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Note: This page contains sample records for the topic "nuclear generation reported" from the National Library of EnergyBeta (NLEBeta).
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1

Nuclear Power Generation and Fuel Cycle Report  

Reports and Publications (EIA)

Final issue. This report provides information and forecasts important to the domestic and world nuclear and uranium industries. 1997 represents the most recent publication year.

Dr. Zdenek D.

1997-09-01T23:59:59.000Z

2

Nuclear power generation and fuel cycle report 1996  

SciTech Connect

This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

NONE

1996-10-01T23:59:59.000Z

3

Next Generation Nuclear Plant GAP Analysis Report  

DOE Green Energy (OSTI)

As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

2008-12-01T23:59:59.000Z

4

Nuclear Power Generation and Fuel Cycle Report 1997  

Gasoline and Diesel Fuel Update (EIA)

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

5

Rancho Seco Nuclear Generating Station Decommissioning Experience Report  

Science Conference Proceedings (OSTI)

Several U.S. nuclear power plants entered decommissioning in the 1990s. Based on current information, the next group of plants whose license will expire will not begin decommissioning for nearly a decade. This report provides detailed information on the decommissioning of one plant, the Rancho Seco Nuclear Generating Station, in order to capture its experience for future plants.

2007-12-19T23:59:59.000Z

6

Nuclear Power Generation and Fuel Cycle Report 1996  

Gasoline and Diesel Fuel Update (EIA)

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

7

San Onofre Nuclear Generating Station - Unit 1 Decommissioning Experience Report  

Science Conference Proceedings (OSTI)

This report provides detailed information on the successful decommissioning activities of San Onofre Nuclear Generating Station, Unit 1 (SONGS 1). The report describes their experiences and lessons learned for managers of US and international plants beginning or currently engaged in decommissioning.

2008-12-04T23:59:59.000Z

8

Nuclear power generation and fuel cycle report 1997  

SciTech Connect

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

1997-09-01T23:59:59.000Z

9

Next Generation Nuclear Plant: A Report to Congress | Department of Energy  

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

Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a high-temperature nuclear energy source. The project is being executed in collaboration with industry, DOE national laboratories, and U.S. universities. The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing and regulatory oversight of the demonstration nuclear reactor.

10

Next Generation Nuclear Plant: A Report to Congress | Department of Energy  

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

Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a high-temperature nuclear energy source. The project is being executed in collaboration with industry, DOE national laboratories, and U.S. universities. The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing and regulatory oversight of the demonstration nuclear reactor.

11

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Final Report  

SciTech Connect

Final report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Mockups applied to design review of AP600/1000, Construction planning for AP 600, and AP 1000 maintenance evaluation. Proof of concept study also performed for GenIV PBMR models.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

12

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 1: Main Report  

DOE Green Energy (OSTI)

A phenomena identification and ranking table (PIRT) process was conducted for the Next Generation Nuclear Plant (NGNP) design. This design (in the conceptual stage) is a modular high-temperature gas-cooled reactor (HTGR) that generates both electricity and process heat for hydrogen production. Expert panels identified safety-relevant phenomena, ranked their importance, and assessed the knowledge levels in the areas of accidents and thermal fluids, fission-product transport and dose, high-temperature materials, graphite, and process heat for hydrogen production. This main report summarizes and documents the process and scope of the reviews, noting the major activities and conclusions. The identified phenomena, analyses, rationales, and associated ratings of the phenomena, plus a summary of each panel's findings, are presented. Individual panel reports for these areas are provided as attached volumes to this main report and provide considerably more detail about each panel's deliberations as well as a more complete listing of the phenomena that were evaluated.

