE process than that from the corn ethanol dry mill process. The coproduction of a significant portion of acetone from the current ABE fermentation presents a challenge. A market analysis of acetone, as well as research and development on robust alternative technologies and processes that minimize acetone while increase the butanol yield, should be conducted.

Wu, M.; Wang, M.; Liu, J.; Huo, H.; Energy Systems

2008-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

Experience from the Short Course on Introduction to Nuclear Chemistry and Fuel Cycle Separations and Future Educational Opportunities  

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

Short Course - Short Course - Overview & Lessons Learned David Kosson, Vanderbilt & CRESP Introduction to Nuclear Chemistry and Fuel Cycle Separations December 16-18, 2008 Vanderbilt University Vanderbilt University Dept. of Civil and Environmental Engineering safety performance cleanup closure M E Environmental Management Environmental Management 1 Course Objective To provide an introduction to the chemistry and p y separations processes of importance to entire nuclear fuel cycle. Targeted Audience: * Professionals in management, oversight and regulation of nuclear processes and facilities. * Graduate students in engineering and sciences planning a career focused on nuclear processes. focused on nuclear processes. * As an introduction for professionals that will be engaged in nuclear

322

Analyzing Nuclear Fuel Cycles from Isotopic Ratios of Waste Products Applicable to Measurement by Accelerator Mass Spectrometry  

SciTech Connect (OSTI)

An extensive study was conducted to determine isotopic ratios of nuclides in spent fuel that may be utilized to reveal historical characteristics of a nuclear reactor cycle. This forensic information is important to determine the origin of unknown nuclear waste. The distribution of isotopes in waste products provides information about a nuclear fuel cycle, even when the isotopes of uranium and plutonium are removed through chemical processing. Several different reactor cycles of the PWR, BWR, CANDU, and LMFBR were simulated for this work with the ORIGEN-ARP and ORIGEN 2.2 codes. The spent fuel nuclide concentrations of these reactors were analyzed to find the most informative isotopic ratios indicative of irradiation cycle length and reactor design. Special focus was given to long-lived and stable fission products that would be present many years after their creation. For such nuclides, mass spectrometry analysis methods often have better detection limits than classic gamma-ray spectroscopy. The isotopic ratios {sup 151}Sm/{sup 146}Sm, {sup 149}Sm/{sup 146}Sm, and {sup 244}Cm/{sup 246}Cm were found to be good indicators of fuel cycle length and are well suited for analysis by accelerator mass spectroscopy.

Biegalski, S R; Whitney, S M; Buchholz, B

2005-08-24T23:59:59.000Z

323

Life Cycle Regulation of Transportation Fuels: Uncertainty and its Policy Implications  

E-Print Network [OSTI]

ethanol; NGCC = natural gas combined-cycle; BIGCC =gasification combined-cycle. P ART III U NCERTAINTY Aaverage, (ii) natural gas combined-cycle (NGCC), (iii) coal

Plevin, Richard Jay

2010-01-01T23:59:59.000Z

324

Mr.~ Richard E..,Cunnlngham, Director Fuel Cycle and,Materials Safety  

Office of Legacy Management (LM)

JUN 25 19g JUN 25 19g Mr.~ Richard E..,Cunnlngham, Director Fuel Cycle and,Materials Safety U.S. Nuclear Regulatory Comm~sslon Washjngton, D. C. 20555 Dear Mr. Cunnlngham: We recetved the enclosed May 21, 1979, radiologjcal survey report for the old Sylvania site at Hicksville, Long Island, from the Brookhaven Area Offfce. Sfnce saae actlvfties at the site were formerly conducted under license, we belleve you may be interested in It. If you have any questions, please give us a call (353-3016). - Sfncerely, William E. Environmental ~Enclosure. cc: Davtd Schweller, 6AO bee: MC # 62426 OFFICIAL FILECOPY Department of Enerw Brookhaven Area Office Upton, New York 11973 May 24, 1979 Will-Lam E. Mott, Director (EV 13) Environmental Control Technology Division, HQ

325

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

SciTech Connect (OSTI)

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

326

Life-Cycle Assessment of Energy Use and Greenhouse Gas Emissions of Soybean-Derived Biodiesel and Renewable Fuels  

SciTech Connect (OSTI)

In this study, we used Argonne National Laboratory's Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation (GREET) model to assess the life-cycle energy and greenhouse gas (GHG) emission impacts of four soybean-derived fuels: biodiesel fuel produced via transesterification, two renewable diesel fuels (I and II) produced from different hydrogenation processes, and renewable gasoline produced from catalytic cracking. Five approaches were employed to allocate the coproducts: a displacement approach; two allocation approaches, one based on the energy value and the other based on the market value; and two hybrid approaches that integrated the displacement and allocation methods. The relative rankings of soybean-based fuels in terms of energy and environmental impacts were different under the different approaches, and the reasons were analyzed. Results from the five allocation approaches showed that although the production and combustion of soybean-based fuels might increase total energy use, they could have significant benefits in reducing fossil energy use (>52%), petroleum use (>88%), and GHG emissions (>57%) relative to petroleum fuels. This study emphasized the importance of the methods used to deal with coproduct issues and provided a comprehensive solution for conducting a life-cycle assessment of fuel pathways with multiple coproducts.

Huo, H.; Wang, M.; Bloyd, C.; Putsche, V.

2009-01-01T23:59:59.000Z

327

An agent-based framework for fuel cycle simulation with recycling  

SciTech Connect (OSTI)

Simulation of the nuclear fuel cycle is an established field with multiple players. Prior development work has utilized techniques such as system dynamics to provide a solution structure for the matching of supply and demand in these simulations. In general, however, simulation infrastructure development has occurred in relatively closed circles, each effort having unique considerations as to the cases which are desired to be modeled. Accordingly, individual simulators tend to have their design decisions driven by specific use cases. Presented in this work is a proposed supply and demand matching algorithm that leverages the techniques of the well-studied field of mathematical programming. A generic approach is achieved by treating facilities as individual entities and actors in the supply-demand market which denote preferences amongst commodities. Using such a framework allows for varying levels of interaction fidelity, ranging from low-fidelity, quick solutions to high-fidelity solutions that model individual transactions (e.g. at the fuel-assembly level). The power of the technique is that it allows such flexibility while still treating the problem in a generic manner, encapsulating simulation engine design decisions in such a way that future simulation requirements can be relatively easily added when needed. (authors)

Gidden, M.J.; Wilson, P.P.H.; Huff, K.D.; Carlsen, R.W. [Department of Nuclear Engineering and Engineering Physics, University of Wisconsin - Madison, Madison, WI 53703 (United States)

2013-07-01T23:59:59.000Z

328

Resource intensities of the front end of the nuclear fuel cycle  

SciTech Connect (OSTI)

This paper presents resource intensities, including direct and embodied energy consumption, land and water use, associated with the processes comprising the front end of the nuclear fuel cycle. These processes include uranium extraction, conversion, enrichment, fuel fabrication and depleted uranium de-conversion. To the extent feasible, these impacts are calculated based on data reported by operating facilities, with preference given to more recent data based on current technologies and regulations. All impacts are normalized per GWh of electricity produced. Uranium extraction is seen to be the most resource intensive front end process. Combined, the energy consumed by all front end processes is equal to less than 1% of the electricity produced by the uranium in a nuclear reactor. Land transformation and water withdrawals are calculated at 8.07 m{sup 2} /GWh(e) and 1.37x10{sup 5} l/GWh(e), respectively. Both are dominated by the requirements of uranium extraction, which accounts for over 70% of land use and nearly 90% of water use.

Schneider, E.; Phathanapirom, U. [The University of Texas at Austin, 1 University Station C2200, Austin TX 78712 (United States); Eggert, R.; Collins, J. [Colorado School of Mines, 1500 Illinois St., Golden CO 80401 (United States)

2013-07-01T23:59:59.000Z

329

Using Backup Generators: Alternative Backup Power Options  

Broader source: Energy.gov [DOE]

In addition to electric generators powered by fuel, homeowners and business owners may consider alternative backup power options.

330

Opportunities exist for the diversion of weapons-usable material at the front end of the fuel cycle, during which  

E-Print Network [OSTI]

Opportunities exist for the diversion of weapons-usable material at the front end of the fuel cycle of proliferation: The more places in which this work is done, the harder it is to monitor. Weapons have been, North Korea, Pakistan, and South Africa. (South Africa abandoned its nuclear weapons in 1991. Libya

Laughlin, Robert B.

331

Life-Cycle Assessment of Energy Use and Greenhouse Gas Emissions of Soybean-Derived Biodiesel and Renewable Fuels  

Science Journals Connector (OSTI)

Life-Cycle Assessment of Energy Use and Greenhouse Gas Emissions of Soybean-Derived Biodiesel and Renewable Fuels ... Hill, J.; Nelson, E.; Tilman, D.; Polasky, S.; Tiffany, D. Environmental, Economic, and Energetic Costs and Benefits of Biodiesel and Ethanol Biofuels Proc. ...

Hong Huo; Michael Wang; Cary Bloyd; Vicky Putsche

2008-12-23T23:59:59.000Z

332

Solar-powered/fuel-assisted Rankine-cycle power and cooling system: Simulation method and seasonal performance  

SciTech Connect (OSTI)

The subject of this analysis is a solar cooling system based on a novel hybrid steam Rankine cycle. Steam is generated by the use of solar energy collected at about 100/sup 0/C, and it is then superheated to about 600/sup 0/C in a fossil-fuel-fired superheater. The addition of about 20-26 percent of fuel doubles the power cycle's efficiencyas compared to organic Rankine cycles operating at similar collector temperatures. A comprehensive computer program was developed to analyze the operation and performance of the entire power/cooling system. Transient simulation was performed on an hourly basis over a cooling season in two representative climatic regions (Washington, D.C. and Phoenix, Ariz.). One of the conclusions is that the seasonal system COP is 0.82 for the design configuration and that the use of watercooled condensers and flat-plate collectors of higher efficiency increases this value to 1.35.

