Powered by Deep Web Technologies
Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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.


1

Fuel Cells Vehicle Systems Analysis (Fuel Cell Freeze Investigation)  

DOE Green Energy (OSTI)

Presentation on Fuel Cells Vehicle Systems Analysis (Fuel Cell Freeze Investigation) for the 2005 Hydrogen, Fuel Cells & Infrastructure Technologies Program Annual Review held in Arlington, Virginia on May 23-26, 2005.

Pesaran, A.; Kim, G.; Markel, T.; Wipke, K.

2005-05-01T23:59:59.000Z

2

Nondestrucive analysis of fuel pins  

DOE Patents (OSTI)

Disclosure is made of a method and a correspondingly adapted facility for the nondestructive analysis of the concentation of fuel and poison in a nuclear reactor fuel pin. The concentrations of fuel and poison in successive sections along the entire length of the fuel pin are determined by measuring the reactivity of a thermal reactor as each successive small section of the fuel pin is exposed to the neutron flux of the reactor core and comparing the measured reactivity with the reactivities measured for standard fuel pins having various known concentrations. Only a small section of the length of the fuel pin is exposed to the neutron flux at any one time while the remainder of the fuel pin is shielded from the neutron flux. In order to expose only a small section at any one time, a boron-10-lined dry traverse tube is passed through the test region within the core of a low-power thermal nuclear reactor which has a very high fuel sensitivity. A narrow window in the boron-10 lining is positioned at the core center line. The fuel pins are then systematically traversed through the tube past the narrow window such that successive small sections along the length of the fuel pin are exposed to the neutron flux which passes through the narrow window.

Stepan, I.E.; Allard, N.P.; Suter, C.R.

1972-11-03T23:59:59.000Z

3

Fuel Cell Technologies Office: Market Analysis Reports  

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

Information Resources Information Resources Printable Version Share this resource Send a link to Fuel Cell Technologies Office: Market Analysis Reports to someone by E-mail Share Fuel Cell Technologies Office: Market Analysis Reports on Facebook Tweet about Fuel Cell Technologies Office: Market Analysis Reports on Twitter Bookmark Fuel Cell Technologies Office: Market Analysis Reports on Google Bookmark Fuel Cell Technologies Office: Market Analysis Reports on Delicious Rank Fuel Cell Technologies Office: Market Analysis Reports on Digg Find More places to share Fuel Cell Technologies Office: Market Analysis Reports on AddThis.com... Publications Program Publications Technical Publications Hydrogen Fuel Cells Safety, Codes & Standards Market Analysis Educational Publications Newsletter

4

Fuel Cell Technologies Office: Market Analysis Reports  

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

of Energy - Energy Efficiency and Renewable Energy Fuel Cell Technologies Office Market Analysis Reports Reports about fuel cell and hydrogen technology market analysis...

5

Economic analysis of fuel recycle  

SciTech Connect

Economic analysis was performed at KAERI with the assistance of US DOE to compare single reactor fuel cycle costs for a once-through option and a thermal recycle option to operate 1 GWe of a PWR plant for its lifetime. A reference fuel cycle cost was first calculated for each option with best estimated reference input data. Then a sensitivity analysis was performed changing each single value of such fuel cycle component costs as yellow cake price, enrichment charges, spent fuel storage cost, reprocessing cost, spent fuel disposal cost and reprocessing waste disposal cost. Savings due to thermal recycle in requirements of uranium, conversion, and enrichment were examined using formulas suggested by US DOE, while MOX fabrication penalty was accounted for. As a result of the reference fuel cycle cost analysis, it is calculated that the thermal recycle option is marginally more economical than the once-through option. The major factors affecting the comparative costs between thermal recycle and once-through are the costs of reprocessing, spent fuel storage and the difference between spent fuel disposal and reprocessing waste disposal. However, considering the uncertainty in these cost parameters there seems no immediate economic incentive for thermal recycle at the present time.

Juhn, P.E.

1985-01-01T23:59:59.000Z

6

NREL: Energy Analysis - Hydrogen and Fuel Cells Technology Analysis  

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

Sciences Geothermal Hydrogen and Fuel Cells Solar Vehicles and Fuels Research Wind Market Analysis Policy Analysis Sustainability Analysis Key Activities Models & Tools Data &...

7

DOE Hydrogen Analysis Repository: Life Cycle Analysis of Vehicles for  

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

Life Cycle Analysis of Vehicles for Canada Life Cycle Analysis of Vehicles for Canada Project Summary Full Title: Life Cycle Analysis of Vehicles Powered by a Fuel Cell and by Internal Combustion Engine for Canada Project ID: 117 Principal Investigator: Xianguo Li Purpose In this study, a full life cycle analysis of an internal combustion engine vehicle (ICEV) and a fuel cell vehicle (FCV) has been carried out. The impact of the material and fuel used in the vehicle on energy consumption and carbon dioxide emissions is analyzed for Canada. Four different methods of obtaining hydrogen were analyzed; using coal and nuclear power to produce electricity and extraction of hydrogen through electrolysis and via steam reforming of natural gas in a natural gas plant and in a hydrogen refueling station.

8

Fuel Cell Technologies Office: Systems Analysis  

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

Office: Systems Analysis on AddThis.com... Home Analysis Methodologies DOE H2A Analysis Scenario Analysis Quick Links Hydrogen Production Hydrogen Delivery Hydrogen Storage Fuel...

9

Fuel Cell Technologies Office: Systems Analysis  

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

| Consumer Information Systems Analysis Search Search Help Systems Analysis EERE Fuel Cell Technologies Office Systems Analysis Printable Version Share this resource Send...

10

Alternative Fueled Fleet Vehicle Analysis  

Science Conference Proceedings (OSTI)

This report documents the results of an analysis conducted to evaluate options available to utilities to "green" their vehicle fleet. The New York Power Authority fleet was used as our test case. In accordance with corporate sustainability goals. NYPA vehicle purchasing decisions are constrained by internal requirements, including operational considerations and funding availability, and external constraints, including, most significantly, the alternative fuel vehicle (AFV) purchasing requirements of the ...

2011-10-27T23:59:59.000Z

11

SEU43 fuel bundle shielding analysis during spent fuel transport  

Science Conference Proceedings (OSTI)

The basic task accomplished by the shielding calculations in a nuclear safety analysis consist in radiation doses calculation, in order to prevent any risks both for personnel protection and impact on the environment during the spent fuel manipulation, transport and storage. The paper investigates the effects induced by fuel bundle geometry modifications on the CANDU SEU spent fuel shielding analysis during transport. For this study, different CANDU-SEU43 fuel bundle projects, developed in INR Pitesti, have been considered. The spent fuel characteristics will be obtained by means of ORIGEN-S code. In order to estimate the corresponding radiation doses for different measuring points the Monte Carlo MORSE-SGC code will be used. Both codes are included in ORNL's SCALE 5 programs package. A comparison between the considered SEU43 fuel bundle projects will be also provided, with CANDU standard fuel bundle taken as reference. (authors)

Margeanu, C. A.; Ilie, P.; Olteanu, G. [Inst. for Nuclear Research Pitesti, No. 1 Campului Street, Mioveni 115400, Arges County (Romania)

2006-07-01T23:59:59.000Z

12

Nuclear Fuel Cycle Integrated System Analysis  

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

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

13

Advanced Fuel Cycle Economic Sensitivity Analysis  

Science Conference Proceedings (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

14

Systems Analysis Sub-Program Overview - DOE Hydrogen and Fuel...  

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

Displaced Technology-Related Total 2009 2010 2011 - PRELIMINARY ANALYSIS - Including Backup Power Fuel Cells and Fuel Cell-Powered Forklifts Employment Impacts of ARRA Fuel Cell...

15

Fuel Performance Analysis Capability in FALCON  

Science Conference Proceedings (OSTI)

The Fuel Analysis and Licensing Code -- New (FALCON) is being developed as a state-of-the-art light water reactor (LWR) fuel performance analysis and modeling code validated to high burnup. Based on a robust finite-element numerical structure, it is capable of analyzing both steady-state and transient fuel behaviors with a seamless transition between the two modes. EPRI plans to release a fully benchmarked and validated beta version of FALCON in 2003.

2002-12-06T23:59:59.000Z

16

Comparative analysis of selected fuel cell vehicles  

DOE Green Energy (OSTI)

Vehicles powered by fuel cells operate more efficiently, more quietly, and more cleanly than internal combustion engines (ICEs). Furthermore, methanol-fueled fuel cell vehicles (FCVs) can utilize major elements of the existing fueling infrastructure of present-day liquid-fueled ICE vehicles (ICEVs). DOE has maintained an active program to stimulate the development and demonstration o fuel cell technologies in conjunction with rechargeable batteries in road vehicles. The purpose of this study is to identify and assess the availability of data on FCVs, and to develop a vehicle subsystem structure that can be used to compare both FCVs and ICEV, from a number of perspectives--environmental impacts, energy utilization, materials usage, and life cycle costs. This report focuses on methanol-fueled FCVs fueled by gasoline, methanol, and diesel fuel that are likely to be demonstratable by the year 2000. The comparative analysis presented covers four vehicles--two passenger vehicles and two urban transit buses. The passenger vehicles include an ICEV using either gasoline or methanol and an FCV using methanol. The FCV uses a Proton Exchange Membrane (PEM) fuel cell, an on-board methanol reformer, mid-term batteries, and an AC motor. The transit bus ICEV was evaluated for both diesel and methanol fuels. The transit bus FCV runs on methanol and uses a Phosphoric Acid Fuel Cell (PAFC) fuel cell, near-term batteries, a DC motor, and an on-board methanol reformer. 75 refs.

NONE

1993-05-07T23:59:59.000Z

17

Lead Fuel Assembly Programs Analysis: Utility Perspectives  

Science Conference Proceedings (OSTI)

Licensees, in association with nuclear fuel vendors, conduct lead fuel assembly (LFA) programs to test new design features prior to batch implementation. A limited number of LFAs are irradiated to obtain data and to confirm successful operation in the host reactor environment. The new LFA design features range from minor changes of dimensions and/or materials to an entirely new design from an alternate fuel vendor. LFA program elements can consist of design activities, methods development, analysis, ...

2013-10-17T23:59:59.000Z

18

Economic Analysis of Alternative Fuel School Buses  

DOE Green Energy (OSTI)

This Clean Cities final report provides a general idea of the potential economic impacts of choosing alternative fuels for school bus fleets. It provides information on different school bus types, as well as analysis of the three main types of alternative fuel used in school bus fleets today (natural gas, propane, and biodiesel).

Laughlin, M.

2004-04-01T23:59:59.000Z

19

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

20

Cryogenic Fuel Tank Draining Analysis Model  

E-Print Network (OSTI)

One of the technological challenges in designing advanced hypersonic aircraft and the next generation of spacecraft is developing reusable flight-weight cryogenic fuel tanks. As an aid in the design and analysis of these cryogenic tanks, a computational fluid dynamics (CFD) model has been developed specifically for the analysis of flow in a cryogenic fuel tank. This model employs the full set of Navier-Stokes equations, except that viscous dissipation is neglected in the energy equation. An explicit finite difference technique in two-dimensional generalized coordinates, approximated to second-order accuracy in both space and time is used. The stiffness resulting from the low Mach number is resolved by using artificial compressibility. The model simulates the transient, two-dimensional draining of a fuel tank cross section. To calculate the slosh wave dynamics the interface between the ullage gas and liquid fuel is modeled as a free surface. Then, experimental data for free convection i...

Donald Greer Research; Donald Greer

1999-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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 System Analysis Handbook  

Science Conference Proceedings (OSTI)

This Handbook aims to improve understanding and communication regarding nuclear fuel cycle options. It is intended to assist DOE, Campaign Managers, and other presenters prepare presentations and reports. When looking for information, check here. The Handbook generally includes few details of how calculations were performed, which can be found by consulting references provided to the reader. The Handbook emphasizes results in the form of graphics and diagrams, with only enough text to explain the graphic, to ensure that the messages associated with the graphic is clear, and to explain key assumptions and methods that cause the graphed results. Some of the material is new and is not found in previous reports, for example: (1) Section 3 has system-level mass flow diagrams for 0-tier (once-through), 1-tier (UOX to CR=0.50 fast reactor), and 2-tier (UOX to MOX-Pu to CR=0.50 fast reactor) scenarios - at both static and dynamic equilibrium. (2) To help inform fast reactor transuranic (TRU) conversion ratio and uranium supply behavior, section 5 provides the sustainable fast reactor growth rate as a function of TRU conversion ratio. (3) To help clarify the difference in recycling Pu, NpPu, NpPuAm, and all-TRU, section 5 provides mass fraction, gamma, and neutron emission for those four cases for MOX, heterogeneous LWR IMF (assemblies mixing IMF and UOX pins), and a CR=0.50 fast reactor. There are data for the first 10 LWR recycle passes and equilibrium. (4) Section 6 provides information on the cycle length, planned and unplanned outages, and TRU enrichment as a function of fast reactor TRU conversion ratio, as well as the dilution of TRU feedstock by uranium in making fast reactor fuel. (The recovered uranium is considered to be more pure than recovered TRU.) The latter parameter impacts the required TRU impurity limits specified by the Fuels Campaign. (5) Section 7 provides flows for an 800-tonne UOX separation plant. (6) To complement 'tornado' economic uncertainty diagrams, which show at a glance combined uncertainty information, section 9.2 has a new set of simpler graphs that show the impact on fuel cycle costs for once through, 1-tier, and 2-tier scenarios as a function of key input parameters.

Steven J. Piet; Brent W. Dixon; Dirk Gombert; Edward A. Hoffman; Gretchen E. Matthern; Kent A. Williams

2009-06-01T23:59:59.000Z

22

Renewable Fuels Legislation Impact Analysis  

Reports and Publications (EIA)

An analysis based on an extension of the ethanol supply curve in our model to allow for enough ethanol production to meet the requirements of S. 650. This analysis provides an update of the May 23, 2005 analysis, with revised ethanol production and cost assumptions.

Information Center

2005-07-01T23:59:59.000Z

23

Current Projects for Reactor Physics and Fuel Cycle Analysis...  

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

Nuclear Systems Modeling and Design Analysis > Reactor Physics and Fuel Cycle Analysis > Current Projects Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics...

24

AN ANALYSIS OF POWER REACTOR FUEL REPROCESSING  

SciTech Connect

This report presents an analysis of the projected economies and processing capacity requirements for a power reactor fuel reprocessing industry based on the recovery of fertile and fissionable materials from presently proposed power reactors within tbe confines of the continental United 8tates for the next five to ten years. An analysis of the present general state of development of a technology required for such an Industry is given. A summary of results of power reactor reprocessing chemical and engineering development at Oak Ridge National Laboratory from July 1955 through December 1956 is given. (auth)

Culler, F.L. Jr.; Blanco, R.E.; Goeller, H.E.; Watson, C.D.

1957-03-27T23:59:59.000Z

25

DOE Hydrogen Analysis Repository: Distributed Hydrogen Fueling Systems  

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

Distributed Hydrogen Fueling Systems Analysis Distributed Hydrogen Fueling Systems Analysis Project Summary Full Title: H2 Production Infrastructure Analysis - Task 1: Distributed Hydrogen Fueling Systems Analysis Project ID: 78 Principal Investigator: Brian James Keywords: Hydrogen infrastructure; costs; methanol; hydrogen fueling Purpose As the DOE considers both direct hydrogen and reformer-based fuel cell vehicles, it is vital to have a clear perspective of the relative infrastructure costs to supply each prospective fuel (gasoline, methanol, or hydrogen). Consequently, this analysis compares these infrastructure costs as well as the cost to remove sulfur from gasoline (as will most likely be required for use in fuel cell systems) and the cost implications for several hydrogen tank filling options. This analysis supports Analysis

26

Data Analysis for ARRA Early Fuel Cell Market Demonstrations (Presentation)  

SciTech Connect

Presentation about ARRA Early Fuel Cell Market Demonstrations, including an overview of the ARRE Fuel Cell Project, the National Renewable Energy Laboratory's data analysis objectives, deployment composite data products, and planned analyses.

Kurtz, J.; Wipke, K.; Sprik, S.; Ramsden, T.

2010-05-01T23:59:59.000Z

27

Severe Degradation of BWR Fuel Failures: Coolant Activity Analysis  

Science Conference Proceedings (OSTI)

Analysis of coolant activities offers considerable insight into the phenomena leading to the degradation of failed BWR fuel. This report provides operational guidelines to help utilities manage failed fuel and mitigate the impact of degradation.

1993-12-01T23:59:59.000Z

28

Analysis of Nuclear Proliferation Resistance of DUPIC Fuel Cycle  

E-Print Network (OSTI)

with other fuel cycle cases. The other fuel cycles considered in this study are PWR of once-through mode (PWR-OT), PWR of reprocessing mode (PWR-MOX), in which spent PWR fuel is reprocessed and recovered plutonium is used for making MOX (Mixed Oxide), CANDU with once-through mode (CANDU-OT), PWR fuel and CANDU fuel in a oncethrough mode with reactor grid equivalent to DUPIC fuel cycle (PWR-CANDU-OT). This study is focused on intrinsic barriers, especially, radiation field of the diverted material, which could be a significant accessibility barrier, amount of special nuclear material based on 1 GWe-yr that has to be diverted and the quality of the separated fissile material. It is indicated from plutonium analysis of each fuel cycle that the MOX spent fuel is containing the largest plutonium per MTHM but PWR-MOX option based on 1 GWe-yr has the best benefit in total plutonium consumption aspects. The DUPIC option is containing a little higher total plutonium based on 1 GWe-yr than the PWR-MOX case, but the DUPIC option has the lowest fissile plutonium content which could be another measure for proliferation resistance. On the whole, the CANDU-OT option has the largest fissile plutonium as well as total plutonium per GWe-yr, which means negative points in nuclear proliferation resistance aspects. It is indicated from the radiation field analysis that fresh DUPIC fuel could play an important radiation barrier role, more than even CANDU spent fuels. In conclusion, due to those inherent features, the DUPIC fuel cycle could include technical characteristics that comply naturally with the Spent Fuel Standard, at all steps along the DUPIC linkage between PWR and CANDU. KEYWORDS: DUPIC (direct use of spent PWR fuel in CANDU), (DUPIC) fuel cycle, nuclear fuel cycle analysis, nuclear proliferaion resistance, proliferation resistance barrier, safeguards, plutonium analysis, candu type reactors, spent fuels, fuel cycles I.

Won Il Ko; Ho Dong Kim

2001-01-01T23:59:59.000Z

29

Fuel Cell Technology Status Analysis Project: Partnership Opportunities (Fact Sheet)  

DOE Green Energy (OSTI)

This fact sheet describes opportunities for leading fuel cell industry partners from the United States and abroad to participate in an objective and credible fuel cell technology performance and durability analysis by sharing their raw fuel cell test data related to operations, maintenance, safety, and cost with the National Renewable Energy Laboratory via the Hydrogen Secure Data Center.

Not Available

2013-01-01T23:59:59.000Z

30

Analysis of Real World Fuel Cell Degradation (Presentation)  

DOE Green Energy (OSTI)

Presentation about the National Renewable Energy Laboratory's Hydrogen Secure Data Center and its work with fuel cell vehicles, fuel cell early market demonstrations, and fuel cell bus demonstrations. This presentation includes results of composite data products and a summary of the analysis objectives and data flow for the projects.

Kurtz, J.; Wipke, K.; Sprik, S.; Ramsden, T.

2009-12-08T23:59:59.000Z

31

Fuel Cell Technologies Office: Hydrogen Systems Analysis Workshop...  

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

Lee Slezak, OFCVT Fuel Pathways Integration Tech Team (PDF 109 KB), Don Gardner, ExxonMobil Planning, Budget, and Analysis (PDF 267 KB), Phil Patterson, PBA Argonne National...

32

Data Collection & Analysis for ARRA Fuel Cell Projects (Presentation)  

DOE Green Energy (OSTI)

The data analysis objectives are: (1) Independent assessment of technology, focused on fuel cell system and hydrogen infrastructure:performance, operation, and safety; (2) Leverage data processing and analysis capabilities from the fuel cell vehicle Learning Demonstration project and DoD Forklift Demo; (3) Establish a baseline of real-world fuel cell operation and maintenance data and identify technical/market barriers; (4) Support market growth of fuel cell technologies by reporting on technology features relevant to the business case; and (5) Report on technology to fuel cell and hydrogen communities and stakeholders.

Kurtz, J.; Ramsden, T.; Wipke, K.; Sprik, S.

2009-08-21T23:59:59.000Z

33

An Economic Analysis of Select Fuel Cycles Using the Steady-State Analysis Model for Advanced Fuel Cycles Schemes (SMAFS)  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy's (DOE) Global Nuclear Energy Partnership (GNEP) is currently considering alternatives to the current U.S. once-through fuel cycle. This report evaluates the relative economics of three alternative fuel cycles to determine those cost components important to overall fuel cycle costs and total generation costs. The analysis determined that the unit cost of nuclear reactors is the most important nuclear generation cost parameter in future fuel cycles. The report also evaluates ...

2007-12-20T23:59:59.000Z

34

Fuel Cell Technologies Office: Critical Updates to the Hydrogen Analysis  

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

Critical Updates to Critical Updates to the Hydrogen Analysis Production Model (H2A v3) (Text Version) to someone by E-mail Share Fuel Cell Technologies Office: Critical Updates to the Hydrogen Analysis Production Model (H2A v3) (Text Version) on Facebook Tweet about Fuel Cell Technologies Office: Critical Updates to the Hydrogen Analysis Production Model (H2A v3) (Text Version) on Twitter Bookmark Fuel Cell Technologies Office: Critical Updates to the Hydrogen Analysis Production Model (H2A v3) (Text Version) on Google Bookmark Fuel Cell Technologies Office: Critical Updates to the Hydrogen Analysis Production Model (H2A v3) (Text Version) on Delicious Rank Fuel Cell Technologies Office: Critical Updates to the Hydrogen Analysis Production Model (H2A v3) (Text Version) on Digg

35

Image analysis for remote examination of fuel pins  

Science Conference Proceedings (OSTI)

An image analysis system operating in the Wing 9 Hot Cell Facility at Los Alamos National Laboratory provides quantitative microstructural analyses of irradiated fuels and materials. With this system, fewer photomicrographs are required during postirradiation microstructural examination and data are available for analysis much faster. The system has been used successfully to examine Westinghouse Advanced Reactors Division experimental fuel pins.

Cook, J.H.; Nayak, U.P.

1982-01-01T23:59:59.000Z

36

DOE Hydrogen Analysis Repository: Life Cycle Assessment of Hydrogen Fuel  

NLE Websites -- All DOE Office Websites (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

37

DOE Hydrogen Analysis Repository: Potential for Stationary Fuel Cells to  

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

Potential for Stationary Fuel Cells to Augment Hydrogen Availability for Potential for Stationary Fuel Cells to Augment Hydrogen Availability for Hydrogen Vehicles Project Summary Full Title: Analyzing the Potential for Stationary Fuel Cells to Augment Hydrogen Availability in the Transition to Hydrogen Vehicles Project ID: 281 Principal Investigator: David Greene Brief Description: This analysis was focused on the role that combined heat and hydrogen power (CHHP) could play in increasing hydrogen refueling availability during the transition to hydrogen vehicles. Keywords: Stationary fuel cell; hydrogen; plug-in hybrid electric vehicle; hydrogen fuel cell vehicle; combined heat, hydrogen and power; internal combustion engine Performer Principal Investigator: David Greene Organization: Oak Ridge National Laboratory (ORNL)

38

DOE Hydrogen Analysis Repository: H2 Fueling Appliances Cost and  

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

H2 Fueling Appliances Cost and Performance H2 Fueling Appliances Cost and Performance Project Summary Full Title: H2 Production Infrastructure Analysis - Task 2: Cost and Performance of H2 Fueling Appliances Project ID: 80 Principal Investigator: Brian James Keywords: Costs; steam methane reforming (SMR); autothermal reforming (ATR); hydrogen fueling Purpose The purpose of the analysis was to estimate the capital cost and the resulting cost of hydrogen of several types of methane-fueled hydrogen production systems. A bottoms-up cost analysis was conducted of each system to generate a system design and detailed bill-of-materials. Estimates of the overall capital cost of the hydrogen production appliance were generated. This work supports Systems Analysis Milestone A1. ("Complete techno-economic analysis on production and delivery technologies currently

39

Life-cycle analysis of alternative aviation fuels in GREET  

SciTech Connect

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

40

Fuel Cell Technologies Office: Systems Analysis  

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

The tool estimates the number of jobs created by deploying fuel cells in forklifts, backup power, and prime power applications. JOBS FC is a spreadsheet model that estimates...

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

DOE Hydrogen Analysis Repository: Hydrogen Quality Issues for Fuel Cell  

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

Quality Issues for Fuel Cell Vehicles Quality Issues for Fuel Cell Vehicles Project Summary Full Title: Hydrogen Quality Issues for Fuel Cell Vehicles Project ID: 201 Principal Investigator: Romesh Kumar Keywords: Lifecycle costs; fuel cells; steam methane reforming (SMR); autothermal reforming (ATR) Purpose Assess the influence of different contaminants and their concentration in fuel hydrogen on the life-cycle costs of hydrogen production, purification, use in fuel cells, and hydrogen analysis and quality verification. Performer Principal Investigator: Romesh Kumar Organization: Argonne National Laboratory (ANL) Address: 9700 S. Cass Avenue Argonne, IL 60439 Telephone: 630-252-4342 Email: kumar@cmt.anl.gov Period of Performance Start: October 2005 End: September 2010 Project Description Type of Project: Analysis

42

Analysis of Fuel Cell Systems Rangan Banerjee  

E-Print Network (OSTI)

/Truck) Primary energy source Vehicle (On-board storage and utilization) Hydrogen production centre (Production Renewable Hydrogen #12;Energy Crisis Present energy systems ­ fossil fuel based (~80%) Finite fossil fuel Concentrations #12;Hydrogen Energy Can hydrogen energy mitigate the energy problem? How does the hydrogen energy

Banerjee, Rangan

43

FUEL SUPPLY SYSTEM ANALYSIS FOR ESF PACKAGE 1E  

SciTech Connect

The primary objective of this analysis is to capture new inputs relative to the design of the Fuel Supply System (FSS) at the Yucca Mountain Site Characterization Project (YMP) Exploratory Studies Facility (ESF). The new inputs are analyzed and changes to the Fuel Supply System are made as necessary.

D.F. Vanica

1995-06-14T23:59:59.000Z

44

22.351 Systems Analysis of the Nuclear Fuel Cycle, Spring 2003  

E-Print Network (OSTI)

In-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, ...

Kazimi, Mujid S.

45

Preliminary analysis of alternative fuel cycles for proliferation evaluation  

SciTech Connect

The ERDA Division of Nuclear Research and Applications proposed 67 nuclear fuel cycles for assessment as to their nonproliferation potential. The object of the assessment was to determine which fuel cycles pose inherently low risk for nuclear weapon proliferation while retaining the major benefits of nuclear energy. This report is a preliminary analysis of these fuel cycles to develop the fuel-recycle data that will complement reactor data, environmental data, and political considerations, which must be included in the overall evaluation. This report presents the preliminary evaluations from ANL, HEDL, ORNL, and SRL and is the basis for a continuing in-depth study. (DLC)

Steindler, M. J.; Ripfel, H. C.F.; Rainey, R. H.

1977-01-01T23:59:59.000Z

46

DOE Hydrogen and Fuel Cells Program: Hydrogen Analysis Resource Center  

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

Hydrogen Production Hydrogen Production Hydrogen Delivery Hydrogen Storage Hydrogen Manufacturing Fuel Cells Applications/Technology Validation Safety Codes and Standards Education Basic Research Systems Analysis Analysis Repository H2A Analysis Hydrogen Analysis Resource Center Scenario Analysis Well-to-Wheels Analysis Systems Integration U.S. Department of Energy Search help Home > Systems Analysis > Hydrogen Analysis Resource Center Printable Version Hydrogen Analysis Resource Center The Hydrogen Analysis Resource Center provides consistent and transparent data that can serve as the basis for hydrogen-related calculations, modeling, and other analytical activities. This new site features the Hydrogen Data Book with data pertinent to hydrogen infrastructure analysis; links to external databases related to

47

An analysis of distributed solar fuel systems  

E-Print Network (OSTI)

While solar fuel systems offer tremendous potential to address global clean energy needs, most existing analyses have focused on the feasibility of large centralized systems and applications. Not much research exists on ...

Thomas, Alex, S.M. Massachusetts Institute of Technology

2012-01-01T23:59:59.000Z

48

Analysis of IFR driver fuel hot channel factors  

Science Conference Proceedings (OSTI)

Thermal-hydraulic uncertainty factors for Integral Fast Reactor (IFR) driver fuels have been determined based primarily on the database obtained from the predecessor fuels used in the IFR prototype, Experimental Breeder Reactor II. The uncertainty factors were applied to the channel factors (HCFs) analyses to obtain separate overall HCFs for fuel and cladding for steady-state analyses. A ``semistatistical horizontal method`` was used in the HCFs analyses. The uncertainty factor of the fuel thermal conductivity dominates the effects considered in the HCFs analysis; the uncertainty in fuel thermal conductivity will be reduced as more data are obtained to expand the currently limited database for the IFR ternary metal fuel (U-20Pu-10Zr). A set of uncertainty factors to be used for transient analyses has also been derived.

Ku, J.Y.; Chang, L.K.; Mohr, D.

1994-03-01T23:59:59.000Z

49

Reactor Physics and Fuel Cycle Analysis - Nuclear Engineering Division  

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

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

50

Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel  

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

Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10 Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10 Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is intended as an information source for the NRC and should serve as a foundation for discussion with industry representatives on the issue. This paper concludes that an ISA is a risk-informed, performance-based way of achieving and maintaining safety at fuel recycling facilities. As

51

Data Analysis of Early Fuel Cell Market Demonstrations (Presentation)  

SciTech Connect

Presentation about early fuel cell markets, the National Renewable Energy Laboratory's Hydrogen Secure Data Center and its role in data analysis and demonstrations, and composite data products, and results reported to multiple stakeholders.

Kurtz, J.; Ramsden, T.; Wipke, K.; Sprik, S.

2009-11-17T23:59:59.000Z

52

Data Analysis of Early Fuel Cell Market Demonstrations (Presentation)  

DOE Green Energy (OSTI)

Presentation about early fuel cell markets, the National Renewable Energy Laboratory's Hydrogen Secure Data Center and its role in data analysis and demonstrations, and composite data products, and results reported to multiple stakeholders.

Kurtz, J.; Ramsden, T.; Wipke, K.; Sprik, S.

2009-11-17T23:59:59.000Z

53

Disposal criticality analysis for aluminum-based DOE fuels  

SciTech Connect

This paper describes the disposal criticality analysis for canisters containing aluminum-based Department of Energy fuels from research reactors. Different canisters were designed for disposal of highly enriched uranium (HEU) and medium enriched uranium (MEU) fuel. In addition to the standard criticality concerns in storage and transportation, such as flooding, the disposal criticality analysis must consider the degradation of the fuel and components within the waste package. Massachusetts Institute of Technology (MIT) U-Al fuel with 93.5% enriched uranium and Oak Ridge Research Reactor (ORR) U-Si-Al fuel with 21% enriched uranium are representative of the HEU and MEU fuel inventories, respectively. Conceptual canister designs with 64 MIT assemblies (16/layer, 4 layers) or 40 ORR assemblies (10/layer, 4 layers) were developed for these fuel types. Borated stainless steel plates were incorporated into a stainless steel internal basket structure within a 439 mm OD, 15 mm thick XM-19 canister shell. The Codisposal waste package contains 5 HLW canisters (represented by 5 Defense Waste Processing Facility canisters from the Savannah River Site) with the fuel canister placed in the center. It is concluded that without the presence of a fairly insoluble neutron absorber, the long-term action of infiltrating water can lead to a small, but significant, probability of criticality for both the HEU and MEU fuels. The use of 1.5kg of Gd distributed throughout the MIT fuel and the use of carbon steels for the structural basket or 1.1 kg of Gd distributed in the ORR fuel will reduce the probability of criticality to virtually zero for both fuels.

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

1997-11-01T23:59:59.000Z

54

DOE Hydrogen Analysis Repository: CO2 Reduction Benefits Analysis for Fuel  

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

CO2 Reduction Benefits Analysis for Fuel Cell Applications CO2 Reduction Benefits Analysis for Fuel Cell Applications Project Summary Full Title: CO2 Reduction Benefits Analysis for Fuel Cell Applications Project ID: 263 Principal Investigator: Chip Friley Brief Description: This analysis used the 10-region U.S. MARKAL model to quantify the impact of changes in production, distribution and vehicle costs and carbon prices on fuel cell vehicle penetration and overall carbon dioxide emissions. Keywords: Carbon dioxide (CO2); Hydrogen; Fuel cells Purpose Perform analysis of topics of interest to the DOE Fuel Cell Technologies program related to projected carbon dioxide reduction benefits of fuel cell applications. Performer Principal Investigator: Chip Friley Organization: Brookhaven National Laboratory (BNL) Address: Mail Stop 475C

55

Fuel Cell Technology Status Analysis Project: Partnership Opportunities (Fact Sheet)  

SciTech Connect

This fact sheet describes National Renewable Energy Laboratory's (NREL's) Fuel Cell Technology Status Analysis Project. NREL is seeking fuel cell industry partners from the United States and abroad to participate in an objective and credible analysis of commercially available fuel cell products to benchmark the current state of the technology and support industry growth. Participating fuel cell developers share price information about their fuel cell products and/or raw fuel cell test data related to operations, maintenance, and safety with NREL via the Hydrogen Secure Data Center (HSDC). The limited-access, off-network HSDC houses the data and analysis tools to protect proprietary information. NREL shares individualized data analysis results as detailed data products (DDPs) with the partners who supplied the data. Aggregated results are published as composite data products (CDPs), which show the technology status without identifying individual companies. The CDPs are a primary benchmarking tool for the U.S. Department of Energy and other stakeholders interested in tracking the status of fuel cell technologies. They highlight durability advancements, identify areas for continued development, and help set realistic price expectations at small-volume production.

2013-06-01T23:59:59.000Z

56

Fuel Cell Technology Status Analysis Project: Partnership Opportunities (Fact Sheet)  

DOE Green Energy (OSTI)

This fact sheet describes National Renewable Energy Laboratory's (NREL's) Fuel Cell Technology Status Analysis Project. NREL is seeking fuel cell industry partners from the United States and abroad to participate in an objective and credible analysis of commercially available fuel cell products to benchmark the current state of the technology and support industry growth. Participating fuel cell developers share price information about their fuel cell products and/or raw fuel cell test data related to operations, maintenance, and safety with NREL via the Hydrogen Secure Data Center (HSDC). The limited-access, off-network HSDC houses the data and analysis tools to protect proprietary information. NREL shares individualized data analysis results as detailed data products (DDPs) with the partners who supplied the data. Aggregated results are published as composite data products (CDPs), which show the technology status without identifying individual companies. The CDPs are a primary benchmarking tool for the U.S. Department of Energy and other stakeholders interested in tracking the status of fuel cell technologies. They highlight durability advancements, identify areas for continued development, and help set realistic price expectations at small-volume production.

Not Available

2013-06-01T23:59:59.000Z

57

Spent Nuclear Fuel Alternative Technology Decision Analysis  

SciTech Connect

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

Shedrow, C.B.

1999-11-29T23:59:59.000Z

58

Energy Storage Fuel Cell Vehicle Analysis: Preprint  

DOE Green Energy (OSTI)

In recent years, hydrogen fuel cell (FC) vehicle technology has received considerable attention as a strategy to decrease oil consumption and reduce harmful emissions. However, the cost, transient response, and cold performance of FC systems may present significant challenges to widespread adoption of the technology for transportation in the next 15 years. The objectives of this effort were to perform energy storage modeling with fuel cell vehicle simulations to quantify the benefits of hybridization and to identify a process for setting the requirements of ES for hydrogen-powered FC vehicles for U.S. Department of Energy's Energy Storage Program.

Markel, T.; Pesaran, A.; Zolot, M.; Sprik, S.; Tataria, H.; Duong, T.

2005-04-01T23:59:59.000Z

59

Energy Storage Fuel Cell Vehicle Analysis  

DOE Green Energy (OSTI)

In recent years, hydrogen fuel cell (FC) vehicle technology has received considerable attention as a strategy to decrease oil consumption and reduce harmful emissions. However, the cost, transient response, and cold performance of FC systems may present significant challenges to widespread adoption of the technology for transportation in the next 15 years. The objectives of this effort were to perform energy storage modeling with fuel cell vehicle simulations to quantify the benefits of hybridization and to identify a process for setting the requirements of ES for hydrogen-powered FC vehicles for U.S. Department of Energy?s Energy Storage Program.

Pesaran, A.; Markel, T.; Zolot, M.; Sprik, S.; Tataria, H.; Duong, T.

2005-08-01T23:59:59.000Z

60

Analysis of vehicle fuel release resulting in waste tank fire  

Science Conference Proceedings (OSTI)

This document reevaluates several aspects of the in-tank vehicle fuel fire/deflagration accident formally documented as an independent accident (representative accident [rep acc] 2). This reevaluation includes frequencies for the accidents and incorporates the behavior of gasoline and diesel fuel in more detail than previous analysis. This reevaluation uses data from RPP-13121, ''Historical Summary of Occurrences from the Tank Farm Safety Analysis Report'', Table B-1, ''Tank Farm Events, Off-Normal and Critiques,'' and B-2, ''Summary of Occurrences,'' and from the River Protection Project--Occurrence Reporting & Processing System (ORPS) reports as a basis for changing some of the conclusions formally reported in HNF-SD-WM-CN-037, ''Frequency Analysis of Vehicle Fuel Releases Resulting in Waste Tank Fire''. This calculation note will demonstrate that the in-tank vehicle fuel fire/deflagration accident event may be relocated to other, more bounding accidents.

STEPHENS, L.S.

2003-03-21T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Safety analysis of IFR fuel processing in the Argonne National Laboratory Fuel Cycle Facility  

SciTech Connect

The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL`s Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed.

Charak, I; Pedersen, D.R. [Argonne National Lab., IL (United States); Forrester, R.J.; Phipps, R.D. [Argonne National Lab., Idaho Falls, ID (United States)

1993-09-01T23:59:59.000Z

62

Automotive and MHE Fuel Cell System Cost Analysis  

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

Vince Contini, Kathya Mahadevan, Fritz Eubanks, Vince Contini, Kathya Mahadevan, Fritz Eubanks, Jennifer Smith, Gabe Stout and Mike Jansen Battelle April 16, 2013 Manufacturing Cost Analysis of Fuel Cells for Material Handling Applications 2 Presentation Outline * Background * Approach * System Design * Fuel Cell Stack Design * Stack, BOP and System Cost Models * System Cost Summary * Results Summary 3 * 10 and 25 kW PEM Fuel Cells for Material Handling Equipment (MHE) applications Background 5-year program to provide feedback to DOE on evaluating fuel cell systems for stationary and emerging markets by developing independent models and cost estimates * Applications - Primary (including CHP) power, backup power, APU, and material handling * Fuel Cell Types - 80°C PEM, 180°C PEM, SOFC technologies

63

DOE Hydrogen Analysis Repository: Evaluation of Energy Recovery Act Fuel  

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

Evaluation of Energy Recovery Act Fuel Cell Initiative Evaluation of Energy Recovery Act Fuel Cell Initiative Project Summary Full Title: Evaluation of U.S. DOE Energy Recovery Act Fuel Cell (Technologies Program) Initiative (ARRA-FCI) Project ID: 284 Principal Investigator: Brian James Brief Description: An evaluation was conducted to assess the early stage "market change" impacts of the Fuel Cell (Technologies Program) Initiative of the American Recovery and Reinvestment Act (ARRA-FCI) to accelerate fuel cell deployment and commercialization. Performer Principal Investigator: Brian James Organization: Strategic Analysis, Inc. Address: 4075 Wilson Blvd. Suite 200 Arlington, VA 22203 Telephone: 703-778-7114 Email: bjames@sainc.com Sponsor(s) Name: Fred Joseck Organization: DOE/EERE/FCTO Telephone: 202-586-7932

64

Analysis of Fuel Cell Vehicles Hybridization and Implications for Energy Storage Devices (Presentation)  

DOE Green Energy (OSTI)

Presents an analysis of hybridization and implications energy storage devices concerning fuel cell vehicles.

Zolot, M.; Markel, T.; Pesaran, A.

2004-06-01T23:59:59.000Z

65

Fuel Cell Power Model for CHP and CHHP Economics and Performance Analysis (Presentation)  

DOE Green Energy (OSTI)

This presentation describes the fuel cell power model for CHP and CHHP economics and performance analysis.

Steward, D.; Penev, M.

2010-03-30T23:59:59.000Z

66

ANALYSIS AND EXAMINATION OF MOX FUEL FROM NONPROLIFERATION PROGRAMS  

SciTech Connect

The U.S. Department of Energy has decided to dispose of a portion of the nation s surplus plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. Four lead assemblies were manufactured and irradiated to a maximum fuel rod burnup of 47.3 MWd/kg heavy metal. This was the first commercial irradiation of MOX fuel with a 240Pu/239Pu ratio of less than 0.10. Five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. The performance of the rods was analyzed with AREVA s next-generation GALILEO code. The results of the analysis confirmed that the fuel rods had performed safely and predictably, and that GALILEO is applicable to MOX fuel with a low 240Pu/239Pu ratio as well as to standard MOX. The results are presented and compared to the GALILEO database. In addition, the fuel cladding was tested to confirm that traces of gallium in the fuel pellets had not affected the mechanical properties of the cladding. The irradiated cladding was found to remain ductile at both room temperature and 350 C for both the axial and circumferential directions.

McCoy, Kevin [Areva NP; Machut, Dr McLean [Areva NP; Morris, Robert Noel [ORNL; Blanpain, Patrick [AREVA NP SAS; Hemrick, James Gordon [ORNL

2013-01-01T23:59:59.000Z

67

Spent fuel pool analysis using TRACE code  

SciTech Connect

The storage requirements of Spent Fuel Pools have been analyzed with the purpose to increase their rack capacities. In the past, the thermal limits have been mainly evaluated with conservative codes developed for this purpose, although some works can be found in which a best estimate code is used. The use of best estimate codes is interesting as they provide more realistic calculations and they have the capability of analyzing a wide range of transients that could affect the Spent Fuel Pool. Two of the most representative thermal-hydraulic codes are RELAP-5 and TRAC. Nowadays, TRACE code is being developed to make use of the more favorable characteristics of RELAP-5 and TRAC codes. Among the components coded in TRACE that can be used to construct the model, it is interesting to use the VESSEL component, which has the capacity of reproducing three dimensional phenomena. In this work, a thermal-hydraulic model of the Maine Yankee spent fuel pool using the TRACE code is developed. Such model has been used to perform a licensing calculation and the results obtained have been compared with experimental measurements made at the pool, showing a good agreement between the calculations predicted by TRACE and the experimental data. (authors)

Sanchez-Saez, F.; Carlos, S.; Villanueva, J. F.; Martorell, S. [Dept. of Chemical and Nuclear Engineering, Universitat Politenica de Valencia, Cami de Vera s/n, 46021, Valencia (Spain)

2012-07-01T23:59:59.000Z

68

SNF fuel retrieval sub project safety analysis document  

SciTech Connect

This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

BERGMANN, D.W.