Ball, Sydney J [ORNL

2008-03-01T23:59:59.000Z

13

High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August, 2000 - July 2001  

DOE Green Energy (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August 2000 - July 2001. Currently no large scale, cost-effective, environmentally attractive hydrogen production process is available for commercialization nor has such a process been identified. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Carbon dioxide emissions from fossil fuel combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. The benefits of this work will include the generation of a low-polluting transportable energy feedstock in an efficient method that has little or no implication for greenhouse gas emissions from a primary energy source whose availability and sources are domestically controlled. This will help to ensure energy for a future transportation/energy infrastructure that is not influenced/controlled by foreign governments. This report describes work accomplished during the second year (Phase 2) of a three year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first year (Phase 1) was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water, in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most, three) for further detailed consideration. Phase 1 met its goals and did select one process, the sulfur-iodine process, for investigation in Phases 2 and 3. The combined goals of Phases 2 and 3 were to select the advanced nuclear reactor best suited to driving the selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

Brown, L.C.

2002-11-01T23:59:59.000Z

14

High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August, 2000 - July 2001  

SciTech Connect

OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August 2000 - July 2001. Currently no large scale, cost-effective, environmentally attractive hydrogen production process is available for commercialization nor has such a process been identified. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Carbon dioxide emissions from fossil fuel combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. The benefits of this work will include the generation of a low-polluting transportable energy feedstock in an efficient method that has little or no implication for greenhouse gas emissions from a primary energy source whose availability and sources are domestically controlled. This will help to ensure energy for a future transportation/energy infrastructure that is not influenced/controlled by foreign governments. This report describes work accomplished during the second year (Phase 2) of a three year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first year (Phase 1) was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water, in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most, three) for further detailed consideration. Phase 1 met its goals and did select one process, the sulfur-iodine process, for investigation in Phases 2 and 3. The combined goals of Phases 2 and 3 were to select the advanced nuclear reactor best suited to driving the selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

Brown, L.C.

2002-11-01T23:59:59.000Z

15

Site Selection & Characterization Status Report for Next Generation Nuclear Plant (NGNP)  

SciTech Connect

In the near future, the US Department of Energy (DOE) will need to make important decisions regarding design and construction of the Next Generation Nuclear Plant (NGNP). One part of making these decisions is considering the potential environmental impacts that this facility may have, if constructed here at the Idaho National Laboratory (INL). The National Environmental Policy Act (NEPA) of 1969 provides DOE decision makers with a process to systematically consider potential environmental consequences of agency decisions. In addition, the Energy Policy Act of 2005 (Title VI, Subtitel C, Section 644) states that the 'Nuclear Regulatory Commission (NRC) shall have licensing and regulatory authority for any reactor authorized under this subtitle.' This stipulates that the NRC will license the NGNP for operation. The NRC NEPA Regulations (10 CFR Part 51) require tha thte NRC prepare an Environmental Impact Statement (EIS) for a permit to construct a nuclear power plant. The applicant is required to submit an Environmental report (ER) to aid the NRC in complying with NEPA.

Mark Holbrook

2007-09-01T23:59:59.000Z

16

Fourth generation nuclear weapons: Military effectiveness and collateral effects, Report ISRI-05-03  

E-Print Network (OSTI)

The paper begins with a general introduction and update to Fourth Generation Nuclear Weapons (FGNW), and then addresses some particularly important military aspects on which there has been only limited public discussion so far. These aspects concern the unique military characteristics of FGNWs which make them radically different from both nuclear weapons based on previous-generation nuclear-explosives and from conventional weapons based on chemical-explosives: yields in the 1 to 100 tons range, greatly enhanced coupling to targets, possibility to drive powerful shaped-charge jets and forged fragments, enhanced prompt radiation effects, reduced collateral damage and residual radioactivity, etc.

Andre Gsponer

2005-01-01T23:59:59.000Z

17

Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report  

SciTech Connect

On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

Hebdon, F.J. [Institute of Nuclear Power Operations, Atlanta, GA (United States)

1993-03-01T23:59:59.000Z

18

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 5 Report: Generation IV Reactor Virtual Mockup Proof-of-Principle Study  

SciTech Connect

Task 5 report is part of a 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Created a virtual mockup of PBMR reactor cavity and discussed applications of virtual mockup technology to improve Gen IV design review, construction planning, and maintenance planning.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

19

Nuclear Energy Research Initiative (NERI): On-Line Intelligent Self-Diagnostic Monitoring for Next Generation Nuclear Plants - Phase I Annual Report  