Lior, N.; Koai, K.

1984-05-01T23:59:59.000Z

333

Closed ThUOX Fuel Cycle for LWRs with ADTT (ATW) Backend for the 21st Century  

SciTech Connect (OSTI)

A future nuclear energy scenario with a closed, thorium-uranium-oxide (ThUOX) fuel cycle and new light water reactors (TULWRs) supported by Accelerator Transmutation of Waste (ATW) systems could provide several improvements beyond today's once-through, UO{sub 2}-fueled nuclear technology. A deployment scenario with TULWRs plus ATWs to burn the actinides produced by these LWRs and to close the back-end of the ThUOX fuel cycle was modeled to satisfy a US demand that increases linearly from 80 GWe in 2020 to 200 GWe by 2100. During the first 20 years of the scenario (2000-2020), nuclear energy production in the US declines from today's 100 GWe to about 80 GWe, in accordance with forecasts of the US DOE's Energy Information Administration. No new nuclear systems are added during this declining nuclear energy period, and all existing LWRs are shut down by 2045. Beginning in 2020, ATWs that transmute the actinides from existing LWRs are deployed, along with TULWRs and additional ATWs with a support ratio of 1 ATW to 7 TULWRs to meet the energy demand scenario. A final mix of 174 GWe from TULWRs and 26 GWe from ATWs provides the 200 GWe demand in 2100. Compared to a once-through LWR scenario that meets the same energy demand, the TULWR/ATW concept could result in the following improvements: depletion of natural uranium resources would be reduced by 50%; inventories of Pu which may result in weapons proliferation will be reduced in quantity by more than 98% and in quality because of higher neutron emissions and 50 times the alpha-decay heating of weapons-grade plutonium; actinides (and possibly fission products) for final disposal in nuclear waste would be substantially reduced; and the cost of fuel and the fuel cycle may be 20-30% less than the once-through UO{sub 2} fuel cycle.

Beller, D.E.; Sailor, W.C.; Venneri, F.

1998-10-06T23:59:59.000Z

334

Rapid thermal cycling of metal-supported solid oxide fuel cell membranes  

E-Print Network [OSTI]

effect of pressure on solid oxide fuel cell performance," inand flat plate solid oxide fuel cells," in Proceedings ofSymposium on Solid Oxide Fuel Cells. Electrochem. Soc. 1993,

Matus, Yuriy B.; De Jonghe, Lutgard C.; Jacobson, Craig P.; Visco, Steven J.

2004-01-01T23:59:59.000Z

335

E-Print Network 3.0 - advanced fuel cycle--potential Sample Search...  

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

Energy, Hydrogen, Fuel Cells and Infrastructure Technologies Program Collection: Energy Storage, Conversion and Utilization ; Renewable Energy 2 August 2005 Fuel Tank...

336

E-Print Network 3.0 - alternate fuel cycles Sample Search Results  

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

Mechanical Engineering Technical Elective Introduction to Fuel Cell Systems Summary: in alternative energy sources. Fuel Cell Basic Design COURSE TOPICS INCLUDE The prevalent...

337

Development and Utilization of mathematical Optimization in Advanced Fuel Cycle Systems Analysis  

SciTech Connect (OSTI)

Over the past sixty years, a wide variety of nuclear power technologies have been theorized, investigated and tested to various degrees. These technologies, if properly applied, could provide a stable, long-term, economical source of CO2-free electric power. However, the recycling of nuclear fuel introduces a degree of coupling between reactor systems which must be accounted for when making long term strategic plans. This work investigates the use of a simulated annealing optimization algorithm coupled together with the VISION fuel cycle simulation model in order to identify attractive strategies from economic, evironmental, non-proliferation and waste-disposal perspectives, which each have associated an objective function. The simulated annealing optimization algorithm works by perturbing the fraction of new reactor capacity allocated to each available reactor type (using a set of heuristic rules) then evaluating the resulting deployment scenario outcomes using the VISION model and the chosen objective functions. These new scenarios, which are either accepted or rejected according the the Metropolis Criterion, are then used as the basis for further perturbations. By repeating this process several thousand times, a family of near-optimal solutions are obtained. Preliminary results from this work using a two-step, Once-through LWR to Full-recycle/FRburner deployment scenario with exponentially increasing electric demand indicate that the algorithm is capable of #12;nding reactor deployment pro#12;les that reduce the long-term-heat waste disposal burden relative to an initial reference scenario. Further work is under way to re#12;ne the current results and to extend them to include the other objective functions and to examine the optimization trade-o#11;s that exist between these di#11;erent objectives.

Paul Turinsky; Ross Hays

2011-09-02T23:59:59.000Z

338

High Purity Americium-241 for Fuel Cycle R&D Program  

SciTech Connect (OSTI)

Previously the U.S. Department of Energy released Am-241 for various applications such as smoke detectors and Am-Be neutron sources for oil wells. At this date there is a shortage of usable, higher purity Am-241 in metal and oxide form available in the United States. Recently, the limited source of Am-241 has been from Russia with production being contracted to existing customers. The shortage has resulted in the price per gram rising dramatically over the last few years. DOE-NE currently has need for high purity Am-241 metal and oxide to fabricate fuel pellets for reactor testing in the Fuel Cycle R&D program. All the available high purity americium has been gathered from within the DOE system of laboratories. However, this is only a fraction of the projected needs of FCRD over the next 10 years. Therefore, FCR&D has proposed extraction and purification concepts to extract Am-241 from a mixed AmO2-PuO2 feedstock stored at the Savannah River Site. The most simple extraction system is based upon high temperature reduction using lanthanum metal with concurrent evaporation and condensation to produce high purity Am metal. Metallic americium has over a four order of magnitude higher vapor pressure than plutonium. Results from small-scale reduction experiments are presented. These results confirm thermodynamic predictions that at 1000 deg C metallic lanthanum reduces both PuO2 and AmO2. Faster kinetics are expected for temperatures up to about 1500 deg C.

Dr. Paul A. Lessing

2011-07-01T23:59:59.000Z

339

Life Cycle Analysis of the Production of Aviation Fuels Using the CE-CERT Process  

E-Print Network [OSTI]

FTR: Fischer-Tropsch reactor LCA: life cycle analysis LCI:software. Life cycle analyses (LCA) using a modified GREETfor the process. Keywords: LCA, Fischer-Tropsch, avation

Hu, Sangran

2012-01-01T23:59:59.000Z

340

University Programs of the U.S. Advanced Fuel Cycle Initiative  

SciTech Connect (OSTI)

As the Advanced Accelerator Applications (AAA) Program, which was initiated in fiscal year 2001 (FY01), grows and transitions to the Advanced Fuel Cycle (AFC) Program in FY03, research for its underlying science and technology will require an ever larger cadre of educated scientists and trained technicians. In addition, other applications of nuclear science and engineering (e.g., proliferation monitoring and defense, nuclear medicine, safety regulation, industrial processes, and many others) require increased academic and national infrastructure and even larger student populations. Because of the recognition of these current and increasing requirements, the DOE began a multi-year program to involve university faculty and students in various phases of these Projects to support the infrastructure requirements of nuclear energy, science and technology fields as well as the special needs of the DOE transmutation program. Herein I summarize the goals and accomplishments of the university programs that have supported the AAA and AFC Programs during FY02, including the involvement of 120 students at more than 30 universities in the U.S. and abroad. I also highlight contributions to academic research from LANL, which hosted students from and sponsored research at more than 18 universities by more than 50 students and 20 faculty members, investing about 10% of its AFC budget.

Beller, D. E. (Denis E.)

2003-01-01T23:59:59.000Z

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


341

The Mass Tracking System for the Integral Fast Reactor fuel cycle  

SciTech Connect (OSTI)

As part of the Fuel Cycle Facility (FCF) of Argonne National Laboratory`s Integral Fast Reactor (IFR) demonstration, a computer-based Mass-Tracking (MTG) System has been developed. The MTG System collects, stores, retrieves and processes data on all operations which directly affect the flow of process material through FCF and supports such activities as process modeling, compliance with operating limits (e.g., criticality safety), material control and accountability and operational information services. Its architecture is client/server, with input and output connections to operator`s equipment-control stations on the floor of FCF as well as to terminal sessions. Its heterogeneous database includes a relational-database manager as well as both binary and ASCII data files. The design of the database, and the software that supports it, is based on a model of discrete accountable items distributed in space and time and constitutes a complete historical record of the material processed in FCF. Although still under development, much of the MTG System has been qualified and is in production use.

Adams, C.H.; Beitel, J.C.; Birgersson, G.; Bucher, R.G.; Carrico, C.B.; Daly, T.A. [Argonne National Lab., IL (United States); Keyes, R.W. [Argonne National Lab., Idaho Falls, ID (United States)

1994-07-01T23:59:59.000Z

342

A computer code to estimate accidental fire and radioactive airborne releases in nuclear fuel cycle facilities: User's manual for FIRIN  

SciTech Connect (OSTI)

This manual describes the technical bases and use of the computer code FIRIN. This code was developed to estimate the source term release of smoke and radioactive particles from potential fires in nuclear fuel cycle facilities. FIRIN is a product of a broader study, Fuel Cycle Accident Analysis, which Pacific Northwest Laboratory conducted for the US Nuclear Regulatory Commission. The technical bases of FIRIN consist of a nonradioactive fire source term model, compartment effects modeling, and radioactive source term models. These three elements interact with each other in the code affecting the course of the fire. This report also serves as a complete FIRIN user's manual. Included are the FIRIN code description with methods/algorithms of calculation and subroutines, code operating instructions with input requirements, and output descriptions. 40 refs., 5 figs., 31 tabs.