1999-02-24T23:59:59.000Z

69

Analysis of vehicle fuel release resulting in waste tank fire  

SciTech Connect

The purpose of the calculation documented here is to support in-tank vehicle fuel fire accident frequencies in the Documented Safety Analysis. This analysis demonstrates that the frequency of the pool fire and deflagration scenarios of the in-tank vehicle fuel fire/deflagration accident are ''extremely unlikely'' to ''unlikely.'' The chains of events that result in each scenario are presented in this document and are the same as used in previous analyses of this accident. Probabilities and frequencies are developed for each event, using wherever possible, information from RPP-13121, Tables B-1 and B-2, and from the River Protection Project ORPS. The estimated probabilities are considered reasonably conservative, but do not necessarily assume the worst possible outcomes or the most conservative possible cases. A sensitivity analysis performed in Section 4.2 shows that if the probability of either the ignition of fuel event or the fuel flows into riser event were underestimated by an order of magnitude, the accident frequency for a pool fire could increase and shift into the ''unlikely'' category. If the probability of an increase in riser strikes, or an increase in broken risers, unignited fuel entering a riser, or a fuel ignition source being present in a tank were underestimated by an order of magnitude, the accident frequency for a deflagration would remain in the ''unlikely'' category. When the likelihood of a broken riser is increased by an order of magnitude, a pool fire remains in the ''extremely unlikely'' category. The DSA accident analysis indicates that an unmitigated flammable gas deflagration resulting from an induced gas release event or an organic solvent fire occurring in either an SST or a DST is an anticipated event (> 10{sup -2}). Deflagration in a DST annulus is considered unlikely (> 10{sup -4} to {le}10{sup -2}). These frequencies clearly bound those of the in-tank vehicle fuel fire family of accidents.

HARRIS, J.P.

2003-10-14T23:59:59.000Z

70

Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis  

Science Conference Proceedings (OSTI)

The severe accident at Fukushima Daiichi nuclear plants illustrates the need for continuous improvements through developing and implementing technologies that contribute to safe, reliable and cost-effective operation of the nuclear fleet. Development of enhanced accident tolerant fuel contributes to this effort. These fuels, in comparison with the standard zircaloy UO2 system currently used by the LWR industry, should be designed such that they tolerate loss of active cooling in the core for a longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, and design-basis events. This report presents a preliminary systems analysis related to most of these concepts. The potential impacts of these innovative LWR fuels on the front-end of the fuel cycle, on the reactor operation and on the back-end of the fuel cycle are succinctly described without having the pretension of being exhaustive. Since the design of these various concepts is still a work in progress, this analysis can only be preliminary and could be updated as the designs converge on their respective final version.

Gilles Youinou; R. Sonat Sen

2013-09-01T23:59:59.000Z

71

DOE Hydrogen Analysis Repository: Stranded Biogas Decision Tool for Fuel  

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

Stranded Biogas Decision Tool for Fuel Cell Co-Production Stranded Biogas Decision Tool for Fuel Cell Co-Production Project Summary Full Title: Stranded Biogas Decision Tool for Fuel Cell Co-Production Project ID: 257 Principal Investigator: Michael Ulsh Brief Description: This project will explore the feasibility and utility of using stranded biogas resources in fuel cell co-production networks as well as lay the basis for development of analysis and decision-making tools for potential biogas sources and energy end-users to evaluate the economic feasibility of deploying these systems. Performer Principal Investigator: Michael Ulsh Organization: National Renewable Energy Laboratory (NREL) Address: 1617 Cole Blvd. Golden, CO 80401 Telephone: 303-275-3842 Email: michael.ulsh@nrel.gov Website: http://www.nrel.gov

72

NREL: ReFUEL Laboratory - Emissions Analysis  

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

Emissions Analysis Photo of researcher weighing a clean particulate filter. Emissions that result in pollution from engines are strictly regulated. The next generation of...

73

Thermal analysis of the FSP-1 fuel pin irradiation test  

SciTech Connect

Thermal analysis of a pin from the FSP-1 fuels irradiation test has been completed. The purpose of the analysis was to provide predictions of fuel pin temperatures, determine the flow regime within the lithium annulus of the test assembly, and provide a standardized model for a consistent basis of comparison between pins within the test assembly. The calculations have predicted that the pin is operating at slightly above the test design temperatures and that the flow regime within the lithium annulus is a laminar buoyancy driven flow. 7 refs., 5 figs.

Lyon, W.F. III.

1990-07-25T23:59:59.000Z

74

22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005  

E-Print Network (OSTI)

This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, ...

Kazimi, Mujid S.

75

Molten Carbonate and Phosphoric Acid Stationary Fuel Cells: Overview and Gap Analysis  

DOE Green Energy (OSTI)

This report describes the technical and cost gap analysis performed to identify pathways for reducing the costs of molten carbonate fuel cell (MCFC) and phosphoric acid fuel cell (PAFC) stationary fuel cell power plants.

Remick, R.; Wheeler, D.

2010-09-01T23:59:59.000Z

76

CASMO-2 spent-fuel-rack criticality analysis  

SciTech Connect

In recent years, utilities have needed to increase their spent-fuel storage capacity. Both Maine Yankee pressurized water reactor (PWR) and Vermont Yankee boiling water reactor (BWR) have increased their spent-fuel rack capacity by decreasing the canister center-to-center spacing while adding fixed poison. Licensing criticality analysis of such changes in spent-fuel rack design have been performed at Yankee Atomic Electric Co. (YAEC) using NITAWL-KENO-IV and the 123-group XSDRN library. However, KENO/Monte Carlo analysis has inherent drawbacks when applied to spent-fuel rack design and modification. These include statistical uncertainty and long computer time. In contrast, the transport theory code, CASMO-2, provides deterministic and fast criticality analysis. Also, since collapsed and transport-corrected cross sections are generated, PDQ can be used to analyze large array problems which are prohibitively expensive using KENO. In this work, the authors apply the CASMO-PDQ methodology to the Maine Yankee and Vermont Yankee high-density spent-fuel rack designs, and compare the final results against KENO.

Napolitano, D.G.; Heinrichs, D.P.; Gorski, J.P.

1986-01-01T23:59:59.000Z

77

The scale analysis sequence for LWR fuel depletion  

Science Conference Proceedings (OSTI)

The SCALE (Standardized Computer Analyses for Licensing Evaluation) code system is used extensively to perform away-from-reactor safety analysis (particularly criticality safety, shielding, heat transfer analyses) for spent light water reactor (LWR) fuel. Spent fuel characteristics such as radiation sources, heat generation sources, and isotopic concentrations can be computed within SCALE using the SAS2 control module. A significantly enhanced version of the SAS2 control module, which is denoted as SAS2H, has been made available with the release of SCALE-4. For each time-dependent fuel composition, SAS2H performs one-dimensional (1-D) neutron transport analyses (via XSDRNPM-S) of the reactor fuel assembly using a two-part procedure with two separate unit-cell-lattice models. The cross sections derived from a transport analysis at each time step are used in a point-depletion computation (via ORIGEN-S) that produces the burnup-dependent fuel composition to be used in the next spectral calculation. A final ORIGEN-S case is used to perform the complete depletion/decay analysis using the burnup-dependent cross sections. The techniques used by SAS2H and two recent applications of the code are reviewed in this paper. 17 refs., 5 figs., 5 tabs.

Hermann, O.W.; Parks, C.V.

1991-01-01T23:59:59.000Z

78

Software: Reactor Physics and Fuel Cycle Analysis - Nuclear Engineering  

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

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

79

Statistical analysis of correlated fossil fuel securities  

E-Print Network (OSTI)

Forecasting the future prices or returns of a security is extraordinarily difficult if not impossible. However, statistical analysis of a basket of highly correlated securities offering a cross-sectional representation of ...

Li, Derek Z

2011-01-01T23:59:59.000Z

80

Nuclear fuel cycle facility accident analysis handbook  

Science Conference Proceedings (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

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Carbon Capture by Fossil Fuel Power Plants: An Economic Analysis  

Science Conference Proceedings (OSTI)

For fossil fuel power plants to be built in the future, carbon capture and storage (CCS) technologies offer the potential for significant reductions in carbon dioxide (CO2) emissions. We examine the break-even value for CCS adoptions, that ... Keywords: accounting, cost--benefit analysis, energy, energy policies, environment, government, natural resources, pollution

zge ??legen; Stefan Reichelstein

2011-01-01T23:59:59.000Z

82

Palmetto Fuel Cell Analysis and Design | Open Energy Information  

Open Energy Info (EERE)

Analysis and Design Analysis and Design Jump to: navigation, search Name Palmetto Fuel Cell Analysis and Design Place Columbia, South Carolina Product Analysis and design spinout of the University of South Carolina, sister to Palmetto Fuel Cell Technologies. Coordinates 37.752467°, -78.161514° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":37.752467,"lon":-78.161514,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

83

Analysis of alternative-fuel price trajectories  

Science Conference Proceedings (OSTI)

Findings are presented from a study to (1) acquire, analyze, and report alternative published price projections including both oil- and coal-price trajectories, and to (2) apply the fixed-annuity formula to the updated primary source projections (Energy Information Administration; Data Resources, Inc.; and Wharton Econometric Forecasting Associates, Inc.) and to the newly acquired price projections. This report also encompasses: comparisons of key assumptions underlying the price projections, and a discussion of the applicability of the fixed-annuity formula as used in the alternative-cost calculation. Section II contains graphic presentations of all updated and newly acquired coal and oil price forecasts and the corresponding calculated annuity equivalents, tabulated presentations and discussions of each forecast and underlying assumptions, and a description of how each forecast price series was transformed into input for the present-value formulas. Section III presents the fixed-annuity formula employed and discusses its appropriateness for this application. Section IV discusses the applicability of the net present value approach for comparing alternate-fuel price trajectories. Appendix A contains a listing of contacts as potential sources of price forecasts. Appendix B contains the raw forecast data from each forecast source and the coal and oil price series derived from the raw data which were actually input into the cost calculation procedure. Appendix C contains a description and listing of the computer program developed to implement the cost calculation procedure. Finally, Appendix D contains tabulations and discussions of other alternative world crude price forecasts that were identified, but for which no corresponding coal-price projections were available. (MCW)

Not Available

1980-12-31T23:59:59.000Z

84

NREL: Energy Analysis - Vehicles and Fuels Research Analysis  

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

303-275-4451 Access more information on all of our Staff Analysts Printable Version Energy Analysis Home Capabilities & Expertise Technology Analysis Biomass Buildings...

85

Analysis of Natural Gas Fuel Cell Plant Configurations  

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

Analysis of Natur Analysis of Natur al Gas Fuel Cell Plant Configur ations March 24, 2011 DOE/NETL-2011/1486 Analysis of Natur al Gas Fuel Cell Plant Configur ations 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 any of their employees, makes any warranty, express 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. Reference therein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement,

86

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

Science Conference Proceedings (OSTI)

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

A. Alsaed

2005-07-28T23:59:59.000Z

87

Selection of Isotopes and Elements for Fuel Cycle Analysis  

Science Conference Proceedings (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

88

Modeling Tools for Solid Oxide Fuel Cell Analysis  

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

Tools for Solid Oxide Fuel Tools for Solid Oxide Fuel Cell Design and Analysis Moe A Khaleel BJ Koeppel, W Liu, K Lai, KP Recknagle, EM Ryan, EV Stephens, X Sun Pacific Northwest National Laboratory Richland, WA 99352 11 th Annual SECA Workshop Pittsburgh, PA July 27-29, 2009 1 PNNL SOFC Modeling Tools SOFC-MP Stack level model for fast analysis of co/counter-flow SOFC stack performance Detailed electrochemistry model Cell level model for the investigation of secondary reactions (degradation/contamination) mechanisms within the tri-layer Component-based design and performance modeling Contact material Interconnect Glass seal 2 SOFC-MP Stack Simulation Code Recent Accomplishments Major memory improvements of 3D model to accommodate 50-cell stacks on LINUX platform. Previously, developed a 2D (or stacked

89

Risk analysis of shipping plutonium pits and mixed oxide fuel  

E-Print Network (OSTI)

With the end of the cold war, there no longer seems to be a credible threat of war between nuclear superpowers, with its possible consequence of billions of fatalities. However, the residue of the cold war, most notably the now excess weapons plutonium, has been identified as the source of a number of potential catastrophes. For example, just a single crude nuclear weapon in the hands of a terrorist organization or rogue state and detonated in even a medium-sized city could lead to hundreds of thousands of deaths. For this reason, the ultimate disposition of this excess plutonium has been identified as a national priority. The process of carrying out this disposition itself carries some risks, and even though any conceivable consequences clearly will be much smaller in magnitude than those cited above, U.S. federal law (the National Environmental Protection Act) mandates that such risks must be analyzed. The ability to carry out one type of such an analysis is demonstrated in this thesis. Specifically, one possible option that has been identified for disposition of excess U.S. weapons plutonium is the transformation into mixed oxide (MOX) fuel, that then would be used as fuel in a commercial nuclear power plant. Any such process will involve the transportation of the MOX fuel from the MOX fuel fabrication facility to the nuclear power plant, and possibly transportation of the plutonium from a storage site to the fuel fabrication facility. This thesis is intended to demonstrate the capability to analyze the risks associated with such transportation campaigns. The primary tool used for these analyses was RADTRAN, a code developed by Sandia National Laboratories for evaluating risk associated with the transportation of radioactive materials. Two sample scenarios were explored relative to the transformation of plutonium pits to MOX fuel. First, the pits would be converted to MOX fuel at a fuel fabrication facility located either at the Pantex Plant or the Savannah River Site (SRS), and then the MOX fuel would be ultimately shipped to a final destination of a commercial power plant, the Palo Verde Generating Station in Arizona. For the scenario of placing the MOX fuel fabrication facility at SRS, pits would need to be shipped from Pantex to SRS and then the MOX fuel would be shipped to Palo Verde. The total number of expected fatalities over a 25 year campaign duration for this scenario would be 1.06, with 0. 1 73 fatalities resulting from latent cancer fatalities due to radiation exposure and 0.89 resulting from traffic accidents. For the placement of the MOX fuel fabrication facility at Pantex, only the MOX fuel would need to be transported from one facility to another, in this case from Pantex to Palo Verde. The total fatalities for this scenario over 25 years would be 0.413, resulting from 5.29 x 10-2 latent cancer fatalities and 0.36 traffic accident fatalities. The maximum exposed individual along any of the three routes would receive 1.0 X 10-5 rem per year or 0.25 mrem over 25 years.

Caldwell, Amy Baker

1997-01-01T23:59:59.000Z

90

Overview hazard analysis for the H2Fuel Bus Program  

DOE Green Energy (OSTI)

The H2Fuel Bus project is a joint development effort to produce a safe, near-zero emission, 32 passenger bus that is propelled by electric power with continuous on-board hydrogen powered battery recharging. A key initiative in the hydrogen bus development effort is a rigorous evaluation of operational safety. Westinghouse Savannah River Co., the prime contractor at the Department of Energy`s Savannah River Site, has developed a hazard analysis methodology designed to provide a systematic, comprehensive identification and evaluation of hazards. Although originally developed to support nuclear/chemical facility safety basis documentation, the SRS Methodology has widespread applicability to operations and/or systems that utilize hazardous materials and energy. This methodology was used to perform an overview hazard analysis for the H2Fuel Bus project to focus attention on those hypothetical circumstances that pose the greatest threat to the populace and property. The hazard analysis yields a listing of all known H2Fuel Bus hazards, postulated accident scenarios describing possible hazardous releases or conditions, an assessment of the scenarios in terms of frequency of occurrence and consequence, and binning in frequency-consequence space to assess the relative severity of postulated scenarios.

Hovis, G.L.

1996-06-18T23:59:59.000Z

91

DOE and FreedomCAR and Fuel Partnership Analysis Workshop  

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

Analysis Workshop Analysis Workshop U.S. Department of Energy - Washington, DC January 25, 2006 A AC CT TI IO ON N I IT TE EM MS S A AN ND D D DI IS SC CU US SS SI IO ON N C CO OM MM ME EN NT TS S Agenda 1. Agenda and Purpose - Mark Paster, DOE-HFCIT 2. On-Board Storage Systems Analysis - Rajesh Ahluwalia, ANL 3. On-Board Storage Cost and Efficiency Analysis - Steve Lasher, TIAX 4. Off-Board Storage and Tube Trailers - Salvador Aceves and Gene Berry, LLNL 5. Forecourt Storage and Compression Options - Mark Richards, GTI 6. H2A Delivery Models and Results: H2A Delivery Team - Marianne Mintz, ANL 7. Delivery Analysis Project, Options, and Trade-Offs - T. P. Chen, Nexant 8. Hydrogen Delivery Demonstrations - Ed Kiczek, Air Products & Chemicals, Inc. 9. Pathway Cost Distributions: Fuel Pathway Integration Tech Team - James Uihlein, BP

92

NMR apparatus for in situ analysis of fuel cells  

Science Conference Proceedings (OSTI)

The subject apparatus is a fuel cell toroid cavity detector for in situ analysis of samples through the use of nuclear magnetic resonance. The toroid cavity detector comprises a gas-tight housing forming a toroid cavity where the housing is exposed to an externally applied magnetic field B.sub.0 and contains fuel cell component samples to be analyzed. An NMR spectrometer is electrically coupled and applies a radiofrequency excitation signal pulse to the detector to produce a radiofrequency magnetic field B.sub.1 in the samples and in the toroid cavity. Embedded coils modulate the static external magnetic field to provide a means for spatial selection of the recorded NMR signals.

Gerald, II, Rex E; Rathke, Jerome W

2012-11-13T23:59:59.000Z

93

Hogged Wood Fuel Supply and Price Analysis : Final Report.  

SciTech Connect

This study discusses the factors that determine the supply and demand for hogged wood in the Pacific Northwest, with particular emphasis on the role of the regional pulp and paper industry and lumber industry. Because hogged wood is often a substitute for conventional fuels, the consumption and price of natural gas, electricity, fuel oil and coal are also addressed. A detailed and comprehensive examination of the indicies relating to the hogged wood market is provided, including analysis and graphing of all time series variables. A spreadsheet- based forecasting model is developed and presented with an emphasis on explaining the process used to arrive at the final model. 42 refs., 46 figs., 14 tabs. (MHB)

Biederman, Richard T.; Blazek, Christopher F.

1991-05-01T23:59:59.000Z

94

Prototype spent-fuel canister design, analysis, and test  

SciTech Connect

Sandia National Laboratories was asked by the US Energy Research and Development Administration (now US Department of Energy) to design the spent fuel shipping cask system for the Clinch River Breeder Reactor Plant (CRBRP). As a part of this task, a canister which holds liquid sodium and the spent fuel assembly was designed, analyzed, and tested. The canister body survived the regulatory Type-B 9.1-m (30-ft) drop test with no apparent leakage. However, the commercially available metal seal used in this design leaked after the tests. This report describes the design approach, analysis, and prototype canister testing. Recommended work for completing the design, when funding is available, is included.

Leisher, W.B.; Eakes, R.G.; Duffey, T.A.

1982-03-01T23:59:59.000Z

95

Fuzzy possibilistic modeling and sensitivity analysis for optimal fuel gas scheduling in refinery  

Science Conference Proceedings (OSTI)

In refinery, fuel gas which is continuously generated during the production process is one of the most important energy sources. Optimal scheduling of fuel gas system helps the refinery to achieve energy cost reduction and cleaner production. However, ... Keywords: Fuel gas, Fuzzy possibilistic programming, Marginal value analysis, Refinery, Scheduling, Sensitivity analysis

J. D. Zhang; G. Rong

2010-04-01T23:59:59.000Z

96

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

SciTech Connect

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

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

2012-06-06T23:59:59.000Z

97

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

NLE Websites -- All DOE Office Websites (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

98

PROTEUS - Simulation Toolset for Reactor Physics and Fuel Cycle Analysis  

NLE Websites -- All DOE Office Websites (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

99

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

SciTech Connect

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

Henrikson, D.J.

1999-09-01T23:59:59.000Z

100

Fuel Cell Technologies Office: Storage Systems Analysis Working...  

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

Energy Efficiency and Renewable Energy EERE Home | Programs & Offices | Consumer Information Fuel Cell Technologies Office Search Search Help Fuel Cell Technologies Office HOME...

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Fuel Cell Technologies Office: Hydrogen Systems Analysis Workshop...  

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

Energy Efficiency and Renewable Energy EERE Home | Programs & Offices | Consumer Information Fuel Cell Technologies Office Search Search Help Fuel Cell Technologies Office HOME...

102

Fuel Cell Technologies Office: DOE Hydrogen Transition Analysis...  

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

Energy Efficiency and Renewable Energy EERE Home | Programs & Offices | Consumer Information Fuel Cell Technologies Office Search Search Help Fuel Cell Technologies Office HOME...

103

DOE Hydrogen Analysis Repository: Future Fuel Cell and Internal...  

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

Future Fuel Cell and Internal Combustion Engine Automobile Technologies Project Summary Full Title: Future Fuel Cell and Internal Combustion Engine Automobile Technologies: A...

104

Renewable & Alternative Fuels - Analysis & Projections - U.S ...  

U.S. Energy Information Administration (EIA)

... (formerly shown in Table 5) was obtained from the Alternative Fuels Data Center (http://www.eere.energy.gov/afdc/fuels/stations_counts.html). ...

105

ANALYSIS OF POWER BALANCING WITH FUEL CELLS & HYDROGEN  

E-Print Network (OSTI)

.....................................................................................17 B.2 Costs of fuels, fuel handling, electricity and CO2 quotas.........................................................................................................35 D. ­ TANK-TO-ELECTRICITY AND TANK...........................................................................................................36 D.2 Reference Car

106

Fuel Cell Technologies Office: Hydrogen Production Analysis Using the H2A  

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

Production Production Analysis Using the H2A v3 Model (Text Version) to someone by E-mail Share Fuel Cell Technologies Office: Hydrogen Production Analysis Using the H2A v3 Model (Text Version) on Facebook Tweet about Fuel Cell Technologies Office: Hydrogen Production Analysis Using the H2A v3 Model (Text Version) on Twitter Bookmark Fuel Cell Technologies Office: Hydrogen Production Analysis Using the H2A v3 Model (Text Version) on Google Bookmark Fuel Cell Technologies Office: Hydrogen Production Analysis Using the H2A v3 Model (Text Version) on Delicious Rank Fuel Cell Technologies Office: Hydrogen Production Analysis Using the H2A v3 Model (Text Version) on Digg Find More places to share Fuel Cell Technologies Office: Hydrogen Production Analysis Using the H2A v3 Model (Text Version) on AddThis.com...

107

Analysis of fuel savings associated with fuel computers in multifamily buildings. Final report  

SciTech Connect

This research was undertaken to quantify the energy savings associated with the installation of a direct monitoring control system (DMC) on steam heating plants in multi-family buildings located in the New York City metropolitan area. The primary objective was to determine whether fuel consumption was lower in buildings employing a DMC relative to those using the more common indirect monitoring control system (IMC) and if so, to what extent. The analysis compares the fuel consumption of 442 buildings over 12 months. The type of control system installed in these buildings was either a Heat-Timer (identified as IMC equipment) or a computer-based unit (identified as DMC equipment). IMC provides control by running the boiler for longer or shorter periods depending on outdoor temperature. This system is termed indirect because there is no feedback from indoor (apartment) temperatures to the control. DMC provides control by sensing apartment temperatures. In a typical multifamily building, sensors are hard wired to between 5 and 10 apartments sensors. The annual savings and simple payback were computed for the DMC buildings by comparing annual fuel consumption among the building groupings. The comparison is based on mean BTUs per degree day consumed annually and normalized for building characteristics, such as, equipment maintenance and boiler steady state efficiency as well as weather conditions. The average annual energy consumption for the DMC buildings was 14.1 percent less than the annual energy consumption for the IMC buildings. This represents 3,826 gallons of No. 6 fuel oil or $2,295 at a price of $0.60 per gallon. A base DMC system costs from $8,400 to $10,000 installed depending on the number of sensors and complexity of the system. The standard IMC system costs from $2,000 to $3,000 installed. Based on this analysis the average simple payback is 2.9 or 4.0 years depending on either an upgrade from IMC to DMC (4.0 years) or a new installation (2.9) years.

McNamara, M.; Anderson, J.; Huggins, E. [EME Group, New York, NY (US)

1993-06-01T23:59:59.000Z

108

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

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

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

109

A dynamic fuel cycle analysis for a heterogeneous thorium-DUPIC recycle in CANDU reactors  

SciTech Connect

A heterogeneous thorium fuel recycle scenario in a Canada deuterium uranium (CANDU) reactor has been analyzed by the dynamic analysis method. The thorium recycling is performed through a dry process which has a strong proliferation resistance. In the fuel cycle model, the existing nuclear power plant construction plan was considered up to 2016, while the nuclear demand growth rate from the year 2016 was assumed to be 0%. In this analysis, the spent fuel inventory as well as the amount of plutonium, minor actinides, and fission products of a multiple thorium recycling fuel cycle were estimated and compared to those of the once-through fuel cycle. The analysis results have shown that the heterogeneous thorium fuel cycle can be constructed through the dry process technology. It is also shown that the heterogeneous thorium fuel cycle can reduce the spent fuel inventory and save on the natural uranium resources when compared with the once-through cycle. (authors)

Jeong, C. J.; Park, C. J.; Choi, H. [Korea Atomic Energy Research Inst., P.O. Box 150, Yuseong, Daejeon, 305-600 (Korea, Republic of)

2006-07-01T23:59:59.000Z

110

Failed Fuel Analysis on Fuel Rods from Exelon BWRs: Volume 2: Hot Cell Investigation Of LaSalle Fuel Rods  

Science Conference Proceedings (OSTI)

A number of fuel failures were experienced in ATRIUM-9B fuel manufactured by Framatome ANP (FANP) and operated at Exelon plants between late 2000 and 2003. The failures tended to correlate with power changes (control blade movement), but a large number of poolside inspections, documented in Volume 1 of this investigation (Failed Fuel Analyses on Fuel Rods from Exelon BWRs, Volume 1: Poolside Inspection, EPRI report 1009494), were unable to determine the precise cause of failure. This Volume 2 report desc...

2005-06-06T23:59:59.000Z

111

GCtool for fuel cell systems design and analysis : user documentation.  

DOE Green Energy (OSTI)

GCtool is a comprehensive system design and analysis tool for fuel cell and other power systems. A user can analyze any configuration of component modules and flows under steady-state or dynamic conditions. Component models can be arbitrarily complex in modeling sophistication and new models can be added easily by the user. GCtool also treats arbitrary system constraints over part or all of the system, including the specification of nonlinear objective functions to be minimized subject to nonlinear, equality or inequality constraints. This document describes the essential features of the interpreted language and the window-based GCtool environment. The system components incorporated into GCtool include a gas flow mixer, splitier, heater, compressor, gas turbine, heat exchanger, pump, pipe, diffuser, nozzle, steam drum, feed water heater, combustor, chemical reactor, condenser, fuel cells (proton exchange membrane, solid oxide, phosphoric acid, and molten carbonate), shaft, generator, motor, and methanol steam reformer. Several examples of system analysis at various levels of complexity are presented. Also given are instructions for generating two- and three-dimensional plots of data and the details of interfacing new models to GCtool.

Ahluwalia, R.K.; Geyer, H.K.

1999-01-15T23:59:59.000Z

112

US Navy mobility fuels: Worldwide survey and analysis of both commercial and Navy fuels. Final report  

SciTech Connect

Quality and worldwide availability of distillate fuels have become increasing concerns to the U.S. Department of Defense. In response to these concerns, the David Taylor Research Center (DTRC) has conducted a worldwide survey of such fuels through a contract with the National Institute for Petroleum and Energy Research (NIPER). Representative fuels were collected at both Navy and commercial ports around the world through a NIPER subcontract to ABS Worldwide Technical Services (ABSTECH). The collected fuels were Naval Distillate Fuel (MIL-F-16884H, NATO F-76), Marine Gas Oil (MGO), Heavy Marine Gas Oil (HMGO), and Marine Diesel Fuel (MDF) for the Navy; Automotive/Truck Diesel for the Army; and Aviation Turbine Fuel (MIL-T-5624L, NATO JP-5) for the Naval Air Propulsion Center. The Navy F-76 fuel samples were characterized at NIPER by 44 different fuel property analyses.

Woodward, P.W.; Shay, J.Y.

1989-07-01T23:59:59.000Z

113

A Near-Term Economic Analysis of Hydrogen Fueling Stations  

E-Print Network (OSTI)

Fuel Cells for Generation and Cogeneration Center for Energy and Environmental Studies Princeton University Princeton, NJ

Weinert, Jonathan X.

2005-01-01T23:59:59.000Z

114

A Near-term Economic Analysis of Hydrogen Fueling Stations  

E-Print Network (OSTI)

Fuel Cells for Generation and Cogeneration Center for Energy and Environmental Studies Princeton University Princeton, NJ

Weinert, Jonathan X.

2005-01-01T23:59:59.000Z

115

DOE Hydrogen and Fuel Cells Program: DOE H2A Analysis  

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

Hydrogen Production Hydrogen Production Hydrogen Delivery Hydrogen Storage Hydrogen Manufacturing Fuel Cells Applications/Technology Validation Safety Codes and Standards Education Basic Research Systems Analysis Analysis Repository H2A Analysis Production Delivery Fuel Cell Power Comments Hydrogen Analysis Resource Center Scenario Analysis Well-to-Wheels Analysis Systems Integration U.S. Department of Energy Search help Home > Systems Analysis > DOE H2A Analysis Printable Version DOE H2A Analysis The Hydrogen Analysis (H2A) Project H2A Basic Model Architecture H2A Standard Economic Assumptions H2A Production Analysis H2A Delivery Analysis Fuel Cell Power Analysis The Hydrogen Analysis (H2A) Project Research and programmatic decisions should be informed by sound analysis - not only a comparative analysis of costs, but also of the energy and

116

Design optimization and analysis of coated particle fuel using advanced fuel performance modeling techniques  

E-Print Network (OSTI)

Modifying material properties provides another approach to optimize coated particle fuel used in pebble bed reactors. In this study, the MIT fuel performance model (TIMCOAT) was applied after benchmarking against the ...

Soontrapa, Chaiyod

2005-01-01T23:59:59.000Z

117

Analysis of the Impact of Fuel Cell Vehicles on Energy Systems...  

Open Energy Info (EERE)

AgencyCompany Organization Tohoku University Focus Area Fuels & Efficiency, Hydrogen Topics Analysis Tools, Policy Impacts, Policy Impacts Website http:www.iaee.org...

118

Analysis of the Impact of Fuel Cell Vehicles on Energy Systems in the  

Open Energy Info (EERE)

Analysis of the Impact of Fuel Cell Vehicles on Energy Systems in the Analysis of the Impact of Fuel Cell Vehicles on Energy Systems in the Transportation Sector in Japan Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Analysis of the Impact of Fuel Cell Vehicles on Energy Systems in the Transportation Sector in Japan Agency/Company /Organization: Tohoku University Focus Area: Fuels & Efficiency, Hydrogen Topics: Analysis Tools, Policy Impacts, Policy Impacts Website: www.iaee.org/documents/Aberdeen/a02nakata.pdf Equivalent URI: cleanenergysolutions.org/content/analysis-impact-fuel-cell-vehicles-en Language: English Policies: Financial Incentives This report examines the recent advances in fuel cell vehicles. The report then evaluates the impact of such vehicles on energy systems in the transportation sector in Japan and effectiveness of government subsidies in

119

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

120

Generic Repository Concepts and Thermal Analysis for Advanced Fuel Cycles  

SciTech Connect

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

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Fuel Cell Technologies Office: Storage Systems Analysis Working Group  

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

Storage Systems Analysis Working Group Storage Systems Analysis Working Group The Storage Systems Analysis Working Group, launched in March 2005, provides a forum to facilitate research and communication of hydrogen storage-related analysis activities among researchers actively engaged in hydrogen storage systems analyses. The working group includes members from DOE, the national laboratories, industry, and academia. Description Technical Targets Meetings Contacts Description Hydrogen storage is a key enabling technology for the advancement of hydrogen and fuel cell power technologies in transportation, stationary, and portable power applications. One of the most challenging technical barriers known is how to efficiently store hydrogen on-board a vehicle to meet customer expectations of a driving range greater than 300 miles-as well as performance, safety, and cost-without impacting passenger or cargo space. The Department of Energy's hydrogen storage activity is coordinated through the "National Hydrogen Storage Project," with multiple university, industry, and federal laboratory partners focused on research and development of on-board vehicular hydrogen storage technologies. This research also has components applicable to off-board storage of hydrogen for refueling infrastructure and the off-board regeneration of chemical hydrogen carriers applicable to hydrogen delivery.

122

Analysis of Fuel Ethanol Transportation Activity and Potential Distribution Constraints  

SciTech Connect

This paper provides an analysis of fuel ethanol transportation activity and potential distribution constraints if the total 36 billion gallons of renewable fuel use by 2022 is mandated by EPA under the Energy Independence and Security Act (EISA) of 2007. Ethanol transport by domestic truck, marine, and rail distribution systems from ethanol refineries to blending terminals is estimated using Oak Ridge National Laboratory s (ORNL s) North American Infrastructure Network Model. Most supply and demand data provided by EPA were geo-coded and using available commercial sources the transportation infrastructure network was updated. The percentage increases in ton-mile movements by rail, waterways, and highways in 2022 are estimated to be 2.8%, 0.6%, and 0.13%, respectively, compared to the corresponding 2005 total domestic flows by various modes. Overall, a significantly higher level of future ethanol demand would have minimal impacts on transportation infrastructure. However, there will be spatial impacts and a significant level of investment required because of a considerable increase in rail traffic from refineries to ethanol distribution terminals.

Das, Sujit [ORNL; Peterson, Bruce E [ORNL; Chin, Shih-Miao [ORNL

2010-01-01T23:59:59.000Z

123

Dynamic Systems Analysis Report for Nuclear Fuel Recycle  

SciTech Connect

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

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

2008-12-01T23:59:59.000Z

124

Fort Saint Vrain HTGR (Th/U carbide) Fuel Characteristics for Disposal Criticality Analysis  

SciTech Connect

DOE-owned spent nuclear fuels encompass many fuel types. In an effort to facilitate criticality analysis for these various fuel types, they were categorized into eight characteristic fuel groups with emphasis on fuel matrix composition. Out of each fuel group, a representative fuel type was chosen for analysis as a bounding case within that fuel group. Generally, burnup data, fissile enrichments and total fuel mass govern the selection of the representative or candidate fuel within that group. For the HTGR group, the Fort Saint Vrain (FSV) reactor fuel has been chosen for the evaluation of viability for waste co-disposal. The FSV reactor was operated by Public Service of Colorado as a licensed power reactor. The FSV fuel employs a U/Th carbide matrix in individually pyrolytic carbon-coated particles. These individual particles are in turn coated with silicon carbide (SiC) and contained within fuel compacts, that are in turn embedded in graphite blocks that comprised the structural core of the reactor.

Taylor, Larry Lorin

2001-01-01T23:59:59.000Z

125

Shippingport LWBR (Th/U Oxide) Fuel Characteristics for Disposal Criticality Analysis  

Science Conference Proceedings (OSTI)

Department of Energy (DOE)-owned spent nuclear fuels encompass many fuel types. In an effort to facilitate criticality analysis for these various fuel types, they were categorized into eight characteristic fuel groups with emphasis on fuel matrix composition. Out of each fuel group, a representative fuel type was chosen for analysis as a bounding case within that fuel group. Generally, burnup data, fissile enrichments, and total fuel and fissile mass govern the selection of the representative or candidate fuel within that group. The Shippingport Light Water Breeder Reactor (LWBR) fuels incorporate more of the conventional materials (zirconium cladding/heavy metal oxides) and fabrication details (rods and spacers) that make them comparable to a typical commercial fuel assembly. The LWBR seed/blanket configuration tested a light-water breeder concept with Th-232/U-233 binary fuel matrix. Reactor design used several assembly configurations at different locations within the same core . The seed assemblies contain the greatest fissile mass per (displaced) unit volume, but the blanket assemblies actually contain more fissile mass in a larger volume; the atom-densities are comparable.

L. L. Taylor; H. H. Loo

1999-09-01T23:59:59.000Z

126

Fuels  

NLE Websites -- All DOE Office Websites (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

127

Thermal hydraulic analysis of hydride fuels in BWR's  

E-Print Network (OSTI)

This thesis contributes to the hydride nuclear fuel project being completed by UC Berkeley and MIT to assess the possible benefits of using hydride fuel in light water nuclear reactors (LWR's). More specifically, this ...

Creighton, John Everett

2005-01-01T23:59:59.000Z

128

Thermomechanical analysis of innovative nuclear fuel pin designs  

E-Print Network (OSTI)

One way to increase the power of a nuclear reactor is to change the solid cylindrical fuel to Internally and Externally Cooled (I&EC) annular fuel, and adjust the flow and the core inlet coolant temperature. The switch to ...

Lerch Andrew (Andrew J.)

2010-01-01T23:59:59.000Z

129

Renewable & Alternative Fuels - Analysis & Projections - U.S ...  

U.S. Energy Information Administration (EIA)

Sales, revenue and prices, power plants, fuel use, stocks, generation, trade, demand & emissions. Consumption & Efficiency. ... Biomass; Geothermal; Hydropower; Solar ...

130

Technical and economic feasibility analysis of the no-fuel compressed air energy storage concept  

DOE Green Energy (OSTI)

The principal goal of this study was to evaluate the technical and economic feasibility of no-fuel compressed air energy storage (CAES) concepts for utility peaking applications. The analysis uncovered no insurmountable problems to preclude the technical feasibility of the no-fuel CAES concept. The results of the economic analysis are sufficiently unfavorable to conclude that no-fuel CAES technology could not compete with conventional CAES or standard gas turbine peaking facilities for conditions foreseeable at this time.

Kreid, D.K.

1976-05-01T23:59:59.000Z

131

Analysis Results for ARRA Projects: Enabling Fuel Cell Market Transformation (Presentation)  

DOE Green Energy (OSTI)

This presentation discusses analysis results for American Recovery and Reinvestment Act early market fuel cell deployments and describes the objective of the project and its relevance to the Department of Energy Hydrogen and Fuel Cells Program; NREL's analysis approach; technical accomplishments including publication of a fourth set of composite data products; and collaborations and future work.

Kurtz, J.; Wipke, K.; Sprik, S.; Ramsden, T.; Ainscough, C.; Saur, G.

2012-06-01T23:59:59.000Z

132

DOE Hydrogen Analysis Repository: Quick Starting Fuel Processors - A  

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

Quick Starting Fuel Processors - A Feasibility Study Quick Starting Fuel Processors - A Feasibility Study Project Summary Full Title: Quick Starting Fuel Processors - A Feasibility Study Project ID: 164 Principal Investigator: Shabbir Ahmed Brief Description: This project studied the feasibility of fast-starting fuel processors to meet DOE goals for on-board fuel processing. Keywords: On-board fuel processor Purpose Study the feasibility of developing fast-starting fuel processors that can meet DOE's targets, investigate designs and strategies capable of meeting the start-up targets, and validate models using experimental and hardware data. Performer Principal Investigator: Shabbir Ahmed Organization: Argonne National Laboratory (ANL) Address: 9700 South Cass Ave Argonne, IL 60439 Telephone: 630-252-4553

133

DOE Hydrogen Analysis Repository: Hydrogen Fueling Station Economics Model  

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

Fueling Station Economics Model Fueling Station Economics Model Project Summary Full Title: Hydrogen Fueling Station Economics Model Project ID: 193 Principal Investigator: Bill Liss Brief Description: The Gas Technology Institute developed a hydrogen fueling station economics model as part of their project to develop a natural gas to hydrogen fuel station. Keywords: Compressed gas; vehicle; refueling station; cost; natural gas Purpose Calculate hydrogen fueling station costs, including capital, operating, and maintenance costs. Performer Principal Investigator: Bill Liss Organization: Gas Technology Institute Address: 1700 South Mount Prospect Road Des Plains, IL 60018-1804 Telephone: 847-768-0530 Email: william.liss@gastechnology.org Project Description Type of Project: Model Category: Hydrogen Fuel Pathways

134

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

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

diesel via hydrogenation Coalbiomass co-feeding for FT diesel production Various corn ethanol plant types with different process fuels * Hydrogen-powered FC systems (not...

135

DOE Hydrogen and Fuel Cells Program: 2010-2025 Scenario Analysis...  

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

Scenario Analysis Printable Version 2010-2025 Scenario Analysis for Hydrogen Fuel Cell Vehicles and Infrastructure A transition from the current U.S. energy system to one based on...

136

Microscopic analysis of irradiated AGR-1 coated particle fuel compacts  

SciTech Connect

The AGR-1 experiment involved irradiation of 72 TRISO-coated particle fuel compacts to a peak burnup of 19.5% FIMA with no in-pile failures observed out of 3105 total particles. Irradiated AGR-1 fuel compacts have been cross-sectioned and analyzed with optical microscopy to characterize kernel, buffer, and coating behavior. Five compacts have been examined so far, spanning a range of irradiation conditions (burnup, fast fluence, and irradiation temperature) and including all four TRISO coating variations irradiated in the AGR-1 experiment. The cylindrical specimens were sectioned both transversely and longitudinally, then polished to expose between approximately 40-80 individual particles on each mount. The analysis focused primarily on kernel swelling and porosity, buffer densification and fracturing, buffer-IPyC debonding, and fractures in the IPyC and SiC layers. Characteristic morphologies have been identified, over 800 particles have been classified, and spatial distributions of particle types have been mapped. No significant spatial patterns were discovered in these cross sections. However, some trends were found between morphological types and certain behavioral aspects. Buffer fractures were found in approximately 23% of the particles, and these fractures often resulted in unconstrained kernel swelling into the open cavities. Fractured buffers and buffers that stayed bonded to IPyC layers appear related to larger pore size in kernels. Buffer-IPyC interface integrity evidently factored into initiation of rare IPyC fractures. Fractures through part of the SiC layer were found in only three particles, all in conjunction with IPyC-SiC debonding. Compiled results suggest that the deliberate coating fabrication variations influenced the frequencies of IPyC fractures, IPyC-SiC debonds, and SiC fractures.