Science Conference Proceedings (OSTI)

OAK-B135 This OSTI ID belongs to an IWO and is being released out of the system. The Program Manager Rebecca Richardson has confirmed that all reports have been received. The objective of this project is to design and demonstrate the operation of the real-time intelligent self-diagnostic and prognostic system for next generation nuclear power plant systems. This new self-diagnostic technology is titled, ''On-Line Intelligent Self-Diagnostic Monitoring System'' (SDMS). This project provides a proof-of-principle technology demonstration for SDMS on a pilot plant scale service water system, where a distributed array of sensors is integrated with active components and passive structures typical of next generation nuclear power reactor and plant systems. This project employs state-of-the-art sensors, instrumentation, and computer processing to improve the monitoring and assessment of the power reactor system and to provide diagnostic and automated prognostics capabilities.

L. J. Bond; S. R. Doctor; R. W. Gilbert; D. B. Jarrell; F. L. Greitzer; R. J. Meador

2000-09-01T23:59:59.000Z

20

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 4 Report: Virtual Mockup Maintenance Task Evaluation  

SciTech Connect

Task 4 report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. This report focuses on using Full-scale virtual mockups for nuclear power plant training applications.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Illinois Nuclear Profile - Dresden Generating Station  

U.S. Energy Information Administration (EIA)

Nuclear Power Plant Data for Dresden Generating Station Author: DOE/EIA Keywords: Dresden Generating Station, Illinois, Nuclear, Plant, Reactor, Generation, Capacity

22

"1. PSEG Salem Generating Station","Nuclear","PSEG Nuclear LLC...  

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

Jersey" "1. PSEG Salem Generating Station","Nuclear","PSEG Nuclear LLC",2370 "2. PSEG Linden Generating Station","Gas","PSEG Fossil LLC",1587 "3. Bergen Generating...

23

Generation IV Nuclear Energy Systems Construction Cost Reductions through the use of Virtual Environments: Task 1 Completion Report  

SciTech Connect

OAK B204 The objective of this project is to demonstrate the feasibility and effectiveness of using full-scale virtual reality simulation in the design, construction, and maintenance of future nuclear power plants. Specifically, this project will test the suitability of Immersive Projection Display (IPD) technology to aid engineers in the design of the next generation nuclear power plant and to evaluate potential cost reductions that can be realized by optimization of installation and construction sequences. The intent is to see if this type of information technology can be used in capacities similar to those currently filled by full-scale physical mockups.

Whisker, V.E.; Baratta, A.J.; Shaw, T.S.; Winters, J.W.; Trikouros, N.; Hess, C.

2002-11-26T23:59:59.000Z

24

NUCLEAR FLASH TYPE STEAM GENERATOR  

DOE Patents (OSTI)

A nuclear steam generating apparatus is designed so that steam may be generated from water heated directly by the nuclear heat source. The apparatus comprises a pair of pressure vessels mounted one within the other, the inner vessel containing a nuclear reactor heat source in the lower portion thereof to which water is pumped. A series of small ports are disposed in the upper portion of the inner vessel for jetting heated water under pressure outwardly into the atmosphere within the interior of the outer vessel, at which time part of the jetted water flashes into steam. The invention eliminates the necessity of any intermediate heat transfer medium and components ordinarily required for handling that medium. (AEC)

Johns, F.L.; Gronemeyer, E.C.; Dusbabek, M.R.

1962-09-01T23:59:59.000Z

25

The Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950°C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.

Dr. David A. Petti

2009-01-01T23:59:59.000Z

26

U.S. Nuclear Generation of Electricity  

U.S. Energy Information Administration (EIA)

U.S. Nuclear Generation: 1957 to latest available EIA final data information in the Annual Energy Review, table 9.2. U. S. Nuclear power plants ...