Chan, M.K.; Ballinger, M.Y.; Owczarski, P.C.

1989-02-01T23:59:59.000Z

343

Life Cycle Analysis of the Production of Aviation Fuels Using the CE-CERT Process  

E-Print Network [OSTI]

Jet fuel and crude oil price history……………………………. …………6Figure 2 Jet fuel and crude oil price history. From IATAa sharp decrease in crude oil price occurred in the 1950s.

Hu, Sangran

2012-01-01T23:59:59.000Z

344

Evaluation of alternative fuel cycle strategies for nuclear power generation in the 21st century  

E-Print Network [OSTI]

The deployment of fuel recycling through either CONFU (COmbined Non-Fertile and UO2 fuel) thermal watercooled reactors (LWRs) or fast ABR (Actinide Burner Reactor) reactors is compared to the Once-Through LWR reactor system ...

Boscher, Thomas

2005-01-01T23:59:59.000Z

345

Use of an Engine Cycle Simulation to Study a Biodiesel Fueled Engine  

E-Print Network [OSTI]

for flow in intake/exhaust system, fuel injection, fuel vaporization and combustion, cylinder heat transfer, and energy transfer in a turbocharging system were combined with a thermodynamic analysis of the engine to yield instantaneous in-cylinder...

Zheng, Junnian

2010-01-14T23:59:59.000Z

346

GREET Development and Applications for Life-Cycle Analysis of Vehicle/Fuel Systems  

Broader source: Energy.gov [DOE]

2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

347

Evaluation and Adaptation of 5-Cycle Fuel Economy Testing and Calculations for HEVs and PHEVs  

Broader source: Energy.gov [DOE]

2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

348

E-Print Network 3.0 - advanced fuel cycles Sample Search Results  

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

Energy, Hydrogen, Fuel Cells and Infrastructure Technologies Program Collection: Energy Storage, Conversion and Utilization ; Renewable Energy 2 Course Announcement:...

349

E-Print Network 3.0 - advanced fuel cycle Sample Search Results  

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

Energy, Hydrogen, Fuel Cells and Infrastructure Technologies Program Collection: Energy Storage, Conversion and Utilization ; Renewable Energy 2 Course Announcement:...

350

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

351

Energetic analysis of a syngas-fueled chemical-looping combustion combined cycle with integration of carbon dioxide sequestration  

Science Journals Connector (OSTI)

Abstract Chemical-looping combustion for power generation has significant advantages over conventional combustion. Mainly, it allows an integration of CO2 capture in the power plant without energy penalty; secondly, a less exergy destruction in the combustion chemical transformation is achieved, leading to a greater overall thermal efficiency. Most efforts have been devoted to systems based on methane as a fuel, although other systems for alternative fuels have can be proposed. This paper focus on the study of the energetic performance of this concept of combustion in a gas turbine combined cycle when synthesis gas is used as fuel. After optimization of some thermodynamic parameters of the cycle, the power plant performance is evaluated under diverse working conditions and compared to a conventional gas turbine system. Energy savings related with CO2 capture and storage have been quantified. The overall efficiency increase is found to be significant, reaching values of around 5% (even more in some cases). In order to analyze the influence of syngas composition on the results, different H2-content fuels are considered. In a context of real urgency to reduce green house gas emissions, this work is intended to contribute to the conceptual development of highly efficient alternative power generation systems.

Ángel Jiménez Álvaro; Ignacio López Paniagua; Celina González Fernández; Rafael Nieto Carlier; Javier Rodríguez Martín

2014-01-01T23:59:59.000Z

352

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

SciTech Connect (OSTI)

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

353

Life-Cycle Analysis of Alternative Automobile Fuel/Propulsion Technologies  

Science Journals Connector (OSTI)

For example, almost all alternatively fueled vehicles currently sold are designed to be able to run on two or more fuels (battery-powered cars are the notable exception). ... When the weight of the fuel tank, engine, or other components of the car change, the structure of the car must be adjusted as well. ... The liquid fuels require a reformer to extract hydrogen for the fuel cell, and so there are emissions of conventional air pollutants and GHG in the reforming process as well as a loss in efficiency. ...

Lester Lave; Heather MacLean; Chris Hendrickson; Rebecca Lankey

2000-08-04T23:59:59.000Z

354

Fast Spectrum Molten Salt Reactor Options  

SciTech Connect (OSTI)

During 2010, fast-spectrum molten-salt reactors (FS-MSRs) were selected as a transformational reactor concept for light-water reactor (LWR)-derived heavy actinide disposition by the Department of Energy-Nuclear Energy Advanced Reactor Concepts (ARC) program and were the subject of a preliminary scoping investigation. Much of the reactor description information presented in this report derives from the preliminary studies performed for the ARC project. This report, however, has a somewhat broader scope-providing a conceptual overview of the characteristics and design options for FS-MSRs. It does not present in-depth evaluation of any FS-MSR particular characteristic, but instead provides an overview of all of the major reactor system technologies and characteristics, including the technology developments since the end of major molten salt reactor (MSR) development efforts in the 1970s. This report first presents a historical overview of the FS-MSR technology and describes the innovative characteristics of an FS-MSR. Next, it provides an overview of possible reactor configurations. The following design features/options and performance considerations are described including: (1) reactor salt options-both chloride and fluoride salts; (2) the impact of changing the carrier salt and actinide concentration on conversion ratio; (3) the conversion ratio; (4) an overview of the fuel salt chemical processing; (5) potential power cycles and hydrogen production options; and (6) overview of the performance characteristics of FS-MSRs, including general comparative metrics with LWRs. The conceptual-level evaluation includes resource sustainability, proliferation resistance, economics, and safety. The report concludes with a description of the work necessary to begin more detailed evaluation of FS-MSRs as a realistic reactor and fuel cycle option.

Gehin, Jess C [ORNL; Holcomb, David Eugene [ORNL; Flanagan, George F [ORNL; Patton, Bruce W [ORNL; Howard, Rob L [ORNL; Harrison, Thomas J [ORNL

2011-07-01T23:59:59.000Z

355

Life-Cycle Water Impacts of U.S. Transportation Fuels  

E-Print Network [OSTI]

importation, or wastewater recycling. Identifying regionsWastewater Recycling Life-Cycle Inputs for Wastewater Recycling (Data Source: (

Scown, Corinne Donahue

2010-01-01T23:59:59.000Z

356

Advanced Fuels Campaign FY 2010 Accomplishments Report  

SciTech Connect (OSTI)

The Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) Accomplishment Report documents the high-level research and development results achieved in fiscal year 2010. The AFC program has been given responsibility to develop advanced fuel technologies for the Department of Energy (DOE) using a science-based approach focusing on developing a microstructural understanding of nuclear fuels and materials. The science-based approach combines theory, experiments, and multi-scale modeling and simulation aimed at a fundamental understanding of the fuel fabrication processes and fuel and clad performance under irradiation. The scope of the AFC includes evaluation and development of multiple fuel forms to support the three fuel cycle options described in the Sustainable Fuel Cycle Implementation Plan4: Once-Through Cycle, Modified-Open Cycle, and Continuous Recycle. The word “fuel” is used generically to include fuels, targets, and their associated cladding materials. This document includes a brief overview of the management and integration activities; but is primarily focused on the technical accomplishments for FY-10. Each technical section provides a high level overview of the activity, results, technical points of contact, and applicable references.

Lori Braase

2010-12-01T23:59:59.000Z

357

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

358

Determining the maximal capacity of a combined-cycle plant operating with afterburning of fuel in the gas conduit upstream of the heat-recovery boiler  

Science Journals Connector (OSTI)

The effect gained from afterburning of fuel in the gas conduit upstream of the heat-recovery boiler used as part of a PGU-450T combined-cycle plant is considered. The results obtained from ... electric and therma...

V. M. Borovkov; N. M. Osmanova

2011-01-01T23:59:59.000Z

359

Assessment of Fuel-Cycle Energy Use and Greenhouse Gas Emissions for Fischer?Tropsch Diesel from Coal and Cellulosic Biomass  

Science Journals Connector (OSTI)

Assessment of Fuel-Cycle Energy Use and Greenhouse Gas Emissions for Fischer?Tropsch Diesel from Coal and Cellulosic Biomass ... There are two general designs for FTD production:(7, 30) recycling (RC) design and once-through (OT) design, as illustrated in Figure 2. ... Wang, M. Q.GREET 1.0 — Transportation Fuel Cycles Model: Methodology and Use, Argonne National Laboratory: Argonne, IL, ANL/ESD-33. ...

Xiaomin Xie; Michael Wang; Jeongwoo Han

2011-03-03T23:59:59.000Z

360

Hydrogen Delivery Options and Issues | Department of Energy  

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

Delivery Options and Issues Hydrogen Delivery Options and Issues Presentation by DOE's Mark Paster at the 2010 - 2025 Scenario Analysis for Hydrogen Fuel Cell Vehicles and...