Scott Ploger; Paul Demkowicz; John Hunn; Robert Morris

2012-10-01T23:59:59.000Z

137

Thermodynamic analysis and comparison on oxy-fuel power generation process - article no. 053001  

SciTech Connect

In this paper, pressurized oxy-fuel combustion power generation processes are modeled and analyzed based on a 350 MW subcritical reheat boiler associated with a condensing steam turbine. The performance results are obtained. Furthermore, the influences of slurry concentration and coal properties on power plant performance are investigated. An oxy-fuel configuration operating at ambient pressure is studied to compare the performance with pressurized oxy-fuel configuration. Thermodynamic analysis reveals the true potentials of the pressurized oxy-fuel process. Based on the system integration, an improved configuration is proposed in which plant efficiency of pressurized oxy-fuel process is increased by 1.36%.

Deng, S.M.; Hynes, R. [Hatch Energy, Oakville, ON (Canada)

2009-09-15T23:59:59.000Z

138

Engineering analysis of low enriched uranium fuel using improved zirconium hydride cross sections  

E-Print Network (OSTI)

A neutronic and thermal hydraulic analysis of the 1-MW TRIGA research reactor at the Texas A&M University Nuclear Science Center using a new low enriched uranium fuel (named 30/20 fuel) was completed. This analysis provides safety assessment for the change out of the existing high enriched uranium fuel to this high-burnup, low enriched uranium fuel design. The codes MCNP and Monteburns were utilized for the neutronic analysis while the code PARET was used to determine fuel and cladding temperatures. All of these simulations used improved zirconium hydride cross sections that were provided by Dr. Ayman Hawari at North Carolina State University. The neutronic and thermal analysis showed that the reactor will operate with approximately the same fuel lifetime as the current high enriched uranium fuel and stay within the thermal and safety limits for the facility. It was also determined that the control rod worths and the temperature coefficient of reactivity would provide sufficient negative reactivity to control the reactor during the fuelâ??s complete lifetime. An assessment of the fuelâ??s viability for use with the Advanced Fuel Cycle Initiativeâ??s Reactor Accelerator Coupling Experiments program was also performed. The objective of this study was to confirm the continued viability of these experiments with the reactor operating using this new fuel. For these experiments, the accelerator driven system must produce fission heating in excess of 1 kW when driven by a 20 kW accelerator system. This criterion was met using the new fuel. Therefore the change out of the fuel will not affect the viability of these experiments.

Candalino, Robert Wilcox

2006-08-01T23:59:59.000Z

139

Detailed analysis of uranium silicide dispersion fuel swelling  

SciTech Connect

Swelling of U{sub 3}Si and U{sub 3}Si{sub 2} is analyzed. The growth of fission gas bubbles appears to be affected by fission rate, fuel loading, and microstructural change taking place in the fuel compounds during irradiation. Several mechanisms are explored to explain the observations. The present work is aimed at a better understanding of the basic swelling phenomenon in order to accurately model irradiation behavior of uranium silicide disperson fuel. 5 refs., 10 figs.

Hofman, G.L.; Ryu, Woo-Seog.

1989-01-01T23:59:59.000Z

140

Finite element analysis of monolithic solid oxide fuel cells  

DOE Green Energy (OSTI)

This paper investigates the stress and fracture behavior of a monolithic solid oxide fuel cell (MSOFC) currently under joint development by Allied Signal Corporation and Argonne National Laboratory. The MSOFC is an all-ceramic fuel cell capable of high power density and tolerant of a variety of hydrocarbon fuels, making it potentially attractive for stationary utility and mobile transportation systems. The monolithic design eliminates inactive structural supports, increases active surface area, and lowers voltage losses caused by internal resistance.

Saigal, A. [Tufts Univ., Medford, MA (United States). Dept. of Mechanical Engineering; Majumdar, S. [Argonne National Lab., IL (United States)

1992-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Finite element analysis of monolithic solid oxide fuel cells  

DOE Green Energy (OSTI)

This paper investigates the stress and fracture behavior of a monolithic solid oxide fuel cell (MSOFC) currently under joint development by Allied Signal Corporation and Argonne National Laboratory. The MSOFC is an all-ceramic fuel cell capable of high power density and tolerant of a variety of hydrocarbon fuels, making it potentially attractive for stationary utility and mobile transportation systems. The monolithic design eliminates inactive structural supports, increases active surface area, and lowers voltage losses caused by internal resistance.

Saigal, A. (Tufts Univ., Medford, MA (United States). Dept. of Mechanical Engineering); Majumdar, S. (Argonne National Lab., IL (United States))

1992-01-01T23:59:59.000Z

142

Retrospective Eddy Current Defect Analysis of Degraded Fuel Rods  

Science Conference Proceedings (OSTI)

EPRIs Fuel Reliability Program is currently sponsoring post-irradiation examination (PIE) projects to develop a correlation between eddy current signals and features of interest in Zircaloy fuel cladding and channel materials. In this report, eddy current PIE data were retrospectively analyzed using Magnifi 2.0 R3 software for comparison to other PIE data for five domestic BWR fuel rods with varying degrees of corrosion, hydride formation, and cracking. One goal was to determine if newer ...

2013-11-14T23:59:59.000Z

143

Infrastructure Analysis of Early Market Transition of Fuel Cell...  

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

1 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Brian Bush (Primary Contact), Marc Melaina, Olga Sozinova, Michael Penev National Renewable Energy Laboratory...

144

Radiological consequence analysis with HEU and LEU fuels  

SciTech Connect

A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and non-site specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on meteorological conditions and release rates and heights can result in substantial reductions in the dose estimates. LEU fuel gives essentially the same doses as HEU fuel. The plutonium buildup in the LEU fuel does not significantly increase the radiological consequences. The dose to the thyroid is the limiting dose. 10 references, 3 figures, 7 tables.

Woodruff, W.L.; Warinner, D.K.; Matos, J.E.

1984-01-01T23:59:59.000Z

145

Davis-Besse Cycle 16 Fuel Deposit Analysis and Characterization  

Science Conference Proceedings (OSTI)

Fuel deposit samples were collected from Davis-Besse Unit 1 during the EOC16 outage. The impetus behind collecting crud samples came from the observation of unusual deposits on fuel during EOC15, as well as measured crud-induced power shape (CIPS) during Cycle 16. The purpose of EOC16 sample campaign therefore was to determine the nature of the fuel deposits. Samples were collected from two fuel assemblies, one after one cycle of exposure and the other after two cycles of exposure. Samples were collected...

2011-12-23T23:59:59.000Z

146

DOE Hydrogen Analysis Repository: Fuel Cell Water Transport Mechanism  

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

Water Transport Mechanism Project Summary Full Title: Neutron Imaging Study of the Water Transport Mechanism in a Working Fuel Cell Project ID: 183 Principal Investigator: Muhammad...

147

Analysis of fuel shares in the industrial sector  

SciTech Connect

These studies describe how fuel shares have changed over time; determine what factors are important in promoting fuel share changes; and project fuel shares to the year 1995 in the industrial sector. A general characterization of changes in fuel shares of four fuel types - coal, natural gas, oil and electricity - for the industrial sector is as follows. Coal as a major fuel source declined rapidly from 1958 to the early 1970s, with oil and natural gas substituting for coal. Coal's share of total fuels stabilized after the oil price shock of 1972-1973, and increased after the 1979 price shock. In the period since 1973, most industries and the industrial sector as a whole appear to freely substitute natural gas for oil, and vice versa. Throughout the period 1958-1981, the share of electricity as a fuel increased. These observations are derived from analyzing the fuel share patterns of more than 20 industries over the 24-year period 1958 to 1981.

Roop, J.M.; Belzer, D.B.

1986-06-01T23:59:59.000Z

148

Final safety analysis report for the irradiated fuels storage facility  

SciTech Connect

A fuel storage facility has been constructed at the Idaho Chemical Processing Plant to provide safe storage for spent fuel from two commercial HTGR's, Fort St. Vrain and Peach Bottom, and from the Rover nuclear rocket program. The new facility was built as an addition to the existing fuel storage basin building to make maximum use of existing facilities and equipment. The completed facility provides dry storage for one core of Peach Bottom fuel (804 elements), 1$sup 1$/$sub 2$ cores of Fort St. Vrain fuel (2200 elements), and the irradiated fuel from the 20 reactors in the Rover program. The facility is designed to permit future expansion at a minimum cost should additional storage space for graphite-type fuels be required. A thorough study of the potential hazards associated with the Irradiated Fuels Storage Facility has been completed, indicating that the facility is capable of withstanding all credible combinations of internal accidents and pertinent natural forces, including design basis natural phenomena of a 10,000 year flood, a 175-mph tornado, or an earthquake having a bedrock acceleration of 0.33 g and an amplification factor of 1.3, without a loss of integrity or a significant release of radioactive materials. The design basis accident (DBA) postulated for the facility is a complete loss of cooling air, even though the occurrence of this situation is extremely remote, considering the availability of backup and spare fans and emergency power. The occurrence of the DBA presents neither a radiation nor an activity release hazard. A loss of coolant has no effect upon the fuel or the facility other than resulting in a gradual and constant temperature increase of the stored fuel. The temperature increase is gradual enough that ample time (28 hours minimum) is available for corrective action before an arbitrarily imposed maximum fuel centerline temperature of 1100$sup 0$F is reached. (LK)

Bingham, G.E.; Evans, T.K.

1976-01-01T23:59:59.000Z

149

Development of a Reliable Fuel Depletion Methodology for the HTR-10 Spent Fuel Analysis  

Science Conference Proceedings (OSTI)

A technical working group formed in 2007 between NNSA and CAEA to develop a reliable fuel depletion method for HTR-10 based on MCNPX and to analyze the isotopic inventory and radiation source terms of the HTR-10 spent fuel. Conclusions of this presentation are: (1) Established a fuel depletion methodology and demonstrated its safeguards application; (2) Proliferation resistant at high discharge burnup ({approx}80 GWD/MtHM) - Unfavorable isotopics, high number of pebbles needed, harder to reprocess pebbles; (3) SF should remain under safeguards comparable to that of LWR; and (4) Diversion scenarios not considered, but can be performed.

Chung, Kiwhan [Los Alamos National Laboratory; Beddingfield, David H. [Los Alamos National Laboratory; Geist, William H. [Los Alamos National Laboratory; Lee, Sang-Yoon [unaffiliated

2012-07-03T23:59:59.000Z

150

Fuel Analysis and Licensing Code: FALCON MOD01: Volume 1: Theoretical and Numerical Bases  

Science Conference Proceedings (OSTI)

FALCON Mod01 software and accompanying three-volume documentation are being released as the state-of-the-art light water reactor (LWR) fuel performance analysis and modeling code validated to high burn-up. Based on a robust finite element numerical structure, FALCON is capable of analyzing both steady state and transient fuel behavior with a seamless transition between the two modes. FALCON is the culmination of focused developmental activities since 1996 (with its origins in EPRI's two historic fuel per...

2004-12-22T23:59:59.000Z

151

Fuel Analysis and Licensing Code: FALCON MOD01: Volume 3: Verification and Validation  

Science Conference Proceedings (OSTI)

FALCON Mod01 software and accompanying three-volume documentation are being released as the state-of-the-art light water reactor (LWR) fuel performance analysis and modeling code validated to high burn-up. Based on a robust finite element numerical structure, FALCON is capable of analyzing both steady state and transient fuel behavior with a seamless transition between the two modes. FALCON is the culmination of focused developmental activities since 1996 (with its origins in EPRI's two historic fuel per...

2004-12-22T23:59:59.000Z

152

Hazard analysis of compressed natural gas fueling systems and fueling procedures used at retail gasoline service stations. Final report  

Science Conference Proceedings (OSTI)

An evaluation of the hazards associated with operations of a typical compressed natural gas (CNG) fueling station is presented. The evaluation includes identification of a typical CNG fueling system; a comparison of the typical system with ANSI/NFPA (American National Standards Institute/National Fire Protection Association) Standard 52, Compressed Natural Gas (CNG) Vehicular Fuel System, requirements; a review of CNG industry safety experience as identified in current literature; hazard identification of potential internal (CNG system-specific causes) and external (interface of co-located causes) events leading to potential accidents; and an analysis of potential accident scenarios as determined from the hazard evaluation. The study considers CNG dispensing equipment and associated equipment, including the compressor station, storate vessels, and fill pressure sensing system.

NONE

1995-04-28T23:59:59.000Z

153

Fuel  

E-Print Network (OSTI)

heavy-water-moderated, light-water-moderated and liquid-metal cooled fast breeder reactors fueled with natural or low-enriched uranium and containing thorium mixed with the uranium or in separate target channels. U-232 decays with a 69-year half-life through 1.9-year half-life Th-228 to Tl-208, which emits a 2.6 MeV gamma ray upon decay. We find that pressurized light-water-reactors fueled with LEU-thorium fuel at high burnup (70 MWd/kg) produce U-233 with U-232 contamination levels of about 0.4 percent. At this contamination level, a 5 kg sphere of U-233 would produce a gammaray dose rate of 13 and 38 rem/hr at 1 meter one and ten years after chemical purification respectively. The associated plutonium contains 7.5 percent of the undesirable heat-generating 88-year half-life isotope Pu-238. However, just as it is possible to produce weapon-grade plutonium in low-burnup fuel, it is also practical to use heavy-water reactors to produce U-233 containing only a few ppm of U-232 if the thorium is segregated in target channels and discharged a few times more frequently than the natural-uranium driver fuel. The dose rate from a 5-kg solid sphere of U-233 containing 5 ppm U-232 could be reduced by a further factor of 30, to about 2 mrem/hr, with a close-fitting lead sphere weighing about 100 kg. Thus the proliferation resistance of thorium fuel cycles depends very much upon how they are implemented. The original version of this manuscript was received by Science & Global Security on

Jungmin Kang A

2001-01-01T23:59:59.000Z

154

A Low-Carbon Fuel Standard for California Part 2: Policy Analysis  

E-Print Network (OSTI)

natural gas generation A Low Carbon Fuel Standard for California Part II: PolicyNatural Gas Industries .. 88 A Low Carbon Fuel Standard for California Part II: PolicyPolicy Analysis Page 88 Appendix A: Structure of the California Oil, Electricity, and Natural Gas

2007-01-01T23:59:59.000Z

155

A Low-Carbon Fuel Standard for California, Part 2: Policy Analysis  

E-Print Network (OSTI)

natural gas generation A Low Carbon Fuel Standard for California Part II: PolicyNatural Gas Industries .. 88 A Low Carbon Fuel Standard for California Part II: PolicyPolicy Analysis Page 88 Appendix A: Structure of the California Oil, Electricity, and Natural Gas

Sperling, Daniel; Farrell, Alexander

2007-01-01T23:59:59.000Z

156

Analysis of the fuel economy benefit of drivetrain hybridization  

DOE Green Energy (OSTI)

Parallel- and series-configured hybrid vehicles likely feasible in next decade arc defined and evaluated using NREL's flexible ADvanced VehIcle SimulatOR ADVISOR. Fuel economics of these two diesel-powered hybrid vehicles are compared to a comparable-technology diesel- powered internal-combustion-engine vehicle. Sensitivities of these fuel economies to various vehicle and component parameters are determined and differences among them are explained. The fuel economy of the parallel hybrid defined here is 24% better than the internal- combustion-engine vehicle and 4% better than the series hybrid.

Cuddy, M.R.; Wipke, K.B.

1997-01-01T23:59:59.000Z

157

The Basis for Developing Samarium AMS for Fuel Cycle Analysis  

SciTech Connect

Modeling of nuclear reactor fuel burnup indicates that the production of samarium isotopes can vary significantly with reactor type and fuel cycle. The isotopic concentrations of {sup 146}Sm, {sup 149}Sm, and {sup 151}Sm are potential signatures of fuel reprocessing, if analytical techniques can overcome the inherent challenges of lanthanide chemistry, isobaric interferences, and mass/charge interferences. We review the current limitations in measurement of the target samarium isotopes and describe potential approaches for developing Sm-AMS. AMS sample form and preparation chemistry will be discussed as well as possible spectrometer operating conditions.

Buchholz, B A; Biegalski, S R; Whitney, S M; Tumey, S J; Weaver, C J

2008-10-13T23:59:59.000Z

158

DOE Hydrogen and Fuel Cells Program: Systems Analysis  

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

Repository H2A Analysis Hydrogen Analysis Resource Center Scenario Analysis Well-to-Wheels Analysis Systems Integration U.S. Department of Energy Search help Home > Systems...

159

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

Science Conference Proceedings (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 Programs understanding of the cost drivers that will determine nuclear powers 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

160

SUPPLEMENT ANALYSIS OF FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL  

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

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

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


161

CRACK GROWTH ANALYSIS OF SOLID OXIDE FUEL CELL ELECTROLYTES  

DOE Green Energy (OSTI)

Defects and Flaws control the structural and functional property of ceramics. In determining the reliability and lifetime of ceramics structures it is very important to quantify the crack growth behavior of the ceramics. In addition, because of the high variability of the strength and the relatively low toughness of ceramics, a statistical design approach is necessary. The statistical nature of the strength of ceramics is currently well recognized, and is usually accounted for by utilizing Weibull or similar statistical distributions. Design tools such as CARES using a combination of strength measurements, stress analysis, and statistics are available and reasonably well developed. These design codes also incorporate material data such as elastic constants as well as flaw distributions and time-dependent properties. The fast fracture reliability for ceramics is often different from their time-dependent reliability. Further confounding the design complexity, the time-dependent reliability varies with the environment/temperature/stress combination. Therefore, it becomes important to be able to accurately determine the behavior of ceramics under simulated application conditions to provide a better prediction of the lifetime and reliability for a given component. In the present study, Yttria stabilized Zirconia (YSZ) of 9.6 mol% Yttria composition was procured in the form of tubes of length 100 mm. The composition is of interest as tubular electrolytes for Solid Oxide Fuel Cells. Rings cut from the tubes were characterized for microstructure, phase stability, mechanical strength (Weibull modulus) and fracture mechanisms. The strength at operating condition of SOFCs (1000 C) decreased to 95 MPa as compared to room temperature strength of 230 MPa. However, the Weibull modulus remains relatively unchanged. Slow crack growth (SCG) parameter, n = 17 evaluated at room temperature in air was representative of well studied brittle materials. Based on the results, further work was planned to evaluate the strength degradation, modulus and failure in more representative environment of the SOFCs.

S. Bandopadhyay; N. Nagabhushana

2003-10-01T23:59:59.000Z

162

Cost Analysis of Fuel Cell Systems for Transportation  

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

Fuel Cell Fuel Cell Systems for Transportation Compressed Hydrogen and PEM Fuel Cell System Discussion Fuel Cell Tech Team FreedomCar Detroit. MI October 20, 2004 TIAX LLC Acorn Park Cambridge, Massachusetts 02140-2390 Ref D0006 SFAA No. DE-SCO2- 98EE50526 Topic 1 Subtopic 1C Agenda EC_2004 10 20 FC Tech Team Presentation 1 1 Project Overview 2 Compressed Hydrogen Storage Cost 3 2004 System Cost Update 4 Appendix Project Overview Approach EC_2004 10 20 FC Tech Team Presentation 2 In our final year of the project, we assessed the cost of compressed hydrogen storage and updated the overall system cost projection. Task 1: PEMFC System Technology Synopsis Task 2: Develop Cost Model and Baseline Estimates Task 3: Identify Opportunities for System Cost Reduction Tasks 4, 5, 6 & 7: Annual Updates

163

DOE Hydrogen Analysis Repository: Gasification-Based Fuels and Electricity  

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

Gasification-Based Fuels and Electricity Production from Biomass Gasification-Based Fuels and Electricity Production from Biomass Project Summary Full Title: Gasification-Based Fuels and Electricity Production from Biomass, without and with Carbon Capture and Storage Project ID: 226 Principal Investigator: Eric D. Larson Keywords: Biomass; Fischer Tropsch; hydrogen Purpose Develop and analyze process designs for gasification-based thermochemical conversion of switchgrass into Fischer-Tropsch (F-T) fuels, dimethyl ether (DME), and hydrogen. All process designs will have some level of co-production of electricity, and some will include capture of byproduct CO2 for underground storage. Performer Principal Investigator: Eric D. Larson Organization: Princeton University Telephone: 609-258-4966 Email: elarson@princeton.edu

164

Transient analysis of hydride fueled pressurized water reactor cores  

E-Print Network (OSTI)

This thesis contributes to the hydride nuclear fuel project led by U. C. Berkeley for which MIT is to perform the thermal hydraulic and economic analyses. A parametric study has been performed to determine the optimum ...

Trant, Jarrod Michael

2004-01-01T23:59:59.000Z

165

Sensitivity analysis of a dry-processed Candu fuel pellet's design parameters  

SciTech Connect

Sensitivity analysis was carried out in order to investigate the effect of a fuel pellet's design parameters on the performance of a dry-processed Canada deuterium uranium (CANDU) fuel and to suggest the optimum design modifications. Under a normal operating condition, a dry-processed fuel has a higher internal pressure and plastic strain due to a higher fuel centerline temperature when compared with a standard natural uranium CANDU fuel. Under a condition that the fuel bundle dimensions do not change, sensitivity calculations were performed on a fuel's design parameters such as the axial gap, dish depth, gap clearance and plenum volume. The results showed that the internal pressure and plastic strain of the cladding were most effectively reduced if a fuel's element plenum volume was increased. More specifically, the internal pressure and plastic strain of the dry-processed fuel satisfied the design limits of a standard CANDU fuel when the plenum volume was increased by one half a pellet, 0.5 mm{sup 3}/K. (authors)

Choi, Hangbok; Ryu, Ho Jin [Korea Atomic Energy Research Institute 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2007-07-01T23:59:59.000Z

166

Thermal-hydraulic analysis of cross-shaped spiral fuel in high power density BWRs  

E-Print Network (OSTI)

Preliminary analysis of the cross-shaped spiral (CSS) fuel assembly suggests great thermal-hydraulic upside. According to computational models, the increase in rod surface area, combined with an increase in coolant turbulence ...

Conboy, Thomas M

2007-01-01T23:59:59.000Z

167

Analysis of the ATR fuel element swaging process  

Science Conference Proceedings (OSTI)

This report documents a detailed evaluation of the swaging process used to connect fuel plates to side plates in Advanced Test Reactor (ATR) fuel elements. The swaging is a mechanical process that begins with fitting a fuel plate into grooves in the side plates. Once a fuel plate is positioned, a lip on each of two side plate grooves is pressed into the fuel plate using swaging wheels to form the joints. Each connection must have a specified strength (measured in terms, of a pullout force capacity) to assure that these joints do not fail during reactor operation. The purpose of this study is to analyze the swaging process and associated procedural controls, and to provide recommendations to assure that the manufacturing process produces swaged connections that meet the minimum strength requirement. The current fuel element manufacturer, Babcock and Wilcox (B&W) of Lynchburg, Virginia, follows established procedures that include quality inspections and process controls in swaging these connections. The procedures have been approved by Lockheed Martin Idaho Technologies and are designed to assure repeatability of the process and structural integrity of each joint. Prior to July 1994, ATR fuel elements were placed in the Hydraulic Test Facility (HTF) at the Idaho National Engineering Laboratory (AGNAIL), Test Reactor Area (TRA) for application of Boehmite (an aluminum oxide) film and for checking structural integrity before placement of the elements into the ATR. The results presented in this report demonstrate that the pullout strength of the swaged connections is assured by the current manufacturing process (with several recommended enhancements) without the need for- testing each element in the HTF.

Richins, W.D.; Miller, G.K.

1995-12-01T23:59:59.000Z

168

Microstructural Analysis of Irradiated U-Mo Fuel Plates: Recent Results  

Science Conference Proceedings (OSTI)

Microstructural characterization of irradiated dispersion and monolithic RERTR fuel plates using scanning electron microscopy (SEM) is being performed in the Electron Microscopy Laboratory at the Idaho National Laboratory. The SEM analysis of samples from U-Mo dispersion fuel plates focuses primarily on the behavior of the Si that has been added to the Al matrix to improve the irradiation performance of the fuel plate and on the overall behavior of fission gases (e.g., Xe and Kr) that develop as bubbles in the fuel microstructure. For monolithic fuel plates, microstructural features of interest, include those found in the U-Mo foil and at the U-Mo/Zr and Zr/6061 Al cladding interfaces. For both dispersion and monolithic fuel plates, samples have been produced using an SEM equipped with a Focused Ion Beam (FIB). These samples are of very high quality and can be used to uncover some very unique microstructural features that are typically not observed when characterizing samples produced using more conventional techniques. Overall, for the dispersion fuel plates with matrices that contained Si, narrower fuel/matrix interaction layers are typically observed compared to the fuel plates with pure Al matrix, and for the monolithic fuel plates microstructural features have been observed in the U-10Mo foil that are similar to what have been observed in the fuel particles found in U-Mo dispersion fuels. Most recently, more prototypic monolithic fuel samples have been characterized and this paper describes the microstructures that have been observed in these samples.

D. D. Keiser, Jr.; J. Jue; B. D. Miller; J. Gan; A. B. Robinson; P. V. Medvedev

2012-03-01T23:59:59.000Z

169

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

E-Print Network (OSTI)

W gasoline SOFC technology development program APU applications can provide entry markets for fuel cell & Select APU Systems 2 · Summarize PEM and SOFC performance parameters · Determine most promising future Task 3: Develop design concepts · Truck Cab/SOFC/diesel · Transit bus/SOFC/CNG or diesel · Police

170

Micro-Pocket Fission Detectors (MPFD) For Fuel Assembly Analysis  

Science Conference Proceedings (OSTI)

Neutron sensors capable of real-time measurement of thermal flux, fast flux, and temperature in a single miniaturized probe are needed in irradiation tests required to demonstrate the performance of candidate new fuels, and cladding materials. In-core ceramic-based miniature neutron detectors or Micro-Pocket Fission Detectors (MPFDs) have been studied at Kansas State University (KSU). The first MPFD prototypes were tested in various neutron fields at the KSU TRIGA research reactor with successful results. Currently, a United States Department of Energy-sponsored joint KSU/Idaho National Laboratory (INL) effort is underway to develop a high-temperature, high-pressure version of the MPFD using radiation-resistant, high temperature materials, which would be capable of withstanding irradiation test conditions in high performance material and test reactors (MTRs). Ultimately, this more compact, more accurate, and longer lifetime flux sensor for critical mock-ups, existing and advanced reactor designs, high performance MTRs, and transient test reactors has the potential to lead to higher accuracy and resolution data from irradiation testing, more detailed core flux measurements and enhanced fuel assembly processing. Prior evaluations by KSU indicate that these sensors could also be used to monitor burn-up of nuclear fuel. If integrated into nuclear fuel assemblies, MPFDs offer several advantages to current spent fuel management systems.

Troy Unruh; Michael Reichenberger; Phillip Ugorowski

2013-09-01T23:59:59.000Z

171

NREL: Hydrogen and Fuel Cells Research - Systems Analysis  

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

analysis modeling activities. To learn more about hydrogen systems analysis, visit Energy Analysis and Tools. Publications The following technical papers, journal articles,...

172

Fuel cycle analysis of once-through nuclear systems.  

SciTech Connect

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

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

2010-08-10T23:59:59.000Z

173

ATR PDQ and MCWO Fuel Burnup Analysis Codes Evaluation  

SciTech Connect

The Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) is being studied to determine the feasibility of converting it from the highly enriched Uranium (HEU) fuel that is currently uses to low enriched Uranium (LEU) fuel. In order to achieve this goal, it would be best to qualify some different computational methods than those that have been used at ATR for the past 40 years. This paper discusses two methods of calculating the burnup of ATR fuel elements. The existing method, that uses the PDQ code, is compared to a modern method that uses A General Monte Carlo N-Particle Transport Code (MCNP) combined with the Origen2.2 code. This modern method, MCNP with ORIGEN2.2 (MCWO), is found to give excellent agreement with the existing method (PDQ). Both of MCWO and PDQ are also in a very good agreement to the 235U burnup data generated by an analytical method.

G.S. Chang; P. A. Roth; M. A. Lillo

2009-11-01T23:59:59.000Z

174

Sustainable Harvest for Food and Fuel Preliminary Food & Fuel Gap Analysis Report  

SciTech Connect

To promote economic growth and energy security, and to protect the environment, the U.S. is pursuing a national strategy of energy independence and climatic protection in which domestic renewable carbon-neutral biofuels displace 30 percent of U.S. oil consumption by the mid-21st century. Such fuels, including ethanol and biodiesel, will be produced from biological feed stocks (biomass). The availability of this billion-ton biomass will hinge on the application of modern scientific and engineering tools to create a highly-integrated biofuel production system. Efforts are underway to identify and develop energy crops, ranging from agricultural residues to genetically engineered perennials; to develop biology-based processing methods; and, to develop large-scale biorefineries to economically convert biomass into fuels. In addition to advancing the biomass-to-biofuel research and development agenda, policy makers are concurrently defining the correct mix of governmental supports and regulations. Given the volumes of biomass and fuels that must flow to successfully enact a national biomass strategy, policies must encourage large-scale markets to form and expand around a tightly integrated system of farmers, fuel producers and transporters, and markets over the course of decades. In formulating such policies, policy makers must address the complex interactions of social, technical, economic, and environmental factors that bound energy production and use. The Idaho National Laboratory (INL) is a science-based, applied engineering national laboratory dedicated to supporting the U.S. Department of Energy (DOE). The INL Bioenergy Program supports the DOE and the U.S. Department of Agriculture. Key multidisciplinary INL capabilities are being leveraged to address major science and technology needs associated with the cost-effective utilization of biomass. INLs whole crop utilization (WCU) vision is focused on the use of the entire crop, including both the grain and traditionally discarded plant biomass to produce food, feed, fiber, energy, and value-added products.

Ray Grosshans; Kevin M. Kostelnik; Jake Jacobson

2007-04-01T23:59:59.000Z

175

Analysis of the ATW fuel cycle using the REBUS-3 code system  

Science Conference Proceedings (OSTI)

Partitioning and transmutation strategies are under study in several countries as a means of reducing the long-term hazards of spent fuel and other high-level nuclear waste. Various reactor and accelerator-driven system concepts have been proposed to transmute the long-lived radioactive nuclei of waste into stable or short-lived species. Among these concepts, the accelerator-driven transmutation of waste (ATW) system has been proposed by the Los Alamos National Laboratory for rapid destruction of transuranic actinides and long-lived fission products ({sup 99}Tc and {sup 129}I). The current reference ATW concept employs a subcritical, liquid-metal-cooled, fast-spectrum nuclear subsystem. Because the discharged fuel is recycled, analysis of ATW nuclear performance requires modeling of the external cycle as well as the in-core fuel management. The fuel cycle analysis of ATW can be performed rigorously using Monte Carlo calculations coupled with detailed depletion calculations. However, the inefficiency of this approach makes it impractical, particularly in view of (a) the large number of fuel cycle calculations needed for design optimization and (b) the need to represent complex in-core and out-of-core fuel cycle operations. To meet the need for design-oriented capabilities, tools previously developed for fast reactor calculations are being adapted for application to ATW. Here, the authors describe the extension and application of the REBUS-3 code to ATW fuel cycle analysis.

Yang, W.S.; Khalil, H.S.

1999-07-01T23:59:59.000Z

176

Intelligent Machine Learning Analysis for Fuel Cell Operations  

SciTech Connect

A performance computational model for a 100 kW nominal solid oxide fuel cell generator system is described. The calculational methods are based on the FORTRAN programming language. Comprehensive parameter input options are presented, and constraints are identified. Example reactant, electrical, and efficiency outputs are demonstrated over the relevant operating ranges. A sample calculated output display at nominal operating conditions is given.

Murphy, R.W.; Hoyt, W.A.

2000-06-30T23:59:59.000Z

177

Receiving Basin for Offsite Fuels and the Resin Regeneration Facility Safety Analysis Report, Executive Summary  

Science Conference Proceedings (OSTI)

The Safety Analysis Report documents the safety authorization basis for the Receiving Basin for Offsite Fuels (RBOF) and the Resin Regeneration Facility (RRF) at the Savannah River Site (SRS). The present mission of the RBOF and RRF is to continue in providing a facility for the safe receipt, storage, handling, and shipping of spent nuclear fuel assemblies from power and research reactors in the United States, fuel from SRS and other Department of Energy (DOE) reactors, and foreign research reactors fuel, in support of the nonproliferation policy. The RBOF and RRF provide the capability to handle, separate, and transfer wastes generated from nuclear fuel element storage. The DOE and Westinghouse Savannah River Company, the prime operating contractor, are committed to managing these activities in such a manner that the health and safety of the offsite general public, the site worker, the facility worker, and the environment are protected.

Shedrow, C.B.

1999-11-29T23:59:59.000Z

178

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

SciTech Connect

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

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

2009-10-01T23:59:59.000Z

179

Waste generation process modeling and analysis for fuel reprocessing technologies  

SciTech Connect

Estimates of electric power generation requirements for the next century, even when taking the most conservative tack, indicate that the United States will have to increase its production capacity significantly. If the country determines that nuclear power will not be a significant component of this production capacity, the nuclear industry will have to die, as maintaining a small nuclear component will not be justifiable. However, if nuclear power is to be a significant component, it will probably require some form of reprocessing technology. The once-through fuel cycle is only feasible for a relatively small number of nuclear power plants. If we are maintaining several hundred reactors, the once-through fuel cycle is more expensive and ethically questionable.

Kornreich, D. E. (Drew E.); Koehler, A. C. (Andrew C.); Farman, Richard F.

2002-01-01T23:59:59.000Z

180

LOFT contribution to PWR fuel analysis and testing  

SciTech Connect

The paper provides a brief overview of the Loss-of-Fluid Test (LOFT) Facility, a review of the key results from LOCA tests performed to date, and plans for the future of LOFT, as an introduction to the more specific information about LOFT fuel that is to follow. The purpose of the LOFT tests is to provide data for assessing the accuracy of the analytical models used in evaluating the safety of commercial nuclear power plants. While the main purpose of LOFT is to investigate phenomena important to the loss-of-coolant accident (LOCA), the 55 MWt LOFT reactor system has been scaled to commercial power reactors and heavily instrumented so that information on fuel and system behavior over a range of normal and off-normal conditions can be obtained.

Leach, L.P.

1978-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

An Analysis of Fuel Demand and Carbon Emissions in China  

E-Print Network (OSTI)

Under the Kyoto Protocol to the United Nations Framework Convention on Climate Change, targets have been set for various developed countries to reduce their carbon emissions. China's share of carbon emissions ranked the second highest in the world in 1996, only after the United States. Although China was not formally required to achieve a reduction in its carbon emissions under the protocol, pressures were mounting, especially from the United States, for China to address the issue seriously. Some recent research on China's carbon emissions has largely been carried out in the framework of computable general equilibrium models. For example, Fisher-Vanden (2003) used such models to assess the impact of market reforms on shaping the level and composition of carbon emissions; Garbaccio et al. (1999) and Zhang (1998) studied macroeconomic and sectoral effects of policies and instruments, such as, a carbon tax, on achieving predefined targets of carbon emissions. A common omission in these studies is the role of fuel price changes in determining the amount of carbon emissions. This paper first shows China's total CO2 emissions from burning all types of fossil fuels over the 50 years or so to 2001, with those from burning coal singled out for the purpose of illustrating coal as the major CO2 emitter. Then, using annual data for the period 1985-2000, the study investigates whether changes in the relative prices of various fuels reduce coal consumption. Four sectors in the Chinese economy are selected for the study, namely, the chemical industry, the metal industry, the non-metal materials industry and the residential sector, which are top energy as well as top coal consumers. Five fuels are considered, namely, coal, crude oil, electricity, natural gas and petroleum products, ...

Baiding Hu Department; Baiding Hu

2004-01-01T23:59:59.000Z

182

Thermal-Hydraulic Analysis of Advanced Mixed-Oxide Fuel Assemblies with VIPRE-01  

E-Print Network (OSTI)

Two new fuel assembly designs for light water reactors using advanced mixed-oxide fuels have been proposed to reduce the radiotoxicity of used nuclear fuel discharged from nuclear power plants. The research efforts of this thesis are the first to consider the effects of burnup on advanced mixed-oxide fuel assembly performance and thermal safety margin over an assembly?s expected operational burnup lifetime. In order to accomplish this, a new burnup-dependent thermal-hydraulic analysis methodology has been developed. The new methodology models many of the effects of burnup on an assembly design by including burnup-dependent variations in fuel pin relative power from neutronic calculations, assembly power reductions due to fissile content depletion and core reshuffling, and fuel material thermal-physical properties. Additionally, a text-based coupling method is developed to facilitate the exchange of information between the neutronic code DRAGON and thermal-hydraulic code VIPRE-01. The new methodology effectively covers the entire assembly burnup lifetime and evaluates the thermal-hydraulic performance against ANS Condition I, II, and III events with respect to the minimum departure from nucleate boiling ratio, peak cladding temperatures, and fuel centerline temperatures. A comprehensive literature survey on the thermal conductivity of posed fuel materials with burnup-dependence has been carried out to model the advanced materials in the thermal-hydraulic code VIPRE-01. Where documented conductivity values are not available, a simplified method for estimating the thermal conductivity has been developed. The new thermal conductivity models are based on established FRAPCON-3 fuel property models used in the nuclear industry, with small adjustments having been made to account for actinide additions. Steady-state and transient thermal-hydraulic analyses are performed with VIPRE- 01 for a reference UO2 assembly design, and two advanced mixed-oxide fuel assembly designs using the new burnup-dependent thermal-hydraulic analysis methodology. All three designs maintain a sufficiently large thermal margin with respect to the minimum departure from nucleate boiling ratio, and maximum cladding and fuel temperatures during partial and complete loss-of-flow accident scenarios. The presence of a thin (Am,Zr)O2 outer layer on the fuel pellet in the two advanced mixed-oxide fuel assembly designs increases maximum fuel temperatures during transient conditions, but does not otherwise greatly compromise the thermal margin of the new designs.

Bingham, Adam R.

2009-05-01T23:59:59.000Z

183

Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities  

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

Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Executive Summary This paper addresses why the use of an Integrated Safety Analysis ("ISA") is appropriate for fuel recycling facilities 1 which would be licensed under new regulations currently being considered by NRC. The use of the ISA for fuel facilities under Part 70 is described and compared to the use of a Probabilistic Risk Assessment ("PRA") for reactor facilities. A basis is provided for concluding that future recycling facilities - which will possess characteristics similar to today's fuel cycle facilities and distinct from reactors - can best be assessed using established qualitative or semi-quantitative ISA techniques to achieve and demonstrate safety in an effective and efficient manner.

184

An analysis of heating fuel market behavior, 1989--1990  

SciTech Connect

The purpose of this report is to fully assess the heating fuel crisis from a broader and longer-term perspective. Using EIA final, monthly data, in conjunction with credible information from non-government sources, the pricing phenomena exhibited by heating fuels in late December 1989 and early January 1990 are described and evaluated in more detail and more accurately than in the interim report. Additionally, data through February 1990 (and, in some cases, preliminary figures for March) make it possible to assess the market impact of movements in prices and supplies over the heating season as a whole. Finally, the longer time frame and the availability of quarterly reports filed with the Securities and Exchange Commission make it possible to weigh the impact of revenue gains in December and January on overall profits over the two winter quarters. Some of the major, related issues raised during the House and Senate hearings in January concerned the structure of heating fuel markets and the degree to which changes in this structure over the last decade may have influenced the behavior and financial performance of market participants. Have these markets become more concentrated Was collusion or market manipulation behind December's rising prices Did these, or other, factors permit suppliers to realize excessive profits What additional costs were incurred by consumers as a result of such forces These questions, and others, are addressed in the course of this report.

1990-06-01T23:59:59.000Z

185

MCWO - Linking MCNP And ORIGEN2 For Fuel Burnup Analysis  

Science Conference Proceedings (OSTI)

The UNIX BASH (Bourne Again Shell) script MCWO has been developed at the Idaho National Engineering and Environment Laboratory (INEEL) to couple the Monte Carlo transport code MCNP with the depletion and buildup code ORIGEN2. MCWO is a fully automated tool that links the Monte Carlo transport code MCNP with the radioactive decay and burnup code ORIGEN2. MCWO can handle a large number of fuel burnup and material loading specifications, Advanced Test Reactor (ATR) powers, and irradiation time intervals. The program processes input from the user that specifies the system geometry, initial material compositions, feed/removal specifications, and other code-specific parameters. Calculated results from MCNP, ORIGEN2, and data process module calculations are then output successively as the code runs. The principal function of MCWO is to transfer one-group cross-section and flux values from MCNP to ORIGEN2, and then transfer the resulting material compositions (after irradiation and/or decay) from ORIGEN2 back to MCNP in a repeated, cyclic fashion. The basic requirement of the code is that the user have a working MCNP input file and other input parameters; all interaction with ORIGEN2 and other calculations are performed by UNIX BASH script MCWO. This paper presents the MCWO-calculated results of the RERTR-1 and -2 , and the Weapons-Grade Mixed Oxiide fuel (Wg-MOX) fuel experiments in ATR and compares the MCWO-calculated results with the measured data.

Gray S Chang

2005-04-01T23:59:59.000Z

186

Economic and Environmental Analysis of Fuel Cell Powered Materials Handling Equipment  

Science Conference Proceedings (OSTI)

This technical update describes an analysis of the economic and environmental attributes of forklift fleets powered by battery and fuel cell power plants. The report first provides background on the fuel cell forklift technology. The fuel cell forklift is then compared to three other technology options: conventional battery-powered forklifts, fast-charge forklifts at 15 kW of charging power, and fast-charge forklifts at 20 kW of charging power. This study develops models of the infrastructure and equipme...