27

NUCLEAR SCIENCE ANNUAL REPORT 1975  

E-Print Network (OSTI)

Gove and A. H. Wapstra, Nuclear Data Tables 11, 127 (1972).P. Jackson, Chalk River Nuclear Laboratories Report (1975)national Conference on Nuclear Structure and Spec­ troscopy,

Authors, Various

2010-01-01T23:59:59.000Z

28

California Nuclear Profile - San Onofre Nuclear Generating Station  

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

San Onofre Nuclear Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

29

NUCLEAR CHEMISTRY ANNUAL REPORT 1970  

E-Print Network (OSTI)

1970). tpresent address: Chemistry Department, University ofSept. 1970); Nuclear Chemistry Division Annual Report, 1969,S. G. Thompson, in Nuclear Chemistry Division Annual Report

Authors, Various

2011-01-01T23:59:59.000Z

30

Nuclear Maintenance Applications Center: Generator Maintenance Guide for Emergency Diesel Generators  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) developed this report to address maintenance and improve long-term reliability and availability of generators within nuclear power plant emergency diesel generator (EDG) systems.

2010-12-11T23:59:59.000Z

31

Microstructural Characterization of Next Generation Nuclear Graphites  

Science Conference Proceedings (OSTI)

This article reports the microstructural characteristics of various petroleum and pitch based nuclear graphites (IG-110, NBG-18, and PCEA) that are of interest to the next generation nuclear plant program. Bright-field transmission electron microscopy imaging was used to identify and understand the different features constituting the microstructure of nuclear graphite such as the filler particles, microcracks, binder phase, rosette-shaped quinoline insoluble (QI) particles, chaotic structures, and turbostratic graphite phase. The dimensions of microcracks were found to vary from a few nanometers to tens of microns. Furthermore, the microcracks were found to be filled with amorphous carbon of unknown origin. The pitch coke based graphite (NBG-18) was found to contain higher concentration of binder phase constituting QI particles as well as chaotic structures. The turbostratic graphite, present in all of the grades, was identified through their elliptical diffraction patterns. The difference in the microstructure has been analyzed in view of their processing conditions.

Karthik Chinnathambi; Joshua Kane; Darryl P. Butt; William E. Windes; Rick Ubic

2012-04-01T23:59:59.000Z

32

Steam Generator Management Program: Steam Generator Progress Report: Revision 18  

Science Conference Proceedings (OSTI)

BackgroundSince 1985, the Electric Power Research Institute (EPRI) has published the Steam Generator Progress Report (SGPR), which provides historical information on worldwide steam generator activities. This document was published once a year and distributed via hardcopy. Until 1998, the method of acquiring data for this report had been to issue annual survey forms to all PWR and pressurized heavy water reactor nuclear utilities worldwide. The information included in ...

2013-11-20T23:59:59.000Z

33

Nuclear Maintenance Applications Center: Generator Maintenance Guide for Emergency Diesel Generators (Japanese Version)  

Science Conference Proceedings (OSTI)

This report is a Japanese translation of Electric Power Research Institute (EPRI) Technical Report 1021479. EPRI developed this report to address maintenance and improve long-term reliability and availability of generators within nuclear power plant emergency diesel generator (EDG) systems. Maintenance of generator stators and rotors is the focus of this report, which highlights maintenance tasks and strategies that can be performed to identify generator degradation and prevent unforeseen failures. This ...

2012-03-21T23:59:59.000Z

34

Observations on A Technology Roadmap for Generation IV Nuclear Energy  

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

Observations on A Technology Roadmap for Generation IV Nuclear Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report The development of advanced nuclear energy systems in the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new installations in the short term. DOE needs to give those immediate objectives the highest priority and any additional support they require to assure their success. DOE is pursuing two initiatives to encourage a greater use of nuclear energy systems. The initiatives have been reviewed by NERAC Subcommittee on Generation IV Technology Planning (GRNS) and they are: * A Near Term Development (NTD) Roadmap which is in the process of being

35

U.S. Nuclear Generation of Electricity  

U.S. Energy Information Administration (EIA)

U.S. Nuclear Generation: 1957 to latest available EIA final data information in the Annual Energy Review, table 9.2. U. S. Nuclear power plants projected electricity

36

WEB RESOURCE: Generation IV Nuclear Energy Systems  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... This web site provides offers a broad overview of the Department of Energy's activities in exploring the development of next generation nuclear ...