Note: This page contains sample records for the topic "fuel cycle options" 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

Life-Cycle Analysis of Vehicle and Fuel Systems with the GREET Model - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

5 5 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Michael Wang (Primary Contact), Amgad Elgowainy, Jeongwoo Han and Hao Cai Argonne National Laboratory (ANL) ESD362 9700 South Cass Avenue Argonne, IL 60439 Phone: (630) 252-2819 Email: mqwang@anl.gov DOE Manager HQ: Fred Joseck Phone: (202) 586-7932 Email: Fred.Joseck@ee.doe.gov Project Start Date: October 2009 Project End Date: Project continuation and direction determined annually by DOE Fiscal Year (FY) 2012 Objectives Evaluate environmental benefits of hydrogen fuel * cell electric vehicles (FCEVs) with various renewable hydrogen production pathways relative to baseline gasoline pathways. Conduct vehicle-cycle analysis of hydrogen FCEVs. *

362

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

SciTech Connect (OSTI)

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

363

Light-Duty Reactivity Controlled Compression Ignition Drive Cycle Fuel Economy and Emissions Estimates  

Broader source: Energy.gov [DOE]

Vehicle systems simulations using experimental data demonstrate improved modeled fuel economy of 15% for passenger vehicles solely from powertrain efficiency relative to a 2009 PFI gasoline baseline.

364

Concerns when designing a safeguards approach for the back-end of the Swedish fuel cycle.  

E-Print Network [OSTI]

?? In Sweden, the construction of an encapsulation plant and a geological repository for the final disposal of spent nuclear fuel is planned to start… (more)

Fritzell, Anni

2006-01-01T23:59:59.000Z

365

Life-Cycle Water Impacts of U.S. Transportation Fuels  

E-Print Network [OSTI]

Livestock Fuel for Water Pumping Motor Efficiency GW EnergyRequired for Water Pumps Using Electric Motors (AdaptedGasoline motors typically used for water pumps are

Scown, Corinne Donahue

2010-01-01T23:59:59.000Z

366

Home composting as an alternative treatment option for organic household waste in Denmark: An environmental assessment using life cycle assessment-modelling  

SciTech Connect (OSTI)

An environmental assessment of the management of organic household waste (OHW) was performed from a life cycle perspective by means of the waste-life cycle assessment (LCA) model EASEWASTE. The focus was on home composting of OHW in Denmark and six different home composting units (with different input and different mixing frequencies) were modelled. In addition, incineration and landfilling was modelled as alternatives to home composting. The most important processes contributing to the environmental impact of home composting were identified as greenhouse gas (GHG) emissions (load) and the avoided emissions in relation to the substitution of fertiliser and peat when compost was used in hobby gardening (saving). The replacement of fertiliser and peat was also identified as one of the most sensible parameters, which could potentially have a significant environmental benefit. Many of the impact categories (especially human toxicity via water (HTw) and soil (HTs)) were affected by the heavy metal contents of the incoming OHW. The concentrations of heavy metals in the compost were below the threshold values for compost used on land and were thus not considered to constitute a problem. The GHG emissions were, on the other hand, dependent on the management of the composting units. The frequently mixed composting units had the highest GHG emissions. The environmental profiles of the home composting scenarios were in the order of -2 to 16 milli person equivalents (mPE) Mg{sup -1} wet waste (ww) for the non-toxic categories and -0.9 to 28 mPE Mg{sup -1} ww for the toxic categories. Home composting performed better than or as good as incineration and landfilling in several of the potential impact categories. One exception was the global warming (GW) category, in which incineration performed better due to the substitution of heat and electricity based on fossil fuels.

Andersen, J.K.; Boldrin, A.; Christensen, T.H. [Department of Environmental Engineering, Technical University of Denmark, DK-2800 Kongens Lyngby (Denmark); Scheutz, C., E-mail: chas@env.dtu.dk [Department of Environmental Engineering, Technical University of Denmark, DK-2800 Kongens Lyngby (Denmark)

2012-01-15T23:59:59.000Z

367

An investigation of high pressure/late cycle injection of CNG (compressed natural gas) as a fuel for rail applications  

SciTech Connect (OSTI)

This report describes a demonstration effort to investigate the use of natural gas in a medium-speed diesel engine. The effort was unique in the sense that natural gas was injected directly into the combustion chamber late in the compression stroke, as a high pressure gas rather than through low pressure fumigation or low pressure injection early in the compression stroke. Tests were performed on a laboratory two-cylinder, two-stroke cycle medium-speed diesel engine in an attempt to define its ability to operate on the high pressure/late cycle injection concept and to define the performance and emission characteristics of the engine under such operation. A small quantity of No.-2 diesel fuel was injected into the cylinder slightly before the gas injection to be used as an ignition source for the gas. Pilot (diesel fuel) and main (natural gas) timing and injection duration were systematically varied to optimize engine performance. The test demonstrated that the medium-speed engine was capable of attaining full rated speed and load (unlike the low pressure approach) with very low percentages of pilot injection with the absence of knock. Thermal efficiency was as much as 10 percent less than thermal efficiency levels obtained with neat diesel fuel. This was primarily due to the placement and injection characteristics of the pilot and main injectors. Optimization of the injection system would undoubtedly result in increased thermal efficiency. 11 figs., 4 tabs.

Wakenell, J.F.; O'Neal, G.G.; Baker, Q.A.; Urban, C.M.

1988-04-01T23:59:59.000Z

368

Life-Cycle Water Impacts of U.S. Transportation Fuels  

E-Print Network [OSTI]

of Freshwater Consumption in LCA. Environmental Science &of Freshwater Consumption in LCA. Environmental Science &Cycle Assessment (EIO-LCA) US 2002 (428) model. Carnegie

Scown, Corinne Donahue

2010-01-01T23:59:59.000Z

369

Safeguards and nonproliferation aspects of a dry fuel recycling technology  

SciTech Connect (OSTI)

Los Alamos National Laboratory undertook an independent assessment of the proliferation potentials and safeguardability of a dry fuel recycling technology, whereby spent pressurized-water reactor (PWR) fuels are used to fuel canadian deuterium uranium (CANDU) reactors. Objectives of this study included (1) the evaluation of presently available technologies that may be useful to safeguard technology options for dry fuel recycling (2) and identification of near-term and long-term research needs to develop process-specific safeguards requirements. The primary conclusion of this assessment is that like all other fuel cycle alternatives proposed in the past, the dry fuel recycle entails prolfferation risks and that there are no absolute technical fixes to eliminate such risks. This study further concludes that the proliferation risks of dry fuel recycling options are relatively minimal and presently known safeguards systems and technologies can be modified and/or adapted to meet the requirements of safeguarding such fuel recycle facilities.

Pillay, K.K.S.

1993-05-01T23:59:59.000Z

370

Fusion transmutation of waste and the role of the In-Zinerator in the nuclear fuel cycle.  

SciTech Connect (OSTI)

The Z-Pinch fusion experiment at Sandia National Laboratories has been making significant progress in developing a high-energy fusion neutron source. This source has the potential to be used for the transmutation of nuclear waste. The goal of this research was to do a scoping-level design of a fusion-based transmuter to determine potential transmutation rates along with the fusion yield requirements. Two ''In-Zinerator'' designs have been developed to transmute the long-lived actinides that dominate the heat production in spent fuel. The first design burns up all transuranics (TRU) in spent fuel (Np, Pu, Am, Cm), and the second is focused only on burning up Am and Cm. The TRU In-Zinerator is designed for a fuel cycle requiring burners to get rid of all the TRU with no light water reactor (LWR) recycle. The Am/Cm In-Zinerator is designed for a fuel cycle with Np/Pu recycling in LWRs. Both types of In-Zinerators operate with a moderate fusion source driving a sub-critical actinide blanket. The neutron multiplication is 30, so a great deal of energy is produced in the blanket. With the design goal of generating 3,000 MW{sub th}, about 1,200 kg/yr of actinides can be destroyed in each In-Zinerator. Each TRU In-Zinerator will require a 20 MW fusion source, and it will take a total of 20 units (each producing 3,000 MWth) to burn up the TRU as fast as the current LWR fleet can produce it. Each Am/Cm In-Zinerator will require a 24 MW fusion source, and it will take a total of 2 units to burn up the Am/Cm as fast as the current LWR fleet can produce it. The necessary fusion yield could be achieved using a 200-240 MJ target fired once every 10 seconds.

Cipiti, Benjamin B.

2006-06-01T23:59:59.000Z

371

Cycle simulation of coal-fueled engines utilizing low heat rejection concepts  

E-Print Network [OSTI]

achieved using the coal water slurry both with and without a diesel pilot. Fuel consumption was also comparable to that of diesel fuel. Ignition delays as long as 6 ms were observed, which was acceptable for the engines speed range. In general, exhaust.... Hsu [15, 16] reports on the successful operation of a General Electric locomotive engine on CWS with and without a diesel pilot. When no pilot was used, inlet air temperature had to be raised by about 40'C. Specific fuel consumption was comparable...

Roth, John M.

2012-06-07T23:59:59.000Z

372

Advanced Fuel Cycle Technology: Special Session in Honor of Dr. Michael Lineberry  

SciTech Connect (OSTI)

The US DOE recently initiated an effort to develop accident tolerant fuel designs for potential use in commercial power reactors. Evaluation of various fuel design concepts will require a broad array of testing that will include performance attributes at both steady state and transient irradiation conditions. The first stage of the transient testing program is intended to establish the relative performance limits of each proposed concept and to support development of first-draft fuel performance models. It is anticipated that this data can subsequently be used as the basis for larger scale qualification testing. This initial stage of the testing program is outlined in this paper.