2010-12-31T23:59:59.000Z

187

Carbon Dioxide Information Analysis Center (CDIAC)-Fossil Fuel CO2  

Open Energy Info (EERE)

Dioxide Information Analysis Center (CDIAC)-Fossil Fuel CO2 Dioxide Information Analysis Center (CDIAC)-Fossil Fuel CO2 Emissions Jump to: navigation, search Tool Summary Name: Carbon Dioxide Information Analysis Center (CDIAC)-Fossil Fuel CO2 Emissions Agency/Company /Organization: Oak Ridge National Laboratory Sector: Energy, Climate Topics: GHG inventory, Background analysis Resource Type: Dataset Website: cdiac.ornl.gov/trends/emis/meth_reg.html Country: United States, Canada, Mexico, Argentina, Brazil, Chile, Colombia, Ecuador, Peru, Venezuela, Austria, Azerbaijan, Belarus, Belgium, Luxembourg, Bulgaria, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Kazakhstan, Lithuania, Netherlands, Norway, Poland, Portugal, Romania, Russia, Slovakia, Spain, Sweden, Switzerland, Turkey, Turkmenistan, Ukraine, United Kingdom, Uzbekistan, Iran, Kuwait, Qatar, Saudi Arabia, United Arab Emirates, Algeria, Egypt, South Africa, Australia, Bangladesh, China, India, Indonesia, Japan, Malaysia, New Zealand, Pakistan, Philippines, Singapore, South Korea, Taiwan, Thailand

188

Analysis of transport mechanisms in dense fuel droplet sprays  

DOE Green Energy (OSTI)

This report deals with numerical analyses of fluid mechanics, heat transfer, mass transfer and particle dynamics of interacting spheres and vaporizing droplets in a linear array or on a 1-D trajectory. Available finite element software has been modified and extended to solve several case studies including closely spaced monodisperse spheres with or without blowing; closely spaced vaporizing fuel droplets; and dynamically interacting vaporizing fuel droplets on a 1-D trajectory. Axisymmetric laminar flow has been assumed for three statically or dynamically interacting spherical solids and vaporizing droplets. Emphasis in this work is evaluating the effects of key system parameters, such as free stream Reynolds number, interparticle spacings, liquid/gas-phase viscosity ratio and variable fluid properties, on interfacial transfer processes and on the particle Nusselt number, vaporization rate and drag coefficient. Computer-generated correlations between integral quantities and system parameters were postulated for blowing spheres and vaporizing droplets. In addition to initial Reynolds number and droplet spacings, variable fluid properties, liquid-phase heating and internal droplet circulation have strong effect on the dynamic behavior of multi-droplet systems. While the lead droplet is most significantly affected by all key parameters, the second and third droplet causes distinct interaction effects which are largely dependent on initial droplet spacings. Applications include spherical-structure/fluid-flow interactions, as well as interacting vaporizing droplets in different sprays related to propulsion systems, irrigation, spray coating, etc. Focusing on fuel droplet sprays, results of the dynamic multi-droplet study can assist in better atomizers and combustion chamber designs which may lead to improved combustion efficiencies, smaller/lighter systems, and reduced pollutant emissions.

Kleinstreuer, C.

1991-05-01T23:59:59.000Z

189

NREL: Energy Analysis - Biomass Technology Analysis  

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

Biomass Technology Analysis Biomass Technology Analysis Conducting full life-cycle assessments for biomass products, including electricity, biodiesel, and ethanol, is important for determining environmental benefits. NREL analysts use a life-cycle inventory modeling package and supporting databases to conduct life-cycle assessments. These tools can be applied on a global, regional, local, or project basis. Integrated system analyses, technoeconomic analyses, life-cycle assessments (LCAs), and other analysis tools are essential to our research and development efforts. They provide an understanding of the economic, technical, and even global impacts of renewable technologies. These analyses also provide direction, focus, and support to the development and commercialization of various biomass conversion technologies. The economic

190

NREL: Vehicles and Fuels Research - July 24 Webinar: DOE Analysis Related  

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

July 24 Webinar: DOE Analysis Related to H2USA July 24 Webinar: DOE Analysis Related to H2USA July 18, 2013 The U.S. Department of Energy will present a live webcast titled "DOE Analysis Related to H2USA" on Wednesday, July 24 from 12 to 1:30 p.m. Eastern Daylight Time. The webinar will provide information about models, tools, and various analyses relevant to H2USA, a new public-private partnership focused on advancing hydrogen infrastructure to support more transportation energy options for U.S. consumers, including fuel cell electric vehicles. The new partnership brings together automakers, government agencies, gas suppliers, and the hydrogen and fuel cell industries to coordinate research and identify cost-effective solutions to deploy infrastructure that can deliver affordable, clean hydrogen fuel in the United States.

191

Validation and application of a physics database for fast reactor fuel cycle analysis  

SciTech Connect

An effort has been made to automate the execution of fast reactor fuel cycle analysis, using EBR-II as a demonstration vehicle, and to validate the analysis results for application to the IFR closed fuel cycle demonstration at EBR-II and its fuel cycle facility. This effort has included: (1) the application of the standard ANL depletion codes to perform core-follow analyses for an extensive series of EBR-II runs, (2) incorporation of the EBR-II data into a physics database, (3) development and verification of software to update, maintain and verify the database files, (4) development and validation of fuel cycle models and methodology, (5) development and verification of software which utilizes this physics database to automate the application of the ANL depletion codes, methods and models to perform the core-follow analysis, and (6) validation studies of the ANL depletion codes and of their application in support of anticipated near-term operations in EBR-II and the Fuel Cycle Facility. Results of the validation tests indicate the physics database and associated analysis codes and procedures are adequate to predict required quantities in support of early phases of FCF operations.

McKnight, R.D.; Stillman, J.A.; Toppel, B.J.; Khalil, H.S.

1994-03-01T23:59:59.000Z

192

Analysis of the ATW fuel cycle using the REBUS-3 code system.  

Science Conference Proceedings (OSTI)

Partitioning and transmutation strategies are under study in several countries as a means of reducing the long-term hazards of spent fuel and other high-level nuclear waste. Various reactor and accelerator-driven system concepts have been proposed to transmute the long-lived radioactive nuclei of waste into stable or short-lived species. Among these concepts, the accelerator-driven transmutation of waste (ATW) system has been proposed by LANL for rapid destruction of transuranic actinides and long-lived fission products ({sup 99}Tc and {sup 129}I).The current reference ATW concept employs a subcritical, liquid metal cooled, fast-spectrum nuclear subsystem. Because the discharged fuel is recycled, analysis of ATW nuclear performance requires modeling of the external cycle as well as the in-core fuel management. The fuel cycle analysis of ATW can be performed rigorously using Monte Carlo calculations coupled with detailed depletion calculations. However, the inefficiency of this approach makes it impractical, particularly in view of (a) the large number of fuel cycle calculations needed for design optimization and (b) the need to represent complex in-core and out-of-core fuel cycle operations. To meet the need for design-oriented capabilities, tools previously developed for fast reactor calculations are being adapted for application to ATW. Here we describe the extension and application of the REBUS-3 code to ATW fuel cycle analysis. This code has been extensively used for advanced liquid metal reactor design and analysis and validated against EBR-II irradiation data.

Khalil, H. S.; Yang, W. S.

1999-06-25T23:59:59.000Z

193

Accident Analysis for the NIST Research Reactor Before and After Fuel Conversion  

SciTech Connect

Postulated accidents have been analyzed for the 20 MW D2O-moderated research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The analysis has been carried out for the present core, which contains high enriched uranium (HEU) fuel and for a proposed equilibrium core with low enriched uranium (LEU) fuel. The analyses employ state-of-the-art calculational methods. Three-dimensional Monte Carlo neutron transport calculations were performed with the MCNPX code to determine homogenized fuel compositions in the lower and upper halves of each fuel element and to determine the resulting neutronic properties of the core. The accident analysis employed a model of the primary loop with the RELAP5 code. The model includes the primary pumps, shutdown pumps outlet valves, heat exchanger, fuel elements, and flow channels for both the six inner and twenty-four outer fuel elements. Evaluations were performed for the following accidents: (1) control rod withdrawal startup accident, (2) maximum reactivity insertion accident, (3) loss-of-flow accident resulting from loss of electrical power with an assumption of failure of shutdown cooling pumps, (4) loss-of-flow accident resulting from a primary pump seizure, and (5) loss-of-flow accident resulting from inadvertent throttling of a flow control valve. In addition, natural circulation cooling at low power operation was analyzed. The analysis shows that the conversion will not lead to significant changes in the safety analysis and the calculated minimum critical heat flux ratio and maximum clad temperature assure that there is adequate margin to fuel failure.

Baek J.; Diamond D.; Cuadra, A.; Hanson, A.L.; Cheng, L-Y.; Brown, N.R.

2012-09-30T23:59:59.000Z

194

A comparative analysis of alternative fuels for the INEL vehicle fleet  

DOE Green Energy (OSTI)

This report summarizes the results of a comparative systems analysis of various alternative fuels for use in the buses, mid-size vehicles, and automobiles that make up the vehicle fleet at the Idaho National Engineering Laboratory (INEL). The study was performed as part of the Laboratory Directed Research and Development (LDRD) Program for EG G Idaho, Inc. Regulations will require the INEL to reduce total gasoline and diesel fuel use 10% by 1995 compared with 1991 levels, and will require that 50% of all new vehicles be fueled by some type of alternative fuel by 1998. A model was developed to analyze how these goals could be achieved, and what the cost would be to implement the goals.

Priebe, S.; Boyer, W.; Church, K.

1992-11-01T23:59:59.000Z

195

A comparative analysis of alternative fuels for the INEL vehicle fleet  

DOE Green Energy (OSTI)

This report summarizes the results of a comparative systems analysis of various alternative fuels for use in the buses, mid-size vehicles, and automobiles that make up the vehicle fleet at the Idaho National Engineering Laboratory (INEL). The study was performed as part of the Laboratory Directed Research and Development (LDRD) Program for EG&G Idaho, Inc. Regulations will require the INEL to reduce total gasoline and diesel fuel use 10% by 1995 compared with 1991 levels, and will require that 50% of all new vehicles be fueled by some type of alternative fuel by 1998. A model was developed to analyze how these goals could be achieved, and what the cost would be to implement the goals.

Priebe, S.; Boyer, W.; Church, K.

1992-11-01T23:59:59.000Z

196

NREL: Hydrogen and Fuel Cells Research - Energy Analysis and...  

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

related studies and research centers. International Council for Clean Transportation McKinsey & Company: A Portfolio of Powertrains for Europe: a Fact-Based Analysis of the Role...

197

Analysis of Integrated Gasification Fuel Cell Plant Configurations  

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

DOENETL - 2011-1482 Final Report February 22, 2011 NETL Contact: Walter Shelton Performance Section, Office of Program Planning and Analysis National Energy Technology...

198

Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling...  

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

by industry for recycling facilities 2 , is a systematic analysis to identify facility and external hazards and their potential for initiating accident sequences, the...

199

Stationary Fuel Cell System Cost Analysis - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Brian D. James (Primary Contact), Andrew B. Spisak, Whitney G. Colella Strategic Analysis, Inc. 4075 Wilson Blvd. Suite 200 Arlington, VA 22203 Phone: (703) 778-7114 Email: bjames@sainc.com DOE Managers HQ: Jason Marcinkoski Phone: (202) 586-7466 Email: Jason.Marcinkoski@ee.doe.gov GO: Gregory Kleen Phone: (720) 356-1672 Email: Gregory.Kleen@go.doe.gov Technical Advisor Bryan Pivovar Phone: (303) 275-3809 Email: bryan.pivovar@nrel.gov Sub-Contract Number No: AGB-0-40628-01 under Prime Contract No. DE-AC36-08G028308 Project Start Date: July 8, 2010 Project End Date: September 7, 2012 Fiscal Year (FY) 2012 Objectives Perform Design for Manufacturing and Assembly * (DFMA ® ) cost analysis for low-temperature (LT)

200

Analysis of the Reuse of Uranium Recovered from the Reprocessing of Commercial LWR Spent Fuel  

Science Conference Proceedings (OSTI)

This report provides an analysis of the factors involved in the reuse of uranium recovered from commercial light-water-reactor (LWR) spent fuels (1) by reenrichment and recycling as fuel to LWRs and/or (2) by recycling directly as fuel to heavy-water-reactors (HWRs), such as the CANDU (registered trade name for the Canadian Deuterium Uranium Reactor). Reuse is an attractive alternative to the current Advanced Fuel Cycle Initiative (AFCI) Global Nuclear Energy Partnership (GNEP) baseline plan, which stores the reprocessed uranium (RU) for an uncertain future or attempts to dispose of it as 'greater-than-Class C' waste. Considering that the open fuel cycle currently deployed in the United States already creates a huge excess quantity of depleted uranium, the closed fuel cycle should enable the recycle of the major components of spent fuel, such as the uranium and the hazardous, long-lived transuranic (TRU) actinides, as well as the managed disposal of fission product wastes. Compared with the GNEP baseline scenario, the reuse of RU in the uranium fuel cycle has a number of potential advantages: (1) avoidance of purchase costs of 11-20% of the natural uranium feed; (2) avoidance of disposal costs for a large majority of the volume of spent fuel that is reprocessed; (3) avoidance of disposal costs for a portion of the depleted uranium from the enrichment step; (4) depending on the {sup 235}U assay of the RU, possible avoidance of separative work costs; and (5) a significant increase in the production of {sup 238}Pu due to the presence of {sup 236}U, which benefits somewhat the transmutation value of the plutonium and also provides some proliferation resistance.

DelCul, Guillermo D [ORNL; Trowbridge, Lee D [ORNL; Renier, John-Paul [ORNL; Ellis, Ronald James [ORNL; Williams, Kent Alan [ORNL; Spencer, Barry B [ORNL; Collins, Emory D [ORNL

2009-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

Fuels, International Nuclear Fuel Cycle Model, ReferenceTable Y-25 continued. Fuel ------> Nuclear Feedstock ------>to plant. 1) For nuclear/uranium, "Fuel production" refers

Delucchi, Mark

2005-01-01T23:59:59.000Z

202

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

Fuels, International Nuclear Fuel Cycle Model, ReferenceTable Y-25 continued. Fuel ------> Nuclear Feedstock ------>to plant. 1) For nuclear/uranium, "Fuel production" refers

Delucchi, Mark

2005-01-01T23:59:59.000Z

203

DIESEL FUEL TANK FOUNDATIONS  

DOE Green Energy (OSTI)

The purpose of this analysis is to design structural foundations for the Diesel Fuel Tank and Fuel Pumps.

M. Gomez

1995-01-18T23:59:59.000Z

204

Sensitivity Analysis of FEAST-Metal Fuel Performance Code: Initial Results  

SciTech Connect

This memo documents the completion of the LANL milestone, M3FT-12LA0202041, describing methodologies and initial results using FEAST-Metal. The FEAST-Metal code calculations for this work are being conducted at LANL in support of on-going activities related to sensitivity analysis of fuel performance codes. The objective is to identify important macroscopic parameters of interest to modeling and simulation of metallic fuel performance. This report summarizes our preliminary results for the sensitivity analysis using 6 calibration datasets for metallic fuel developed at ANL for EBR-II experiments. Sensitivity ranking methodology was deployed to narrow down the selected parameters for the current study. There are approximately 84 calibration parameters in the FEAST-Metal code, of which 32 were ultimately used in Phase II of this study. Preliminary results of this sensitivity analysis led to the following ranking of FEAST models for future calibration and improvements: fuel conductivity, fission gas transport/release, fuel creep, and precipitation kinetics. More validation data is needed to validate calibrated parameter distributions for future uncertainty quantification studies with FEAST-Metal. Results of this study also served to point out some code deficiencies and possible errors, and these are being investigated in order to determine root causes and to improve upon the existing code models.

Edelmann, Paul Guy [Los Alamos National Laboratory; Williams, Brian J. [Los Alamos National Laboratory; Unal, Cetin [Los Alamos National Laboratory; Yacout, Abdellatif [Argonne National Laboratories

2012-06-27T23:59:59.000Z

205

A Second Look at Neutron Resonance Transmission Analysis as a Spent Fuel NDA Technique  

Science Conference Proceedings (OSTI)

Many different nondestructive analysis techniques are currently being investigated as a part of the United States Department of Energy's Next Generation Safeguards Initiative (NGSI) seeking methods to quantify plutonium in spent fuel. Neutron Resonance Transmission Analysis (NRTA) is one of these techniques. Having first been explored in the mid-1970s for the analysis of individual spent-fuel pins a second look, using advanced simulation and modeling methods, is now underway to investigate the suitability of the NRTA technique for assaying complete spent nuclear fuel assemblies. The technique is similar to neutron time-of-flight methods used for cross-section determinations but operates over only the narrow 0.1-20 eV range where strong, distinguishable resonances exist for both the plutonium (239, 240, 241,242Pu) and uranium (235,236,238U) isotopes of interest in spent fuel. Additionally, in this energy range resonances exists for six important fission products (99Tc, 103Rh, 131Xe, 133Cs, 145Nd, and 152Sm) which provide additional information to support spent fuel plutonium assay determinations. Initial modeling shows excellent agreement with previously published experimental data for measurements of individual spent-fuel pins where plutonium assays were demonstrated to have a precision of 2-4%. Within the simulation and modeling analyses of this project scoping studies have explored fourteen different aspects of the technique including the neutron source, drift tube configurations, and gross neutron transmission as well as the impacts of fuel burn up, cooling time, and fission-product interferences. These results show that NRTA may be a very capable experimental technique for spent-fuel assay measurements. The results suggest sufficient transmission strength and signal differentiability is possible for assays through up to 8 pins. For an 8-pin assay (looking at an assembly diagonally), 64% of the pins in a typical 17 ? 17 array of a pressurized water reactor fuel assembly can be part of a complete transmission assay measurement with high precision. Analysis of rows with up to 12 pins may also be feasible but with diminished precision. Preliminary data analysis of an NRTA simulation has demonstrated the simplicity of the technique.

James W .Sterbentz; David L. Chichester

2011-07-01T23:59:59.000Z

206

Lead Slowing-Down Spectrometry Time Spectral Analysis for Spent Fuel Assay: FY12 Status Report  

SciTech Connect

Executive Summary Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R&D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration, of which PNNL is a part, to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive assay method that has the potential to provide independent, direct measurement of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the approximately 10% typical of todays confirmatory methods. This document is a progress report for FY2012 PNNL analysis and algorithm development. Progress made by PNNL in FY2012 continues to indicate the promise of LSDS analysis and algorithms applied to used fuel assemblies. PNNL further refined the semi-empirical model developed in FY2011 based on singular value decomposition (SVD) to numerically account for the effects of self-shielding. The average uncertainty in the Pu mass across the NGSI-64 fuel assemblies was shown to be less than 3% using only six calibration assemblies with a 2% uncertainty in the isotopic masses. When calibrated against the six NGSI-64 fuel assemblies, the algorithm was able to determine the total Pu mass within <2% uncertainty for the 27 diversion cases also developed under NGSI. Two purely empirical algorithms were developed that do not require the use of Pu isotopic fission chambers. The semi-empirical and purely empirical algorithms were successfully tested using MCNPX simulations as well applied to experimental data measured by RPI using their LSDS. The algorithms were able to describe the 235U masses of the RPI measurements with an average uncertainty of 2.3%. Analyses were conducted that provided valuable insight with regard to design requirements (e.g. Pb stack size, neutron source location) of an LSDS for the purpose of assaying used fuel assemblies. Sensitivity studies were conducted that provide insight as to how the LSDS instrument can be improved by making it more sensitive to the center of the fuel assemblies. In FY2013, PNNL will continue efforts to develop and refine design requirements of an LSDS for the ultimate purpose of assaying used fuel assemblies. Future efforts will be directed toward more extensive experimental benchmarking of currently implemented time-spectra analysis algorithms.

Kulisek, Jonathan A.; Anderson, Kevin K.; Casella, Andrew M.; Siciliano, Edward R.; Warren, Glen A.

2012-09-28T23:59:59.000Z

207

Lead Slowing-Down Spectrometry Time Spectral Analysis for Spent Fuel Assay: FY12 Status Report  

Science Conference Proceedings (OSTI)

Executive Summary Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R&D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration, of which PNNL is a part, to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive assay method that has the potential to provide independent, direct measurement of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the approximately 10% typical of todays confirmatory methods. This document is a progress report for FY2012 PNNL analysis and algorithm development. Progress made by PNNL in FY2012 continues to indicate the promise of LSDS analysis and algorithms applied to used fuel assemblies. PNNL further refined the semi-empirical model developed in FY2011 based on singular value decomposition (SVD) to numerically account for the effects of self-shielding. The average uncertainty in the Pu mass across the NGSI-64 fuel assemblies was shown to be less than 3% using only six calibration assemblies with a 2% uncertainty in the isotopic masses. When calibrated against the six NGSI-64 fuel assemblies, the algorithm was able to determine the total Pu mass within Pu isotopic fission chambers. The semi-empirical and purely empirical algorithms were successfully tested using MCNPX simulations as well applied to experimental data measured by RPI using their LSDS. The algorithms were able to describe the 235U masses of the RPI measurements with an average uncertainty of 2.3%. Analyses were conducted that provided valuable insight with regard to design requirements (e.g. Pb stack size, neutron source location) of an LSDS for the purpose of assaying used fuel assemblies. Sensitivity studies were conducted that provide insight as to how the LSDS instrument can be improved by making it more sensitive to the center of the fuel assemblies. In FY2013, PNNL will continue efforts to develop and refine design requirements of an LSDS for the ultimate purpose of assaying used fuel assemblies. Future efforts will be directed toward more extensive experimental benchmarking of currently implemented time-spectra analysis algorithms.

Kulisek, Jonathan A.; Anderson, Kevin K.; Casella, Andrew M.; Siciliano, Edward R.; Warren, Glen A.

2012-09-28T23:59:59.000Z

208

Steady state thermal hydraulic analysis of hydride fueled BWRs  

E-Print Network (OSTI)

(cont.) Since the results obtained in the main body of the analysis account only for thermal-hydraulic constraints, an estimate of the power reduction due to the application of neutronic constraints is also performed. This ...

Ferroni, Paolo, Ph. D. Massachusetts Institute of Technology

2006-01-01T23:59:59.000Z

209

Fuel Cell Technologies Office: DOE Hydrogen Transition Analysis...  

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

Inc. Overview of NEMS-H2, Version 1.0 (PDF 294 KB), Frances Wood, OnLocation, Inc. Agent-Based Modeling and Simulation for Hydrogen Transition Analysis (PDF 515 KB),...

210

DOE Hydrogen and Fuel Cells Program Record 5035: Cost Analysis...  

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

5 Date: May 22, 2006 Title: Cost Analysis of Hydrogen Production from Natural Gas 2003 - 2005 Originator: Patrick Davis Approved by: JoAnn Milliken Approval Date: May 22, 2006 Item...

211

CONTAINMENT ANALYSIS METHODOLOGY FOR TRANSPORT OF BREACHED CLAD ALUMINUM SPENT FUEL  

Science Conference Proceedings (OSTI)

Aluminum-clad, aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site and placed in interim storage in a water basin. To enter the United States, a cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part 71. The requirements include demonstration of containment of the cask with its contents under normal and accident conditions. Many Al-SNF assemblies have suffered corrosion degradation in storage in poor quality water, and many of the fuel assemblies are 'failed' or have through-clad damage. A methodology was developed to evaluate containment of Al-SNF even with severe cladding breaches for transport in standard casks. The containment analysis methodology for Al-SNF is in accordance with the methodology provided in ANSI N14.5 and adopted by the U. S. Nuclear Regulatory Commission in NUREG/CR-6487 to meet the requirements of 10CFR71. The technical bases for the inputs and assumptions are specific to the attributes and characteristics of Al-SNF received from basin and dry storage systems and its subsequent performance under normal and postulated accident shipping conditions. The results of the calculations for a specific case of a cask loaded with breached fuel show that the fuel can be transported in standard shipping casks and maintained within the allowable release rates under normal and accident conditions. A sensitivity analysis has been conducted to evaluate the effects of modifying assumptions and to assess options for fuel at conditions that are not bounded by the present analysis. These options would include one or more of the following: reduce the fuel loading; increase fuel cooling time; reduce the degree of conservatism in the bounding assumptions; or measure the actual leak rate of the cask system. That is, containment analysis for alternative inputs at fuel-specific conditions and at cask-loading-specific conditions could be performed to demonstrate that release is within the allowable leak rates of the cask.

Vinson, D.

2010-07-11T23:59:59.000Z

212

Control-relevant Modelling and Linear Analysis of Instabilities in Oxy-fuel Combustion  

E-Print Network (OSTI)

Control-relevant Modelling and Linear Analysis of Instabilities in Oxy-fuel Combustion Dagfinn combustion have been proposed as an alternative to conventional gas turbine cycles for achieving CO2-capture for CO2 sequestration purposes. While combustion instabilities is a problem in modern conventional gas

Foss, Bjarne A.

213

Radiation Shielding Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)  

Science Conference Proceedings (OSTI)

As a part of the compatibility analysis of DUPIC fuel in Canada deuterium uranium (CANDU) reactors, the radiation physics calculations have been performed for the CANDU primary shielding system, which was originally designed for natural uranium core. At first, the conventional CANDU primary shield analysis method was validated using the Monte Carlo code MCNP-4B in order to assess the current analysis code system and the cross-section data. The computational benchmark calculation was performed for the CANDU end shield system, which has shown that the conventional method produces results consistent with the reference calculations as far as the total dose rate and total heat deposition rate are concerned. Second, the primary shield system analysis was performed for the DUPIC fuel core based on the power distribution obtained from the time-average core model, and the results have shown that the dose rates and heat deposition rates through the primary shield of the DUPIC fuel core are not much different from those of the natural uranium core because the power levels on the core periphery are similar for both cores. This study has shown that the current primary shield system is adaptable for the DUPIC fuel CANDU core without design modification.

Roh, Gyuhong; Choi, Hangbok [Korea Atomic Energy Research Institute (Korea, Republic of)

2004-06-15T23:59:59.000Z

214

Link Analysis of Fuel Laundering Scams and Implications of Results for Scheme Understanding and Prosecutor Strategy  

Science Conference Proceedings (OSTI)

Fuel laundering scam is prevalent in many countries. Typically, a case may concern 100 companies, several hundred people, and up to 100 thousand money transfers/invoices. Analysis of this amount of data is difficult even if it is stored in a database. ...

Czeslaw Jedrzejek; Maciej Falkowski; Maciej Smolenski

2009-07-01T23:59:59.000Z

215

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

E-Print Network (OSTI)

Gas-cooled nuclear reactors have been receiving specific attention for Generation IV possibilities due to desired characteristics such as relatively low cost, short construction period, and inherent safety. Attractive inherent characteristics include an inert, single phase helium coolant, refractory coated fuel with high temperature capability and low fission product release, and graphite moderator with high temperature stability and long response times. The passively safe design has a relatively low power density, annular core, large negative temperature coefficient, and passive decay heat removal system. The objective of the U.S. DOE NERI Project is to assess the possibility, advantages and limitations of achieving ultra-long life VHTR (Very High Temperature Reactor) configurations by utilizing minor actinides as a fuel component. The present analysis takes into consideration and compares capabilities of pebble-bed core designs with various core and reflector configuration to allow spectrum shifting for advanced actinide fuels. Whole-core 3D models for pebble-bed design with multi-heterogeneity treatments in SCALE 5.0 are developed to compare computational results with experiments. Obtained results are in agreement with the available HTR-10 data. By altering the moderator to fuel ratio, a shift in the spectrum is observed. The use of minor actinides as fuel components relies on spectrum shifting capabilities. Actinide fueled VHTR configurations reveal promising performance. With an optimized pebble-bed model, the spectrum shifting abilities are apparent and effects of altered moderator to fuel ratio, and Dancoff factor are investigated. This will lead to a facilitated development of new fuel cycles in support of future operation of Generation IV nuclear energy systems.

Pritchard, Megan; Tsvetkov, Pavel

2009-09-30T23:59:59.000Z

216

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

E-Print Network (OSTI)

Gas-cooled nuclear reactors have been receiving specific attention for Generation IV possibilities due to desired characteristics such as relatively low cost, short construction period, and inherent safety. Attractive inherent characteristics include an inert, single phase helium coolant, refractory coated fuel with high temperature capability and low fission product release, and graphite moderator with high temperature stability and long response times. The passively safe design has a relatively low power density, annular core, large negative temperature coefficient, and passive decay heat removal system. The objective of the U.S. DOE NERI Project is to assess the possibility, advantages and limitations of achieving ultra-long life VHTR (Very High Temperature Reactor) configurations by utilizing minor actinides as a fuel component. The present analysis takes into consideration and compares capabilities of pebble-bed core designs with various core and reflector configuration to allow spectrum shifting for advanced actinide fuels. Whole-core 3D models for pebble-bed design with multi-heterogeneity treatments in SCALE 5.0 are developed to compare computational results with experiments. Obtained results are in agreement with the available HTR-10 data. By altering the moderator to fuel ratio, a shift in the spectrum is observed. The use of minor actinides as fuel components relies on spectrum shifting capabilities. Actinide fueled VHTR configurations reveal promising performance. With an optimized pebble-bed model, the spectrum shifting abilities are apparent and effects of altered moderator to fuel ratio, and Dancoff factor are investigated. This will lead to a facilitated development of new fuel cycles in support of future operation of Generation IV nuclear energy systems.

Pritchard, Megan

2006-07-11T23:59:59.000Z

217

Radiolysis Model Sensitivity Analysis for a Used Fuel Storage Canister  

SciTech Connect

This report fulfills the M3 milestone (M3FT-13PN0810027) to report on a radiolysis computer model analysis that estimates the generation of radiolytic products for a storage canister. The analysis considers radiolysis outside storage canister walls and within the canister fill gas over a possible 300-year lifetime. Previous work relied on estimates based directly on a water radiolysis G-value. This work also includes that effect with the addition of coupled kinetics for 111 reactions for 40 gas species to account for radiolytic-induced chemistry, which includes water recombination and reactions with air.

Wittman, Richard S.

2013-09-20T23:59:59.000Z

218

Analysis of fission gas release in LWR fuel using the BISON code  

SciTech Connect

Recent advances in the development of the finite-element based, multidimensional fuel performance code BISON of Idaho National Laboratory are presented. Specifically, the development, implementation and testing of a new model for the analysis of fission gas behavior in LWR-UO2 fuel during irradiation are summarized. While retaining a physics-based description of the relevant mechanisms, the model is characterized by a level of complexity suitable for application to engineering-scale nuclear fuel analysis and consistent with the uncertainties pertaining to some parameters. The treatment includes the fundamental features of fission gas behavior, among which are gas diffusion and precipitation in fuel grains, growth and coalescence of gas bubbles at grain faces, grain growth and grain boundary sweeping effects, thermal, athermal, and transient gas release. The BISON code incorporating the new model is applied to the simulation of irradiation experiments from the OECD/NEA International Fuel Performance Experiments database, also included in the IAEA coordinated research projects FUMEX-II and FUMEX-III. The comparison of the results with the available experimental data at moderate burn-up is presented, pointing out an encouraging predictive accuracy, without any fitting applied to the model parameters.

G. Pastore; J.D. Hales; S.R. Novascone; D.M. Perez; B.W. Spencer; R.L. Williamson

2013-09-01T23:59:59.000Z

219

Carbon Capture by Fossil Fuel Power Plants: An Economic Analysis  

E-Print Network (OSTI)

capabilities. Our analysis takes explicitly into account that the supply of electricity at the wholesale level an alternative scenario in which utilities procure electric power in a competitive wholesale market, biofuels and afforestation. The overall marginal cost of achieving a particular level of emission

Silver, Whendee

220

Root Cause Analysis of Failed Westinghouse 17OFA Fuel Rod in Callaway  

Science Conference Proceedings (OSTI)

Fuel rod F8 of fuel assembly V36 was identified as leaking during the Callaway Unit 1 EOC-17 core offload in April 2010. V36 was a once-burned assembly that resided in interior core location F-6. According to inspection results of the rod, the root cause analysis (RCA) team initially determined, in mid-2010, that debris fretting or internal primary hydriding was the most probable leaking mechanism. However, the team also recommended additional inspections to assist in the final determination of the leaki...

2012-06-25T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Analysis of Laboratory Fuel Cell Technology Status … Voltage Degradation - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Jennifer Kurtz (Primary Contact), Keith Wipke, Sam Sprik, Genevieve Saur, Huyen Dinh National Renewable Energy Laboratory (NREL) 15013 Denver West Parkway Golden, CO 80401-3305 Phone: (303) 275-4061 Email: jennifer.kurtz@nrel.gov DOE Manager HQ: Kathi Epping Martin Phone: (202) 586-7425 Email: Kathi.Epping@ee.dog.gov Project Start Date: July 1, 2009 Project End Date: Project continuation and direction determined annually by DOE Fiscal Year (FY) 2012 Objectives Conduct an independent assessment to benchmark * state-of-the-art fuel cell durability in a non-proprietary method Leverage analysis experience from the Fuel Cell Electric * Vehicle Learning Demonstration project Collaborate with key fuel cell developers on the analysis

222

Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility  

SciTech Connect

The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable.

Johnson, D.J.; Brehm, J.R.

1994-01-01T23:59:59.000Z

223

Detailed analysis of an endoreversible fuel cell : Maximum power and optimal operating temperature determination  

E-Print Network (OSTI)

Producing useful electrical work in consuming chemical energy, the fuel cell have to reject heat to its surrounding. However, as it occurs for any other type of engine, this thermal energy cannot be exchanged in an isothermal way in finite time through finite areas. As it was already done for various types of systems, we study the fuel cell within the finite time thermodynamics framework and define an endoreversible fuel cell. Considering different types of heat transfer laws, we obtain an optimal value of the operating temperature, corresponding to a maximum produced power. This analysis is a first step of a thermodynamical approach of design of thermal management devices, taking into account performances of the whole system.

A. Vaudrey; P. Baucour; F. Lanzetta; R. Glises

2009-05-18T23:59:59.000Z

224

Detailed analysis of an endoreversible fuel cell : Maximum power and optimal operating temperature determination  

E-Print Network (OSTI)

Producing useful electrical work in consuming chemical energy, the fuel cell have to reject heat to its surrounding. However, as it occurs for any other type of engine, this thermal energy cannot be exchanged in an isothermal way in finite time through finite areas. As it was already done for various types of systems, we study the fuel cell within the finite time thermodynamics framework and define an endoreversible fuel cell. Considering different types of heat transfer laws, we obtain an optimal value of the operating temperature, corresponding to a maximum produced power. This analysis is a first step of a thermodynamical approach of design of thermal management devices, taking into account performances of the whole system.

Vaudrey, A; Lanzetta, F; Glises, R

2009-01-01T23:59:59.000Z

225

Analysis of the Reactor Physics of Low-Enrichment Fuel for the INL Advanced Test Reactor in support of RERTR  

Science Conference Proceedings (OSTI)

Analysis of the performance of the ATR with a LEU fuel design shows promise in terms of a core design that will yield the same neutron sources in target locations. A proposed integral cladding burnable absorber design appears to meet power profile requirements that will satisfy power distributions for safety limits. Performance of this fuel design is ongoing; the current work is the initial evaluation of the core performance of this fuel design with increasing burnup. Results show that LEU fuel may have a longer lifetime that HEU fuel however, such limits may be set by mechanical performance of the fuel rather that available reactivity. Changes seen in the radial fuel power distribution with burnup in LEU fuel will require further study to ascertain the impact on neutron fluxes in target locations. Source terms for discharged fuel have also been studied. By its very nature, LEU fuel produces much more plutonium than is present in HEU fuel at discharge. However, the effect of the plutonium inventory appears to have little affect on radiotoxicity or decay heat in the fuel.

Mark DeHart; William Skerjanc; Sean Morrell

2012-06-01T23:59:59.000Z

226

Technology gap analysis on sodium-cooled reactor fuel handling system supporting advanced burner reactor development.  

Science Conference Proceedings (OSTI)

The goals of the Global Nuclear Energy Partnership (GNEP) are to expand the use of nuclear energy to meet increasing global energy demand in an environmentally sustainable manner, to address nuclear waste management issues without making separated plutonium, and to address nonproliferation concerns. The advanced burner reactor (ABR) is a fast reactor concept which supports the GNEP fuel cycle system. Since the integral fast reactor (IFR) and advanced liquid-metal reactor (ALMR) projects were terminated in 1994, there has been no major development on sodium-cooled fast reactors in the United States. Therefore, in support of the GNEP fast reactor program, the history of sodium-cooled reactor development was reviewed to support the initiation of this technology within the United States and to gain an understanding of the technology gaps that may still remain for sodium fast reactor technology. The fuel-handling system is a key element of any fast reactor design. The major functions of this system are to receive, test, store, and then load fresh fuel into the core; unload from the core; then clean, test, store, and ship spent fuel. Major requirements are that the system must be reliable and relatively easy to maintain. In addition, the system should be designed so that it does not adversely impact plant economics from the viewpoints of capital investment or plant operations. In this gap analysis, information on fuel-handling operating experiences in the following reactor plants was carefully reviewed: EBR-I, SRE, HNPF, Fermi, SEFOR, FFTF, CRBR, EBR-II, DFR, PFR, Rapsodie, Phenix, Superphenix, KNK, SNR-300, Joyo, and Monju. The results of this evaluation indicate that a standardized fuel-handling system for a commercial fast reactor is yet to be established. However, in the past sodium-cooled reactor plants, most major fuel-handling components-such as the rotatable plug, in-vessel fuel-handling machine, ex-vessel fuel transportation cask, ex-vessel sodium-cooled storage, and cleaning stations-have accumulated satisfactory construction and operation experiences. In addition, two special issues for future development are described in this report: large capacity interim storage and transuranic-bearing fuel handling.

Chikazawa, Y.; Farmer, M.; Grandy, C.; Nuclear Engineering Division

2009-03-01T23:59:59.000Z

227

PWR core design, neutronics evaluation and fuel cycle analysis for thorium-uranium breeding recycle  

Science Conference Proceedings (OSTI)

This paper was focused on core design, neutronics evaluation and fuel cycle analysis for Thorium-Uranium Breeding Recycle in current PWRs, without any major change to the fuel lattice and the core internals, but substituting the UOX pellet with Thorium-based pellet. The fuel cycle analysis indicates that Thorium-Uranium Breeding Recycle is technically feasible in current PWRs. A 4-loop, 193-assembly PWR core utilizing 17 x 17 fuel assemblies (FAs) was taken as the model core. Two mixed cores were investigated respectively loaded with mixed reactor grade Plutonium-Thorium (PuThOX) FAs and mixed reactor grade {sup 233}U-Thorium (U{sub 3}ThOX) FAs on the basis of reference full Uranium oxide (UOX) equilibrium-cycle core. The UOX/PuThOX mixed core consists of 121 UOX FAs and 72 PuThOX FAs. The reactor grade {sup 233}U extracted from burnt PuThOX fuel was used to fabrication of U{sub 3}ThOX for starting Thorium-. Uranium breeding recycle. In UOX/U{sub 3}ThOX mixed core, the well designed U{sub 3}ThOX FAs with 1.94 w/o fissile uranium (mainly {sup 233}U) were located on the periphery of core as a blanket region. U{sub 3}ThOX FAs remained in-core for 6 cycles with the discharged burnup achieving 28 GWD/tHM. Compared with initially loading, the fissile material inventory in U{sub 3}ThOX fuel has increased by 7% via 1-year cooling after discharge. 157 UOX fuel assemblies were located in the inner of UOX/U{sub 3}ThOX mixed core refueling with 64 FAs at each cycle. The designed UOX/PuThOX and UOX/U{sub 3}ThOX mixed core satisfied related nuclear design criteria. The full core performance analyses have shown that mixed core with PuThOX loading has similar impacts as MOX on several neutronic characteristic parameters, such as reduced differential boron worth, higher critical boron concentration, more negative moderator temperature coefficient, reduced control rod worth, reduced shutdown margin, etc.; while mixed core with U{sub 3}ThOX loading on the periphery of core has no visible impacts on neutronic characteristics compared with reference full UOX core. The fuel cycle analysis has shown that {sup 233}U mono-recycling with U{sub 3}ThOX fuel could save 13% of natural uranium resource compared with UOX once through fuel cycle, slightly more than that of Plutonium single-recycling with MOX fuel. If {sup 233}U multi-recycling with U{sub 3}ThOX fuel is implemented, more natural uranium resource would be saved. (authors)

Bi, G.; Liu, C.; Si, S. [Shanghai Nuclear Engineering Research and Design Inst., No. 29, Hongcao Road, Shanghai, 200233 (China)

2012-07-01T23:59:59.000Z

228

Analysis of Fuel Cell Vehicle Hybridization and Implications for Energy Storage Devices: June 2004  

DOE Green Energy (OSTI)

This paper addresses the impact of fuel efficiency characteristics on vehicle system efficiency, fuel economy from downsizing different fuel cells, as well as the energy storage system.

Zolot, M.; Markel, T.; Pesaran, A.

2007-01-01T23:59:59.000Z

229

Program on Technology Innovation: Feasibility of Laser-Induced Breakdown Spectroscopy for Fuel Analysis in Gasification Applications  

Science Conference Proceedings (OSTI)

Information on the composition of minerals in fuels and the slagging characteristics of the fuels are important for the efficient operation of gasifiers for power generation. Standard fuel fusibility and viscosity analysis have practical limitations that prevent their being used reliably to control real gasification processes. Recent developments in advanced laser-based methods have confirmed some maturity in technologies that could be used to determine coal elemental composition and properties. A study ...

2011-03-07T23:59:59.000Z

230

DOE/EIS-0218-SA-3: Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program (November 2004)  

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

SUPPLEMENT ANALYSIS FOR THE FOREIGN SUPPLEMENT ANALYSIS FOR THE FOREIGN RESEARCH REACTOR SPENT NUCLEAR FUEL ACCEPTANCE PROGRAM NOVEMBER 2004 DOE/EIS-0218-SA-3 U.S. Department of Energy National Nuclear Security Administration Washington, DC Final Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program Final i TABLE OF CONTENTS Page 1. Introduction.............................................................................................................................................. 1 2. Background .............................................................................................................................................. 1 3. The Proposed Action ...............................................................................................................................