37

Decommissioning San Onofre Nuclear Generating Station Unit 1 (SONGS-1)  

Science Conference Proceedings (OSTI)

Decommissioning a nuclear power plant and termination of the plant license requires the removal of highly activated materials from inside the nuclear reactor pressure vessel (RPV). Such a task presents a major challenge in terms of technology, project management, and worker exposure. This report documents the approach taken by Southern California Edison (SCE) in their highly successful reactor vessel internals (RVI) segmentation of San Onofre Nuclear Generating Station Unit 1 (SONGS-1). The report detail...

2005-12-12T23:59:59.000Z

38

AN ALGORITHM FOR THE GENERATION OF NUCLEAR SPIN SPECIES AND NUCLEAR SPIN STATISTICAL WEIGHTS  

E-Print Network (OSTI)

Chemistry AN ALGORITHM FOR THE GENERATION OF NUCLEAR SPINSPECIES AND NUCLEAR SPIN STATISTICAL WEIGHTS K.for the Generation of Nuclear Spin and Nuclear Spin

Balasubramanian, K.

2013-01-01T23:59:59.000Z

39

Operating strategy generators for nuclear reactors  

Science Conference Proceedings (OSTI)

Operating strategy generators, i.e., the software intended for increasing the efficiency of work of nuclear power plant operators, are discussed. The possibilities provided by the domestic and foreign operating-strategy generators are analyzed.

Solovyev, D. A., E-mail: and@est.mephi.ru; Semenov, A. A.; Shchukin, N. V. [National Research Nuclear University MEPhI (Russian Federation)

2011-12-15T23:59:59.000Z

40

U.S. Nuclear Generation of Electricity  

Annual Energy Outlook 2012 (EIA)

U.S. Nuclear Generation and Generating Capacity Data Released: July 25, 2013 Data for : May 2013 Next Release: August 2013 Contacts: Michael Mobilia Phone: 202-287-6318 E-mail:...

Note: This page contains sample records for the topic "nuclear generation reported" 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

NUCLEAR ENERGY RESEARCH INITIATIVE (NERI) PROGRAM GRANT NUMBER DE-FG03-00SF22168 TECHNICAL PROGRESS REPORT (Nov. 15, 2001 - Feb. 15,2002) ''Design and Layout Concepts for Compact, Factory-Produced, Transportable, Generation IV Reactor Systems''  

SciTech Connect

The objectives of this project are to develop and evaluate nuclear power plant designs and layout concepts to maximize the benefits of compact modular Generation IV reactor concepts including factory fabrication and packaging for optimal transportation and siting. Three nuclear power plant concepts are being studied representing water, helium and lead-bismuth coolants. This is the sixth quarterly progress report.

Fred R. Mynatt; Andy Kadak; Marc Berte; Larry Miller; Mohammed Khan; Joe McConn; Lawrence Townsend; Wesley Williams; Martin Williamson

2002-03-15T23:59:59.000Z

42

"1. Braidwood Generation Station","Nuclear","Exelon Nuclear",2330  

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

Illinois" Illinois" "1. Braidwood Generation Station","Nuclear","Exelon Nuclear",2330 "2. Byron Generating Station","Nuclear","Exelon Nuclear",2300 "3. LaSalle Generating Station","Nuclear","Exelon Nuclear",2238 "4. Baldwin Energy Complex","Coal","Dynegy Midwest Generation Inc",1785 "5. Quad Cities Generating Station","Nuclear","Exelon Nuclear",1774 "6. Dresden Generating Station","Nuclear","Exelon Nuclear",1734 "7. Powerton","Coal","Midwest Generations EME LLC",1538 "8. Elwood Energy LLC","Gas","Dominion Elwood Services Co",1350

43

Proceedings of the 2. MIT international conference on the next generation of nuclear power technology. Final report  