D.M. Wachs; N. Woolstenhulme

2014-06-01T23:59:59.000Z

373

Hydrogen Delivery Infrastructure Option Analysis  

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

Hydrogen Delivery Infrastructure Hydrogen Delivery Infrastructure Option Analysis Option Analysis DOE and FreedomCAR & Fuel Partnership Hydrogen Delivery and On-Board Storage Analysis Workshop January 25, 2005 Washington DC This presentation does not contain any proprietary or confidential information Tan-Ping Chen Nexant Jim Campbell Bhadra Grover Air Liquide Stefan Unnasch TIAX Glyn Hazelden GTI Graham Moore Chevron Matt Ringer NREL Ray Hobbs Pinnacle West 2 Presentation Outline Project Background Knowledge Collected and Preliminary Results for Each Delivery Option Summary of Observations Next Step Project Background Project Background 4 Delivery Options Option 1* GH delivery by new pipelines Option 2 Converting NG/oil pipelines for GH delivery Option 3 Blending GH into NG pipelines Option 4* GH tube trailers

374

Study on a gas-steam combined cycle system with CO2 capture by integrating molten carbonate fuel cell  

Science Journals Connector (OSTI)

Abstract This paper studies a gas-steam combined cycle system with CO2 capture by integrating the MCFC (molten carbonate fuel cell). With the Aspen plus software, this paper builds the model of the overall MCFC-GT hybrid system with CO2 capture and analyzes the effects of the key parameters on the performances of the overall system. The result shows that compared with the gas-steam combined cycle system without CO2 capture, the efficiency of the new system with CO2 capture does not decrease obviously and keeps the same efficiency with the original gas steam combined cycle system when the carbon capture percentage is 45%. When the carbon capture percentage reaches up to 85%, the efficiency of the new system is about 54.96%, only 0.67 percent points lower than that of the original gas-steam combined cycle system. The results show that the new system has an obvious superiority of thermal performance. However, its technical economic performance needs be improved with the technical development of MCFC and ITM (oxygen ion transfer membrane). Achievements from this paper will provide the useful reference for CO2 capture with lower energy consumption from the traditional power generation system.

Liqiang Duan; Jingnan Zhu; Long Yue; Yongping Yang

2014-01-01T23:59:59.000Z

375

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

SciTech Connect (OSTI)

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

376

A Life-Cycle Assessment Comparing Select Gas-to-Liquid Fuels...  

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

with both conventional and ultra-low sulfur diesel, and FRFG motor fuels. * The UCF LCA develops a set of near-term (2006) and long-term (2015) scenarios to assess impacts...

377

Life-Cycle Water Impacts of U.S. Transportation Fuels  

E-Print Network [OSTI]

Impact Analysis for a Shale Oil Complex at Parachute Creek,of Paraho Crude Shale Oil Into Military Specification Fuels.CO, 1974; An Assessment of Oil Shale Technologies. Office of

Scown, Corinne Donahue

2010-01-01T23:59:59.000Z

378

Project Description Advanced Fuel Cycle Initiative AFC-2A and AFC-2B Experiments  

SciTech Connect (OSTI)

The proposed AFC-2A and AFC-2B irradiation experiments are a continuation of the AFC-1 fuel test series currently in progress in the ATR. This document discusses the experiments and the planned activities that will take place.

AFCI AFC-2A and AFC-2B Experiments Project Executi

2007-03-01T23:59:59.000Z

379

Comparative Life-Cycle Assessment of Residential Heating Systems, Focused on Solid Oxide Fuel Cells  

Science Journals Connector (OSTI)

This study aims to analyze a Solid Oxide Fuel Cell (SOFC) for residential heating applications by...producer, the user as an individual and the user...intended as the heating demand of a building, applied by defa...

Alba Cánovas; Rainer Zah; Santiago Gassó

2013-01-01T23:59:59.000Z

380

Life Cycle Analysis of the Production of Aviation Fuels Using the CE-CERT Process  

E-Print Network [OSTI]

of Municipal Sewage Sludge to Produce Synthetic Fuels,5.4 million dry metric tons of sludge annually or 47pounds of sewage sludge (dry weight basis) for every

Hu, Sangran

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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

Life Cycle Regulation of Transportation Fuels: Uncertainty and its Policy Implications  

E-Print Network [OSTI]

in several earlier corn ethanol energy analysis is thatR. (2006). Ethanol’s energy return on investment: A surveyD. (1991). Ethanol fuels - energy security, economics, and

Plevin, Richard Jay

2010-01-01T23:59:59.000Z

382

A cycle simulation of coal particle fueled reciprocating internal-combustion engines  

E-Print Network [OSTI]

- Summary of Experimental Diesel Engine Operation on Solid Coal Fuels Page Table 2 - Property Data for Coal (Char) Particles . . 23 Table 3 - Summary of the Combustion Model and Reaction Constants 40 Table 4 ? Specifications of the Base Case Engine... Efforts The first attempt to operate a solid particle fueled piston engine was performed nearly a century ago by Rudolf Diesel, inventor of the compression-ignition engine. Since then, at least a dozen separate attempts to oper- ate diesel engines...

Rosegay, Kenneth Harold

2012-06-07T23:59:59.000Z

383

Life-Cycle Water Impacts of U.S. Transportation Fuels  

E-Print Network [OSTI]

144 Figure 63: Impact of Hydroelectricity on the Life-Cycle157 Figure 64: Impact of Hydroelectricity on the Water68 Table 14: Hydroelectricity-Related FWSE (Data Source: (

Scown, Corinne Donahue

2010-01-01T23:59:59.000Z

384

Compliant alkali silicate sealing glass for solid oxide fuel cell applications: thermal cycle stability and chemical compatibility  

SciTech Connect (OSTI)

An alkali silicate glass (SCN-1) is currently being evaluated as a candidate sealing glass for solid oxide fuel (SOFC) applications. The glass containing ~17 mole% alkalis (K2O and Na2O) remains vitreous and compliant during SOFC operation, unlike conventional SOFC sealing glasses, which experience substantial devitrification after the sealing process. The non-crystallizing compliant sealing glass has lower glass transition and softening temperatures since the microstructure remains glassy without significant crystallite formation, and hence can relieve or reduce residual stresses and also has the potential for crack healing. Sealing approaches based on compliant glass will also need to satisfy all the mechanical, thermal, chemical, physical, and electrical requirements for SOFC applications, not only in bulk properties but also at sealing interfaces. In this first of a series of papers we will report the thermal cycle stability of the glass when sealed between two SOFC components, i.e., a NiO/YSZ anode supported YSZ bilayer and a coated ferritic stainless steel interconnect material. High temperature leak rates were monitored versus thermal cycles between 700-850oC using back pressures ranging from 0.2 psi to 1.0 psi. Isothermal stability was also evaluated in a dual environment consisting of flowing dilute H2 fuel versus ambient air. In addition, chemical compatibility at the alumina and YSZ interfaces was examined with scanning electron microscopy and energy dispersive spectroscopy. The results shed new light on the topic of SOFC glass seal development.

Chou, Y. S.; Thomsen, Edwin C.; Williams, Riley T.; Choi, Jung-Pyung; Canfield, Nathan L.; Bonnett, Jeff F.; Stevenson, Jeffry W.; Shyam, Amit; Lara-Curzio, E.

2011-03-01T23:59:59.000Z

385

NREL: More Search Options  

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

More Search Options More Search Options Search More Search Options Site Map Printable Version The following options help you find information on the National Renewable Energy Laboratory site, locate NREL staff, browse publication and photograph collections, and see what hot topics other site visitors are looking for. Search the NREL Web Site Search Tip: use quotes to find exact phrases Example: "renewable energy" Tip: use plus signs to find results that contain all your search terms Example: +biodiesel +buses Search Help Find NREL Staff in the Employee Locator Search by first or last name: Search Select a search type Select your criteria Enter your search term Look at Recent Hot Topics Biomass HOMER (computer model) Hybrid Electric Vehicles Hydrogen and Fuel Cells Jobs PVWATTS (software)

386

High efficiency direct fuel cell hybrid power cycle for near term application  

SciTech Connect (OSTI)

Direct carbonate fuel cells being developed by Energy Research Corporation can generate power at an efficiency approaching 60% LHV. This unique fuel cell technology can consume natural gas and other hydrocarbon based fuels directly without requiring an external reformer, thus providing a simpler and inherently efficient power generation system. A 2 MW power plant demonstration of this technology has been initiated at an installation in the city of Santa Clara in California. A 2.85 MW commercial configuration shown in Figure 1 is presently being developed. The complete plant includes the carbonate fuel cell modules, an inverter, transformer and switchgear, a heat recovery unit and supporting instrument air and water treatment systems. The emission levels for this 2.85 MW plant are projected to be orders of magnitude below existing or proposed standards. The 30 year levelized cost of electricity, without inflation, is projected to be approximately 5{cents}/kW-h assuming capital cost for the carbonate fuel cell system of $1000/kW.