231

Cost Analysis of PEM Fuel Cell Systems for Transportation: September 30, 2005  

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

Subcontract Report Subcontract Report Cost Analysis of PEM Fuel Cell NREL/SR-560-39104 Systems for Transportation December 2005 September 30, 2005 E.J. Carlson, P. Kopf, J. Sinha, S. Sriramulu, and Y. Yang TIAX LLC Cambridge, Massachusetts NREL is operated by Midwest Research Institute ● Battelle Contract No. DE-AC36-99-GO10337 Cost Analysis of PEM Fuel Cell Systems for Transportation September 30, 2005 E.J. Carlson, P. Kopf, J. Sinha, S. Sriramulu, and Y. Yang TIAX LLC Cambridge, Massachusetts NREL Technical Monitor: K. Wipke Prepared under Subcontract No. KACX-5-44452-01 Subcontract Report NREL/SR-560-39104 December 2005 National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov Operated for the U.S. Department of Energy

232

Molten Carbonate and Phosphoric Acid Stationary Fuel Cells: Overview and Gap Analysis  

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

9072 9072 September 2010 Molten Carbonate and Phosphoric Acid Stationary Fuel Cells: Overview and Gap Analysis Robert Remick National Renewable Energy Laboratory Douglas Wheeler DJW Technology, LLC National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy Operated by the Alliance for Sustainable Energy, LLC Contract No. DE-AC36-08-GO28308 Technical Report NREL/TP-560-49072 September 2010 Molten Carbonate and Phosphoric Acid Stationary Fuel Cells: Overview and Gap Analysis Robert Remick National Renewable Energy Laboratory Douglas Wheeler DJW Technology, LLC Prepared under Task No. H278.7210

233

Neutronic Analysis of an Advanced Fuel Design Concept for the High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

This study presents the neutronic analysis of an advanced fuel design concept for the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) that could significantly extend the current fuel cycle length under the existing design and safety criteria. A key advantage of the fuel design herein proposed is that it would not require structural changes to the present HFIR core, in other words, maintaining the same rated power and fuel geometry (i.e., fuel plate thickness and coolant channel dimensions). Of particular practical importance, as well, is the fact that the proposed change could be justified within the bounds of the existing nuclear safety basis. The simulations herein reported employed transport theory-based and exposure-dependent eigenvalue characterization to help improve the prediction of key fuel cycle parameters. These parameters were estimated by coupling a benchmarked three-dimensional MCNP5 model of the HFIR core to the depletion code ORIGEN via the MONTEBURNS interface. The design of an advanced HFIR core with an improved fuel loading is an idea that evolved from early studies by R. D. Cheverton, formerly of ORNL. This study contrasts a modified and increased core loading of 12 kg of 235U against the current core loading of 9.4 kg. The simulations performed predict a cycle length of 39 days for the proposed fuel design, which represents a 50% increase in the cycle length in response to a 25% increase in fissile loading, with an average fuel burnup increase of {approx}23%. The results suggest that the excess reactivity can be controlled with the present design and arrangement of control elements throughout the core's life. Also, the new power distribution is comparable or even improved relative to the current power distribution, displaying lower peak to average fission rate densities across the inner fuel element's centerline and bottom cells. In fact, the fission rate density in the outer fuel element also decreased at these key locations for the proposed design. Overall, it is estimated that the advanced core design could increase the availability of the HFIR facility by {approx}50% and generate {approx}33% more neutrons annually, which is expected to yield sizeable savings during the remaining life of HFIR, currently expected to operate through 2014. This study emphasizes the neutronics evaluation of a new fuel design. Although a number of other performance parameters of the proposed design check favorably against the current design, and most of the core design features remain identical to the reference, it is acknowledged that additional evaluations would be required to fully justify the thermal-hydraulic and thermal-mechanical performance of a new fuel design, including checks for cladding corrosion performance as well as for industrial and economic feasibility.

Xoubi, Ned [ORNL; Primm, Trent [ORNL; Maldonado, G. Ivan [University of Tennessee, Knoxville (UTK)

2009-01-01T23:59:59.000Z

234

Improvement of the Post-Blowdown Fuel Channel Analysis Model of Candu for a 35% RIH Break LOCA Without ECC  

SciTech Connect

A CATHENA model for a post-blowdown fuel channel analysis has been improved from an existing one for a Candu-6 reactor, and the analysis for a RIH 35% LBLOCA/LOECC has been performed. The results for the blowdown and post blowdown analyses show that the post blowdown model and its connection with the blowdown analysis model is successfully implemented. Also the 3-D CFD model for the fluid flow and heat transfer in the Candu fuel channel, is being developed for the post blowdown fuel channel heatup experiment CS28-1 using CFX 5.6 and its recent progress is described. (authors)

Rhee, B. W.; Kang, H.S.; Min, B.J. [Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-600 (Korea, Republic of)

2004-07-01T23:59:59.000Z

235

Analysis of the Social, Economic, and Environmental Effects of Replacing Petroleum-Based Fuels with Biodiesel Fuels.  

E-Print Network (OSTI)

??Purpose of the Study: Biofuels are a category of alternative fuels derived from organic matter. Biodiesel, a lipid oil-based biofuel, is produced from oilseed crops. (more)

Johnson, Shirley J.

2008-01-01T23:59:59.000Z

236

Data Collection for Class-8 Long-Haul Operations and Fuel Economy Analysis  

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

Long-Haul Long-Haul Operations and Fuel Economy Analysis A s part of a long-term study sponsored by the U.S. Department of Energy (DOE) Office of Vehicle Technologies (OVT), the Oak Ridge National Laboratory (ORNL) in conjunction with a number of industry partners (Michelin Americas Research Company - Michelin), have collected data and information related to Class-8 heavy truck long-haul operations in real-world

237

DOE and FreedomCAR & Fuel Partnership Analysis Workshop U.S. Department of Energy -Washington, DC  

E-Print Network (OSTI)

that software, math, and assumptions are consistent. o What should we use as the standard electric grid mixDOE and FreedomCAR & Fuel Partnership Analysis Workshop U.S. Department of Energy - Washington, DC-board storage needs will depend on forecourt station fueling profiles, weekday-to-weekend and summer

238

Cost probability analysis of reprocessing spent nuclear fuel in the US G.D. Recktenwald, M.R. Deinert  

E-Print Network (OSTI)

to the sustainability of nuclear power while others argue against them on economic, environmental and security groundsCost probability analysis of reprocessing spent nuclear fuel in the US G.D. Recktenwald, M P48 Keywords: Reprocessing Nuclear power Spent fuel The methods by which nuclear power's radioactive

Deinert, Mark

239

Economic and Nonproliferation Analysis Framework for Assessing Reliable Nuclear Fuel Service Arrangements  

Science Conference Proceedings (OSTI)

Nuclear power is now broadly recognized as an essential technology in national strategies to provide energy security while meeting carbon management goals. Yet a long standing conundrum remains: how to enable rapid growth in the global nuclear power infrastructure while controlling the spread of sensitive enrichment and reprocessing technologies that lie at the heart of nuclear fuel supply and nuclear weapons programs. Reducing the latent proliferation risk posed by a broader horizontal spread of enrichment and reprocessing technology has been a primary goal of national nuclear supplier policies since the beginning of the nuclear power age. Attempts to control the spread of sensitive nuclear technology have been the subject of numerous initiatives in the intervening decades sometimes taking the form of calls to develop fuel supply and service assurances to reduce market pull to increase the number of states with fuel cycle capabilities. A clear understanding of what characteristics of specific reliable nuclear fuel service (RNFS) and supply arrangements qualify them as 'attractive offers' is critical to the success of current and future efforts. At a minimum, RNFS arrangements should provide economic value to all participants and help reduce latent proliferation risks posed by the global expansion of nuclear power. In order to inform the technical debate and the development of policy, Pacific Northwest National Laboratory has been developing an analytical framework to evaluate the economics and nonproliferation merits of alternative approaches to RNFS arrangements. This paper provides a brief overview of the economic analysis framework developed and applied to a model problem of current interest: full-service nuclear fuel leasing arrangements. Furthermore, this paper presents an extended outline of a proposed analysis approach to evaluate the non-proliferation merits of various RNFS alternatives.

Phillips, Jon R.; Kreyling, Sean J.; Short, Steven M.; Weimar, Mark R.

2010-04-14T23:59:59.000Z

240

North Portal Fuel Storage System Fire Hazard Analysis-ESF Surface Design Package ID  

SciTech Connect

The purpose of the fire hazard analysis is to comprehensively assess the risk from fire within the individual fire areas. This document will only assess the fire hazard analysis within the Exploratory Studies Facility (ESF) Design Package ID, which includes the fuel storage system area of the North Portal facility, and evaluate whether the following objectives are met: 1.1.1--This analysis, performed in accordance with the requirements of this document, will satisfy the requirements for a fire hazard analysis in accordance with U.S. Department of Energy (DOE) Order 5480.7A. 1.1.2--Ensure that property damage from fire and related perils does not exceed an acceptable level. 1.1.3--Provide input to the ESF Basis For Design (BFD) Document. 1.1.4 Provide input to the facility Safety Analysis Report (SAR) (Paragraph 3.8).

N.M. Ruonavaara

1995-01-18T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Thermo-Mechanical Analysis of Coated Particle Fuel Experiencing a Fast Control Rod Ejection Transient  

SciTech Connect

A rapid increase of the temperature and the mechanical stress is expected in TRISO coated particle fuel that experiences a fast Total Control Rod Ejection (CRE) transient event. During this event the reactor power in the pebble bed core increases significantly for a short time interval. The power is deposited instantly and locally in the fuel kernel. This could result in a rapid increase of the pressure in the buffer layer of the coated fuel particle and, consequently, in an increase of the coating stresses. These stresses determine the mechanical failure probability of the coatings, which serve as the containment of radioactive fission products in the Pebble Bed Reactor (PBR). A new calculation procedure has been implemented at the Idaho National Laboratory (INL), which analyzes the transient fuel performance behavior of TRISO fuel particles in PBRs. This early capability can easily be extended to prismatic designs, given the availability of neutronic and thermal-fluid solvers. The full-core coupled neutronic and thermal-fluid analysis has been modeled with CYNOD-THERMIX. The temperature fields for the fuel kernel and the particle coatings, as well as the gas pressures in the buffer layer, are calculated with the THETRIS module explicitly during the transient calculation. Results from this module are part of the feedback loop within the neutronic-thermal fluid iterations performed for each time step. The temperature and internal pressure values for each pebble type in each region of the core are then input to the PArticle STress Analysis (PASTA) code, which determines the particle coating stresses and the fraction of failed particles. This paper presents an investigation of a Total Control Rod Ejection (TCRE) incident in the 400 MWth Pebble Bed Modular reactor design using the above described calculation procedure. The transient corresponds to a reactivity insertion of $3 (~2000 pcm) reaching 35 times the nominal power in 0.5 seconds. For each position in the core the coated particle temperature and the stress history during a TCRE transient has been computed and the fuel failure probability has been quantified.

Ortensi, J.; Brian Boer; Abderrafi M. Ougouag

2010-10-01T23:59:59.000Z

242

Analysis of the risk of transporting spent nuclear fuel by train  

SciTech Connect

This report uses risk analyses to analyze the safety of transporting spent nuclear fuel for commercial rail shipping systems. The rail systems analyzed are those expected to be used in the United States when the total electricity-generating capacity by nuclear reactors is 100 GW in the late 1980s. Risk as used in this report is the product of the probability of a release of material to the environment and the consequences resulting from the release. The analysis includes risks in terms of expected fatalities from release of radioactive materials due to transportation accidents involving PWR spent fuel shipped in rail casks. The expected total risk from such shipments is 1.3 x 10/sup -4/ fatalities per year. Risk spectrums are developed for shipments of spent fuel that are 180 days and 4 years out-of-reactor. The risk from transporting spent fuel by train is much less (by 2 to 4 orders of magnitude) than the risk to society from other man-caused events such as dam failure.

Elder, H.K.

1981-09-01T23:59:59.000Z

243

A full fuel-cycle analysis of energy and emissions impacts of transportation fuels produced from natural gas  

DOE Green Energy (OSTI)

Because of its abundance and because it offers significant energy and evironmental advantages, natural gas has been promoted for use in motor vehicles. A number of transportation fuels are produced from natural gas; each is distinct in terms of upstream production activities and vehicle usage. In this study, the authors avaluate eight fuels produced from natural gas - compressed natural gas, liquefied petroleum gas, methanol, hydrogen, dimethyl ether, Fischer-Tropsch diesel, and electricity--for use in five types of motor vehicles--spark-ignition vehicles, compression-ignition vehicles, hybrid electric vehicles, battery-powered electric vehicles, and fuel-cell vehicles. Because of great uncertainties associated with advances both in fuel production and vehicle technologies, they evaluate near-term and long-term fuels and vehicle technologies separately. Furthermore, for long-term options, they establish both an incremental technology scenario and a leap-forward technology scenario to address potential technology improvements. The study reveals that, in general, the use of natural gas-based fuels reduces energy use and emissions relative to use of petroleum-based gasoline and diesel fuel, although different natural gas-based fuels in different vehicle technologies can have significantly different energy and emissions impacts.

Wang, M.Q.; Huang, H.S.

2000-01-25T23:59:59.000Z

244

Results of the MCNP analysis of 20/20 LEU fuel for the Oregon State University TRIGA reactor  

SciTech Connect

The Monte Carlo Neutron/Photon (MCNP) code has been used to perform the neutronics analysis required to support revision of the Oregon State University TRIGA Reactor (OSTR) Safety Analysis Report (SAR). The SAR revision is a necessary part of the preparation of the application for authorization to convert the OSTR core from High Enriched Uranium (HEU) FLIP fuel to a Low Enriched Uranium (LEU) fuel. Before MCNP was applied to LEU-fueled cores, it was first validated by comparing MCNP calculations on FLIP cores to historical, measured values for these cores. The LEU fuel considered was the 20 wt%, 20 % enriched (20/20) TRIGA fuel approved by the Nuclear Regulatory Commission (NRC) in NUREG 1282. The results show that the 20/20 fuel is much more reactive than FLIP fuel. A just-critical OSTR FLIP core contains 65 elements, while a just-critical 20/20 core only needs 51 elements. Similarly, the current operational FLIP core consists of 88 elements, whereas a 20/20 core giving the same core excess only requires 65 elements. This presents a significant problem for the OSTR because of potentially significant neutron flux loss in experimental facilities. Further analysis shows that to achieve a full size operational core of about 90 LEU elements the erbium content of the LEU fuel would need to be increased from 0.47 wt% to about 0.85 wt%. (author)

Dodd, B.; Klein, A.C.; Lewis, B.R.; Merritt, P.A

1994-07-01T23:59:59.000Z

245

Evaluation of methods for seismic analysis of mixed-oxide fuel fabrication plants  

SciTech Connect

Guidelines are needed for selecting appropriate methods of structural analyses to evaluate the seismic hazard of mixed-oxide fuel fabrication plants. This study examines the different available methods and their applicability to fabrication plants. These results should provide a basis for establishing guidelines recommending methods of analysis to ensure safe design against seismic hazards. Using the Westinghouse Recycle Fuels Plant as representative of future mixed-oxide fuel fabrication plants, critical structures and equipment (systems, components, and piping/ducting) were identified. These included the manufacturing building and 11 different pieces of equipment. After examination of the dynamic response characteristics of the building and the different methods available to analyze equipment, appropriate methods of analyses were recommended. Because critical equipment analysis and test methods generally use floor-response spectra as their seismic input loading, several methods used to generate floor spectra were also examined. These include the time-history approach and the Kapur and Biggs approximate methods. The examination included the effect of site characteristics and both horizontal and vertical structural response. (auth)

Tokarz, F.J.; Arthur, D.F.; Murray, R.C.

1975-10-01T23:59:59.000Z

246

Further Evaluation of the Neutron Resonance Transmission Analysis (NRTA) Technique for Assaying Plutonium in Spent Fuel  

Science Conference Proceedings (OSTI)

This is an end-of-year report (Fiscal Year (FY) 2011) for the second year of effort on a project funded by the National Nuclear Security Administration's Office of Nuclear Safeguards (NA-241). The goal of this project is to investigate the feasibility of using Neutron Resonance Transmission Analysis (NRTA) to assay plutonium in commercial light-water-reactor spent fuel. This project is part of a larger research effort within the Next-Generation Safeguards Initiative (NGSI) to evaluate methods for assaying plutonium in spent fuel, the Plutonium Assay Challenge. The second-year goals for this project included: (1) assessing the neutron source strength needed for the NRTA technique, (2) estimating count times, (3) assessing the effect of temperature on the transmitted signal, (4) estimating plutonium content in a spent fuel assembly, (5) providing a preliminary assessment of the neutron detectors, and (6) documenting this work in an end of the year report (this report). Research teams at Los Alamos National Laboratory (LANL), Lawrence Berkeley National Laboratory (LBNL), Pacific Northwest National Laboratory (PNNL), and at several universities are also working to investigate plutonium assay methods for spent-fuel safeguards. While the NRTA technique is well proven in the scientific literature for assaying individual spent fuel pins, it is a newcomer to the current NGSI efforts studying Pu assay method techniques having just started in March 2010; several analytical techniques have been under investigation within this program for two to three years or more. This report summarizes work performed over a nine month period from January-September 2011 and is to be considered a follow-on or add-on report to our previous published summary report from December 2010 (INL/EXT-10-20620).

J. W. Sterbentz; D. L. Chichester

2011-09-01T23:59:59.000Z

247

DOE Hydrogen and Fuel Cells Program Record 6002: Electrolysis Analysis to Support Technical Targets  

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

Record #: 6002 Date: September 28, 2006 Title: Electrolysis Analysis to Support Technical Targets Originator: Roxanne Garland Approved by: Sunita Satyapal Date: December 16, 2008 Distributed Water Electrolysis - Technical Targets. Item #1: Table 3.1.4 and Table 3.1.4A in the Hydrogen, Fuel Cells & Infrastructure Technologies Program Multi-Year Research, Development and Demonstration Plan. This Record provides further information vis-à-vis the assumptions and corresponding references used in Table 3.1.4 "Technical Targets: Distributed Water Electrolysis Hydrogen Production" and Table 3.1.4A "Distributed Electrolysis H2A Example Cost Contributions" in the Hydrogen, Fuel Cells & Infrastructure Technologies Program Multi-Year Research,

248

Techno-Economic Analysis of Biomass Fast Pyrolysis to Transportation Fuels  

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

Biomass Fast Pyrolysis to Biomass Fast Pyrolysis to Transportation Fuels Mark M. Wright, Justinus A. Satrio, and Robert C. Brown Iowa State University Daren E. Daugaard ConocoPhillips Company David D. Hsu National Renewable Energy Laboratory Technical Report NREL/TP-6A20-46586 November 2010 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No. DE-AC36-08GO28308 Techno-Economic Analysis of Biomass Fast Pyrolysis to Transportation Fuels Mark M. Wright, Justinus A. Satrio, and Robert C. Brown Iowa State University

249

Synthesis and Analysis of Alpha Silicon Carbide Components for Encapsulation of Fuel Rods and Pellets  

Science Conference Proceedings (OSTI)

The chemical, mechanical and thermal properties of silicon carbide (SiC) along with its low neutron activation and stability in a radiation field make it an attractive material for encapsulating fuel rods and fuel pellets. The alpha phase (6H) is particularly stable. Unfortunately, it requires very high temperature processing and is not readily available in fibers or near-net shapes. This paper describes an investigation to fabricate a-SiC as thin films, fibers and near-net-shape products by direct conversion of carbon using silicon monoxide vapor at temperatures less than 1700 C. In addition, experiments to nucleate the alpha phase during pyrolysis of polysilazane, are also described. Structure and composition were characterized using scanning electron microscopy, energy dispersive spectroscopy and X-ray diffraction. Preliminary tensile property analysis of fibers was also performed.

Kevin M. McHugh; John E. Garnier; George W. Griffith

2011-09-01T23:59:59.000Z

250

Benefits analysis for the production of fuels and chemicals using solar thermal energy. Final report  

DOE Green Energy (OSTI)

Numerous possibilities exist for using high temperature solar thermal energy in the production of various chemicals and fuels (Sun Fuels). Research and development activities have focused on the use of feedstocks such as coal and biomass to provide synthesis gas, hydrogen, and a variety of other end-products. A Decision Analysis technique geared to the analysis of Sun Fuels options was developed. Conventional scoring methods were combined with multi-attribute utility analysis in a new approach called the Multi-Attribute Preference Scoring (MAPS) system. MAPS calls for the designation of major categories of attributes which describe critical elements of concern for the processes being examined. The six major categories include: Process Demonstration; Full-Scale Process, Feedstock; End-Product Market; National/Social Considerations; and Economics. MAPS calls for each attribute to be weighted on a simple scale for all of the candidate processes. Next, a weight is assigned to each attribute, thus creating a multiplier to be used with each individual value to derive a comparative weighting. Last, each of the categories of attributes themselves are weighted, thus creating another multiplier, for use in developing an overall score. With sufficient information and industry input, each process can be ultimately compared using a single figure of merit. After careful examination of available information, it was decided that only six of the 20 candidate processes were adequately described to allow a complete MAPS analysis which would allow direct comparisons for illustrative purposes. These six processes include three synthesis gas processes, two hydrogen and one ammonia. The remaining fourteen processes were subjected to only a partial MAPS assessment.

None

1982-05-01T23:59:59.000Z

251

Issues in Three-Dimensional Depletion Analysis of Measured Data Near the End of a Fuel Rod  

Science Conference Proceedings (OSTI)

The dynamics of reactor operation result in nonuniform axial-burnup profiles in fuel with any significant burnup. At the beginning of life in a pressurized water reactor (PWR), a near-cosine axial-shaped flux will begin depleting fuel near the axial center of a fuel assembly at a greater rate than at the ends. As the reactor continues to operate, the cosine flux shape will flatten because of the fuel depletion and fission-product buildup that occur near the center. However, because of the high leakage near the end of the fuel assembly, burnup will drop off rapidly near the ends. Partial-length absorbers or nonuniform axial fuel loadings can further complicate the burnup profile. In a boiling water reactor, the same phenomena come into play, but the burnup profile is complicated by the significant variation of axial moderator density and by nonuniform axial loadings of burnable poison rods. Numerous studies of axial burnup effects have been published. However, most analyses performed in estimation of isotopic distributions due to axial burnup have been based on a set of two-dimensional (2-D) calculations performed for burnups that represent the axial burnup distribution in a fuel assembly. In general, this approach works quite well because the in-core axial gradient of the neutron flux is small over most of the length of the fuel rod, and the 2-D approximation is appropriate. Conversely, because the axial gradient becomes significant as one approaches either end of the fuel assembly, the 2-D approximation begins to break down at that point. It has been theorized that axial leakage will lead to a reduced fast flux relative to the thermal flux, softening the spectrum near the ends of the fuel, and that a 2-D approximation is conservative in that it provides more plutonium production. This has not been put the test, however, for two reasons--a lack of good three-dimensional (3-D) analysis methods acceptable for away-from-reactor applications and, more importantly, a scarcity of experimental measurements for fuel taken from the end regions of a fuel rod. A number of 3-D depletion approaches based on Monte Carlo methods have been introduced in the past decade including, but not limited to, those listed in Refs. 5-7. A full listing would be quite extensive. Recent fuel-sample measurements from two discharged assemblies of the Takahama Unit 3 PWR provide data for fuel samples taken very close to the top of the active region of the fuel rod. This paper discusses results of TRITON-based 3-D depletion calculations completed in the analysis of the Takahama fuel samples.

DeHart, Mark D [ORNL; Gauld, Ian C [ORNL; Suyama, Kenya [Japan Atomic Energy Agency (JAEA)

2008-01-01T23:59:59.000Z

252

An Econometric Analysis of the Elasticity of Vehicle Travel with Respect to Fuel Cost per Mile Using RTEC Survey Data  

Science Conference Proceedings (OSTI)

This paper presents the results of econometric estimation of the ''rebound effect'' for household vehicle travel in the United States based on a comprehensive analysis of survey data collected by the U.S. Energy Information Administration (EIA) at approximately three-year intervals over a 15-year period. The rebound effect is defined as the percent change in vehicle travel for a percent change in fuel economy. It summarizes the tendency to ''take back'' potential energy savings due to fuel economy improvements in the form of increased vehicle travel. Separate vehicles use models were estimated for one-, two-, three-, four-, and five-vehicle households. The results are consistent with the consensus of recently published estimates based on national or state-level data, which show a long-run rebound effect of about +0.2 (a ten percent increase in fuel economy, all else equal, would produce roughly a two percent increase in vehicle travel and an eight percent reduction in fuel use). The hypothesis that vehicle travel responds equally to changes in fuel cost-per-mile whether caused by changes in fuel economy or fuel price per gallon could not be rejected. Recognizing the interdependency in survey data among miles of travel, fuel economy and price paid for fuel for a particular vehicle turns out to be crucial to obtaining meaningful results.

Greene, D.L.; Kahn, J.; Gibson, R.

1999-03-01T23:59:59.000Z

253

A finite element analysis modeling tool for solid oxide fuel cell development: coupled electrochemistry, thermal and flow analysis in MARC  

Science Conference Proceedings (OSTI)

A 3D simulation tool for modeling solid oxide fuel cells is described. The tool combines the versatility and efficiency of a commercial finite element analysis code, MARC{reg_sign}, with an in-house developed robust and flexible electrochemical (EC) module. Based upon characteristic parameters obtained experimentally and assigned by the user, the EC module calculates the current density distribution, heat generation, and fuel and oxidant species concentration, taking the temperature profile provided by MARC{reg_sign} and operating conditions such as the fuel and oxidant flow rate and the total stack output voltage or current as the input. MARC{reg_sign} performs flow and thermal analyses based on the initial and boundary thermal and flow conditions and the heat generation calculated by the EC module. The main coupling between MARC{reg_sign} and EC is for MARC{reg_sign} to supply the temperature field to EC and for EC to give the heat generation profile to MARC{reg_sign}. The loosely coupled, iterative scheme is advantageous in terms of memory requirement, numerical stability and computational efficiency. The coupling is iterated to self-consistency for a steady-state solution. Sample results for steady states as well as the startup process for stacks with different flow designs are presented to illustrate the modeling capability and numerical performance characteristic of the simulation tool.

Khaleel, Mohammad A.; Lin, Zijing; Singh, Prabhakar; Surdoval, Wayne; Collin, D

2004-05-03T23:59:59.000Z

254

A Low-Carbon Fuel Standard for California, Part 1: Technical Analysis  

E-Print Network (OSTI)

UCDITSRR0707 A Low-Carbon Fuel Standard for CaliforniaEnergy Commission. A Low Carbon Fuel Standard For CaliforniaCalifornia, Davis. A Low Carbon Fuel Standard For California

Farrell, Alexander; Sperling, Daniel

2007-01-01T23:59:59.000Z

255

A Low-Carbon Fuel Standard for California Part 1: Technical Analysis  

E-Print Network (OSTI)

A Low-Carbon Fuel Standard for California Part 1: TechnicalOrder S-01-07: Low Carbon Fuel Standard. Sacramento, CA.California, Davis. A Low Carbon Fuel Standard For California

2007-01-01T23:59:59.000Z

256

Molten Carbonate and Phosphoric Acid Stationary Fuel Cells: Overview and Gap Analysis  

Fuel Cell Technologies Publication and Product Library (EERE)

This report details technical and cost gap analyses of molten carbonate fuel cell and phosphoric acid fuel cell stationary fuel cell power plants and identifies pathways for reducing costs.

257

Techno-Economic Analysis of Biomass Fast Pyrolysis to Transportation Fuels  

SciTech Connect

This study develops techno-economic models for assessment of the conversion of biomass to valuable fuel products via fast pyrolysis and bio-oil upgrading. The upgrading process produces a mixture of naphtha-range (gasoline blend stock) and diesel-range (diesel blend stock) products. This study analyzes the economics of two scenarios: onsite hydrogen production by reforming bio-oil, and hydrogen purchase from an outside source. The study results for an nth plant indicate that petroleum fractions in the naphtha distillation range and in the diesel distillation range are produced from corn stover at a product value of $3.09/gal ($0.82/liter) with onsite hydrogen production or $2.11/gal ($0.56/liter) with hydrogen purchase. These values correspond to a $0.83/gal ($0.21/liter) cost to produce the bio-oil. Based on these nth plant numbers, product value for a pioneer hydrogen-producing plant is about $6.55/gal ($1.73/liter) and for a pioneer hydrogen-purchasing plant is about $3.41/gal ($0.92/liter). Sensitivity analysis identifies fuel yield as a key variable for the hydrogen-production scenario. Biomass cost is important for both scenarios. Changing feedstock cost from $50-$100 per short ton changes the price of fuel in the hydrogen production scenario from $2.57-$3.62/gal ($0.68-$0.96/liter).

Wright, M. M.; Satrio, J. A.; Brown, R. C.; Daugaard, D. E.; Hsu, D. D.

2010-11-01T23:59:59.000Z

258

Sampling and analysis plan for the preoperational environmental survey of the spent nuclear fuel project facilities  

Science Conference Proceedings (OSTI)

This sampling and analysis plan will support the preoperational environmental monitoring for construction, development, and operation of the Spent Nuclear Fuel (SNF) Project facilities, which have been designed for the conditioning and storage of spent nuclear fuels; particularly the fuel elements associated with the operation of N-Reactor. The SNF consists principally of irradiated metallic uranium, and therefore includes plutonium and mixed fission products. The primary effort will consist of removing the SNF from the storage basins in K East and K West Areas, placing in multicanister overpacks, vacuum drying, conditioning, and subsequent dry vault storage in the 200 East Area. The primary purpose and need for this action is to reduce the risks to public health and safety and to the environment. Specifically these include prevention of the release of radioactive materials into the air or to the soil surrounding the K Basins, prevention of the potential migration of radionuclides through the soil column to the nearby Columbia River, reduction of occupational radiation exposure, and elimination of the risks to the public and to workers from the deterioration of SNF in the K Basins.

MITCHELL, R.M.

1999-04-01T23:59:59.000Z

259

High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor  

SciTech Connect

The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450MWth DB-HTRs. The TRISO fuel microanalysis covers the gas pressure buildup in a coated fuel particle including helium production, the thermo-mechanical behavior of a CFP, the failure probabilities of CFPs, the temperature distribution in a CPF, and the fission product (FP) transport in a CFP and a graphite. In Chapter VIII, it contains the core design and analysis of sodium cooled fast reactor (SFR) with deep burn HTR reactor. It considers a synergistic combination of the DB-MHR and an SFR burner for a safe and efficient transmutation of the TRUs from LWRs. Chapter IX describes the design and analysis results of the self-cleaning (or self-recycling) HTR core. The analysis is considered zero and 5-year cooling time of the spent LWR fuels.

Francesco Venneri; Chang-Keun Jo; Jae-Man Noh; Yonghee Kim; Claudio Filippone; Jonghwa Chang; Chris Hamilton; Young-Min Kim; Ji-Su Jun; Moon-Sung Cho; Hong-Sik Lim; MIchael A. Pope; Abderrafi M. Ougouag; Vincent Descotes; Brian Boer

2010-09-01T23:59:59.000Z

260

CASMO5/TSUNAMI-3D spent nuclear fuel reactivity uncertainty analysis  

Science Conference Proceedings (OSTI)

The CASMO5 lattice physics code is used in conjunction with the TSUNAMI-3D sequence in ORNL's SCALE 6 code system to estimate the uncertainties in hot-to-cold reactivity changes due to cross-section uncertainty for PWR assemblies at various burnup points. The goal of the analysis is to establish the multiplication factor uncertainty similarity between various fuel assemblies at different conditions in a quantifiable manner and to obtain a bound on the hot-to-cold reactivity uncertainty over the various assembly types and burnup attributed to fundamental cross-section data uncertainty. (authors)

Ferrer, R.; Rhodes, J. [Studsvik Scandpower, Inc., 504 Shoup Ave., Idaho Falls, ID 83402 (United States); Smith, K. [Dept. of Nuclear Science and Engineering, Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139 (United States)

2012-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Fuel Cycle Analysis Framework Base Cases for the IAEA/INPRO GAINS Collaborative Project  

SciTech Connect

Thirteen countries participated in the Collaborative Project GAINS Global Architecture of Innovative Nuclear Energy Systems Based on Thermal and Fast Reactors Including a Closed Fuel Cycle, which was the primary activity within the IAEA/INPRO Program Area B: Global Vision on Sustainable Nuclear Energy for the last three years. The overall objective of GAINS was to develop a standard framework for assessing future nuclear energy systems taking into account sustainable development, and to validate results through sample analyses. This paper details the eight scenarios that constitute the GAINS framework base cases for analysis of the transition to future innovative nuclear energy systems. The framework base cases provide a reference for users of the framework to start from in developing and assessing their own alternate systems. Each base case is described along with performance results against the GAINS sustainability evaluation metrics. The eight cases include four using a moderate growth projection and four using a high growth projection for global nuclear electricity generation through 2100. The cases are divided into two sets, addressing homogeneous and heterogeneous scenarios developed by GAINS to model global fuel cycle strategies. The heterogeneous world scenario considers three separate nuclear groups based on their fuel cycle strategies, with non-synergistic and synergistic cases. The framework base case analyses results show the impact of these different fuel cycle strategies while providing references for future users of the GAINS framework. A large number of scenario alterations are possible and can be used to assess different strategies, different technologies, and different assumptions about possible futures of nuclear power. Results can be compared to the framework base cases to assess where these alternate cases perform differently versus the sustainability indicators.

Brent Dixon

2012-09-01T23:59:59.000Z

262

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

from Transportation Fuels, Motor Vehicles, Transportationfrom alternative fuels for motor vehicles and electricity-Environmental Externalities of Motor-Vehicle Use in the U.

Delucchi, Mark

2005-01-01T23:59:59.000Z

263

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

from Transportation Fuels, Motor Vehicles, Transportationfrom alternative fuels for motor vehicles and electricity-Environmental Externalities of Motor-Vehicle Use in the U.

Delucchi, Mark

2005-01-01T23:59:59.000Z

264

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

methanol, nuclear, and hydro power plants, individually orvehicles]) H = Hydro power (% of electricity generation [power plant fuel. Coal Fuel oil NG/ boiler NG/ turbine Nuclear* Biomass Hydro*

Delucchi, Mark

2005-01-01T23:59:59.000Z

265

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

methanol, nuclear, and hydro power plants, individually orvehicles]) H = Hydro power (% of electricity generation [power plant fuel. Coal Fuel oil NG/ boiler NG/ turbine Nuclear* Biomass Hydro*

Delucchi, Mark

2005-01-01T23:59:59.000Z

266

Early Market TRL/MRL Analysis - DOE Hydrogen and Fuel Cells Program...  

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

2011a. The Department of Energy Hydrogen and Fuel Cells Program Plan - An Integrated Strategic Plan for the Research, Development and Demonstration of Hydrogen and Fuel Cell...

267

Fuel cycle design and analysis of SABR: subrcritical advanced burner reactor.  

E-Print Network (OSTI)

??Various fuel cycles for a sodium-cooled, subcritical, fast reactor with a fusion neutron source for the transmutation of light water reactor spent fuel have been (more)

Sommer, Christopher

2008-01-01T23:59:59.000Z

268

Overview of An Analysis Project for Renewable Biogas / Fuel Cell Technologies (Presentation)  

DOE Green Energy (OSTI)

Presentation on renewable biogas: as an opportunity for commercialization of fuel cells presented as part of a panel discussion at the 2009 Fuel Cell Seminar, Palm Springs, CA.

Jalalzadeh-Azar, A.

2009-11-19T23:59:59.000Z

269

Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - III: Spent DUPIC Fuel Disposal Cost  

Science Conference Proceedings (OSTI)

The disposal costs of spent pressurized water reactor (PWR), Canada deuterium uranium (CANDU) reactor, and DUPIC fuels have been estimated based on available literature data and the engineering design of a spent CANDU fuel disposal facility by the Atomic Energy of Canada Limited. The cost estimation was carried out by the normalization concept of total electricity generation. Therefore, the future electricity generation scale was analyzed to evaluate the appropriate capacity of the high-level waste disposal facility in Korea, which is a key parameter of the disposal cost estimation. Based on the total electricity generation scale, it is concluded that the disposal unit costs for spent CANDU natural uranium, CANDU-DUPIC, and PWR fuels are 192.3, 388.5, and 696.5 $/kg heavy element, respectively.

Ko, Won Il; Choi, Hangbok; Roh, Gyuhong; Yang, Myung Seung [Korea Atomic Energy Research Institute (Korea, Republic of)

2001-05-15T23:59:59.000Z

270

Hydrogen and Fuel Cells R&D  

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

Liquids --Hydrogen Storage Materials --Hydrogen Storage Systems Modeling and Analysis --Thermochemical Hydrogen * Fuel Cells --Polymer Electrolyte --Modeling & Analysis --Fuel...

271

CMVRTC: Fuel Tax Evasion  

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

concentration of fuel markers in the fuel. This research integrated advances in sensor technology, wireless communications, vehicle tracking, and information analysis. An...

272

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

CH2 NG MeOH NG n.e. MeOH coal n.e. MeOH Ethanol Ethanol woodTO END USERS (U. S. Fuel --> Coal CG RFG Diesel FTD Fuel oilLPG CNG Nuclear Feedstock ----> Coal Fuel dispensing Fuel

Delucchi, Mark

2005-01-01T23:59:59.000Z

273

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

CH2 NG MeOH NG n.e. MeOH coal n.e. MeOH Ethanol Ethanol woodTO END USERS (U. S. Fuel --> Coal CG RFG Diesel FTD Fuel oilLPG CNG Nuclear Feedstock ----> Coal Fuel dispensing Fuel

Delucchi, Mark

2005-01-01T23:59:59.000Z

274

Fuel Cell Technologies Program Multi-Year Research, Development and Demonstration Plan - Section 4.0 Systems Analysis  

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

Systems Analysis Systems Analysis Multi-Year Research, Development and Demonstration Plan Page 4 - 1 4.0 Systems Analysis The Fuel Cell Technologies Program (FCT Program) conducts a coordinated, comprehensive effort in modeling and analysis to clarify where hydrogen and fuel cells can be most effective from an economic, environmental, and energy security standpoint, as well as to guide RD&D priorities and set program goals. These activities support the FCT Program's decision- making process by evaluating technologies and pathways and determining technology gaps, risks, and benefits. The Systems Analysis sub-program works at all levels of the program, including technology analysis for specific sub-programs, policy and infrastructure analysis, and high-level implementation and

275

PWR core and spent fuel pool analysis using scale and nestle  

SciTech Connect

The SCALE nuclear analysis code system [SCALE, 2011], developed and maintained at Oak Ridge National Laboratory (ORNL) is widely recognized as high quality software for analyzing nuclear systems. The SCALE code system is composed of several validated computer codes and methods with standard control sequences, such as the TRITON/NEWT lattice physics sequence, which supplies dependable and accurate analyses for industry, regulators, and academia. Although TRITON generates energy-collapsed and space-homogenized few group cross sections, SCALE does not include a full-core nodal neutron diffusion simulation module within. However, in the past few years, the open-source NESTLE core simulator [NESTLE, 2003], originally developed at North Carolina State Univ. (NCSU), has been updated and upgraded via collaboration between ORNL and the Univ. of Tennessee (UT), so it now has a growingly seamless coupling to the TRITON/NEWT lattice physics [Galloway, 2010]. This study presents the methodology used to couple lattice physics data between TRITON and NESTLE in order to perform a three-dimensional full-core analysis employing a 'real-life' Duke Energy PWR as the test bed. The focus for this step was to compare the key parameters of core reactivity and radial power distribution versus plant data. Following the core analysis, following a three cycle burn, a spent fuel pool analysis was done using information generated from NESTLE for the discharged bundles and was compared to Duke Energy spent fuel pool models. The KENO control module from SCALE was employed for this latter stage of the project. (authors)

Murphy, J. E.; Maldonado, G. I. [Dept. of Nuclear Engineering, Univ. of Tennessee, Knoxville, TN 37996-2300 (United States); St Clair, R.; Orr, D. [Duke Energy, 526 S. Church St, Charlotte, NC 28202 (United States)

2012-07-01T23:59:59.000Z

276

Stationery and Emerging Market Fuel Cell System Cost Analysis - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

1 1 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Kathya Mahadevan (Primary Contact), VinceContini, Matt Goshe, and Fritz Eubanks Battelle 505 King Avenue Columbus, OH 43201 Phone: (614) 424-3197 Email: mahadevank@battelle.org DOE Managers HQ: Jason Marcinkoski Phone: (202) 586-7466 Email: Jason.Marcinkoski@ee.doe.gov GO: Reg Tyler Phone: (720) 356-1805 Email: Reginald.Tyler@go.doe.gov Contract Number: DE-EE0005250/001 Project Start Date: September 30, 2011 Project End Date: Project continuation and direction determined annually by DOE Fiscal Year (FY) 2012 Objectives To assist the DOE in developing fuel cell systems for stationary and emerging markets by developing independent cost models and costs estimates for manufacture and

277

Fuel Cell Technologies Office: Fuel Cell Technical Publications  

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

Cell Technical Cell Technical Publications to someone by E-mail Share Fuel Cell Technologies Office: Fuel Cell Technical Publications on Facebook Tweet about Fuel Cell Technologies Office: Fuel Cell Technical Publications on Twitter Bookmark Fuel Cell Technologies Office: Fuel Cell Technical Publications on Google Bookmark Fuel Cell Technologies Office: Fuel Cell Technical Publications on Delicious Rank Fuel Cell Technologies Office: Fuel Cell Technical Publications on Digg Find More places to share Fuel Cell Technologies Office: Fuel Cell Technical Publications on AddThis.com... Publications Program Publications Technical Publications Hydrogen Fuel Cells Safety, Codes & Standards Market Analysis Educational Publications Newsletter Program Presentations Multimedia Conferences & Meetings

278

Analysis of Accidents at the Pakistan Research Reactor-1 Using Proposed Mixed-Fuel (HEU and LEU) Core  

Science Conference Proceedings (OSTI)

The Pakistan Research Reactor-1 (PARR-1) was converted from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel in 1991. The reactor is running successfully, with an upgraded power level of 10 MW. To save money on the purchase of costly fresh LEU fuel elements, the use of less burnt HEU spent fuel elements along with the present LEU fuel elements is being considered. The proposal calls for the HEU fuel elements to be placed near the thermal column to gain the required excess reactivity. In the present study the safety analysis of a proposed mixed-fuel core has been carried out at a calculated steady-state power level of 9.8 MW. Standard computer codes and correlations were employed to compute various parameters. Initiating events in reactivity-induced accidents involve various modes of reactivity insertion, namely, start-up accident, accidental drop of a fuel element on the core, flooding of a beam tube with water, and removal of an in-pile experiment during reactor operation. For each of these transients, time histories of reactor power, energy released, temperature, and reactivity were determined.

Bokhari, Ishtiaq H. [Pakistan Institute of Nuclear Science and Technology (Pakistan)

2004-12-15T23:59:59.000Z

279

Economic feasibility analysis of distributed electric power generation based upon the natural gas-fired fuel cell. Final report  

DOE Green Energy (OSTI)

The final report provides a summary of results of the Cost of Ownership Model and the circumstances under which a distributed fuel cell is economically viable. The analysis is based on a series of micro computer models estimate the capital and operations cost of a fuel cell central utility plant configuration. Using a survey of thermal and electrical demand profiles, the study defines a series of energy user classes. The energy user class demand requirements are entered into the central utility plant model to define the required size the fuel cell capacity and all supporting equipment. The central plant model includes provisions that enables the analyst to select optional plant features that are most appropriate to a fuel cell application, and that are cost effective. The model permits the choice of system features that would be suitable for a large condominium complex or a residential institution such as a hotel, boarding school or prison. Other applications are also practical; however, such applications have a higher relative demand for thermal energy, a characteristic that is well-suited to a fuel cell application with its free source of hot water or steam. The analysis combines the capital and operation from the preceding models into a Cost of Ownership Model to compute the plant capital and operating costs as a function of capacity and principal features and compares these estimates to the estimated operating cost of the same central plant configuration without a fuel cell.