SciTech Connect

The goal of the conference was to try to attract a variety of points of view from well-informed people to debate issues concerning nuclear power. Hopefully from that process a better understanding of what one should be doing will emerge. In organizing the conference lessons learned from the previous one were applied. A continuous effort was made to see to it that the arguments for the alternatives to nuclear power were given abundant time for presentation. This is ultimately because nuclear power is going to have to compete with all of the energy technologies. Thus, in discussing energy strategy all of the alternatives must be considered in a reasonable fashion. The structure the conference used has seven sessions. The first six led up to the final session which was concerned with what the future nuclear power strategy should be. Each session focused upon a question concerning the future. None of these questions has a unique correct answer. Rather, topics are addressed where reasonable people can disagree. In order to state some of the important arguments for each session`s question, the combination of a keynote paper followed by a respondent was used. The respondent`s paper is not necessarily included to be a rebuttal to the keynote; but rather, it was recognized that two people will look at a complex question with different shadings. Through those two papers the intention was to get out the most important arguments affecting the question for the session. The purpose of the papers was to set the stage for about an hour of discussion. The real product of this conference was that discussion.

NONE

1993-12-31T23:59:59.000Z

44

Program on Technology Innovation: Nuclear Power Generation Technologies  

Science Conference Proceedings (OSTI)

The United States and other countries are currently planning to expand their nuclear power electrical generation base in order to provide energy security and price stability while reducing greenhouse gas emissions. Since the existing fleet of nuclear plants was built during or before the 1970s, new plants will incorporate more advanced designs. This report documents the current status and potential for advanced nuclear power technology development and/or commercialization over the next 5 to 15 years.

2007-06-20T23:59:59.000Z

45

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER FINAL RECHNICAL REPORT FOR THE PERIOD AUGUST 1, 1999 THROUGH SEPTEMBER 30, 2002 REV. 1  

SciTech Connect

OAK-B135 Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy [1-1,1-2]. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties [1-3,1-4]. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.''

BROWN,LC; BESENBRUCH,GE; LENTSCH, RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-12-01T23:59:59.000Z

46

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER FINAL RECHNICAL REPORT FOR THE PERIOD AUGUST 1, 1999 THROUGH SEPTEMBER 30, 2002 REV. 1  

DOE Green Energy (OSTI)

OAK-B135 Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy [1-1,1-2]. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties [1-3,1-4]. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.''

BROWN,LC; BESENBRUCH,GE; LENTSCH, RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-12-01T23:59:59.000Z

47

Generation Risk Assessment (GRA) at Cooper Nuclear Station  

Science Conference Proceedings (OSTI)

A previous EPRI guide described how generating plants can implement various forms of component and system models for generation risk assessment (GRA). This report describes a trial application of GRA modeling at the Cooper Nuclear Station and evaluates the usefulness and accuracy of the EPRI GRA guide.

2005-12-06T23:59:59.000Z

48

THE BIRTH OF NUCLEAR-GENERATED ELECTRICITY  

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

BIRTH OF NUCLEAR-GENERATED ELECTRICITY BIRTH OF NUCLEAR-GENERATED ELECTRICITY The first time that electricity was generated from nuclear energy occurred in an experimental breeder reactor in Idaho in 1951. The idea for a breeder reactor (a reactor that could produce more fuel than it uses) first occurred to scientists working on the nation's wartime atomic energy program in the early 1940's. Experimental evidence indicated that the breeding of nuclear fuel was possible in a properly designed reactor, but time and resources were not then available to pursue the idea After the war, the newly established Atomic Energy Commission (now the Department of Energy) assigned some of the nation's nuclear skills and resources to developing peaceful uses of the atom. The large bodies of uranium ore found in the 1950's were

49

The Fourth Generation of Nuclear Power  

SciTech Connect

The outlook for nuclear power in the U.S. is currently very bright. The economics, operations and safety performance of U.S. nuclear power plants is excellent. In addition, both the safety and economic regulation of nuclear power are being changed to produce better economic parameters for future nuclear plant operations and the licenses for plant operations are being extended to 60 years. There is further a growing awareness of the value of clean, emissions-free nuclear power. These parameters combine to form a firm foundation for continued successful U.S. nuclear plant operations, and even the potential In order to realize a bright future for nuclear power, we must respond successfully to five challenges: • Nuclear power must remain economically competitive, • The public must remain confident in the safety of the plants and the fuel cycle. • Nuclear wastes and spent fuel must be managed and the ultimate disposition pathways for nuclear wastes must be politically settled. • The proliferation potential of the commercial nuclear fuel cycle must continue to be minimized, and • We must assure a sustained manpower supply for the future and preserve the critical nuclear technology infrastructure. The Generation IV program is conceived to focus the efforts of the international nuclear community on responding to these challenges.