Steinfeld, G.; Maru, H.C. [Energy Research Corp., Danbury, CT (United States); Sanderson, R.A. [Fuel Cell Systems Consultant, Wethersfield, CT (United States)

1996-12-31T23:59:59.000Z

387

Compatibility Analysis on Existing Reactivity Devices in CANDU 6 Reactors for DUPIC Fuel Cycle  

SciTech Connect (OSTI)

The performance of reactivity devices for a Canada deuterium uranium (CANDU) 6 reactor loaded with Direct Use of Spent Pressurized Water Reactor Fuel In CANDU reactors (DUPIC) fuel is assessed. The reactivity devices studied are the zone controller units, the adjuster rods, and the mechanical control absorbers. For the zone controller system, the bulk reactivity control, spatial power control, and damping capability for spatial oscillation are investigated. For the adjusters, the xenon override, restart after a poison-out, shim operation, and power step-back capabilities are confirmed. The mechanical control absorber is assessed for the function of compensating temperature reactivity feedback following a power reduction. This study shows that the current reactivity device system of a CANDU 6 reactor is compatible with DUPIC fuel for normal and transient operations.

Jeong, Chang-Joon; Choi, Hangbok [Korea Atomic Energy Research Institute (Korea, Republic of)

2000-03-15T23:59:59.000Z

388

Analysis and optimization of a solid oxide fuel cell and intercooled gas turbine (SOFC–ICGT) hybrid cycle  

Science Journals Connector (OSTI)

The power generation community faces a major challenge: to protect the environment while producing a plentiful supply of clean low-cost energy. “21st Century Energy Plants” (Vision 21 Plants) have been proposed and conceptualized to meet the energy and environmental challenges. The solid oxide fuel cell and intercooled gas turbine (SOFC–ICGT) hybrid cycle introduced in this work is one example of a Vision 21 Plant. The system includes an internal-reforming tubular-SOFC, an intercooled gas turbine, a humidifier, and other auxiliary components. A recently developed thermodynamic analysis computer code entitled advanced power systems analyses tools (APSAT) was applied to analyze the system performance of the SOFC–ICGT cycle. Sensitivity analyses of several major system parameters were studied to identify the key development needs and design and operating improvements for this hybrid cycle. A novel optimization strategy including a design of experiments (DOEx) approach is proposed and applied to the hybrid system. Using this optimization strategy, a system electrical efficiency higher than 75% (net ac/lower heating value (LHV)) could be achieved when the system was designed to operate under a high operating pressure (50 bara) and with a low percent excess air (EA) (55%) in the SOFC.

Yaofan Yi; Ashok D. Rao; Jacob Brouwer; G.Scott Samuelsen

2004-01-01T23:59:59.000Z

389

Emission Reduction Using RTP Green Fuel in Industry Facilities: A Life Cycle Study  

Science Journals Connector (OSTI)

Scenario analyses were also conducted to determine responses to model assumptions including different biomass feedstocks, feedstock transport mode and distance, and geographical locations of the pyrolysis process. ... The savings of GHG emissions compared to fossil heavy fuel oil is greater than 80% for all of these biomass feedstocks. ...

Jiqing Fan; David Shonnard; Tom Kalnes; Monique Streff; Geoff Hopkins

2013-08-23T23:59:59.000Z

390

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 (OSTI)

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

391

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle description  

SciTech Connect (OSTI)

The Nonproliferation Alterntive Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates.

Not Available

1980-06-01T23:59:59.000Z

392

Fuel cycle facility control system for the Integral Fast Reactor Program  

SciTech Connect (OSTI)

As part of the Integral Fast Reactor (IFR) Fuel Demonstration, a new distributed control system designed, implemented and installed. The Fuel processes are a combination of chemical and machining processes operated remotely. To meet this special requirement, the new control system provides complete sequential logic control motion and positioning control and continuous PID loop control. Also, a centralized computer system provides near-real time nuclear material tracking, product quality control data archiving and a centralized reporting function. The control system was configured to use programmable logic controllers, small logic controllers, personal computers with touch screens, engineering work stations and interconnecting networks. By following a structured software development method the operator interface was standardized. The system has been installed and is presently being tested for operations.

Benedict, R.W.; Tate, D.A.

1993-09-01T23:59:59.000Z

393

Life cycle assessment of biohydrogen and biomethane production and utilisation as a vehicle fuel  

Science Journals Connector (OSTI)

Environmental burdens for the production and utilisation of biomethane vehicle fuel or a biohydrogen/biomethane blend produced from food waste or wheat feed, based on data from two different laboratory experiments, have been compared. For food waste treated by batch processes the two stage system gave high hydrogen yields (84.2 l H2 kg?1 VS added) but a lower overall energy output than the single stage system. Reduction in environmental burdens compared with diesel was achieved, supported by the diversion of waste from landfill. For wheat feed, the semi continuously fed two stage process gave low hydrogen yields (7.5 l H2 kg?1 VS added) but higher overall energy output. The process delivers reduction in fossil fuel burdens, and improvements in process efficiencies will lead to reduction in CO2 burdens compared with diesel. The study highlights the importance of understanding and optimising biofuel production parameters according to the feedstock utilised.

Tim Patterson; Sandra Esteves; Richard Dinsdale; Alan Guwy; Jon Maddy

2013-01-01T23:59:59.000Z

394

Comparative analysis of the production costs and life-cycle GHG emissions of FT liquid fuels from coal and natural gas  

SciTech Connect (OSTI)

Liquid transportation fuels derived from coal and natural gas could help the United States reduce its dependence on petroleum. The fuels could be produced domestically or imported from fossil fuel-rich countries. The goal of this paper is to determine the life-cycle GHG emissions of coal- and natural gas-based Fischer-Tropsch (FT) liquids, as well as to compare production costs. The results show that the use of coal- or natural gas-based FT liquids will likely lead to significant increases in greenhouse gas (GHG) emissions compared to petroleum-based fuels. In a best-case scenario, coal- or natural gas-based FT-liquids have emissions only comparable to petroleum-based fuels. In addition, the economic advantages of gas-to-liquid (GTL) fuels are not obvious: there is a narrow range of petroleum and natural gas prices at which GTL fuels would be competitive with petroleum-based fuels. CTL fuels are generally cheaper than petroleum-based fuels. However, recent reports suggest there is uncertainty about the availability of economically viable coal resources in the United States. If the U.S. has a goal of increasing its energy security, and at the same time significantly reducing its GHG emissions, neither CTL nor GTL consumption seem a reasonable path to follow. 28 refs., 2 figs., 4 tabs.

Paulina Jaramillo; W. Michael Griffin; H. Scott Matthews [Carnegie Mellon University, Pittsburgh, PA (USA). Civil and Environmental Engineering Department

2008-10-15T23:59:59.000Z

395

Quantifying Variability in Life Cycle Greenhouse Gas Inventories of Alternative Middle Distillate Transportation Fuels  

Science Journals Connector (OSTI)

The presence of variability in life cycle analysis (LCA) is inherent due to both inexact LCA procedures and variation of numerical inputs. ... Carbon storage in soils of traditional slash-and-burn agriculture up to 6 m depth (185 t ha-1) was not significantly lower than under a primary forest (196 t ha-1) but declined significantly under (semi-) permanent cultures (to 146-167 t ha-1). ...

Russell W. Stratton; Hsin Min Wong; James I. Hileman

2011-04-22T23:59:59.000Z

396

Public Meeting and Availability of Statement of Policy for Adopting Full-Fuel-Cycle Analyses Into Energy Conservation Standards Program  

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

10 Aug 19, 2010 10 Aug 19, 2010 Jkt 220001 PO 00000 Frm 00001 Fmt 4702 Sfmt 4702 E:\FR\FM\20AUP1.SGM 20AUP1 jdjones on DSK8KYBLC1PROD with PROPOSALS-1 51423 Federal Register Proposed Rules Vol. 75, No. 161 Friday, August 20, 2010 This section of the FEDERAL REGISTER contains notices to the public of the proposed issuance of rules and regulations. The purpose of these notices is to give interested persons an opportunity to participate in the rule making prior to the adoption of the final rules. DEPARTMENT OF ENERGY 10 CFR Part 431 [Docket No (EERE-2010-BT-NOA-0028)] RIN 1904-AC24 Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment: Public Meeting and Availability of Statement of Policy for Adopting Full- Fuel-Cycle Analyses Into Energy

397

Regulatory analysis on emergency preparedness for fuel cycle and other radioactive material licensees. Draft report for comment  

SciTech Connect (OSTI)

Potential accidents for 15 types of fuel cycle and other radioactive material licensees were analyzed. The most potentially hazardous accident, by a large margin, was determined to be the sudden rupture of a heated multi-ton cylinder of UF/sub 6/. Acute fatalities offsite are probably not credible. Acute permanent injuries may be possible for many hundreds of meters, and clinically observable transient effects of unknown long term consequences may be possible for distances up to a few miles. These effects would be caused by the chemical toxicity of the UF/sub 6/. Radiation doses would not be significant. The most potentially hazardous accident due to radiation exposure was determined to be a large fire at certain facilities handling large quantities of alpha-emitting radionuclides (i.e., Po-210, Pu-238, Pu-239, Am-241, Cm-242, Cm-244) or radioiodines (I-125 and I-131). However, acute fatalities or injuries to people offsite due to accidental releases of these materials do not seem plausible. The only other significant accident was identified as a long-term pulsating criticality at fuel cycle facilities handling high-enriched uranium or plutonium. An important feature of the most serious accidents is that releases are likely to start without prior warning. The releases would usually end within about half an hour. Thus protective actions would have to be taken quickly to be effective. There is not likely to be enough time for dose projections, complicated decisionmaking during the accident, or the participation of personnel not in the immediate vicinity of the site. The appropriate response by the facility is to immediately notify local fire, police, and other emergency personnel and give them a brief predetermined message recommending protective actions. Emergency personnel are generally well qualified to respond effectively to small accidents of these types.

McGuire, S.A.