Not Available

1994-03-01T23:59:59.000Z

280

Transient three-dimensional thermal-hydraulic analysis of nuclear reactor fuel rod arrays: general equations and numerical scheme  

SciTech Connect

A mathematical model and a numerical solution scheme for thermal- hydraulic analysis of fuel rod arrays are given. The model alleviates the two major deficiencies associated with existing rod array analysis models, that of a correct transverse momentum equation and the capability of handling reversing and circulatory flows. Possible applications of the model include steady state and transient subchannel calculations as well as analysis of flows in heat exchangers, other engineering equipment, and porous media. (auth)

Wnek, W.J.; Ramshaw, J.D.; Trapp, J.A.; Hughes, E.D.; Solbrig, C.W.

1975-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Hydrogen Fuel Cell Analysis: Lessons Learned from Stationary Power Generation Final Report  

DOE Green Energy (OSTI)

This study considered opportunities for hydrogen in stationary applications in order to make recommendations related to RD&D strategies that incorporate lessons learned and best practices from relevant national and international stationary power efforts, as well as cost and environmental modeling of pathways. The study analyzed the different strategies utilized in power generation systems and identified the different challenges and opportunities for producing and using hydrogen as an energy carrier. Specific objectives included both a synopsis/critical analysis of lessons learned from previous stationary power programs and recommendations for a strategy for hydrogen infrastructure deployment. This strategy incorporates all hydrogen pathways and a combination of distributed power generating stations, and provides an overview of stationary power markets, benefits of hydrogen-based stationary power systems, and competitive and technological challenges. The motivation for this project was to identify the lessons learned from prior stationary power programs, including the most significant obstacles, how these obstacles have been approached, outcomes of the programs, and how this information can be used by the Hydrogen, Fuel Cells & Infrastructure Technologies Program to meet program objectives primarily related to hydrogen pathway technologies (production, storage, and delivery) and implementation of fuel cell technologies for distributed stationary power. In addition, the lessons learned address environmental and safety concerns, including codes and standards, and education of key stakeholders.

Scott E. Grasman; John W. Sheffield; Fatih Dogan; Sunggyu Lee; Umit O. Koylu; Angie Rolufs

2010-04-30T23:59:59.000Z

282

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

NLE Websites -- All DOE Office Websites (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. *

283

Analysis of the Hydrogen Infrastructure Needed to Enable Commercial Introduction of Hydrogen-Fueled Vehicles: Preprint  

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

Conference Paper Conference Paper Analysis of the Hydrogen NREL/CP-540-37903 Infrastructure Needed to March 2005 Enable Commercial Introduction of Hydrogen- Fueled Vehicles Preprint M. Melendez and A. Milbrandt National Renewable Energy Laboratory To be presented at the National Hydrogen Association � Annual Hydrogen Conference 2005 � Washington, DC � March 29-April 1, 2005 � NREL is operated by Midwest Research Institute ● Battelle Contract No. DE-AC36-99-GO10337 NOTICE The submitted manuscript has been offered by an employee of the Midwest Research Institute (MRI), a contractor of the US Government under Contract No. DE-AC36-99GO10337. Accordingly, the US Government and MRI retain a nonexclusive royalty-free license to publish or reproduce the published form of

284

Depletion Analysis of Modular High Temperature Gas-cooled Reactor Loaded with LEU/Thorium Fuel  

SciTech Connect

Thorium based fuel has been considered as an option to uranium-based fuel, based on considerations of resource utilization (Thorium is more widely available when compared to Uranium). The fertile isotope of Thorium (Th-232) can be converted to fissile isotope U-233 by neutron capture during the operation of a suitable nuclear reactor such as High Temperature Gas-cooled Reactor (HTGR). However, the fertile Thorium needs a fissile supporter to start and maintain the conversion process such as U-235 or Pu-239. This report presents the results of a study that analyzed the thorium utilization in a prismatic HTGR, namely Modular High Temperature Gas-Cooled Reactor (MHTGR) that was designed by General Atomics (GA). The collected for the modeling of this design come from Chapter 4 of MHTGR Preliminary Safety Information Document that GA sent to Department of Energy (DOE) on 1995. Both full core and unit cell models were used to perform this analysis using SCALE 6.1 and Serpent 1.1.18. Because of the long mean free paths (and migration lengths) of neutrons in HTRs, using a unit cell to represent a whole core can be non-trivial. The sizes of these cells were set to match the spectral index between unit cell and full core domains. It was found that for the purposes of this study an adjusted unit cell model is adequate. Discharge isotopics and one-group cross-sections were delivered to the transmutation analysis team. This report provides documentation for these calculations

Sonat Sen; Gilles Youinou

2013-02-01T23:59:59.000Z

285

Heavy Duty Diesel Particulate Matter and Fuel Consumption Modeling for Transportation Analysis  

E-Print Network (OSTI)

fuel use. Mesoscale Modeling Data Set and Mesoscale Modelobserved, quantified in the data set, and modeled to improveerrors for the validation data set are less than 2% for fuel

Scora, George Alexander

2011-01-01T23:59:59.000Z

286

ROBUST CONTROL ANALYSIS USING REAL-TIME IMPLEMENTATION OF A HYBRID FUEL CELL POWER GENERATION SYSTEM  

E-Print Network (OSTI)

is performed for a hybrid Fuel Cell/Supercapacitor generation system with power management, realized through converters interfacing the Fuel Cell (FC) and the Supercapacitor (SC) with the system electrical load

Paris-Sud XI, Université de

287

Fuel Examination and Crud Analysis from Columbia Generating Station EOC20  

Science Conference Proceedings (OSTI)

At the Columbia Generating Station end of cycle-20 (EOC-20) refueling outage, 2- and 3-cycle ATRIUM-10 fuel assemblies were examined to assess the impact of reduced Cycle 20 feedwater iron (Fe) and zinc (Zn) transport on crud loadings of fuel and fuel performance in general.BackgroundCrud spallation was observed on 2- and 3-cycle fuel at Columbia Generating Station (CGS) during EOC19. This observation was linked to moderate feedwater (FW) zinc (Zn) and iron ...

2013-09-05T23:59:59.000Z

288

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

hydrogen, LPG = liquefied petroleum gases. 1) The gasolinegas; LPG = liquefied petroleum gases; cell. = cellulosic; EV177 Other petroleum fuel sulfur

Delucchi, Mark

2005-01-01T23:59:59.000Z

289

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

hydrogen, LPG = liquefied petroleum gases. 1) The gasolinegas; LPG = liquefied petroleum gases; cell. = cellulosic; EV177 Other petroleum fuel sulfur

Delucchi, Mark

2005-01-01T23:59:59.000Z

290

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

wood, grass, or corn. It considers fuel-cell electric vehicles (FCVs) as well as internal- combustion

Delucchi, Mark

2005-01-01T23:59:59.000Z

291

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

wood, grass, or corn. It considers fuel-cell electric vehicles (FCVs) as well as internal- combustion

Delucchi, Mark

2005-01-01T23:59:59.000Z

292

Strategic Analysis of Biomass and Waste Fuels for Electric Power Generation  

Science Conference Proceedings (OSTI)

Biomass, waste fuels, and power technologies based on advanced combustion and gasification show promise for renewable baseload generation. Utilities can use the results of this study to evaluate the potential performance and cost of biomass and waste fuel-fired power plants in their systems and examine fuel use in integrated resource plans.

1994-01-01T23:59:59.000Z

293

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

E-Print Network (OSTI)

Nuclear power has the potential to help reduce rising carbon emissions, but to be considered sustainable, it must also demonstrate the availability of an indefinite fuel supply as well as not produce any significant negative environmental effects. The objective of this research was to evaluate the sustainability of nuclear power and to explore the nuclear fuel cycles that best meet this goal. First, the study quantified current and promising nuclear fuel cycles to be further evaluated and developed a set of objective metrics to describe the environmental effects of each cycle. The metrics included such factors as the amount of waste generated and the isotopic composition of the waste. Next, the evaluation used the International Atomic Energy Agency's Nuclear Fuel Cycle Simulation System to compute nuclide compositions at various stages of the fuel cycles. Finally, the study looked at the radioactivity of the waste generated and used this and other characteristics to determine which fuel cycle meets the objectives of sustainability. Results confirm that incorporating recycling into the fuel cycle would help reduce the volume of waste needing to be stored long-term. Also, calculations made with data from the Nuclear Fuel Cycle Simulation System predicted that the waste from fuel cycles using recycling would be slightly more radiotoxic than the open fuel cycle?s waste. However, the small increase in radiotoxicity is a manageable issue and would not detract from the benefits of recycling. Therefore, recycling and reprocessing spent fuel must be incorporated into the nuclear fuel cycle to achieve sustainability.

Yancey, Kristina D.

2010-05-01T23:59:59.000Z

294

EVALUATION OF CORE PHYSICS ANALYSIS METHODS FOR CONVERSION OF THE INL ADVANCED TEST REACTOR TO LOW-ENRICHMENT FUEL  

Science Conference Proceedings (OSTI)

Computational neutronics studies to support the possible conversion of the ATR to LEU are underway. Simultaneously, INL is engaged in a physics methods upgrade project to put into place modern computational neutronics tools for future support of ATR fuel cycle and experiment analysis. A number of experimental measurements have been performed in the ATRC in support of the methods upgrade project, and are being used to validate the new core physics methods. The current computational neutronics work is focused on performance of scoping calculations for the ATR core loaded with a candidate LEU fuel design. This will serve as independent confirmation of analyses that have been performed previously, and will evaluate some of the new computational methods for analysis of a candidate LEU fuel for ATR.

Mark DeHart; Gray S. Chang

2012-04-01T23:59:59.000Z

295

Evaluation of core physics analysis methods for conversion of the INL advanced test reactor to low-enrichment fuel  

Science Conference Proceedings (OSTI)

Computational neutronics studies to support the possible conversion of the ATR to LEU are underway. Simultaneously, INL is engaged in a physics methods upgrade project to put into place modern computational neutronics tools for future support of ATR fuel cycle and experiment analysis. A number of experimental measurements have been performed in the ATRC in support of the methods upgrade project, and are being used to validate the new core physics methods. The current computational neutronics work is focused on performance of scoping calculations for the ATR core loaded with a candidate LEU fuel design. This will serve as independent confirmation of analyses that have been performed previously, and will evaluate some of the new computational methods for analysis of a candidate LEU fuel for ATR. (authors)

DeHart, M. D.; Chang, G. S. [Idaho National Laboratory, 2525 Fremont Street, Idaho Falls, ID 83415-3870 (United States)

2012-07-01T23:59:59.000Z

296

Preliminary Analysis of Energy Storage Options for Hydrogen Fuel Cell Buses for Urban Transport  

Science Conference Proceedings (OSTI)

The United Nations Development Program/Global Environment Facility (UNDP/GEF) Fuel Cell Bus Project will develop a fuel cell transit bus by combining two Ballard automotive fuel cells with an energy storage system. The battery system will be an important component of the bus and will assist the fuel cell systems (FC-S) to store regenerative baking energy in the hybrid system. The battery also has the potential to increase fuel cell system performance, efficiency, and durability by reducing FC-S transient...

2010-01-18T23:59:59.000Z

297

Strategic backdrop analysis for fossil fuel planning. Task 1. Default Case. Report 468-117-07/03  

Science Conference Proceedings (OSTI)

This report presents data describing a default case analysis performed using the strategic backdrop analytical framework developed to facilitate fossil fuel planning within the DOE. Target years are 1985, 2000, and 2025. Residential, commercial, and industrial energy demands and impacts of energy technology implementation and market penetration are forecast using a set of energy technology assumptions.

Not Available

1980-06-01T23:59:59.000Z

298

Analysis of near-term spent fuel transportation hardware requirements and transportation costs  

SciTech Connect

A computer model was developed to quantify the transportation hardware requirements and transportation costs associated with shipping spent fuel in the commercial nucler fuel cycle in the near future. Results from this study indicate that alternative spent fuel shipping systems (consolidated or disassembled fuel elements and new casks designed for older fuel) will significantly reduce the transportation hardware requirements and costs for shipping spent fuel in the commercial nuclear fuel cycle, if there is no significant change in their operating/handling characteristics. It was also found that a more modest cost reduction results from increasing the fraction of spent fuel shipped by truck from 25% to 50%. Larger transportation cost reductions could be realized with further increases in the truck shipping fraction. Using the given set of assumptions, it was found that the existing spent fuel cask fleet size is generally adequate to perform the needed transportation services until a fuel reprocessing plant (FRP) begins to receive fuel (assumed in 1987). Once the FRP opens, up to 7 additional truck systems and 16 additional rail systems are required at the reference truck shipping fraction of 25%. For the 50% truck shipping fraction, 17 additional truck systems and 9 additional rail systems are required. If consolidated fuel only is shipped (25% by truck), 5 additional rail casks are required and the current truck cask fleet is more than adequate until at least 1995. Changes in assumptions could affect the results. Transportation costs for a federal interim storage program could total about $25M if the FRP begins receiving fuel in 1987 or about $95M if the FRP is delayed until 1989. This is due to an increased utilization of federal interim storage facility from 350 MTU for the reference scenario to about 750 MTU if reprocessing is delayed by two years.

Daling, P.M.; Engel, R.L.

1983-01-01T23:59:59.000Z

299

DOE Hydrogen Analysis Repository: Review of FreedomCAR and Fuel Partnership  

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

Review of FreedomCAR and Fuel Partnership Review of FreedomCAR and Fuel Partnership Project Summary Full Title: Review of the Research Program of the U.S. DRIVE Partnership Previous Title(s): Review of the Research Program of the FreedomCAR and Fuel Partnership Project ID: 203 Principal Investigator: Brief Description: The National Research Council's Committee on Review of the FreedomCAR and Fuel Research Program evaluates the structure and management of the Partnership as well as the Partnership's adequacy, progress, and technical problem areas on a biannual basis. Keywords: Advanced technology vehicles, fuel cells, hydrogen storage, hydrogen production Purpose Evaluate DOE-sponsored research efforts directed at the goal of a hydrogen economy under the U.S. DRIVE Partnership (formerly the FreedomCAR and Fuel

300

Cost Impact of Using ISG-8 Rev. 3 for PWR Spent Fuel Pool Criticality Analysis  

Science Conference Proceedings (OSTI)

Nuclear Regulatory Commission (NRC) guidance for applying burnup credit in criticality analyses for spent fuel storage and transportation requirements recently changed with the release of Interim Staff Guidance (ISG) 8 Revision 3, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks. If ISG-8 Rev. 3 were imposed upon pressurized water reactor (PWR) spent fuel pool (SFP) criticality analyses, the burnup requirements for loading would ...

2012-11-21T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Root Cause Analysis of Failed ATRIUM-10B Fuel Rod from Forsmark-1  

Science Conference Proceedings (OSTI)

The Fuel Reliability Program (FRP) is co-sponsoring numerous research projects to investigate fuel failures associated with power or sequence changes in boiling water reactors (BWRs), and thereby identify the root cause of these failures and provide guidance to avoid future failures. This subject report is complementary to Electric Power Research Institute (EPRI) report 1015453, Fuel Reliability Guideline: Pellet-Cladding Interaction, as well as other EPRI technical reports (1011100, 1014876, 1018037, 10...

2011-11-30T23:59:59.000Z

302

COBRA-SFS (Spent Fuel Storage): A thermal-hydraulic analysis computer code: Volume 2, User's manual  

Science Conference Proceedings (OSTI)

COBRA-SFS (Spent Fuel Storage) is a general thermal-hydraulic analysis computer code used to predict temperatures and velocities in a wide variety of systems. The code was refined and specialized for spent fuel storage system analyses for the US Department of Energy's Commercial Spent Fuel Management Program. The finite-volume equations governing mass, momentum, and energy conservation are written for an incompressible, single-phase fluid. The flow equations model a wide range of conditions including natural circulation. The energy equations include the effects of solid and fluid conduction, natural convection, and thermal radiation. The COBRA-SFS code is structured to perform both steady-state and transient calculations; however, the transient capability has not yet been validated. This volume contains the input instructions for COBRA-SFS and an auxiliary radiation exchange factor code, RADX-1. It is intended to aid the user in becoming familiar with the capabilities and modeling conventions of the code.

Rector, D.R.; Cuta, J.M.; Lombardo, N.J.; Michener, T.E.; Wheeler, C.L.

1986-11-01T23:59:59.000Z

303

COBRA-SFS (Spent Fuel Storage): A thermal-hydraulic analysis computer code: Volume 1, Mathematical models and solution method  

Science Conference Proceedings (OSTI)

COBRA-SFS (Spent Fuel Storage) is a general thermal-hydraulic analysis computer code used to predict temperatures and velocities in a wide variety of systems. The code was refined and specialized for spent fuel storage system analyses for the US Department of Energy's Commercial Spent Fuel Management Program. The finite-volume equations governing mass, momentum, and energy conservation are written for an incompressible, single-phase fluid. The flow equations model a wide range of conditions including natural circulation. The energy equations include the effects of solid and fluid conduction, natural convection, and thermal radiation. The COBRA-SFS code is structured to perform both steady-state and transient calculations: however, the transient capability has not yet been validated. This volume describes the finite-volume equations and the method used to solve these equations. It is directed toward the user who is interested in gaining a more complete understanding of these methods.

Rector, D.R.; Wheeler, C.L.; Lombardo, N.J.

1986-11-01T23:59:59.000Z

304

Analysis of Coconut-Derived Biodiesel and Conventional Diesel Fuel Samples from the Philippines: Task 2 Final Report  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Analysis of Coconut-Derived Analysis of Coconut-Derived Biodiesel and Conventional Diesel Fuel Samples from the Philippines Task 2 Final Report T.L. Alleman and R.L. McCormick Milestone Report NREL/MP-540-38643 January 2006 National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov Operated for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy by Midwest Research Institute * Battelle Contract No. DE-AC36-99-GO10337 Analysis of Coconut- Derived Biodiesel and Conventional Diesel Fuel Samples from the Philippines Task 2 Final Report T.L. Alleman and R.L. McCormick Prepared under Task Nos. WF3Y.1000 and FC02.0800 under an agreement between the U.S. Agency for International Development

305

Hydrogen, Fuel Cells, & Infrastructure - Program Areas - Energy...  

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

fuel cell Welcome> Program Areas> Program Areas Hydrogen, Fuel Cells & Infrastructure Production & Delivery | Storage | Fuel Cell R&D | Systems Integration & Analysis | Safety...

306

Advanced system analysis for indirect methanol fuel cell power plants for transportation applications  

DOE Green Energy (OSTI)

The indirect methanol cell fuel concept actively pursued by the USDOE and General Motors Corporation proposes the development of an electrochemical engine'' (e.c.e.), an electrical generator capable for usually efficient and clean power production from methanol fuel for the transportation sector. This on-board generator works in consort with batteries to provide electrical power to drive propulsion motors for a range of electric vehicles. Success in this technology could do much to improve impacted environmental areas and to convert part of the transportation fleet to natural gas- and coal-derived methanol as the fuel source. These developments parallel work in Europe and Japan where various fuel cell powered vehicles, often fueled with tanked or hydride hydrogen, are under active development. Transportation applications present design challenges that are distinctly different from utility requirements, the thrust of most of previous fuel cell programs. In both cases, high conversion efficiency (fuel to electricity) is essential. However, transportation requirements dictate as well designs for high power densities, rapid transients including short times for system start up, and consumer safety. The e.c.e. system is formed from four interacting components: (1) the fuel processor; (2) the fuel cell stack; (3) the air compression and decompression device; and (4) the condensing cross flow heat exchange device. 2 figs.

Vanderborgh, N.E.; McFarland, R.D.; Huff, J.R.

1990-01-01T23:59:59.000Z

307

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

by type of fuel; electricity distribution efficiency in athe efficiency of electricity distribution for every country1994, and that the electricity distribution system was 91.3%

Delucchi, Mark

2005-01-01T23:59:59.000Z

308

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

by type of fuel; electricity distribution efficiency in athe efficiency of electricity distribution for every country1994, and that the electricity distribution system was 91.3%

Delucchi, Mark

2005-01-01T23:59:59.000Z

309

Magnetic Analysis of Nickel Nano-Particles in Solid Oxide Fuel Cell ...  

Science Conference Proceedings (OSTI)

During operation of the fuel cell in reducing environments, nickel particle formation ... of Advanced Ferritic Creep Resistant Steels for Fossil Energy Applications.

310

DOE Hydrogen and Fuel Cells Program: DOE H2A Production Analysis  

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

filling-station) facilities. Required input to the models includes capital and operating costs for the hydrogen production process, fuel type and use, and financial parameters...

311

Fuel Cell Power Model for CHHP System Economics and Performance Analysis (Presentation)  

DOE Green Energy (OSTI)

Presentation about Fuel Cell Power (FCPower) Model used to analyze the economics and performance of combined heat, hydrogen, and power (CHHP) systems.

Steward, D.

2009-11-16T23:59:59.000Z

312

Simulation of a hydrogen fueled hybrid vehicle using powertrain system analysis toolkit.  

E-Print Network (OSTI)

??With shrinking energy reserves, and the rising concerns for the environmental status, the need for fuel efficient and low emission vehicles is increasing day by (more)

Jean, B. Jacob

2009-01-01T23:59:59.000Z

313

Modeling and Experimental Analysis of Biogas in Diesel and Solid Oxide Fuel Cell Generators.  

E-Print Network (OSTI)

??Biogas is a green fuel generally produced by agricultural or household waste, whose range of applications has become wider and wider in recent years. The (more)

Quesito, Francesco

2012-01-01T23:59:59.000Z

314

A Low-Carbon Fuel Standard for California, Part 2: Policy Analysis  

E-Print Network (OSTI)

must be provided (such as E85 filling stations, dedicatedmodest changes (e.g. , E85 flex-fuel vehicles), but

Farrell, Alexander; Sperling, Daniel

2007-01-01T23:59:59.000Z

315

A Low-Carbon Fuel Standard for California Part 2: Policy Analysis  

E-Print Network (OSTI)

must be provided (such as E85 filling stations, dedicatedmodest changes (e.g. , E85 flex-fuel vehicles), but

2007-01-01T23:59:59.000Z

316

Stationary Fuel Cell Application Codes and Standards: Overview and Gap Analysis  

DOE Green Energy (OSTI)

This report provides an overview of codes and standards related to stationary fuel cell applications and identifies gaps and resolutions associated with relative codes and standards.

Blake, C. W.; Rivkin, C. H.

2010-09-01T23:59:59.000Z

317

Advanced system analysis for indirect methanol fuel cell power plants for transportation applications  

SciTech Connect

The indirect methanol cell fuel concept actively pursued by the USDOE and General Motors Corporation proposes the development of an electrochemical engine'' (e.c.e.), an electrical generator capable for usually efficient and clean power production from methanol fuel for the transportation sector. This on-board generator works in consort with batteries to provide electrical power to drive propulsion motors for a range of electric vehicles. Success in this technology could do much to improve impacted environmental areas and to convert part of the transportation fleet to natural gas- and coal-derived methanol as the fuel source. These developments parallel work in Europe and Japan where various fuel cell powered vehicles, often fueled with tanked or hydride hydrogen, are under active development. Transportation applications present design challenges that are distinctly different from utility requirements, the thrust of most of previous fuel cell programs. In both cases, high conversion efficiency (fuel to electricity) is essential. However, transportation requirements dictate as well designs for high power densities, rapid transients including short times for system start up, and consumer safety. The e.c.e. system is formed from four interacting components: (1) the fuel processor; (2) the fuel cell stack; (3) the air compression and decompression device; and (4) the condensing cross flow heat exchange device. 2 figs.

Vanderborgh, N.E.; McFarland, R.D.; Huff, J.R.

1990-01-01T23:59:59.000Z

318

A Low-Carbon Fuel Standard for California, Part 2: Policy Analysis  

E-Print Network (OSTI)

conversion from soybean to corn ethanol production in theproduced in the US: corn ethanol and soybean biodiesel. USDAdifferent fuels such as corn ethanol, cellulosic ethanol,

Sperling, Daniel; Farrell, Alexander

2007-01-01T23:59:59.000Z

319

A Low-Carbon Fuel Standard for California Part 2: Policy Analysis  

E-Print Network (OSTI)

conversion from soybean to corn ethanol production in theproduced in the US: corn ethanol and soybean biodiesel. USDAdifferent fuels such as corn ethanol, cellulosic ethanol,

2007-01-01T23:59:59.000Z

320

Analysis of the Hydrogen Infrastructure Needed to Enable Commercial Introduction of Hydrogen-Fueled Vehicles: Preprint  

DOE Green Energy (OSTI)

This paper for the 2005 National Hydrogen Association conference analyzes the hydrogen infrastructure needed to accommodate a transitional hydrogen fuel cell vehicle demand.

Melendez, M.; Milbrandt, A.

2005-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Analysis of U.S. School Bus Populations and Alternative Fuel Potential  

DOE Green Energy (OSTI)

This Clean Cities final report provides information concerning different school bus types, school bus populations, school bus miles and fuel use, school bus emissions, alternative fuel school buses, and potential for alternative fuel school bus use through 2010. It is intended to provide general information concerning the size of the school bus market in the U.S., as well as to provide some quantification of the potential for alternative fuel use in school buses in the U.S., and what that might mean for petroleum displacement and emissions reductions.

Laughlin, M.

2004-04-01T23:59:59.000Z

322

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

like fuel via the Fischer-Tropsch process, or emissions fromvehicles. FTD = Fischer-Tropsch diesel, CNG = compressedvolume % in LPG) FTD = Fischer-Tropsch dieses (volume % in

Delucchi, Mark

2005-01-01T23:59:59.000Z

323

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

like fuel via the Fischer-Tropsch process, or emissions fromvehicles. FTD = Fischer-Tropsch diesel, CNG = compressedvolume % in LPG) FTD = Fischer-Tropsch dieses (volume % in

Delucchi, Mark

2005-01-01T23:59:59.000Z

324

A Low-Carbon Fuel Standard for California Part 1: Technical Analysis  

E-Print Network (OSTI)

existing solid-fuel biomass direct combustion sector stemGasification The partial combustion of biomass in an oxygen-biomass) and energy conversion technologies (combustion,

2007-01-01T23:59:59.000Z

325

A Low-Carbon Fuel Standard for California, Part 1: Technical Analysis  

E-Print Network (OSTI)

existing solid-fuel biomass direct combustion sector stemGasification The partial combustion of biomass in an oxygen-biomass) and energy conversion technologies (combustion,

Farrell, Alexander; Sperling, Daniel

2007-01-01T23:59:59.000Z

326

Linear regression analysis of emissions factors when firing fossil fuels and biofuels in a commercial water-tube boiler  

Science Conference Proceedings (OSTI)

This paper compares the emissions factors for a suite of liquid biofuels (three animal fats, waste restaurant grease, pressed soybean oil, and a biodiesel produced from soybean oil) and four fossil fuels (i.e., natural gas, No. 2 fuel oil, No. 6 fuel oil, and pulverized coal) in Penn State's commercial water-tube boiler to assess their viability as fuels for green heat applications. The data were broken into two subsets, i.e., fossil fuels and biofuels. The regression model for the liquid biofuels (as a subset) did not perform well for all of the gases. In addition, the coefficient in the models showed the EPA method underestimating CO and NOx emissions. No relation could be studied for SO{sub 2} for the liquid biofuels as they contain no sulfur; however, the model showed a good relationship between the two methods for SO{sub 2} in the fossil fuels. AP-42 emissions factors for the fossil fuels were also compared to the mass balance emissions factors and EPA CFR Title 40 emissions factors. Overall, the AP-42 emissions factors for the fossil fuels did not compare well with the mass balance emissions factors or the EPA CFR Title 40 emissions factors. Regression analysis of the AP-42, EPA, and mass balance emissions factors for the fossil fuels showed a significant relationship only for CO{sub 2} and SO{sub 2}. However, the regression models underestimate the SO{sub 2} emissions by 33%. These tests illustrate the importance in performing material balances around boilers to obtain the most accurate emissions levels, especially when dealing with biofuels. The EPA emissions factors were very good at predicting the mass balance emissions factors for the fossil fuels and to a lesser degree the biofuels. While the AP-42 emissions factors and EPA CFR Title 40 emissions factors are easier to perform, especially in large, full-scale systems, this study illustrated the shortcomings of estimation techniques. 23 refs., 3 figs., 8 tabs.

Sharon Falcone Miller; Bruce G. Miller [Pennsylvania State University, University Park, PA (United States). Energy Institute

2007-12-15T23:59:59.000Z

327

COBRA-SFS (Spent Fuel Storage): A thermal-hydraulic analysis computer code: Volume 3, Validation assessments  

Science Conference Proceedings (OSTI)

This report presents the results of the COBRA-SFS (Spent Fuel Storage) computer code validation effort. COBRA-SFS, while refined and specialized for spent fuel storage system analyses, is a lumped-volume thermal-hydraulic analysis computer code that predicts temperature and velocity distributions in a wide variety of systems. Through comparisons of code predictions with spent fuel storage system test data, the code's mathematical, physical, and mechanistic models are assessed, and empirical relations defined. The six test cases used to validate the code and code models include single-assembly and multiassembly storage systems under a variety of fill media and system orientations and include unconsolidated and consolidated spent fuel. In its entirety, the test matrix investigates the contributions of convection, conduction, and radiation heat transfer in spent fuel storage systems. To demonstrate the code's performance for a wide variety of storage systems and conditions, comparisons of code predictions with data are made for 14 runs from the experimental data base. The cases selected exercise the important code models and code logic pathways and are representative of the types of simulations required for spent fuel storage system design and licensing safety analyses. For each test, a test description, a summary of the COBRA-SFS computational model, assumptions, and correlations employed are presented. For the cases selected, axial and radial temperature profile comparisons of code predictions with test data are provided, and conclusions drawn concerning the code models and the ability to predict the data and data trends. Comparisons of code predictions with test data demonstrate the ability of COBRA-SFS to successfully predict temperature distributions in unconsolidated or consolidated single and multiassembly spent fuel storage systems.

Lombardo, N.J.; Cuta, J.M.; Michener, T.E.; Rector, D.R.; Wheeler, C.L.

1986-12-01T23:59:59.000Z

328

TRUMP-BD: A computer code for the analysis of nuclear fuel assemblies under severe accident conditions  

Science Conference Proceedings (OSTI)

TRUMP-BD (Boil Down) is an extension of the TRUMP (Edwards 1972) computer program for the analysis of nuclear fuel assemblies under severe accident conditions. This extension allows prediction of the heat transfer rates, metal-water oxidation rates, fission product release rates, steam generation and consumption rates, and temperature distributions for nuclear fuel assemblies under core uncovery conditions. The heat transfer processes include conduction in solid structures, convection across fluid-solid boundaries, and radiation between interacting surfaces. Metal-water reaction kinetics are modeled with empirical relationships to predict the oxidation rates of steam-exposed Zircaloy and uranium metal. The metal-water oxidation models are parabolic in form with an Arrhenius temperature dependence. Uranium oxidation begins when fuel cladding failure occurs; Zircaloy oxidation occurs continuously at temperatures above 13000{degree}F when metal and steam are available. From the metal-water reactions, the hydrogen generation rate, total hydrogen release, and temporal and spatial distribution of oxide formations are computed. Consumption of steam from the oxidation reactions and the effect of hydrogen on the coolant properties is modeled for independent coolant flow channels. Fission product release from exposed uranium metal Zircaloy-clad fuel is modeled using empirical time and temperature relationships that consider the release to be subject to oxidation and volitization/diffusion ( bake-out'') release mechanisms. Release of the volatile species of iodine (I), tellurium (Te), cesium (Ce), ruthenium (Ru), strontium (Sr), zirconium (Zr), cerium (Cr), and barium (Ba) from uranium metal fuel may be modeled.

Lombardo, N.J.; Marseille, T.J.; White, M.D.; Lowery, P.S.

1990-06-01T23:59:59.000Z

329

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

SciTech Connect

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

E. R. Johnson; R. E. Best

2009-12-28T23:59:59.000Z

330

Phase analysis of metallic plutonium-containing fuel alloys using neutron diffraction  

Science Conference Proceedings (OSTI)

Pulsed neutron powder diffraction studies at IPNS have expanded our understanding of the phases present in Integral Fast Reactor (IFR) metal fuel alloys at temperatures in the range of reactor operating conditions. We report results from the binary alloy (U-10 wt % Zr) and ternary alloys (U-8% Pu-10% Zr) and (U-19% Pu-10% Zr). Determining the role and the location of Zr and Pu in these alloys is considered of fundamental importance for maximizing engineering efficiency. Rietveld profile analysis was utilized to study the phase diagrams. Data were collected at temperatures ranging from 25--650{degree}C. Although the expected U/Pu/Zr phases ({alpha}-U, {beta}-U, {gamma}-U, {delta}-U/Zr/Pu, {zeta}-U/Pu) were observed in appropriate temperature ranges, there were some unexpected results. Relative amounts of all phases at each temperature were calculated from Rietveld scale factors and inferences were made as to the location of zirconium and plutonium, i.e. amounts in each phase, from site occupancies and absorption characteristics of the phases present. Finally, we were able to identify ZrO and ZrO{sub 1-x} inclusion phases in the U-Zr alloy present in very small (0.5--1.0%) amounts. 15 refs., 9 figs., 2 tabs.

Mueller, M.H.; Richardson, J.W. Jr.; Strain, R.V.; Hofman, G.L.

1990-01-01T23:59:59.000Z

331

Analysis of the leak-detection system for top welds of EBR-II fuel elements  

SciTech Connect

An analysis of the leak detector used to check the top welds on EBR-II fuel elements was performed. Data were obtained to allow calculation of volumes of the metering chamber and test chamber at each station of the leak detector. These volumes and a mathematical model were used to calculate decrease in pressure with time for each station. Values for calibrated leaks and unknown leak rates were compared with calculated ones. The calculated results for the two calibrated leaks agreed with the observed pressure-time results for the two leaks. Results show that determining the volumes of each leak-detector station allows the leakrate sensitivity to be readily calculated for each station. One leak-detector station could not detect a minimum leak rate of 2 x 10/sup -4/ std cm/sup 3/ sec at 40 atm, which is the current specification. The other four stations could meet the specification. Suggestions are given for periodic calibration of the leak detectors as well as precautions that must be observed to achieve optimum sensitivity when operating the leak detector. (auth)

Hudman, G.D.; Walters, L.C.

1973-05-01T23:59:59.000Z

332

Computational analysis of heat and water transfer in a PEM fuel cell  

Science Conference Proceedings (OSTI)

Proton exchange membrane (PEM) fuel cells are promising power-generation sources for mobile and stationary applications. In this paper a non-isothermal, single-domain and two-dimensional computational fluid dynamics model is presented to investigate ... Keywords: CFD, PEM fuel cell, heat, non-isothermal, single-domain

Ebrahim Afshari; Seyed Ali Jazayeri

2008-02-01T23:59:59.000Z

333

A Neural Network Model for the Tomographic Analysis of Irradiated Nuclear Fuel Rods  

SciTech Connect

A tomographic method based on a multilayer feed-forward artificial neural network is proposed for the reconstruction of gamma-radioactive fission product distribution in irradiated nuclear fuel rods. The quality of the method is investigated as compared to a conventional technique on experimental results concerning a Canada deuterium uranium reactor (CANDU)-type fuel rod irradiated in a TRIGA reactor.

Craciunescu, Teddy [National Institute of Nuclear Physics and Engineering (Romania)

2004-04-15T23:59:59.000Z

334

Analysis of Severe Accident Scenarios and Proposals for Safety Improvements for ADS Transmuters with Dedicated Fuel  

SciTech Connect

So-called dedicated fuels will be utilized to obtain maximum transmutation and incineration rates of minor actinides (MAs) in accelerator-driven systems (ADSs). These fuels are characterized by a high-MA content and the lack of the classical fertile materials such as {sup 238}U or {sup 232}Th. Dedicated fuels still have to be developed; however, programs are under way for their fabrication, irradiation, and testing. In Europe, mainly the oxide route is investigated and developed. A dedicated core will contain multiple 'critical' fuel masses, resulting in a certain recriticality potential under core degradation conditions. The use of dedicated fuels may also lead to strong deterioration of the safety parameters of the reactor core, such as, e.g., the void worth, Doppler or the kinetics quantities, neutron generation time, and {beta}{sub eff}. Critical reactors with this kind of fuel might encounter safety problems, especially under severe accident conditions. For ADSs, it is assumed that because of the subcriticality of the system, the poor safety features of such fuels could be coped with. Analyses reveal some safety problems for ADSs with dedicated fuels. Additional inherent and passive safety measures are proposed to achieve the required safety level. A safety strategy along the lines of a defense approach is presented where these measures can be integrated. The ultimate goal of these measures is to eliminate any mechanistic severe accident scenario and the potential for energetics.

Maschek, Werner [Forschungszentrum Karlsruhe Institute for Nuclear and Energy Technologies (Germany); Rineiski, Andrei [Forschungszentrum Karlsruhe Institute for Nuclear and Energy Technologies (Germany); Flad, Michael [Forschungszentrum Karlsruhe Institute for Nuclear and Energy Technologies (Germany); Morita, Koji [Kyushu University Institute of Environmental Systems (Japan); Coste, Pierre [Commissariat a l'Energie Atomique CE Grenoble (France)

2003-02-15T23:59:59.000Z

335

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

n.a. n.a. n.a. n.a. n.a. Coke oil n.a. n.a. n.a. n.a. n.a.CG RFG Diesel FTD Fuel oil Stillgas Coke LPG LPG CNG NuclearFTD NG Fuel oil Still gas Coke oil oil oil LPG oil LPG NGL57

Delucchi, Mark

2005-01-01T23:59:59.000Z

336

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

n.a. n.a. n.a. n.a. n.a. Coke oil n.a. n.a. n.a. n.a. n.a.CG RFG Diesel FTD Fuel oil Stillgas Coke LPG LPG CNG NuclearFTD NG Fuel oil Still gas Coke oil oil oil LPG oil LPG NGL57

Delucchi, Mark

2005-01-01T23:59:59.000Z

337

Critical analysis of the Hanford spent nuclear fuel project activity based cost estimate  

Science Conference Proceedings (OSTI)

In 1997, the SNFP developed a baseline change request (BCR) and submitted it to DOE-RL for approval. The schedule was formally evaluated to have a 19% probability of success [Williams, 1998]. In December 1997, DOE-RL Manager John Wagoner approved the BCR contingent upon a subsequent independent review of the new baseline. The SNFP took several actions during the first quarter of 1998 to prepare for the independent review. The project developed the Estimating Requirements and Implementation Guide [DESH, 1998] and trained cost account managers (CAMS) and other personnel involved in the estimating process in activity-based cost (ABC) estimating techniques. The SNFP then applied ABC estimating techniques to develop the basis for the December Baseline (DB) and documented that basis in Basis of Estimate (BOE) books. These BOEs were provided to DOE in April 1998. DOE commissioned Professional Analysis, Inc. (PAI) to perform a critical analysis (CA) of the DB. PAI`s review formally began on April 13. PAI performed the CA, provided three sets of findings to the SNFP contractor, and initiated reconciliation meetings. During the course of PAI`s review, DOE directed the SNFP to develop a new baseline with a higher probability of success. The contractor transmitted the new baseline, which is referred to as the High Probability Baseline (HPB), to DOE on April 15, 1998 [Williams, 1998]. The HPB was estimated to approach a 90% confidence level on the start of fuel movement [Williams, 1998]. This high probability resulted in an increased cost and a schedule extension. To implement the new baseline, the contractor initiated 26 BCRs with supporting BOES. PAI`s scope was revised on April 28 to add reviewing the HPB and the associated BCRs and BOES.

Warren, R.N.

1998-09-29T23:59:59.000Z

338

Analysis of the Relationship Between Vehicle Weight/Size and Safety, and Implications for Federal Fuel Economy Regulation  

E-Print Network (OSTI)

for Federal Fuel Economy Regulation Final Report preparedand have higher fuel economy, and safer than conventionaland have higher fuel economy, without sacrificing safety. 1.

Wenzel, Thomas P.

2010-01-01T23:59:59.000Z

339

Validation of Inverse Methods Applied to Forensic Analysis of Spent Fuel  

Science Conference Proceedings (OSTI)

Inverse depletion/decay methods are useful tools for application to nuclear forensics. Previously, inverse methods were applied to the generic case of predicting the burnup, initial enrichment, and cooling time for selected spent nuclear fuels based on measured actinide and fission product concentrations. These existing measurements were not developed or optimized for use by these inverse techniques, and hence previous work demonstrated the prediction of only the fuel burnup, initial enrichment, and cooling time. Previously, nine spent fuel samples from an online data compilation were randomly selected for study. This work set out to demonstrate the full prediction capabilities using measured isotopic data, but with a more deliberate selection of fuel samples. The current approach is to evaluate nuclides within the same element to see if complementary information can be obtained in addition to the reactor burnup, enrichment, and cooling. Specifically, the reactor power and the fuel irradiation time values are desired to achieve the maximum prediction capabilities of these techniques.

Broadhead, Bryan L [ORNL; Weber, Charles F [ORNL

2010-01-01T23:59:59.000Z

340

RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel  

E-Print Network (OSTI)

A RELAP5/MOD3.2 model of a VVER-1000/MODEL V320 nuclear power plant, Balakovo Unit 4, was updated, improved and validated on the basis of an input deck prepared by the Kurchatov Institute of Moscow. The RELAP5 model includes both the primary and the secondary systems. The Emergency Core Cooling System (ECCS) is modeled according to the plant configuration. The feedwater system, along with the emergency feedwater system, is included in the model. The point reactor kinetics model, in which the decay heat is calculated with ANS decay heat data, enables the model to be used for analysis of a large spectrum of transients and accidents. The plant model is used for analysis and prediction of a cold leg Large Break Loss-of-Coolant Accident (LBLOCA). The RELAP5/MOD3.2 results showed a good agreement with calculations obtained with TECH-M computer program. The cladding temperatures of the MOX assembly have been compared with that of the hot UO? assembly. The peak cladding temperature of MOX assembly is about 55 K higher than that of UO? assembly. An uncertainty analysis has been performed for the peak cladding temperature, in which Monte Carlo calculations have been performed using the response surface built up from fifteen sets of RELAP5 calculations. The result shows that the ECCS would be sufficient to keep the cladding temperature during the scenario of a LBLOCA well below the required licensing limit.