Lake, James Alan

2000-11-01T23:59:59.000Z

50

Nuclear Science | Publications and Reports | ORNL  

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

NSED Monthly Reports Reactor and Nuclear Systems Publications News and Awards Nuclear Science Home | Science & Discovery | Nuclear Science | Publications and Reports SHARE...

51

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

Nuclear Reactor Operational Status Tables (Information and data on nuclear power reactors Generation: by State and Reactor. Annual Energy Review, ...

52

STEAM GENERATOR FOR NUCLEAR REACTOR  

DOE Patents (OSTI)

The steam generator described for use in reactor powergenerating systems employs a series of concentric tubes providing annular passage of steam and water and includes a unique arrangement for separating the steam from the water. (AEC)

Kinyon, B.W.; Whitman, G.D.

1963-07-16T23:59:59.000Z

53

Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

The National Nuclear Security Administration Reports Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Test and...

54

Case Study: Darlington Nuclear Generating Station  

Science Conference Proceedings (OSTI)

Darlington is a four-reactor nuclear plant east of Toronto. It is operated by Ontario Hydro. Each reactor has two independent shutdown systems: SDS1 drops neutron-absorbing rods into the core, while SDS2 injects liquid poison into the moderator. Both ... Keywords: Atomic Energy Control Board of Canada, Canada, Darlington nuclear generating station, Ontario Hydro, case study, certification, code quality, decision-making logic, documentation, fission reactor core control and monitoring, fission reactor safety, formal methods, formal model-based inspection, formal specification, licensing, liquid poison injection, neutron-absorbing rods, nuclear engineering computing, nuclear plant, safety, safety-critical systems, software driven shutdown systems, software reliability, specifications

Dan Craigen; Susan Gerhart; Ted Ralston

1994-01-01T23:59:59.000Z

55

Reporting of Nuclear Incidents (Connecticut)  

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

Each operator of a nuclear power generating facility shall notify the Commissioner of Environmental Protection or his designee, which may be another State Agency, as soon as possible but in all...

56

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Charges Relating to Nuclear Reactor Safety," 1976, availableissues impor tant to nuclear reactor safety. This report wasstudies of overall nuclear reactor safety have been

Nero, A.V.

2010-01-01T23:59:59.000Z

57

NMMSS Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

> NMMSS Information, Reports & Forms > NMMSS Reports NMMSS Reports U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards...

58

Steam Generator Management Program: Steam Generator Progress Report  

Science Conference Proceedings (OSTI)

Since 1985, EPRI has published the Steam Generator Progress Report (SGPR), which provides historical information on worldwide steam generator activities.

2009-10-19T23:59:59.000Z

59

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT  

E-Print Network (OSTI)

Generating Plant. The enclosed report documents the inspection findings which were discussed on February 22, 2001, with you and other members of your staff. This inspection examined activities conducted under your license as they relate to safety and compliance with the Commission’s rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, the inspectors identified two issues of very low safety significance (Green). One of these issues was determined to involve a violation of NRC requirements. However, because of its very low safety significance and because it has been entered into your corrective action program, the NRC is treating the issue as a non-cited violation, in accordance with Section VI.A.1 of the NRC’s Enforcement Policy. If you deny the non-cited violation, you should provide a response with the basis for your denial, within 30 days of the date of this inspection report, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator,