1985-06-01T23:59:59.000Z

398

Analysis of the Pebble-Bed VHTR Spectrum Shifting Capabilities for Advanced Fuel Cycles  

E-Print Network [OSTI]

to be subcritical is indeed subcritical. KENO-VI and CENTRM have validation reports noting that the codes were validated using the 238-group ENDF/B-V library against critical experiments. A wide range of experiments were selected, which include high... fuel, the neutron steaming effects in a pebble-bed type HTR, and the effects of accidental water ingress (since HTR systems generally tend to be under moderated, an accident of this type can lead to large positive reactivity changes, in particular...

Pritchard, Megan; Tsvetkov, Pavel

2009-09-30T23:59:59.000Z

399

Analysis of Pebble-Bed VHTR Spectrum Shifting Capabilities for Advanced Fuel Cycles  

E-Print Network [OSTI]

of validation is to establish an acceptance criteria such that there is a high degree of confidence that a system is calculated to be subcritical is indeed subcritical. KENO-VI and CENTRM have validation reports noting that the codes were...-heterogeneity in LEU fuel, the neutron steaming effects in a pebble-bed type HTR, and the effects of accidental water ingress (since HTR systems generally tend to be under moderated, an accident of this type can lead to large positive reactivity changes...

Pritchard, Megan

2006-07-11T23:59:59.000Z

400

Passive and Active Fast-Neutron Imaging in Support of Advanced Fuel Cycle Initiative Safeguards Campaign  

SciTech Connect (OSTI)

Results from safeguards-related passive and active coded-aperture fast-neutron imaging measurements of plutonium and highly enriched uranium (HEU) material configurations performed at Idaho National Laboratory s Zero Power Physics Reactor facility are presented. The imaging measurements indicate that it is feasible to use fast neutron imaging in a variety of safeguards-related tasks, such as monitoring storage, evaluating holdup deposits in situ, or identifying individual leached hulls still containing fuel. The present work also presents the first demonstration of imaging of differential die away fast neutrons.

Blackston, Matthew A [ORNL; Hausladen, Paul [ORNL

2010-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel cycle options" 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
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401

Fuel Processing [and Discussion  

Science Journals Connector (OSTI)

28 June 1990 research-article Fuel Processing [and Discussion] R. H. Allardice R. S...efficiently, reliably and economically through the reactor and fuel cycle facilities. Thus the fuel cycle is an integral and essential part of the system...

1990-01-01T23:59:59.000Z

402

Hydrogen as a fuel for fuel cell vehicles: A technical and economic comparison  

SciTech Connect (OSTI)

All fuel cells currently being developed for near term use in vehicles require hydrogen as a fuel. Hydrogen can be stored directly or produced onboard the vehicle by reforming methanol, ethanol or hydrocarbon fuels derived from crude oil (e.g., Diesel, gasoline or middle distillates). The vehicle design is simpler with direct hydrogen storage, but requires developing a more complex refueling infrastructure. In this paper, the authors compare three leading options for fuel storage onboard fuel cell vehicles: compressed gas hydrogen storage; onboard steam reforming of methanol; onboard partial oxidation (POX) of hydrocarbon fuels derived from crude oil. Equilibrium, kinetic and heat integrated system (ASPEN) models have been developed to estimate the performance of onboard steam reforming and POX fuel processors. These results have been incorporated into a fuel cell vehicle model, allowing us to compare the vehicle performance, fuel economy, weight, and cost for various fuel storage choices and driving cycles. A range of technical and economic parameters were considered. The infrastructure requirements are also compared for gaseous hydrogen, methanol and hydrocarbon fuels from crude oil, including the added costs of fuel production, storage, distribution and refueling stations. Considering both vehicle and infrastructure issues, the authors compare hydrogen to other fuel cell vehicle fuels. Technical and economic goals for fuel cell vehicle and hydrogen technologies are discussed. Potential roles for hydrogen in the commercialization of fuel cell vehicles are sketched.

Ogden, J.; Steinbugler, M.; Kreutz, T. [Princeton Univ., NJ (United States). Center for Energy and Environmental Studies

1997-12-31T23:59:59.000Z

403

The combined cycle  

Science Journals Connector (OSTI)

Any combination of at least two cyclic processes converting thermal energy (‘heat’) to work forms a combined cycle. In principle, the potential number of ... number of options reduces to a variety of cycles consi...

R. U. Pitt

1995-01-01T23:59:59.000Z

404

Financing Options  

Broader source: Energy.gov [DOE]

A growing variety of options are available for financing an LED street lighting replacement program. One or another approach may be preferable based on the system ownership and maintenance model in...

405

Program Record 13006 (Offices of Vehicle Technologies and Fuel Cell Technologies: Life-Cycle Costs of Mid-Size Light-Duty Vehicles  

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

Program Record (Offices of Vehicle Technologies & Fuel Cell Program Record (Offices of Vehicle Technologies & Fuel Cell Technologies) Record #: 13006 Date: April 24, 2013 Title: Life-cycle Costs of Mid-Size Light-Duty Vehicles Originator: Tien Nguyen & Jake Ward Approved by: Sunita Satyapal Pat Davis Date: April 25, 2013 Items: DOE is pursuing a portfolio of technologies with the potential to significantly reduce greenhouse gases (GHG) emissions and petroleum consumption while being cost-effective. This record documents the assumptions and results of analyses conducted to estimate the life-cycle costs resulting from several fuel/vehicle pathways, for a future mid-size car. The results are summarized graphically in the following figure. Costs of Operation for Future Mid-Size Car

406

Conceptual design study on very small long-life gas cooled fast reactor using metallic natural Uranium-Zr as fuel cycle input  

SciTech Connect (OSTI)

A conceptual design study of very small 350 MWth Gas-cooled Fast Reactors with Helium coolant has been performed. In this study Modified CANDLE burn-up scheme was implemented to create small and long life fast reactors with natural Uranium as fuel cycle input. Such system can utilize natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. The core with metallic fuel based was subdivided into 10 regions with the same volume. The fresh Natural Uranium is initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each region-1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all axial regions. The reactor discharge burn-up is 31.8% HM. From the neutronic point of view, this design is in compliance with good performance.

Monado, Fiber, E-mail: fiber.monado@gmail.com [Nuclear Physics and Biophysics Research Group, Dept. of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung, Indonesia and Dept. of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University (Indonesia); Ariani, Menik [Dept. of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University (Indonesia); Su'ud, Zaki; Waris, Abdul; Basar, Khairul; Permana, Sidik [Nuclear Physics and Biophysics Research Group, Dept. of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung (Indonesia); Aziz, Ferhat [National Nuclear Energy Agency of Indonesia (BATAN) (Indonesia); Sekimoto, Hiroshi [CRINES, Tokyo Institute of Technology, O-okoyama, Meguro-ku, Tokyo 152-8550 (Japan)

2014-02-12T23:59:59.000Z

407

DETERMINATION OF THE QUANTITY OF I-135 RELEASED FROM THE AGR-1 TEST FUELS AT THE END OF ATR OPERATING CYCLE 138B  

SciTech Connect (OSTI)

The AGR-1 experiment is a multiple fueled-capsule irradiation experiment being conducted in the Advanced Test Reactor (ATR) in support of the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The experiment began irradiation in the ATR with a cycle that reached full power on December 26, 2006 and ended with shutdown of the reactor for a brief outage on February 10, 2007 at 0900. The AGR-1 experiment will continue cyclical irradiation for about 2.5 years. In order to allow estimation of the amount of radioiodine released during the first cycle, purge gas flow to all capsules continued for about 4 days after reactor shutdown. The FPMS data acquired during part of that shutdown flow period has been analyzed to elucidate the level of 135I released during the operating cycle.

J. K. Hartwell; D. M. Scates; J. B. Walter; M. W. Drigert

2007-05-01T23:59:59.000Z

408

Fuels  

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

Goals > Fuels Goals > Fuels XMAT for nuclear fuels XMAT is ideally suited to explore all of the radiation processes experienced by nuclear fuels.The high energy, heavy ion accleration capability (e.g., 250 MeV U) can produce bulk damage deep in the sample, achieving neutron type depths (~10 microns), beyond the range of surface sputtering effects. The APS X-rays are well matched to the ion beams, and are able to probe individual grains at similar penetrations depths. Damage rates to 25 displacements per atom per hour (DPA/hr), and doses >2500 DPA can be achieved. MORE» Fuels in LWRs are subjected to ~1 DPA per day High burn-up fuel can experience >2000 DPA. Traditional reactor tests by neutron irradiation require 3 years in a reactor and 1 year cool down. Conventional accelerators (>1 MeV/ion) are limited to <200-400 DPAs, and

409

Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979  

SciTech Connect (OSTI)

In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing of refractory metals and alloys, graphite, and SiC in PDPM environments was done. A tungsten-metallized Al/sub 2/O/sub 3/-3% Y/sub 2/O/sub 3/ crucible was successfully fabricated. Tungsten microstructure of a plasma-sprayed tungsten crucible was stabilized by nickel infiltration and heat treatment. Solubility measurements of Th in Cd and Cd-Mg alloys were continued, as were experiments to study the reduction of high-fired ThO/sub 2/. Work on the fused salt electrolysis of CaO also was continued. The method of coprocessing of U and Pu by a salt transport process was modified. Tungsten-coated molybdenum crucibles were fabricated. The proliferation resistance of chloride volatility processing of thorium-based fuels is being evaluated by studying the behavior of fission product elements during chlorination of U and Th. Thermodynamic analysis of the phase relationships in the U-Pu-Zn system was initiated. The Pyro-Civex reprocessing method is being reviewed. Reactivity of UO/sub 2/ and PuO/sub 2/ with molten equimolar NaNO/sub 3/-KNO/sub 3/ is being studied along with the behavior of selected fission product elements. Work was continued on the reprocessing of actinide oxides by extracting the actinides from a bismuth solution. Rate of dissolution of UO/sub 2/ microspheres in LiCl/AlCl/sub 3/ was measured. Nitriding rates of Th and U dissolved in molten tin were measured. In work on the encapsulation of radioactive waste in metal, leach rates of a simulated waste glass were studied. Rates of dissolution of metals (potential barrier materials) in aqueous media are being studied. In work on the transport properties of nuclear waste in geologic media, the adsorption of iodate by hematite as a function of pH and iodate concentration was measured. The migration behavior of cesium in limestone was studied in relation to the cesium concentration and pH of simulated groundwater solutions.