Fu, Chun

2000-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Letter from Nuclear Energy Institute regarding Integrated Safety Analysis: Why it is Appropropriate for Fuel Recycling Facilities  

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

082 l F: 202.533.0166 l rxm@nei.org l www.nei.org 082 l F: 202.533.0166 l rxm@nei.org l www.nei.org Rod McCullum DIRECTOR FUEL CYCLE PROJECTS NUCLEAR GENERATION DIVISION September 10, 2010 Ms. Catherine Haney Director Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689 Dear Ms. Haney: Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is intended as an information source for the NRC and should serve as a foundation for discussion with industry representatives on the issue.

342

HEAVY ELEMENT ISOTOPIC ANALYSIS OF UO$sub 2$ FUEL IRRADIATED IN THE VBWR. Report No. 1  

SciTech Connect

Slightly enriched UO/sub 2/ fuel, irradiated in the Vallecitos Boiling Water Reactor (VBWR), with exposures ranging from 100 Mwd/t to 3200 Mwd/t was analyzed for heavy element isotopic composition and compared with computed data. The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of UO/sub 2/ fuel in a boiling water reactor. This information is important in both evaluating the economics of a given reactor design and also in providing a sounder physics basis for improving reactor designs to minimize the resuiting fuel costs. Uranium oxide pellets, with an enrichment of 2.8 atom percent, were analyzed at several axial positions along the fuel rod, spanning the void (steam fraction) range of 0 to 30%. The isotopic composition for each pellet was computed, utilizing a general fuel cycle depletion code. Results of the analysis of the comparison of the measured and computed data indicate that the total amount of Pu computed is consistently lower than that implied from the measurement by approximately 10%, and the percentage difference between the measured and computed data increases slightly with exposure. One rod was irradiated near a control rod which was approximately 25% inserted. As expected, since no control rod effects were included in the calcuiation, the measured data in that region of the rod shows a greater Pu production per Mwd/t than computed. Physical effects which might explain the small, but apparentiy consistent, differences between the measured and computed data were postulated. It is concluded that the observed differences are the result of a substantial underestimate of void fraction and small uncertainties in fuel exposure and cross sections. (auth)

Hackney, M.R.; Ruiz, C.P.

1962-12-28T23:59:59.000Z

343

Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor  

Science Conference Proceedings (OSTI)

This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemical assay data and the use of the data to validate computer code predictions of isotopic composition for spent nuclear fuel, to establish the uncertainty and bias associated with code predictions. The experimental data analyzed in the current report were acquired from a high-burnup fuel program coordinated by Spanish organizations. The measurements included extensive actinide and fission product data of importance to spent fuel safety applications, including burnup credit, decay heat, and radiation source terms. Six unique spent fuel samples from three uranium oxide fuel rods were analyzed. The fuel rods had a 4.5 wt % {sup 235}U initial enrichment and were irradiated in the Vandellos II pressurized water reactor operated in Spain. The burnups of the fuel samples range from 42 to 78 GWd/MTU. The measurements were used to validate the two-dimensional depletion sequence TRITON in the SCALE computer code system.

Ilas, Germina [ORNL; Gauld, Ian C [ORNL

2011-01-01T23:59:59.000Z

344

THERMAL ANALYSIS OF A PROPOSED TRANSPORT CASK FOR THREE ADVANCED BURNER REACTOR USED FUEL ASSEMBLIES  

SciTech Connect

Preliminary studies of used fuel generated in the US Department of Energys Advanced Fuel Cycle Initiative have indicated that current used fuel transport casks may be insufficient for the transportation of said fuel. This work considers transport of three 5-year-cooled oxide Advanced Burner Reactor used fuel assemblies with a burn-up of 160 MWD/kg. A transport cask designed to carry these assemblies is proposed. This design employs a 7-cm-thick lead gamma shield and a 20-cm-thick NS-4-FR composite neutron shield. The temperature profile within the cask, from its center to its exterior surface, is determined by two dimensional computational fluid dynamics simulations of conduction, convection, and radiation within the cask. Simulations are performed for a cask with a smooth external surface and various neutron shield thicknesses. Separate simulations are performed for a cask with a corrugated external surface and a neutron shield thickness that satisfies shielding constraints. Resulting temperature profiles indicate that a three-assembly cask with a smooth external surface will meet fuel cladding temperature requirements but will cause outer surface temperatures to exceed the regulatory limit. A cask with a corrugated external surface will not exceed the limits for both the fuel cladding and outer surface temperatures.

T. Bullard; M. Greiner; M. Dennis; S. Bays; R. Weiner

2010-09-01T23:59:59.000Z

345

Costs and benefits of automotive fuel economy improvement: A partial analysis  

SciTech Connect

This paper is an exercise in estimating the costs and benefits of technology-based fuel economy improvements for automobiles and light trucks. Benefits quantified include vehicle cots, fuel savings, consumer's surplus effects, the effect of reduced weight on vehicle safety, impacts on emissions of CO{sub 2} and criteria pollutants, world oil market and energy security benefits, and the transfer of wealth from US consumes to oil producers. A vehicle stock model is used to capture sales, scrappage, and vehicle use effects under three fuel price scenarios. Three alternative fuel economy levels for 2001 are considered, ranging from 32.9 to 36.5 MPG for cars and 24.2 to 27.5 MPG for light trucks. Fuel economy improvements of this size are probably cost-effective. The size of the benefit, and whether there is a benefit, strongly depends on the financial costs of fuel economy improvement and judgments about the values of energy security, emissions, safety, etc. Three sets of values for eight parameters are used to define the sensitivity of costs and benefits to key assumptions. The net present social value (1989$) of costs and benefits ranges from a cost of $11 billion to a benefit of $286 billion. The critical parameters being the discount rate (10% vs. 3%) and the values attached to externalities. The two largest components are always the direct vehicle costs and fuel savings, but these tend to counterbalance each other for the fuel economy levels examined here. Other components are the wealth transfer, oil cost savings, CO{sub 2} emissions reductions, and energy security benefits. Safety impacts, emissions of criteria pollutants, and consumer's surplus effects are relatively minor components. The critical issues for automotive fuel economy are therefore: (1) the value of present versus future costs and benefits, (2) the values of external costs and benefits, and (3) the financially cost-effective level of MPG achievable by available technology. 53 refs.

Greene, D.L. (Oak Ridge National Lab., TN (United States)); Duleep, K.G. (Energy and Environmental Analysis, Inc., Arlington, VA (United States))

1992-03-01T23:59:59.000Z

346

Costs and benefits of automotive fuel economy improvement: A partial analysis  

SciTech Connect

This paper is an exercise in estimating the costs and benefits of technology-based fuel economy improvements for automobiles and light trucks. Benefits quantified include vehicle cots, fuel savings, consumer`s surplus effects, the effect of reduced weight on vehicle safety, impacts on emissions of CO{sub 2} and criteria pollutants, world oil market and energy security benefits, and the transfer of wealth from US consumes to oil producers. A vehicle stock model is used to capture sales, scrappage, and vehicle use effects under three fuel price scenarios. Three alternative fuel economy levels for 2001 are considered, ranging from 32.9 to 36.5 MPG for cars and 24.2 to 27.5 MPG for light trucks. Fuel economy improvements of this size are probably cost-effective. The size of the benefit, and whether there is a benefit, strongly depends on the financial costs of fuel economy improvement and judgments about the values of energy security, emissions, safety, etc. Three sets of values for eight parameters are used to define the sensitivity of costs and benefits to key assumptions. The net present social value (1989$) of costs and benefits ranges from a cost of $11 billion to a benefit of $286 billion. The critical parameters being the discount rate (10% vs. 3%) and the values attached to externalities. The two largest components are always the direct vehicle costs and fuel savings, but these tend to counterbalance each other for the fuel economy levels examined here. Other components are the wealth transfer, oil cost savings, CO{sub 2} emissions reductions, and energy security benefits. Safety impacts, emissions of criteria pollutants, and consumer`s surplus effects are relatively minor components. The critical issues for automotive fuel economy are therefore: (1) the value of present versus future costs and benefits, (2) the values of external costs and benefits, and (3) the financially cost-effective level of MPG achievable by available technology. 53 refs.

Greene, D.L. [Oak Ridge National Lab., TN (United States); Duleep, K.G. [Energy and Environmental Analysis, Inc., Arlington, VA (United States)

1992-03-01T23:59:59.000Z

347

Costs and benefits of automotive fuel economy improvement: A partial analysis  

SciTech Connect

This paper is an exercise in estimating the costs and benefits of technology-based fuel economy improvements for automobiles and light trucks. Benefits quantified include vehicle cots, fuel savings, consumer's surplus effects, the effect of reduced weight on vehicle safety, impacts on emissions of CO{sub 2} and criteria pollutants, world oil market and energy security benefits, and the transfer of wealth from US consumes to oil producers. A vehicle stock model is used to capture sales, scrappage, and vehicle use effects under three fuel price scenarios. Three alternative fuel economy levels for 2001 are considered, ranging from 32.9 to 36.5 MPG for cars and 24.2 to 27.5 MPG for light trucks. Fuel economy improvements of this size are probably cost-effective. The size of the benefit, and whether there is a benefit, strongly depends on the financial costs of fuel economy improvement and judgments about the values of energy security, emissions, safety, etc. Three sets of values for eight parameters are used to define the sensitivity of costs and benefits to key assumptions. The net present social value (1989$) of costs and benefits ranges from a cost of $11 billion to a benefit of $286 billion. The critical parameters being the discount rate (10% vs. 3%) and the values attached to externalities. The two largest components are always the direct vehicle costs and fuel savings, but these tend to counterbalance each other for the fuel economy levels examined here. Other components are the wealth transfer, oil cost savings, CO{sub 2} emissions reductions, and energy security benefits. Safety impacts, emissions of criteria pollutants, and consumer's surplus effects are relatively minor components. The critical issues for automotive fuel economy are therefore: (1) the value of present versus future costs and benefits, (2) the values of external costs and benefits, and (3) the financially cost-effective level of MPG achievable by available technology. 53 refs.

Greene, D.L. (Oak Ridge National Lab., TN (United States)); Duleep, K.G. (Energy and Environmental Analysis, Inc., Arlington, VA (United States))

1992-03-01T23:59:59.000Z

348

Neutron Resonance Transmission Analysis (NRTA): Initial Studies of a Method for Assaying Plutonium in Spent Fuel  

SciTech Connect

Neutron Resonance Transmission Analysis (NRTA) is an analytical technique that uses neutrons to assay the isotopic content of bulk materials. The technique uses a pulsed accelerator to produce an intense, short pulse of neutrons in a time-of-flight configuration. These neutrons, traveling at different speeds according to their energy, can be used to interrogate a spent fuel (SF) assembly to determine its plutonium content. Neutron transmission through the assembly is monitored as a function of neutron energy (time after the pulse), similar to the way neutron cross-section data is often collected. The transmitted neutron intensity is recorded as a function of time, with faster (higher-energy) neutrons arriving first and slower (lower-energy) neutrons arriving later. The low-energy elastic scattering and absorption resonances of plutonium and other isotopes modulate the transmitted neutron spectrum. Plutonium content in SF can be determined by analyzing this attenuation. Work is currently underway at Idaho National Laboratory, as a part of United States Department of Energy's Next Generation Safeguards Initiative (NGSI), to investigate the NRTA technique and to assess its feasibility for quantifying the plutonium content in SF and for determining the diversion of SF pins from assemblies. Preliminary results indicate that NRTA has great potential for being able to assay intact SF assemblies. Operating in the 1-40 eV range, it can identify four plutonium isotopes (239, 240, 241, & 242Pu), three uranium isotopes (235, 236, & 238U), and six resonant fission products (99Tc, 103Rh, 131Xe, 133Cs, 145Nd, and 152Sm). It can determine the areal density or mass of these isotopes in single- or multiple-pin integral transmission scans. Further, multiple observables exist to allow the detection of material diversion (pin defects) including fast-neutron and x-ray radiography, gross-transmission neutron counting, plutonium resonance absorption analysis, and fission-product resonance absorption analysis. Initial benchmark modeling has shown excellent agreement with previously published experimental data for measurements of individual SF pins where plutonium assays were experimentally demonstrated to have a precision of better than 3%.

David L. Chichester; James W. Sterbentz

2011-05-01T23:59:59.000Z

349

Analysis of Two Biomass Gasification/Fuel Cell Scenarios for Small-Scale Power Generation  

DOE Green Energy (OSTI)

Two scenarios were examined for small-scale electricity production from biomass using a gasifier/fuel cell system. In one case, a stand-alone BCL/FERC gasifier is used to produce synthesis gas that is reformed and distributed through a pipeline network to individual phosphoric acid fuel cells. In the second design, the gasifier is integrated with a molten carbonate fuel cell stack and a steam bottoming cycle. In both cases, the gasifiers are fed the same amount of material, with the integrated system producing 4 MW of electricity, and the stand-alone design generating 2 MW of electricity.

Amos, W. A.

1999-01-12T23:59:59.000Z

350

Use of Sensitivity and Uncertainty Analysis in the Design of Reactor Physics and Criticality Benchmark Experiments for Advanced Nuclear Fuel  

Science Conference Proceedings (OSTI)

Technical Paper / Advances in Nuclear Fuel Management - Increased Enrichment/High Burnup and Light Water Reactor Fuel Cycle Optimization

B. T. Rearden; W. J. Anderson; G. A. Harms

351

Techno-economic analysis of pressurized oxy-fuel combustion power cycle for CO? capture  

E-Print Network (OSTI)

Growing concerns over greenhouse gas emissions have driven extensive research into new power generation cycles that enable carbon dioxide capture and sequestration. In this regard, oxy-fuel combustion is a promising new ...

Hong, Jongsup

2009-01-01T23:59:59.000Z

352

CO? abatement by multi-fueled electric utilities: an analysis based on Japanese data  

E-Print Network (OSTI)

Multi-fueled electric utilities are commonly seen as offering relatively greater opportunities for reasonably priced carbon abatement through changes in the dispatch of generating units from capacity using high emission ...

Ellerman, A. Denny.; Tsukada, Natsuki.

353

A Low-Carbon Fuel Standard for California, Part 1: Technical Analysis  

E-Print Network (OSTI)

53 Figure 3-2: Production costs and GHG emissions for fossil58 Figure 3-5: Fuel production costFigure 4-5: Ethanol production costs from MSW with variable

Farrell, Alexander E.; Sperling, Dan

2007-01-01T23:59:59.000Z

354

A Low-Carbon Fuel Standard for California Part 1: Technical Analysis  

E-Print Network (OSTI)

53 Figure 3-2: Production costs and GHG emissions for fossil58 Figure 3-5: Fuel production costFigure 4-5: Ethanol production costs from MSW with variable

2007-01-01T23:59:59.000Z

355

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

171 Emissions related to the use of lubricating oil by motoruse of lubricating oil by motor vehicles The LEM estimatesoil refining to gasoline), the efficiency of fuel use by motor

Delucchi, Mark

2005-01-01T23:59:59.000Z

356

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

171 Emissions related to the use of lubricating oil by motoruse of lubricating oil by motor vehicles The LEM estimatesoil refining to gasoline), the efficiency of fuel use by motor

Delucchi, Mark

2005-01-01T23:59:59.000Z

357

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

total world mine production of uranium, Australia producedin 2010 mine production will satisfy 75% of world uraniummine production worldwide, 0.50 for reprocessed tails and spent fuel, and 0.30 for military high-enriched uranium.

Delucchi, Mark

2005-01-01T23:59:59.000Z

358

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

total world mine production of uranium, Australia producedin 2010 mine production will satisfy 75% of world uraniummine production worldwide, 0.50 for reprocessed tails and spent fuel, and 0.30 for military high-enriched uranium.

Delucchi, Mark

2005-01-01T23:59:59.000Z

359

A Low-Carbon Fuel Standard for California, Part 1: Technical Analysis  

E-Print Network (OSTI)

A. Miller (1980). "Oil Shales and Carbon Dioxide." Sciencefor CO2 evolved from oil shale." Fuel Processing TechnologyCTLs, or CTL synfuels), and oil shale-based synthetic crude

Farrell, Alexander E.; Sperling, Dan

2007-01-01T23:59:59.000Z

360

A Low-Carbon Fuel Standard for California Part 1: Technical Analysis  

E-Print Network (OSTI)

A. Miller (1980). "Oil Shales and Carbon Dioxide." Sciencefor CO2 evolved from oil shale." Fuel Processing TechnologyCTLs, or CTL synfuels), and oil shale-based synthetic crude

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

A Low-Carbon Fuel Standard for California, Part 1: Technical Analysis  

E-Print Network (OSTI)

for CO2 evolved from oil shale." Fuel Processing TechnologyT. and G. A. Miller (1980). "Oil Shales and Carbon Dioxide."oil, coal, tar sands, oil shale Natural gas, biomass Natural

Farrell, Alexander; Sperling, Daniel

2007-01-01T23:59:59.000Z

362

Sensitivity analysis and optimization of the nuclear fuel cycle : a systematic approach  

E-Print Network (OSTI)

For decades, nuclear energy development was based on the expectation that recycling of the fissionable materials in the used fuel from today's light water reactors into advanced (fast) reactors would be implemented as soon ...

Passerini, Stefano

2012-01-01T23:59:59.000Z

363

A Low-Carbon Fuel Standard for California, Part 2: Policy Analysis  

E-Print Network (OSTI)

S. Denning, C. B. A Low Carbon Fuel Standard for California227-241. E4Tech. 2007. Carbon Reporting under the Renewablepatterns and mechanisms of carbon exchange by terrestrial

Sperling, Daniel; Farrell, Alexander

2007-01-01T23:59:59.000Z

364

A Low-Carbon Fuel Standard for California Part 2: Policy Analysis  

E-Print Network (OSTI)

S. Denning, C. B. A Low Carbon Fuel Standard for California227-241. E4Tech. 2007. Carbon Reporting under the Renewablepatterns and mechanisms of carbon exchange by terrestrial

2007-01-01T23:59:59.000Z

365

A Low-Carbon Fuel Standard for California Part 1: Technical Analysis  

E-Print Network (OSTI)

for CO2 evolved from oil shale." Fuel Processing TechnologyT. and G. A. Miller (1980). "Oil Shales and Carbon Dioxide."oil, coal, tar sands, oil shale Natural gas, biomass Natural

2007-01-01T23:59:59.000Z

366

A Low-Carbon Fuel Standard for California, Part 1: Technical Analysis  

E-Print Network (OSTI)

in the Manufacture of Corn Ethanol. St. Louis, National CornWetcake is a form of corn ethanol co-product that requiresTypical dry-grind corn ethanol facilities burn fossil fuels

Farrell, Alexander E.; Sperling, Dan

2007-01-01T23:59:59.000Z

367

Cost Analysis of PEM Fuel Cell Systems for Transportation: September 30, 2005  

DOE Green Energy (OSTI)

The results of sensitivity and Monte Carlo analyses on PEM fuel cell components and the overall system are presented including the most important cost factors and the effects of selected scenarios.

Carlson, E. J.; Kopf, P.; Sinha, J.; Sriramulu, S.; Yang, Y.

2005-12-01T23:59:59.000Z

368

A Low-Carbon Fuel Standard for California, Part 1: Technical Analysis  

E-Print Network (OSTI)

hybrid vehicles (C5) Fuel cell vehicles Battery electric vehicles Low- GHG Biofuel Existing Vehicles and Advancedand Advanced Batteries Plug-in hybrid vehicles (F5, F10) Battery electric

Farrell, Alexander E.; Sperling, Dan

2007-01-01T23:59:59.000Z

369

A Low-Carbon Fuel Standard for California Part 1: Technical Analysis  

E-Print Network (OSTI)

hybrid vehicles (C5) Fuel cell vehicles Battery electric vehicles Low-GHG Biofuel Existing Vehicles and Advancedand Advanced Batteries Plug-in hybrid vehicles (F5, F10) Battery electric

2007-01-01T23:59:59.000Z

370

Cost-benefit analysis of ultra-low sulfur jet fuel  

E-Print Network (OSTI)

The growth of aviation has spurred increased study of its environmental impacts and the possible mitigation thereof. One emissions reduction option is the introduction of an Ultra Low Sulfur (ULS) jet fuel standard for ...

Kuhn, Stephen (Stephen Richard)

2010-01-01T23:59:59.000Z

371

A Low-Carbon Fuel Standard for California, Part 1: Technical Analysis  

E-Print Network (OSTI)

for production of Fischer Tropsch liquids and power viahigher value is for Fischer-Tropsch liquids. See Section 4.cellulosic ethanol and Fischer-Tropsch diesel fuel from wood

Farrell, Alexander E.; Sperling, Dan

2007-01-01T23:59:59.000Z

372

A Low-Carbon Fuel Standard for California Part 1: Technical Analysis  

E-Print Network (OSTI)

for production of Fischer Tropsch liquids and power viahigher value is for Fischer-Tropsch liquids. See Section 4.cellulosic ethanol and Fischer-Tropsch diesel fuel from wood

2007-01-01T23:59:59.000Z

373

General analysis of breed-and-burn reactors and limited-separations fuel cycles  

E-Print Network (OSTI)

A new theoretical framework is introduced, the "neutron excess" concept, which is useful for analyzing breed-and-burn (B&B) reactors and their fuel cycles. Based on this concept, a set of methods has been developed which ...

Petroski, Robert C

2011-01-01T23:59:59.000Z

374

Assessing the Feasibility of Using Neutron Resonance Transmission Analysis (NRTA) for Assaying Plutonium in Spent Fuel Assemblies  

SciTech Connect

Neutron resonance transmission analysis (NRTA) is an active-interrogation nondestructive assay (NDA) technique capable of assaying spent nuclear fuel to determine plutonium content. Prior experimental work has definitively shown the technique capable of assaying plutonium isotope composition in spent-fuel pins to a precision of approximately 3%, with a spatial resolution of a few millimeters. As a Grand Challenge to investigate NDA options for assaying spent fuel assemblies (SFAs) in the commercial fuel cycle, Idaho National Laboratory has explored the feasibility of using NRTA to assay plutonium in a whole SFA. The goal is to achieve a Pu assay precision of 1%. The NRTA technique uses low-energy neutrons from 0.1-40 eV, at the bottom end of the actinide-resonance range, in a time-of-flight arrangement. Isotopic composition is determined by relating absorption of the incident neutrons to the macroscopic cross-section of the actinides of interest in the material, and then using this information to determine the areal density of the isotopes in the SFA. The neutrons used for NRTA are produced using a pulsed, accelerator-based neutron source. Distinguishable resonances exist for both the plutonium (239,240,241,242Pu) and uranium (235,236,238U) isotopes of interest in spent fuel. Additionally, in this energy range resonances exists for six important fission products (99Tc, 103Rh, 131Xe, 133Cs, 145Nd, and 152Sm) which provide additional information to support spent fuel plutonium assay determinations. Based on extensive modeling of the problem using Monte Carlo-based simulation codes, our preliminary results suggest that by rotating an SFA to acquire four symmetric views, sufficient neutron transmission can be achieved to assay a SFA. In this approach multiple scan information for the same pins may also be unfolded to potentially allow the determination of plutonium for sub-regions of the assembly. For a 17 ? 17 pressurized water reactor SFA, a simplistic preliminary analysis indicates the mass of 239Pu may be determined with a precision on the order of 5%, without the need for operator-supplied fuel information or operational histories. This paper will present our work to date on this topic, indicate our preliminary findings for a conceptual assay approach, discuss resilience against spoofing, and outline our future plans for evaluating the NRTA technique for SFA plutonium determination.

D. L. Chichester; J. W. Sterbentz

2012-07-01T23:59:59.000Z

375

Analysis for a Fast Food Restaurant: Comparison of Three Fuel Choices  

Science Conference Proceedings (OSTI)

Electricity consumes 75 percent or more of the energy dollar of a typical fast food restaurant. This report describes the results of a computer simulation comparing energy costs for four fast food restaurants in Phoenix, Arizona, with differences only in the fuel used for certain end uses. The all-electric restaurant with high-efficiency equipment proved a cost-competitive alternative to the fossil-fuel-based restaurant in this area.

1996-03-09T23:59:59.000Z

376

Coal-fueled high-speed diesel engine development: Task 2, Market assessment and economic analysis  

DOE Green Energy (OSTI)

Based on the preliminary coal engine design developed, this task was conducted to identify the best opportunity(s) to enter the market with the future coal-fueled, high-speed diesel engine. The results of this market and economic feasibility assessment will be used to determine what specific heavy duty engine application(s) are most attractive for coal fuel, and also define basic economic targets for the engine to be competitive.

Not Available

1991-12-01T23:59:59.000Z

377

Industrial fuel choice analysis model. Volume II. Appendices to model documentation  

SciTech Connect

Descriptions, documentation, and other information are included in these appendices dealing with industrial fuel choices: Energy Consumption Data Base; Major Fuel Burning Installation Survey; American Boiler Manufacturers Association Data File; Midrange Energy Forecasting System; Projection Method; Capacity Utilization Rates; Nonboiler Characteristics; Boiler Capital and O and M Cost Data; Nonboiler Capital and O and M Cost Data; Approach to Estimating Energy Impacts of the Coal Conversion Regulatory Program; Index or Acronyms.

1979-01-08T23:59:59.000Z

378

Criticality Analysis for Proposed Maximum Fuel Loading in a Standardized SNF Canister with Type 1a Baskets  

SciTech Connect

This document represents a summary version of the criticality analysis done to support loading SNF in a Type 1a basket/standard canister combination. Specifically, this engineering design file (EDF) captures the information pertinent to the intact condition of four fuel types with different fissile loads and their calculated reactivities. These fuels are then degraded into various configurations inside a canister without the presence of significant moderation. The important aspect of this study is the portrayal of the fuel degradation and its effect on the reactivity of a single canister given the supposition there will be continued moderation exclusion from the canister. Subsequent analyses also investigate the most reactive dry canister in a nine canister array inside a hypothetical transport cask, both dry and partial to complete flooding inside the transport cask. The analyses also includes a comparison of the most reactive configuration to other benchmarked fuels using a software package called TSUNAMI, which is part of the SCALE 5.0 suite of software.

Chad Pope; Larry L. Taylor; Soon Sam Kim

2007-02-01T23:59:59.000Z

379

Fuel processing for fuel cell powered vehicles.  

DOE Green Energy (OSTI)

A number of auto companies have announced plans to have fuel cell powered vehicles on the road by the year 2004. The low-temperature polymer electrolyte fuel cells to be used in these vehicles require high quality hydrogen. Without a hydrogen-refueling infrastructure, these vehicles need to convert the available hydrocarbon fuels into a hydrogen-rich gas on-board the vehicle. Earlier analysis has shown that fuel processors based on partial oxidation reforming are well suited to meet the size and weight targets and the other performance-related needs of on-board fuel processors for light-duty fuel cell vehicles (1).

Ahmed, S.; Wilkenhoener, R.; Lee, S. H. D.; Carter, J. D.; Kumar, R.; Krumpelt, M.

1999-01-22T23:59:59.000Z

380

Data Collection, Quality Assurance, and Analysis Plan for the 2008/2009 Hydrogen and Fuel Cells Knowledge and Opinions Survey  

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

13 13 DATA COLLECTION, QUALITY ASSURANCE, AND ANALYSIS PLAN FOR THE 2008/2009 HYDROGEN AND FUEL CELLS KNOWLEDGE AND OPINIONS SURVEYS R. L. Schmoyer Tykey Truett Susan Diegel September 2008 Prepared by the OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831-6073 Managed by UT-BATTELLE, LLC For the U.S. DEPARTMENT OF ENERGY Under contract No. DE-AC05-00OR22725 Prepared for the Hydrogen Program Office of Energy Efficiency and Renewable Energy U.S. DEPARTMENT OF ENERGY Washington, D.C. Analysis Plan: Hydrogen Surveys i 9/29/2008 TABLE OF CONTENTS ACRONYMS ................................................................................................................ii ABSTRACT ................................................................................................................

Note: This page contains sample records for the topic "full-life-cycle fuel analysis" 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

Thermal-Hydraulic Analysis of Seed-Blanket Unit Duplex Fuel Assemblies with VIPRE-01  

E-Print Network (OSTI)

One of the greatest challenges facing the nuclear power industry is the final disposition of nuclear waste. To meet the needs of the nuclear power industry, a new fuel assembly design, called DUPLEX, has been developed which provides higher fuel burnups, burns transuranic waste while reducing minor actinides, reduces the long term radiotoxicity of spent nuclear fuel, and was developed for use in current light water reactors. The DUPLEX design considered in this thesis is based on a seed and blanket unit (SBU) configuration, where the seed region contains standard UO2 fuel, and the blanket region contains an inert matrix (Pu,Np,Am)O2-MgO-ZrO2 fuel. The research efforts of this thesis are first to consider the higher burnup effects on DUPLEX assembly thermal-hydraulic performance and thermal safety margin over the assemblys expected operational lifetime. In order to accomplish this, an existing burnup-dependent thermal-hydraulic methodology for conventional homogeneous fuel assemblies has been updated to meet the modeling needs specific to SBU-type assemblies. The developed framework dramatically expands the capabilities of the latest thermal-hydraulic evaluation framework such that the most promising and unique DUPLEX fuel design can be evaluated. As part of this updated methodology, the posed DUPLEX design is evaluated with respect to the minimum departure from nucleate boiling ratio, peak fuel temperatures for both regions, and the peak cladding temperatures, under ANS Condition I, II, and III transient events with the thermal-hydraulic code VIPRE-01. Due to difficulty in the fabrication and handling of minor actinide dioxides, documented thermal conductivity values for the considered IMF design are unavailable. In order to develop a representative thermal conductivity model for use in VIPRE-01, an extensive literature survey on the thermal conductivity of (Pu,Np,Am)O2-MgO-ZrO2 component materials and a comprehensive review of combinatory models was performed. Using the updated methodology, VIPRE-01 is used to perform steady-state and transient thermal hydraulic analyses for the DUPLEX fuel assembly. During loss-of-flow accident scenarios, the DUPLEX design is shown to meet imposed safety criteria. However, using the most conservative thermal conductivity modeling approach for (Pu,Np,Am)O2-MgO-ZrO2, the blanket region fuel temperatures remain only slightly below the design limit.

McDermott, Patrick 1987-

2012-12-01T23:59:59.000Z

382

FINAL SAFETY ANALYSIS REPORT--SNAP 1A RADIOISOTOPE FUELED THERMOELECTRIC GENERATOR  

SciTech Connect

The safety aspects involved in utilizing the Task 2 radioisotope-powered thermoelectric generator in a terrestrial satellite are described. It is based upon a generalized satellite mission having a 600-day orbital lifetime. A description of the basic design of the generator is presented in order to establish the analytical model. This includes the generator design, radiocerium fuel properties, and the fuel core. The transport of the generator to the launch site is examined, including the shipping cask, shipping procedures, and shipping hazards. A description of ground handling and vehicle integration is presented including preparation for fuel transfer, transfer, mating of generators to final stage, mating final stage to booster, and auxiliary support equipment. The flight vehicle is presented to complete the analytical model. Contained in this chapter are descriptions of the booster-sustainer, final stage, propellants, and built-in safety systems. The typical missile range is examined with respect to the launch complex and range safety characteristics. The shielding of the fuel is discussed and includes both dose rates and shield thicknesses required. The bare core, shielded generator, fuel transfer operation and dose rates for accidental conditions are treated. mechanism of re-entry from the successful mission is covered. Radiocerium inventories with respect to time and the chronology of re-entry are specifically treated. The multiplicity of conditions for aborted missions is set forth. The definition of aborted missions is treated first in order to present the initial conditions. Following this, a definition of the forces imposed upon the generator is presented. The aborted missions is presented. A large number of initial vehicle failure cases is narrowed down into categories of consequences. Since stratospheric injection of fuel results in cases where the fuel is not contained after re-entry, an extensive discussion of the fall-out mechanism is presented. (auth)

Dix, G.P.

1960-06-30T23:59:59.000Z

383

Spent fuel sabotage test program, characterization of aerosol dispersal : technical review and analysis supplement.  

SciTech Connect

This project seeks to provide vital data required to assess the consequences of a terrorist attack on a spent fuel transportation cask. One such attack scenario involves the use of conical shaped charges (CSC), which are capable of damaging a spent fuel transportation cask. In the event of such an attack, the amount of radioactivity that may be released as respirable aerosols is not known with great certainty. Research to date has focused on measuring the aerosol release from single short surrogate fuel rodlets subjected to attack by a small CSC device in various aerosol chamber designs. The last series of three experiments tested surrogate fuel rodlets made with depleted uranium oxide ceramic pellets in a specially designed double chamber aerosol containment apparatus. This robust testing apparatus was designed to prevent any radioactive release and allow high level radioactive waste disposal of the entire apparatus following testing of actual spent fuel rodlets as proposed. DOE and Sandia reviews of the project to date identified a number of issues. The purpose of this supplemental report is to address and document the DOE review comments and to resolve the issues identified in the Sandia technical review.

Durbin, Samuel G.; Lindgren, Eric Richard

2009-07-01T23:59:59.000Z

384

Analysis of Actual Operating Conditions of an Off-grid Solid Oxide Fuel Cell  

DOE Green Energy (OSTI)

Fuel cells have been proposed as ideal replacements for other technologies in remote locations such as Rural Alaska. A number of suppliers have developed systems that might be applicable in these locations, but there are several requirements that must be met before they can be deployed: they must be able to operate on portable fuels, and be able to operate with little operator assistance for long periods of time. This project was intended to demonstrate the operation of a 5 kW fuel cell on propane at a remote site (defined as one without access to grid power, internet, or cell phone, but on the road system). A fuel cell was purchased by the National Park Service for installation in their newly constructed visitor center at Exit Glacier in the Kenai Fjords National Park. The DOE participation in this project as initially scoped was for independent verification of the operation of this demonstration. This project met with mixed success. The fuel cell has operated over 6 seasons at the facility with varying degrees of success, with one very good run of about 1049 hours late in the summer of 2006, but in general the operation has been below expectations. There have been numerous stack failures, the efficiency of electrical generation has been lower than expected, and the field support effort required has been far higher than expected. Based on the results to date, it appears that this technology has not developed to the point where demonstrations in off road sites are justified.

Dennis Witmer; Thomas Johnson; Jack Schmid

2008-12-31T23:59:59.000Z

385

Fuels - Biodiesel  

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

* Biodiesel * Biodiesel * Butanol * Ethanol * Hydrogen * Natural Gas * Fischer-Tropsch Batteries Cross-Cutting Assessments Engines GREET Hybrid Electric Vehicles Hydrogen & Fuel Cells Materials Modeling, Simulation & Software Plug-In Hybrid Electric Vehicles PSAT Smart Grid Student Competitions Transportation Research and Analysis Computing Center Working With Argonne Contact TTRDC Clean Diesel Fuels Background Reducing our country's dependence on foreign oil and the rising costs of crude oil are primary reasons for a renewed interest in alternative fuels for the transportation sector. Stringent emissions regulations and public concern about mobile sources of air pollution provide additional incentives to develop fuels that generate fewer emissions, potentially reducing the need for sophisticated, expensive exhaust after-treatment devices.

386

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

Science Conference Proceedings (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

387

Steam gasification of tyre waste, poplar, and refuse-derived fuel: A comparative analysis  

SciTech Connect

In the field of waste management, thermal disposal is a treatment option able to recover resources from 'end of life' products. Pyrolysis and gasification are emerging thermal treatments that work under less drastic conditions in comparison with classic direct combustion, providing for reduced gaseous emissions of heavy metals. Moreover, they allow better recovery efficiency since the process by-products can be used as fuels (gas, oils), for both conventional (classic engines and heaters) and high efficiency apparatus (gas turbines and fuel cells), or alternatively as chemical sources or as raw materials for other processes. This paper presents a comparative study of a steam gasification process applied to three different waste types (refuse-derived fuel, poplar wood and scrap tyres), with the aim of comparing the corresponding yields and product compositions and exploring the most valuable uses of the by-products.

Galvagno, S. [Department of Environment, Global Change and Sustainable Development, C.R. ENEA Portici, via Vecchio Macello loc. Granatello, 80055 Portici (Italy)], E-mail: sergio.galvagno@portici.enea.it; Casciaro, G. [Department of Physical Technologies and New Materials, C.R. ENEA Brindisi, SS. 7 Appia-km 706, 72100 Brindisi (Italy); Casu, S. [Department of Environment, Global Change and Sustainable Development, C.R. ENEA Bologna, via Martiri di Monte Sole 4, 40129 Bologna (Italy); Martino, M. [Department of Environment, Global Change and Sustainable Development, C.R. ENEA Trisaia, SS 106 Jonica km 419-500, 75026 Rotondella (Italy); Mingazzini, C. [Department of Physical Technologies and New Materials, C.R. ENEA Faenza, via Ravegnana 186, 48018 Faenza (Italy); Russo, A. [Department of Environment, Global Change and Sustainable Development, C.R. ENEA Trisaia, SS 106 Jonica km 419-500, 75026 Rotondella (Italy); Portofino, S. [Department of Environment, Global Change and Sustainable Development, C.R. ENEA Portici, via Vecchio Macello loc. Granatello, 80055 Portici (Italy)

2009-02-15T23:59:59.000Z

388

Analysis of Underground Storage Tanks System Materials to Increased Leak Potential Associated with E15 Fuel  

DOE Green Energy (OSTI)

The Energy Independence and Security Act (EISA) of 2007 was enacted by Congress to move the nation toward increased energy independence by increasing the production of renewable fuels to meet its transportation energy needs. The law establishes a new renewable fuel standard (RFS) that requires the nation to use 36 billion gallons annually (2.3 million barrels per day) of renewable fuel in its vehicles by 2022. Ethanol is the most widely used renewable fuel in the US, and its production has grown dramatically over the past decade. According to EISA and RFS, ethanol (produced from corn as well as cellulosic feedstocks) will make up the vast majority of the new renewable fuel requirements. However, ethanol use limited to E10 and E85 (in the case of flex fuel vehicles or FFVs) will not meet this target. Even if all of the E0 gasoline dispensers in the country were converted to E10, such sales would represent only about 15 billion gallons per year. If 15% ethanol, rather than 10% were used, the potential would be up to 22 billion gallons. The vast majority of ethanol used in the United States is blended with gasoline to create E10, that is, gasoline with up to 10% ethanol. The remaining ethanol is sold in the form of E85, a gasoline blend with as much as 85% ethanol that can only be used in FFVs. Although DOE remains committed to expanding the E85 infrastructure, that market will not be able to absorb projected volumes of ethanol in the near term. Given this reality, DOE and others have begun assessing the viability of using intermediate ethanol blends as one way to transition to higher volumes of ethanol. In October of 2010, the EPA granted a partial waiver to the Clean Air Act allowing the use of fuel that contains up to 15% ethanol for the model year 2007 and newer light-duty motor vehicles. This waiver represents the first of a number of actions that are needed to move toward the commercialization of E15 gasoline blends. On January 2011, this waiver was expanded to include model year 2001 light-duty vehicles, but specifically prohibited use in motorcycles and off-road vehicles and equipment. UST stakeholders generally consider fueling infrastructure materials designed for use with E0 to be adequate for use with E10, and there are no known instances of major leaks or failures directly attributable to ethanol use. It is conceivable that many compatibility issues, including accelerated corrosion, do arise and are corrected onsite and, therefore do not lead to a release. However, there is some concern that higher ethanol concentrations, such as E15 or E20, may be incompatible with current materials used in standard gasoline fueling hardware. In the summer of 2008, DOE recognized the need to assess the impact of intermediate blends of ethanol on the fueling infrastructure, specifically located at the fueling station. This includes the dispenser and hanging hardware, the underground storage tank, and associated piping. The DOE program has been co-led and funded by the Office of the Biomass Program and Vehicle Technologies Program with technical expertise from the Oak Ridge National Laboratory (ORNL) and the National Renewable Energy Laboratory (NREL). The infrastructure material compatibility work has been supported through strong collaborations and testing at Underwriters Laboratories (UL). ORNL performed a compatibility study investigating the compatibility of fuel infrastructure materials to gasoline containing intermediate levels of ethanol. These results can be found in the ORNL report entitled Intermediate Ethanol Blends Infrastructure Materials Compatibility Study: Elastomers, Metals and Sealants (hereafter referred to as the ORNL intermediate blends material compatibility study). These materials included elastomers, plastics, metals and sealants typically found in fuel dispenser infrastructure. The test fuels evaluated in the ORNL study were SAE standard test fuel formulations used to assess material-fuel compatibility within a relatively short timeframe. Initially, these material studies included test fuels of Fuel C,

Kass, Michael D [ORNL; Theiss, Timothy J [ORNL; Janke, Christopher James [ORNL; Pawel, Steven J [ORNL

2012-07-01T23:59:59.000Z

389

Analysis of Underground Storage Tanks System Materials to Increased Leak Potential Associated with E15 Fuel  

Science Conference Proceedings (OSTI)

The Energy Independence and Security Act (EISA) of 2007 was enacted by Congress to move the nation toward increased energy independence by increasing the production of renewable fuels to meet its transportation energy needs. The law establishes a new renewable fuel standard (RFS) that requires the nation to use 36 billion gallons annually (2.3 million barrels per day) of renewable fuel in its vehicles by 2022. Ethanol is the most widely used renewable fuel in the US, and its production has grown dramatically over the past decade. According to EISA and RFS, ethanol (produced from corn as well as cellulosic feedstocks) will make up the vast majority of the new renewable fuel requirements. However, ethanol use limited to E10 and E85 (in the case of flex fuel vehicles or FFVs) will not meet this target. Even if all of the E0 gasoline dispensers in the country were converted to E10, such sales would represent only about 15 billion gallons per year. If 15% ethanol, rather than 10% were used, the potential would be up to 22 billion gallons. The vast majority of ethanol used in the United States is blended with gasoline to create E10, that is, gasoline with up to 10% ethanol. The remaining ethanol is sold in the form of E85, a gasoline blend with as much as 85% ethanol that can only be used in FFVs. Although DOE remains committed to expanding the E85 infrastructure, that market will not be able to absorb projected volumes of ethanol in the near term. Given this reality, DOE and others have begun assessing the viability of using intermediate ethanol blends as one way to transition to higher volumes of ethanol. In October of 2010, the EPA granted a partial waiver to the Clean Air Act allowing the use of fuel that contains up to 15% ethanol for the model year 2007 and newer light-duty motor vehicles. This waiver represents the first of a number of actions that are needed to move toward the commercialization of E15 gasoline blends. On January 2011, this waiver was expanded to include model year 2001 light-duty vehicles, but specifically prohibited use in motorcycles and off-road vehicles and equipment. UST stakeholders generally consider fueling infrastructure materials designed for use with E0 to be adequate for use with E10, and there are no known instances of major leaks or failures directly attributable to ethanol use. It is conceivable that many compatibility issues, including accelerated corrosion, do arise and are corrected onsite and, therefore do not lead to a release. However, there is some concern that higher ethanol concentrations, such as E15 or E20, may be incompatible with current materials used in standard gasoline fueling hardware. In the summer of 2008, DOE recognized the need to assess the impact of intermediate blends of ethanol on the fueling infrastructure, specifically located at the fueling station. This includes the dispenser and hanging hardware, the underground storage tank, and associated piping. The DOE program has been co-led and funded by the Office of the Biomass Program and Vehicle Technologies Program with technical expertise from the Oak Ridge National Laboratory (ORNL) and the National Renewable Energy Laboratory (NREL). The infrastructure material compatibility work has been supported through strong collaborations and testing at Underwriters Laboratories (UL). ORNL performed a compatibility study investigating the compatibility of fuel infrastructure materials to gasoline containing intermediate levels of ethanol. These results can be found in the ORNL report entitled Intermediate Ethanol Blends Infrastructure Materials Compatibility Study: Elastomers, Metals and Sealants (hereafter referred to as the ORNL intermediate blends material compatibility study). These materials included elastomers, plastics, metals and sealants typically found in fuel dispenser infrastructure. The test fuels evaluated in the ORNL study were SAE standard test fuel formulations used to assess material-fuel compatibility within a relatively short timeframe. Initially, these material studies included test fuels of Fuel C,

Kass, Michael D [ORNL; Theiss, Timothy J [ORNL; Janke, Christopher James [ORNL; Pawel, Steven J [ORNL

2012-07-01T23:59:59.000Z

390

Validation of EPRI Methodology for Analysis of Spend-Fuel Cask Drop and Tipover Events  

Science Conference Proceedings (OSTI)

Dry storage pads(typically consisting of reinforced concrete slabs constructed on engineered fill(ultimately serve as in situ impact limiters which can be designed to minimize the impact forces on a spent-fuel storage cask. This report presents experimental validation of a previously developed EPRI method for calculating deceleration forces sustained by a spent-fuel cask during its accidental drop or tipover onto a concrete storage pad. The report also describes a step-by-step procedure for applying the ...