Steindler, M J; Ader, M; Barletta, R E

1980-01-01T23:59:59.000Z

410

Preliminary studies on the heat exchanger option for S-CO{sub 2} power conversion cycle coupled to water cooled SMR  

SciTech Connect (OSTI)

For more than a half century, the steam Rankine cycle had been the major power conversion cycle for a nuclear power plant. However, as the interest on the next generation reactors grows, a variety of alternative power conversion systems have been studied. Among them, the S-CO{sub 2} cycle (Supercritical carbon dioxide Brayton cycle) is considered as a promising candidate due to several benefits such as 1) Relatively high thermal efficiency at relatively low turbine inlet temperature, 2) High efficiency with simple lay-out 3) Compactness of turbo-machineries. 4) Compactness of total cycle combined with PCHE (Printed Circuit Heat Exchanger). According to the conventional classification of heat exchangers (HE), there are three kind of HE, 1) Tubular HEs, 2) Plate-type HEs, 3) Extended surface HEs. So far, the researcher has mostly assumed PCHE type HE for the S-CO{sub 2} cycle due to its compactness with reasonably low pressure drop. However, PCHE is currently one of the most expensive components in the cycle, which can have a negative effect on the economics of the cycle. Therefore, an alternative for the HE should be seriously investigated. By comparing the operating condition (pressure and temperature) there are three kind of HE in the S-CO{sub 2} cycle, 1) IHX (Intermediate Heat exchanger) 2) Recuperator and 3) Pre-cooler. In each heat exchanger, hot side and cold side coolants are different, i.e. reactor coolant to S-CO{sub 2} (IHX), S-CO{sub 2} to S-CO{sub 2}(Recuperator), S-CO{sub 2} to water (Pre-cooler). By considering all the attributes mentioned above, all existing types of heat exchangers are compared to find a possible alternative to PCHE. The comparing factors are 1) Size(volume), 2) Cost. Plate fin type HEs are considered to be the most competitive heat exchanger regarding the size and the cost after some improvements on the design limit are made. (authors)

Ahn, Y.; Lee, J. [Dept. of Nuclear and Quantum Engineering, Korea Advanced Inst. of Science and Technology, 373-1 Guseong-dong Yuseong-gu, Daejeon, 305-701 (Korea, Republic of); Lee, J. I. [Dept. of Nuclear and Quantum Engineering, Korea Advanced Inst. of Science and Technology, 373-1 Guseong-dong Yuseong-gu, Daejeon, 305-701 (Korea, Republic of); Dept. of Nuclear Engineering, Khalifa Univ. of Science, Technology and Research (KUSTAR), P.O.Box 127788, Abu Dhabi (United Arab Emirates)

2012-07-01T23:59:59.000Z

411

Thorium–based fuel cycles : saving uranium in a 200 MWth pebble bed high temperature reactor / S.K. Gintner.  

E-Print Network [OSTI]

??The predominant nuclear fuel used globally at present is uranium which is a finite resource. Thorium has been identified as an alternative nuclear fuel source… (more)

Gintner, Stephan Konrad

2010-01-01T23:59:59.000Z

412

A Science-Based Approach to Understanding Waste Form Durability in Open and Closed Nuclear Fuel Cycles  

SciTech Connect (OSTI)

There are two compelling reasons for understanding source term and near-field processes in a radioactive waste geologic repository. First, almost all of the radioactivity is initially in the waste form, mainly in the spent nuclear fuel (SNF) or nuclear waste glass. Second, over long periods, after the engineered barriers are degraded, the waste form is a primary control on the release of radioactivity. Thus, it is essential to know the physical and chemical state of the waste form after hundreds of thousands of years. The United States Department of Energy's Yucca Mountain Repository Program has initiated a long-term program to develop a basic understanding of the fundamental mechanisms of radionuclide release and a quantification of the release as repository conditions evolve over time. Specifically, the research program addresses four critical areas: (a) SNF dissolution mechanisms and rates; (b) formation and properties of U{sup 6+}-secondary phases; (c) waste form-waste package interactions in the near-field; and (d) integration of in-package chemical and physical processes. The ultimate goal is to integrate the scientific results into a larger scale model of source term and near-field processes. This integrated model will be used to provide a basis for understanding the behavior of the source term over long time periods (greater than 10{sup 5} years). Such a fundamental and integrated experimental and modeling approach to source term processes can also be readily applied to development of advanced waste forms as part of a closed nuclear fuel cycle. Specifically, a fundamental understanding of candidate waste form materials stability in high temperature/high radiation environments and near-field geochemical/hydrologic processes could enable development of advanced waste forms ''tailored'' to specific geologic settings.

M.T. Peters; R.C. Ewing

2006-06-22T23:59:59.000Z

413

Americium/Lanthanide Separations in Alkaline Solutions for Advanced Nuclear Fuel Cycles  

SciTech Connect (OSTI)

Project goals: Can used nuclear fuel be partitioned by dissolution in alkaline aqueous solution to give a solution of uranium, neptunium, plutonium, americium and curium and a filterable solid containing nearly all of the lanthanide fission products and certain other fission products? What is the chemistry of Am/Cm/Ln in oxidative carbonate solutions? Can higher oxidation states of Am be stabilized and exploited? Conclusions: Am(VI) is kinetically stable in 0.5-2.0 M carbonate solutions for hours. Aliquat 336 in toluene has been successfully shown to extract U(VI) and Pu(VI) from carbonate solutions. (Stepanov et al 2011). Higher carbonate concentration gives lower D, SF{sub U/Eu} for = 4 in 1 M K{sub 2}CO{sub 3}. Experiments with Am(VI) were unsuccessful due to reduction by the organics. Multiple sources of reducing organics...more optimization. Reduction experiments of Am(VI) in dodecane/octanol/Aliquat 336 show that after 5 minutes of contact, only 30-40% of the Am(VI) has been reduced. Long enough to perform an extraction. Shorter contact times, lower T, and lower Aliquat 336 concentration still did not result in any significant extraction of Am. Anion exchange experiments using a strong base anion exchanger show uptake of U(VI) with minimal uptake of Nd(III). Experiments with Am(VI) indicate Am sorption with a Kd of 9 (10 minute contact) but sorption mechanism is not yet understood. SF{sub U/Nd} for = 7 and SF{sub U/Eu} for = 19 after 24 hours in 1 M K{sub 2}CO{sub 3}.

Goff, George S. [Los Alamos National Laboratory; Long, Kristy Marie [Los Alamos National Laboratory; Reilly, Sean D. [Los Alamos National Laboratory; Jarvinen, Gordon D. [Los Alamos National Laboratory; Runde, Wolfgang H. [Los Alamos National Laboratory

2012-06-11T23:59:59.000Z

414

Recovery Act: Brea California Combined Cycle Electric Generating Plant Fueled by Waste Landfill Gas  

SciTech Connect (OSTI)

The primary objective of the Project was to maximize the productive use of the substantial quantities of waste landfill gas generated and collected at the Olinda Landfill near Brea, California. An extensive analysis was conducted and it was determined that utilization of the waste gas for power generation in a combustion turbine combined cycle facility was the highest and best use. The resulting Project reflected a cost effective balance of the following specific sub-objectives: • Meeting the environmental and regulatory requirements, particularly the compliance obligations imposed on the landfill to collect, process and destroy landfill gas • Utilizing proven and reliable technology and equipment • Maximizing electrical efficiency • Maximizing electric generating capacity, consistent with the anticipated quantities of landfill gas generated and collected at the Olinda Landfill • Maximizing equipment uptime • Minimizing water consumption • Minimizing post-combustion emissions • The Project produced and will produce a myriad of beneficial impacts. o The Project created 360 FTE construction and manufacturing jobs and 15 FTE permanent jobs associated with the operation and maintenance of the plant and equipment. o By combining state-of-the-art gas clean up systems with post combustion emissions control systems, the Project established new national standards for best available control technology (BACT). o The Project will annually produce 280,320 MWh’s of clean energy o By destroying the methane in the landfill gas, the Project will generate CO2 equivalent reductions of 164,938 tons annually. The completed facility produces 27.4 MWnet and operates 24 hours a day, seven days a week.

Galowitz, Stephen

2012-12-31T23:59:59.000Z

415

Nevada Transportatoion Options Study  

SciTech Connect (OSTI)

This study performs a cost and schedule analysis of three Nevada Transportation options that support waste receipt at the repository. Based on the U.S. Department of Energy preference for rail transportation in Nevada (given in the Final Environmental Impact Statement), it has been assumed that a branch rail line would be constructed to support waste receipt at the repository. However, due to potential funding constraints, it is uncertain when rail will be available. The three Nevada Transportation options have been developed to meet a varying degree of require