1997-09-12T23:59:59.000Z

391

Comparison and Analysis of Regulatory and Derived Requirements for Certain DOE Spent Nuclear Fuel Shipments; Lessons Learned for Future Spent Fuel Transportation Campaigns  

Science Conference Proceedings (OSTI)

Radioactive materials transportation is stringently regulated by the Department of Transportation and the Nuclear Regulatory Commission to protect the public and the environment. As a Federal agency, however, the U.S. Department of Energy (DOE) must seek State, Tribal and local input on safety issues for certain transportation activities. This interaction has invariably resulted in the imposition of extra-regulatory requirements, greatly increasing transportation costs and delaying schedules while not significantly enhancing the level of safety. This paper discusses the results an analysis of the regulatory and negotiated requirements established for a July 1998 shipment of spent nuclear fuel from foreign countries through the west coast to the Idaho National Engineering and Environmental Laboratory (INEEL). Staff from the INEEL Nuclear Materials Engineering and Disposition Department undertook the analysis in partnership with HMTC, to discover if there were instances where requirements derived from stakeholder interactions duplicate, contradict, or otherwise overlap with regulatory requirements. The study exhaustively lists and classifies applicable Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regulations. These are then compared with a similarly classified list of requirements from the Environmental Impact Statements (EIS) and those developed during stakeholder negotiations. Comparison and analysis reveals numerous attempts to reduce transportation risk by imposing more stringent safety measures than those required by DOT and NRC. These usually took the form of additional inspection, notification and planning requirements. There are also many instances of overlap with, and duplication of regulations. Participants will gain a greater appreciation for the need to understand the risk-oriented basis of the radioactive materials regulations and their effectiveness in ensuring safety when negotiating extra-regulatory requirements.

Kramer, George L., Ph.D.; Fawcett, Rick L.; Rieke, Philip C.

2003-02-27T23:59:59.000Z

392

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

SciTech Connect

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

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

2007-05-01T23:59:59.000Z

393

Analysis of using fuel cell technology for autonomous underwater vehicle power supply  

Science Conference Proceedings (OSTI)

Nowadays underwater robotics aims at semi or whole autonomous underwater vehicles. Autonomy of underwater robots depends on their control systems usually based on artificial intelligence methods and capacity of supply sources mounted on their boards. ... Keywords: fuel cell, underwater vehicle power supply

Grzegorz Grzeczka; Piotr Szymak

2009-05-01T23:59:59.000Z

394

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

Administration, Persian Gulf Oil and Gas Exports Fact Sheet,Emissions from the Oil and Gas Industry, Report Numbern.e. FTD NG n.e. Fuel oil Still gas oil n.a. n.a. n.a. n.a.

Delucchi, Mark

2005-01-01T23:59:59.000Z

395

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

Administration, Persian Gulf Oil and Gas Exports Fact Sheet,Emissions from the Oil and Gas Industry, Report Numbern.e. FTD NG n.e. Fuel oil Still gas oil n.a. n.a. n.a. n.a.

Delucchi, Mark

2005-01-01T23:59:59.000Z

396

Analysis of Technology Options to Reduce the Fuel Consumption of Idling Trucks  

SciTech Connect

Long-haul trucks idling overnight consume more than 838 million gallons (20 million barrels) of fuel annually. Idling also emits pollutants. Truck drivers idle their engines primarily to (1) heat or cool the cab and/or sleeper, (2) keep the fuel warm in winter, and (3) keep the engine warm in the winter so that the engine is easier to start. Alternatives to overnight idling could save much of this fuel, reduce emissions, and cut operating costs. Several fuel-efficient alternatives to idling are available to provide heating and cooling: (1) direct-fired heater for cab/sleeper heating, with or without storage cooling; (2) auxiliary power units; and (3) truck stop electrification. Many of these technologies have drawbacks that limit market acceptance. Options that supply electricity are economically viable for trucks that are idled for 1,000-3,000 or more hours a year, while heater units could be used across the board. Payback times for fleets, which would receive quantity discounts on the prices, would be somewhat shorter.

F. Stodolsky; L. Gaines; A. Vyas

2000-06-01T23:59:59.000Z

397

Drive Cycle Analysis, Measurement of Emissions and Fuel Consumption of a PHEV School Bus: Preprint  

DOE Green Energy (OSTI)

The National Renewable Energy Laboratory (NREL) collected and analyzed real-world school bus drive cycle data and selected similar standard drive cycles for testing on a chassis dynamometer. NREL tested a first-generation plug-in hybrid electric vehicle (PHEV) school bus equipped with a 6.4L engine and an Enova PHEV drive system comprising a 25-kW/80 kW (continuous/peak) motor and a 370-volt lithium ion battery pack. A Bluebird 7.2L conventional school bus was also tested. Both vehicles were tested over three different drive cycles to capture a range of driving activity. PHEV fuel savings in charge-depleting (CD) mode ranged from slightly more than 30% to a little over 50%. However, the larger fuel savings lasted over a shorter driving distance, as the fully charged PHEV school bus would initially operate in CD mode for some distance, then in a transitional mode, and finally in a charge-sustaining (CS) mode for continued driving. The test results indicate that a PHEV school bus can achieve significant fuel savings during CD operation relative to a conventional bus. In CS mode, the tested bus showed small fuel savings and somewhat higher nitrogen oxide (NOx) emissions than the baseline comparison bus.

Barnitt, R.; Gonder, J.

2011-04-01T23:59:59.000Z

398

Development program for heat balance analysis fuel to steam efficiency boiler and data wireless transfer  

Science Conference Proceedings (OSTI)

This research aim to improve a combustion system of boiler within increase combustion efficiency and use all out of the energy. The large boilers were used in the industrial factories which consume a lot of energy for production. By oil and gas fuel ... Keywords: boiler, cogeneration energy, heat balance, steam efficiency, wireless data transfer

Nattapong Phanthuna; Warunee Srisongkram; Sunya Pasuk; Thaweesak Trongtirakul

2009-02-01T23:59:59.000Z

399

Analysis and design of high frequency link power conversion systems for fuel cell power conditioning  

E-Print Network (OSTI)

In this dissertation, new high frequency link power conversion systems for the fuel cell power conditioning are proposed to improve the performance and optimize the cost, size, and weight of the power conversion systems. The first study proposes a new soft switching technique for the phase-shift controlled bi-directional dc-dc converter. The described dc-dc converter employs a low profile high frequency transformer and two active full-bridge converters for bidirectional power flow capability. The proposed new soft switching technique guarantees soft switching over wide range from no load to full load without any additional circuit components. The load range for proposed soft switching technique is analyzed by mathematical approach with equivalent circuits and verified by experiments. The second study describes a boost converter cascaded high frequency link direct dc-ac converter suitable for fuel cell power sources. A new multi-loop control for a boost converter to reduce the low frequency input current harmonics drawn from the fuel cell is proposed, and a new PWM technique for the cycloconverter at the secondary to reject the low order harmonics in the output voltages is presented. The performance of the proposed scheme is verified by the various simulations and experiments, and their trade-offs are described in detail using mathematical evaluation approach. The third study proposes a current-fed high frequency link direct dc-ac converter suitable for residential fuel cell power systems. The high frequency full-bridge inverter at the primary generates sinusoidally PWM modulated current pulses with zero current switching (ZCS), and the cycloconverter at the secondary which consists of only two bidirectional switches and output filter capacitors produces sinusoidally modulated 60Hz split single phase output voltage waveforms with near zero current switching. The active harmonic filter connected to the input terminal compensates the low order input current harmonics drawn from the fuel cell without long-term energy storage devices such as batteries and super capacitors.

Song, Yu Jin

2004-08-01T23:59:59.000Z

400

Analysis of drying wood waste fuels with boiler exhaust gases: simulation, performance, and economics  

DOE Green Energy (OSTI)

This study evaluates the feasibility of retrofitting a rotary dryer to a hog fuel boiler, using the boiler exhaust gases as the drying medium. Two simulation models were developed. Each model accurately predicts system performance given site-specific parameters such as boiler steam demand, fue moisture content, boiler exhaust temperature and combustion excess air. Three rotary dryers/hog fuel boilers currently in operation in the forest products industry were analyzed. The data obtained were used to validate te accuracy of the simulation models and to establish the performance of boiler/dryer systems under field conditions. The boiler exhaust temperatures observed ranged from 340 to 500/sup 0/F and indicated that significant drying could be realized at moderate stack temperatures, as substantitated by experimental moisture content data. The simulation models were used to evaluate a general boiler/dryer system's sensitivity to variation in operating conditions. The sensitivity analyses indicated that under moderate conditions (400/sup 0/F boiler exhaust, etc.) the installation of a rotary dryer results in a 15% increase in boiler efficiency and a 13% decrease in fuel consumption. Both the field data and sensitivity analyses indicated that a greater increase in boiler efficiency could be realized at higher stack temperatures, approximately a 30% increase in boiler efficiency for a stack temperature of 600/sup 0/F. The cash flow basis payback periods based on hog fuel savings due to dryer installation ranged from 2.7 years for a used dryer to 3.9 years for a new dryer. The payback periods for equivalent BTU savings of gas and oil ranged from 1.2 to 2.0 for gas and from 1.3 to 2.1 years for oil. This study concludes that retrofitting a rotary dryer to an existing hog fuel boiler is an economically feasible option to the forest products industry. 31 references, 24 figures, 18 tables.

Kirk, R.W.; Wilson, J.B.

1984-09-01T23:59:59.000Z

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


401

Use of Sensitivity and Uncertainty Analysis in the Design of Reactor Physics and Criticality Benchmark Experiments for Advanced Nuclear Fuel  

SciTech Connect

Framatome ANP, Sandia National Laboratories (SNL), Oak Ridge National Laboratory (ORNL), and the University of Florida are cooperating on the U.S. Department of Energy Nuclear Energy Research Initiative (NERI) project 2001-0124 to design, assemble, execute, analyze, and document a series of critical experiments to validate reactor physics and criticality safety codes for the analysis of commercial power reactor fuels consisting of UO{sub 2} with {sup 235}U enrichments {>=}5 wt%. The experiments will be conducted at the SNL Pulsed Reactor Facility.Framatome ANP and SNL produced two series of conceptual experiment designs based on typical parameters, such as fuel-to-moderator ratios, that meet the programmatic requirements of this project within the given restraints on available materials and facilities. ORNL used the Tools for Sensitivity and Uncertainty Analysis Methodology Implementation (TSUNAMI) to assess, from a detailed physics-based perspective, the similarity of the experiment designs to the commercial systems they are intended to validate. Based on the results of the TSUNAMI analysis, one series of experiments was found to be preferable to the other and will provide significant new data for the validation of reactor physics and criticality safety codes.

Rearden, B.T. [Oak Ridge National Laboratory (United States); Anderson, W.J. [Framatome ANP, Inc. (France); Harms, G.A. [Sandia National Laboratories (United States)

2005-08-15T23:59:59.000Z

402

High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor With Results from FY-2011 Activities  

SciTech Connect

The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450MWth DB-HTRs. The TRISO fuel microanalysis covers the gas pressure buildup in a coated fuel particle including helium production, the thermo-mechanical behavior of a CFP, the failure probabilities of CFPs, the temperature distribution in a CPF, and the fission product (FP) transport in a CFP and a graphite. In Chapter VIII, it contains the core design and analysis of sodium cooled fast reactor (SFR) with deep burn HTR reactor. It considers a synergistic combination of the DB-MHR and an SFR burner for a safe and efficient transmutation of the TRUs from LWRs. Chapter IX describes the design and analysis results of the self-cleaning (or self-recycling) HTR core. The analysis is considered zero and 5-year cooling time of the spent LWR fuels.

Michael A. Pope

2011-10-01T23:59:59.000Z

403

Inductive Double-Contingency Analysis of UO2 Powder Bulk Blending Operations at a Commercial Fuel Plant (U)  

SciTech Connect

An inductive double-contingency analysis (DCA) method developed by the criticality safety function at the Savannah River Site, was applied in Criticality Safety Evaluations (CSEs) of five major plant process systems at the Westinghouse Electric Corporation`s Commercial Nuclear Fuel Manufacturing Plant in Columbia, South Carolina (WEC-Cola.). The method emphasizes a thorough evaluation of the controls intended to provide barriers against criticality for postulated initiating events, and has been demonstrated effective at identifying common mode failure potential and interdependence among multiple controls. A description of the method and an example of its application is provided.

Skiles, S. K. [Westinghouse Savannah River Company, Aiken, SC (United States)

1994-12-22T23:59:59.000Z

404

DATA COLLECTION, QUALITY ASSURANCE, AND ANALYSIS PLAN FOR THE 2008/2009 HYDROGEN AND FUEL CELLS KNOWLEDGE AND OPINIONS SURVEYS  

DOE Green Energy (OSTI)

The 2008/2009 Knowledge and Opinions Survey, conducted for the Department of Energy's Hydrogen Program will measure the levels of awareness and understanding of hydrogen and fuel cell technologies within five target populations: (1) the general public, (2) students, (3) personnel in state and local governments, (4) potential end users of hydrogen fuel and fuel cell technologies in business and industry, and (5) safety and code officials. The ultimate goal of the surveys is a statistically valid, nationally based assessment. Distinct information collections are required for each of the target populations. Each instrument for assessing baseline knowledge is targeted to the corresponding population group. While many questions are identical across all populations, some questions are unique to each respondent group. The biggest data quality limitation of the hydrogen survey data (at least of the general public and student components) will be nonresponse bias. To ensure as high a response rate as possible, various measures will be taken to minimize nonresponse, including automated callbacks, cycling callbacks throughout the weekdays, and availability of Spanish speaking interviewers. Statistical adjustments (i.e., sampling weights) will also be used to account for nonresponse and noncoverage. The primary objective of the data analysis is to estimate the proportions of target population individuals who would respond to the questions in the various possible ways. Data analysis will incorporate necessary adjustments for the sampling design and sampling weights (i.e., probability sampling). Otherwise, however, the analysis will involve standard estimates of proportions of the interviewees responding in various ways to the questions. Sample-weight-adjusted contingency table chi-square tests will also be computed to identify differences between demographic groups The first round of Knowledge and Opinions Surveys was conducted in 2004. Analysis of these surveys produced a baseline assessment of technical knowledge about hydrogen and fuel cells and a statistically valid description of opinions about safety and potential usage in the United States. The current surveys will repeat the process used in 2004. In addition the 2008/2009 survey results will be compared with the 2004 baseline results to assess changes in knowledge levels and opinions. In 2011/2012, the surveys will be repeated, and changes in knowledge and opinions will again be assessed. The information gained from these surveys will be used to enhance and update the DOE Hydrogen Program's education efforts.

Schmoyer, Richard L [ORNL; Truett, Lorena Faith [ORNL; Diegel, Susan W [ORNL

2008-09-01T23:59:59.000Z

405

Thermal analysis for a spent reactor fuel storage test in granite  

Science Conference Proceedings (OSTI)

A test is conducted in which spent fuel assemblies from an operating commercial nuclear power reactor are emplaced in the Climax granite at the US Department of Energy`s Nevada Test Site. In this generic test, 11 canisters of spent PWR fuel are emplaced vertically along with 6 electrical simulator canisters on 3 m centers, 4 m below the floor of a storage drift which is 420 m below the surface. Two adjacent parallel drifts contain electrical heaters, operated to simulate (in the vicinity of the storage drift) the temperature fields of a large repository. This test, planned for up to five years duration, uses fairly young fuel (2.5 years out of core) so that the thermal peak will occur during the time frame of the test and will not exceed the peak that would not occur until about 40 years of storage had older fuel (5 to 15 years out of core) been used. This paper describes the calculational techniques and summarizes the results of a large number of thermal calculations used in the concept, basic design and final design of the spent fuel test. The results of the preliminary calculations show the effects of spacing and spent fuel age. Either radiation or convection is sufficient to make the drifts much better thermal conductors than the rock that was removed to create them. The combination of radiation and convection causes the drift surfaces to be nearly isothermal even though the heat source is below the floor. With a nominal ventilation rate of 2 m{sup 3}/s and an ambient rock temperature of 23{sup 0}C, the maximum calculated rock temperature (near the center of the heat source) is about 100{sup 0}C while the maximum air temperature in the drift is around 40{sup 0}C. This ventilation (1 m{sup 3}/s through the main drift and 1/2 m{sup 3}/s through each of the side drifts) will remove about 1/3 of the heat generated during the first five years of storage.

Montan, D.N.

1980-09-01T23:59:59.000Z

406

Thermal Analysis of Surrogate Simulated Molten Salts with Metal Chloride Impurities for Electrorefining Used Nuclear Fuel  

SciTech Connect

This project is a fundamental study to measure thermal properties (liquidus, solidus, phase transformation, and enthalpy) of molten salt systems of interest to electrorefining operations, which are used in both the fuel cycle research & development mission and the spent fuel treatment mission of the Department of Energy. During electrorefining operations the electrolyte accumulates elements more active than uranium (transuranics, fission products and bond sodium). The accumulation needs to be closely monitored because the thermal properties of the electrolyte will change as the concentration of the impurities increases. During electrorefining (processing techniques used at the Idaho National Laboratory to separate uranium from spent nuclear fuel) it is important for the electrolyte to remain in a homogeneous liquid phase for operational safeguard and criticality reasons. The phase stability of molten salts in an electrorefiner may be adversely affected by the buildup of fission products in the electrolyte. Potential situations that need to be avoided are: (i) build up of fissile elements in the salt approaching the criticality limits specified for the vessel (ii) freezing of the salts due to change in the liquidus temperature and (iii) phase separation (non-homogenous solution) of elements. The stability (and homogeneity) of the phases can potentially be monitored through the thermal characterization of the salts, which can be a function of impurity concentration. This work describes the experimental results of typical salts compositions, consisting of chlorides of strontium, samarium, praseodymium, lanthanum, barium, cerium, cesium, neodymium, sodium and gadolinium (as a surrogate for both uranium and plutonium), used in the processing of used nuclear fuels. Differential scanning calorimetry was used to analyze numerous salt samples providing results on the thermal properties. The property of most interest to pyroprocessing is the liquidus temperature. It was previously known the liquidus temperature of the molten salt would change as spent fuel is processed through the Mk-IV electrorefiner. However, the extent of the increase in liquidus temperature was not known. This work is first of its kind in determining thermodynamic properties of a molten salt electrolyte containing transuranics, fission products and bond sodium. Experimental data concluded that the melting temperature of the electrolyte will become greater than the operating temperature of the Mk-IV ER during current fuel processing campaigns. Collected data also helps predict when the molten salt electrolyte will no longer be able to support electrorefining operations.

Toni Y. Gutknecht; Guy L. Fredrickson; Vivek Utgikar

2012-04-01T23:59:59.000Z

407

Hydrogen Delivery Infrastructure Analysis - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

3 3 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Amgad Elgowainy (Primary Contact), Marianne Mintz and Krishna Reddi Argonne National Laboratory 9700 South Cass Avenue Argonne, IL 60439 Phone: (630) 252-3074 Email: aelgowainy@anl.gov DOE Manager HQ: Erika Sutherland Phone: (202) 586-3152 Email: Erika.Sutherland@ee.doe.gov Project Start Date: October 2007 Project End Date: Project continuation and direction determined annually by DOE Fiscal Year (FY) 2012 Objectives Identify cost drivers of current technologies for hydrogen * delivery to early market applications of fuel cells Evaluate role of high-pressure tube-trailers in reducing * hydrogen delivery cost Identify and evaluate benefits of synergies between *

408

Analysis of H2 storage needs for early market non-motive fuel cell applications.  

DOE Green Energy (OSTI)

Hydrogen fuel cells can potentially reduce greenhouse gas emissions and the United States dependence on foreign oil, but issues with hydrogen storage are impeding their widespread use. To help overcome these challenges, this study analyzes opportunities for their near-term deployment in five categories of non-motive equipment: portable power, construction equipment, airport ground support equipment, telecom backup power, and man-portable power and personal electronics. To this end, researchers engaged end users, equipment manufacturers, and technical experts via workshops, interviews, and electronic means, and then compiled these data into meaningful and realistic requirements for hydrogen storage in specific target applications. In addition to developing these requirements, end-user benefits (e.g., low noise and emissions, high efficiency, potentially lower maintenance costs) and concerns (e.g., capital cost, hydrogen availability) of hydrogen fuel cells in these applications were identified. Market data show potential deployments vary with application from hundreds to hundreds of thousands of units.

Johnson, Terry Alan; Moreno, Marcina; Arienti, Marco; Pratt, Joseph William; Shaw, Leo; Klebanoff, Leonard E.

2012-03-01T23:59:59.000Z

409

Fuel plate stability experiments and analysis for the Advanced Neutron Source  

Science Conference Proceedings (OSTI)

The planned reactor for the Advanced Neutron Source (ANS) will use closely spaced arrays of involute-shaped fuel plates that will be cooled by water flowing through the channels between the plates. There is concern that at certain coolant flow velocities, adjacent plates may deflect and touch, with resulting failure of the plates. Experiments have been conducted at the Oak Ridge National Laboratory to examine this potential phenomenon. Results of the experiments and comparison with analytical predictions are reported. The tests were conducted using full-scale epoxy plate models of the aluminum/uranium silicide ANS involute-shaped fuel plates. Use of epoxy plates and model theory allowed lower flow velocities and pressures to explore the potential failure mechanism. Plate deflections and channel pressures as functions of the flow velocity are examined. Comparisons with mathematical models are noted.

Swinson, W.F.; Battiste, R.L.; Luttrell, C.R.; Yahr, G.T.

1993-05-01T23:59:59.000Z

410

A MULTI-COUNTRY ANALYSIS OF LIFECYCLE EMISSIONS FROM TRANSPORTATION FUELS AND MOTOR VEHICLES  

E-Print Network (OSTI)

oil n.e. ULSD oil n.e. FTD NG n.e. Fuel oil Still gas oiln.a. n.a. n.a. n.a. n.a. n.a. n.a. n.a. CH2 water CH2 NGMeOH NG n.e. MeOH coal n.e. MeOH Ethanol Ethanol wood n.e.

Delucchi, Mark

2005-01-01T23:59:59.000Z

411

A Multi-Country Analysis of Lifecycle Emissions From Transportation Fuels and Motor Vehicles  

E-Print Network (OSTI)

oil n.e. ULSD oil n.e. FTD NG n.e. Fuel oil Still gas oiln.a. n.a. n.a. n.a. n.a. n.a. n.a. n.a. CH2 water CH2 NGMeOH NG n.e. MeOH coal n.e. MeOH Ethanol Ethanol wood n.e.

Delucchi, Mark

2005-01-01T23:59:59.000Z

412

Analysis of dose consequences arising from the release of spent nuclear fuel from dry storage casks.  

SciTech Connect

The resulting dose consequences from releases of spent nuclear fuel (SNF) residing in a dry storage casks are examined parametrically. The dose consequences are characterized by developing dose versus distance curves using simplified bounding assumptions. The dispersion calculations are performed using the MELCOR Accident Consequence Code System (MACCS2) code. Constant weather and generic system parameters were chosen to ensure that the results in this report are comparable with each other and to determine the relative impact on dose of each variable. Actual analyses of site releases would need to accommodate local weather and geographic data. These calculations assume a range of fuel burnups, release fractions (RFs), three exposure scenarios (2 hrs and evacuate, 2 hrs and shelter, and 24 hrs exposure), two meteorological conditions (D-4 and F-2), and three release heights (ground level - 1 meter (m), 10 m, and 100 m). This information was developed to support a policy paper being developed by U.S. Nuclear Regulatory Commission (NRC) staff on an independent spent fuel storage installation (ISFSI) and monitored retrievable storage installation (MRS) security rulemaking.

Durbin, Samuel G.; Morrow, Charles W.

2013-01-01T23:59:59.000Z

413

DOE/EIS-0251; Supplemental Analysis For a Container System for the Management of DOE Spent Nuclear Fuel Located at the INEEL  

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

ID-10636 ID-10636 SUPPLEMENT ANALYSIS FOR A CONTAINER SYSTEM FOR THE MANAGEMENT OF DOE SPENT NUCLEAR FUEL LOCATED AT THE INEEL March 1999 U.S. Department of Energy Idaho Operations Office Idaho Falls, Idaho DOE/ID-10636 SUPPLEMENT ANALYSIS FOR A CONTAINER SYSTEM FOR THE MANAGEMENT OF DOE SPENT NUCLEAR FUEL LOCATED AT THE INEEL March 1999 Department of Energy Idaho Operations Office Idaho Falls, Idaho SNF Supplement Analysis ii March 1999 CONTENTS Acronyms and Abbreviations .............................................................................................. v Summary ..........................................................................................................................S-1 1.0 Purpose and Proposed Action ......................................................................................

414

FCT Fuel Cells: Basics  

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

Basics to someone by E-mail Basics to someone by E-mail Share FCT Fuel Cells: Basics on Facebook Tweet about FCT Fuel Cells: Basics on Twitter Bookmark FCT Fuel Cells: Basics on Google Bookmark FCT Fuel Cells: Basics on Delicious Rank FCT Fuel Cells: Basics on Digg Find More places to share FCT Fuel Cells: Basics on AddThis.com... Home Basics Current Technology DOE R&D Activities Quick Links Hydrogen Production Hydrogen Delivery Hydrogen Storage Technology Validation Manufacturing Codes & Standards Education Systems Analysis Contacts Basics Photo of a fuel cell stack A fuel cell uses the chemical energy of hydrogen to cleanly and efficiently produce electricity with water and heat as byproducts. (How much water?) Fuel cells are unique in terms of the variety of their potential applications; they can provide energy for systems as large as a utility

415

2010-2025 Scenario Analysis for Hydrogen Fuel Cell Vehicles and...  

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

and trade - - offs) need to be assessed as part of offs) need to be assessed as part of scenario analysis. What makes hydrogen scenario analysis. What makes hydrogen FCVs FCVs...

416

Analysis of transport mechanisms in dense fuel droplet sprays. Final report  

DOE Green Energy (OSTI)

This report deals with numerical analyses of fluid mechanics, heat transfer, mass transfer and particle dynamics of interacting spheres and vaporizing droplets in a linear array or on a 1-D trajectory. Available finite element software has been modified and extended to solve several case studies including closely spaced monodisperse spheres with or without blowing; closely spaced vaporizing fuel droplets; and dynamically interacting vaporizing fuel droplets on a 1-D trajectory. Axisymmetric laminar flow has been assumed for three statically or dynamically interacting spherical solids and vaporizing droplets. Emphasis in this work is evaluating the effects of key system parameters, such as free stream Reynolds number, interparticle spacings, liquid/gas-phase viscosity ratio and variable fluid properties, on interfacial transfer processes and on the particle Nusselt number, vaporization rate and drag coefficient. Computer-generated correlations between integral quantities and system parameters were postulated for blowing spheres and vaporizing droplets. In addition to initial Reynolds number and droplet spacings, variable fluid properties, liquid-phase heating and internal droplet circulation have strong effect on the dynamic behavior of multi-droplet systems. While the lead droplet is most significantly affected by all key parameters, the second and third droplet causes distinct interaction effects which are largely dependent on initial droplet spacings. Applications include spherical-structure/fluid-flow interactions, as well as interacting vaporizing droplets in different sprays related to propulsion systems, irrigation, spray coating, etc. Focusing on fuel droplet sprays, results of the dynamic multi-droplet study can assist in better atomizers and combustion chamber designs which may lead to improved combustion efficiencies, smaller/lighter systems, and reduced pollutant emissions.

Kleinstreuer, C.

1991-05-01T23:59:59.000Z

417

Comparative analysis of monetary estimates of external environmental costs associated with combustion of fossil fuels  

SciTech Connect

Public utility commissions in a number of states have begun to explicitly treat costs of environmental externalities in the resource planning and acquisition process (Cohen et al. 1990). This paper compares ten different estimates and regulatory determinations of external environmental costs associated with fossil fuel combustion, using consistent assumptions about combustion efficiency, emissions factors, and resource costs. This consistent comparison is useful because it makes explicit the effects of various assumptions. This paper uses the results of the comparison to illustrate pitfalls in calculation of external environmental costs, and to derive lessons for design of policies to incorporate these externalities into resource planning. 38 refs., 2 figs., 10 tabs.

Koomey, J.

1990-07-01T23:59:59.000Z

418

Polymers for hydrogen infrastructure and vehicle fuel systems : applications, properties, and gap analysis.  

SciTech Connect

This document addresses polymer materials for use in hydrogen service. Section 1 summarizes the applications of polymers in hydrogen infrastructure and vehicle fuel systems and identifies polymers used in these applications. Section 2 reviews the properties of polymer materials exposed to hydrogen and/or high-pressure environments, using information obtained from published, peer-reviewed literature. The effect of high pressure on physical and mechanical properties of polymers is emphasized in this section along with a summary of hydrogen transport through polymers. Section 3 identifies areas in which fuller characterization is needed in order to assess material suitability for hydrogen service.

Barth, Rachel Reina; Simmons, Kevin L. [Pacific Northwest National Laboratory, Richland, WA] [Pacific Northwest National Laboratory, Richland, WA; San Marchi, Christopher W.

2013-10-01T23:59:59.000Z

419

Projections of Full-Fuel-Cycle Energy and Emissions Metrics  

E-Print Network (OSTI)

Nuclear Fuel ..to characterize the nuclear fuel cycle (Wu et al. Renewableby the heat content of nuclear fuel. In this analysis we use

Coughlin, Katie

2013-01-01T23:59:59.000Z

420

Analysis of fresh fuel critical experiments appropriate for burnup credit validation  

SciTech Connect

The ANS/ANS-8.1 standard requires that calculational methods used in determining criticality safety limits for applications outside reactors be validated by comparison with appropriate critical experiments. This report provides a detailed description of 34 fresh fuel critical experiments and their analyses using the SCALE-4.2 code system and the 27-group ENDF/B-IV cross-section library. The 34 critical experiments were selected based on geometry, material, and neutron interaction characteristics that are applicable to a transportation cask loaded with pressurized-water-reactor spent fuel. These 34 experiments are a representative subset of a much larger data base of low-enriched uranium and mixed-oxide critical experiments. A statistical approach is described and used to obtain an estimate of the bias and uncertainty in the calculational methods and to predict a confidence limit for a calculated neutron multiplication factor. The SCALE-4.2 results for a superset of approximately 100 criticals are included in uncertainty analyses, but descriptions of the individual criticals are not included.

DeHart, M.D.; Bowman, S.M.

1995-10-01T23:59:59.000Z

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


421

Hybrid Technique in SCALE for Fission Source Convergence Applied to Used Nuclear Fuel Analysis  

SciTech Connect

The new hybrid SOURCE ConveRgence accelERator (SOURCERER) sequence in SCALE deterministically computes a fission distribution and uses it as the starting source in a Monte Carlo eigenvalue criticality calculation. In addition to taking the guesswork out of defining an appropriate, problem-dependent starting source, the more accurate starting source provided by the deterministic calculation decreases the probability of producing inaccurate tally estimates associated with undersampling problems caused by inadequate source convergence. Furthermore, SOURCERER can increase the efficiency of the overall simulation by decreasing the number of cycles that has to be skipped before the keff accumulation. SOURCERER was applied to a representative example for a used nuclear fuel cask utilized at the Maine Yankee storage site {Scaglione and Ilas}. Because of the time constraints of the Used Fuel Research, Development, and Demonstration project, it was found that using more than 30,000 neutrons per cycle will lead to inaccurate Monte Carlo calculation of keff due to the inevitable decrease in the number of skipped and active cycles used with this problem. For a fixed uncertainty objective and by using 30,000 neutron per cycle, the use of SOURCERER increased the efficiency of the keff calculation by 60%compared to a Monte Carlo calculation that used a starting source distributed uniformly in fissionable regions, even with the inclusion of the extra computational time required by the deterministic calculation. Additionally, the use of SOURCERER increased the reliability of keff calculation using any number of skipped cycles below 350.

Ibrahim, Ahmad M [ORNL; Peplow, Douglas E. [ORNL; Bekar, Kursat B [ORNL; Celik, Cihangir [ORNL; Scaglione, John M [ORNL; Ilas, Dan [ORNL; Wagner, John C [ORNL

2013-01-01T23:59:59.000Z

422

Uncertainty analysis of steady state incident heat flux measurements in hydrocarbon fuel fires.  

SciTech Connect

The objective of this report is to develop uncertainty estimates for three heat flux measurement techniques used for the measurement of incident heat flux in a combined radiative and convective environment. This is related to the measurement of heat flux to objects placed inside hydrocarbon fuel (diesel, JP-8 jet fuel) fires, which is very difficult to make accurately (e.g., less than 10%). Three methods will be discussed: a Schmidt-Boelter heat flux gage; a calorimeter and inverse heat conduction method; and a thin plate and energy balance method. Steady state uncertainties were estimated for two types of fires (i.e., calm wind and high winds) at three times (early in the fire, late in the fire, and at an intermediate time). Results showed a large uncertainty for all three methods. Typical uncertainties for a Schmidt-Boelter gage ranged from {+-}23% for high wind fires to {+-}39% for low wind fires. For the calorimeter/inverse method the uncertainties were {+-}25% to {+-}40%. The thin plate/energy balance method the uncertainties ranged from {+-}21% to {+-}42%. The 23-39% uncertainties for the Schmidt-Boelter gage are much larger than the quoted uncertainty for a radiative only environment (i.e ., {+-}3%). This large difference is due to the convective contribution and because the gage sensitivities to radiative and convective environments are not equal. All these values are larger than desired, which suggests the need for improvements in heat flux measurements in fires.

Nakos, James Thomas

2005-12-01T23:59:59.000Z

423

Fuel Cell Technologies Office: Automotive and MHE Fuel Cell System Cost  

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

Automotive and MHE Automotive and MHE Fuel Cell System Cost Analysis (Text Version) to someone by E-mail Share Fuel Cell Technologies Office: Automotive and MHE Fuel Cell System Cost Analysis (Text Version) on Facebook Tweet about Fuel Cell Technologies Office: Automotive and MHE Fuel Cell System Cost Analysis (Text Version) on Twitter Bookmark Fuel Cell Technologies Office: Automotive and MHE Fuel Cell System Cost Analysis (Text Version) on Google Bookmark Fuel Cell Technologies Office: Automotive and MHE Fuel Cell System Cost Analysis (Text Version) on Delicious Rank Fuel Cell Technologies Office: Automotive and MHE Fuel Cell System Cost Analysis (Text Version) on Digg Find More places to share Fuel Cell Technologies Office: Automotive and MHE Fuel Cell System Cost Analysis (Text Version) on AddThis.com...

424

A Low-Carbon Fuel Standard for California Part 1: Technical Analysis  

E-Print Network (OSTI)

Vehicle Technologies, Argonne National Laboratory, ReportAmerican Analysis: Volume I, Executive Summary. Argonne,Il, Argonne National Laboratory: 47. Jonathan Weinert,

2007-01-01T23:59:59.000Z

425

Neutronic Analysis of a Thorium-Uranium Fueled Water Cooled Fusion-Fission Hybrid Blanket  

Science Conference Proceedings (OSTI)

Nuclear Systems: Analysis and Experiments / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012

S. C. Xiao; Z. Zhou; Jing Zhao; Y. Yang

426

Agenda for the 2010-2025 Scenario Analysis for Hydrogen Fuel...  

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

1:00 pm Program stakeholders convene in 2 parallel breakout groups to discuss scenario analysis results and provide feedback on the following focus questions: Does the...

427

Hydrogen Refueling Infrastructure Cost Analysis - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

9 9 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Marc W. Melaina (Primary Contact), Michael Penev and Darlene Steward National Renewable Energy Laboratory (NREL) 15013 Denver West Parkway Golden, CO 80401 Phone: (303) 275-3836 Email: Marc.Melaina@nrel.gov DOE Manager HQ: Fred Joseck Phone: (202) 586-7932 Email: Fred.Joseck@hq.doe.gov Subcontractor: IDC Energy Insights, Framingham, MA Project Start Date: October 1, 2010 Project End Date: September 28, 2012 Fiscal Year (FY) 2012 Objectives Identify the capacity (kg/day) and capital costs * associated with "Early Commercial" hydrogen stations (defined below) Identify cost metrics for larger numbers of stations and * larger capacities Technical Barriers This project addresses the following technical barriers

428

Resource Analysis for Hydrogen Production - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

3 3 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Marc W. Melaina (Primary Contact), Michael Penev and Donna Heimiller National Renewable Energy Laboratory 15013 Denver West Parkway Golden, CO 80401 Phone: (303) 275-3836 Email: Marc.Melaina@nrel.gov DOE Manager HQ: Fred Joseck Phone: (202) 586-7932 Email: Fred.Joseck@hq.doe.gov Project Start Date: October 1, 2009 Project End Date: September 28, 2012 Fiscal Year (FY) 2012 Objectives Understand the hydrogen production requirements for a * future demand scenario Estimate low-carbon energy resources required to meet * the future scenario demand Compare resource requirements to current consumption * and projected future consumption Determine resource availability geographically and on a *

429

Hydrogen Scenario Analysis Summary Report: Analysis of the Transition to Hydrogen Fuel Cell Vehicles and the Potential Hydrogen Energy Infrastructure Requirements  

DOE Green Energy (OSTI)

Achieving a successful transition to hydrogen-powered vehicles in the U.S. automotive market will require strong and sustained commitment by hydrogen producers, vehicle manufacturers, transporters and retailers, consumers, and governments. The interaction of these agents in the marketplace will determine the real costs and benefits of early market transformation policies, and ultimately the success of the transition itself. The transition to hydrogen-powered transportation faces imposing economic barriers. The challenges include developing and refining a new and different power-train technology, building a supporting fuel infrastructure, creating a market for new and unfamiliar vehicles, and achieving economies of scale in vehicle production while providing an attractive selection of vehicle makes and models for car-buyers. The upfront costs will be high and could persist for a decade or more, delaying profitability until an adequate number of vehicles can be produced and moved into consumer markets. However, the potential rewards to the economy, environment, and national security are immense. Such a profound market transformation will require careful planning and strong, consistent policy incentives. Section 811 of the Energy Policy Act (EPACT) of 2005, Public Law 109-59 (U.S. House, 2005), calls for a report from the Secretary of Energy on measures to support the transition to a hydrogen economy. The report was to specifically address production and deployment of hydrogen-fueled vehicles and the hydrogen production and delivery infrastructure needed to support those vehicles. In addition, the 2004 report of the National Academy of Sciences (NAS, 2004), The Hydrogen Economy, contained two recommendations for analyses to be conducted by the U.S. Department of Energy (DOE) to strengthen hydrogen energy transition and infrastructure planning for the hydrogen economy. In response to the EPACT requirement and NAS recommendations, DOE's Hydrogen, Fuel Cells and Infrastructure Technologies Program (HFCIT) has supported a series of analyses to evaluate alternative scenarios for deployment of millions of hydrogen fueled vehicles and supporting infrastructure. To ensure that these alternative market penetration scenarios took into consideration the thinking of the automobile manufacturers, energy companies, industrial hydrogen suppliers, and others from the private sector, DOE held several stakeholder meetings to explain the analyses, describe the models, and solicit comments about the methods, assumptions, and preliminary results (U.S. DOE, 2006a). The first stakeholder meeting was held on January 26, 2006, to solicit guidance during the initial phases of the analysis; this was followed by a second meeting on August 9-10, 2006, to review the preliminary results. A third and final meeting was held on January 31, 2007, to discuss the final analysis results. More than 60 hydrogen energy experts from industry, government, national laboratories, and universities attended these meetings and provided their comments to help guide DOE's analysis. The final scenarios attempt to reflect the collective judgment of the participants in these meetings. However, they should not be interpreted as having been explicitly endorsed by DOE or any of the stakeholders participating. The DOE analysis examined three vehicle penetration scenarios: Scenario 1--Production of thousands of vehicles per year by 2015 and hundreds of thousands per year by 2019. This option is expected to lead to a market penetration of 2.0 million fuel cell vehicles (FCV) by 2025. Scenario 2--Production of thousands of FCVs by 2013 and hundreds of thousands by 2018. This option is expected to lead to a market penetration of 5.0 million FCVs by 2025. Scenario 3--Production of thousands of FCVs by 2013, hundreds of thousands by 2018, and millions by 2021 such that market penetration is 10 million by 2025. Scenario 3 was formulated to comply with the NAS recommendation: 'DOE should map out and evaluate a transition plan consistent with developing the infrastructure and hydrogen res

Greene, David L [ORNL; Leiby, Paul Newsome [ORNL; James, Brian [Directed Technologies, Inc.; Perez, Julie [Directed Technologies, Inc.; Melendez, Margo [National Renewable Energy Laboratory (NREL); Milbrandt, Anelia [National Renewable Energy Laboratory (NREL); Unnasch, Stefan [Life Cycle Associates; Rutherford, Daniel [TIAX, LLC; Hooks, Matthew [TIAX, LLC

2008-03-01T23:59:59.000Z