Dear Mr. Sorensen; Roger D. Lanksbury

2001-01-01T23:59:59.000Z

60

Nuclear chemistry. Annual report, 1974  

SciTech Connect

The 1974 Nuclear Chemistry Annual Report contains information on research in the following areas: nuclear science (nuclear spectroscopy and radioactivity, nuclear reactions and scattering, nuclear theory); chemical and atomic physics (heavy ion-induced atomic reactions, atomic and molecular spectroscopy, photoelectron spectroscopy and hyperfine interactions); physical, inorganic, and analytical chemistry (x-ray crystallography, physical and inorganic chemistry, geochemistry); and instrumentation. Thesis abstracts, 1974 publication titles, and an author index are also included. Papers having a significant amount of information are listed separately by title. (RWR)

Conzett, H.E.; Edelstein, N.M.; Tsang, C.F. (eds.)

1975-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

International Nuclear Energy Research Initiative: Annual Report...  

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

sitesallmodulescontribredisredis.autoload.inc). You are here Home International Nuclear Energy Research Initiative: Annual Report 2005 International Nuclear Energy...

62

Employee Concerns Reporting Form | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Reporting Form | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing...

63

Annual Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Annual Reports | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing...

64

Steam Generator Tube Integrity Facilities - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

65

International Nuclear Energy Research Initiative (I-NERI) Annual Reports |  

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

International Nuclear Energy Policy and Cooperation International Nuclear Energy Policy and Cooperation » Bilateral Cooperation » International Nuclear Energy Research Initiative (I-NERI) Annual Reports International Nuclear Energy Research Initiative (I-NERI) Annual Reports August 13, 2013 International Nuclear Energy Research Initiative: 2012 Annual Report Nuclear energy represents the single largest carbon-free baseload source of energy in the United States, accounting for nearly 20 percent of the electricity generated and over 60 percent of our low-carbon production. Worldwide, nuclear power generates 14 percent of global electricity. Continually increasing demand for clean energy both domestically and across the globe, combined with research designed to make nuclear power ever-safer and more cost-effective, will keep nuclear in the energy mix for the

66

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

20555. u. S. Nuclear U. S. NRC. Reactor Safety Study: AnNUREG-75! 094, October 1975. NRC Regulatory Guide 1. 101. "Report on Current Activities NRC and the Federal Interagency

Yen, W.W.S.

2010-01-01T23:59:59.000Z

67

Analyzing auxiliary system in nuclear generating stations  

Science Conference Proceedings (OSTI)

The design for most nuclear generating stations took place before the widespread use of computerized engineering tools. The manual design basis calculations that were performed vary in quantity from only a few feet of shelf space for some of the first stations to bookcases full for stations that are now receiving their operating licenses. Some of the following issues may apply to the manual calculation files of any nuclear station: Errors and lack of detail in hand calculations; Calculations that may not document the required safety functions; Calculations that lag behind the as-built condition of the station; Documentation that does not add up to a coherent whole; and incomplete auditability and traceability of data. The increasing use of computerized tools in nuclear generating station analysis has helped address the hand-calculation problems. The use of a master system model to study various scenarios also ensures that uniform assumptions are being used for all related analyses. This article presents an overview of how computerized tools are being used for both ac and dc auxiliary system calculations. Problems that may be created by the use of these tools are discussed, along with a review of those issues specific to nuclear generating stations.

Jancauskas, J.R. (Gilber/Commonwealth (US))

1992-07-01T23:59:59.000Z

68

Life Cycle Management Plan for Main Generator and Exciter at Palo Verde Nuclear Generating Station: Generic Version  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This report provides an optimized LCM plan for the main generators and exciters at the Palo Verde Nuclear Generating Station (PVNGS).

2003-09-30T23:59:59.000Z

69

THE NEXT GENERATION NUCLEAR PLANT GRAPHITE PROGRAM  

Science Conference Proceedings (OSTI)

Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor (HTGR) is one of the critical development activities being pursued within the Next Generation Nuclear Plant (NGNP) program. Graphite’s thermal stability (in an inert gas environment), high compressive strength, fabricability, and cost effective price make it an ideal core structural material for the HTGR reactor design. While the general characteristics necessary for producing nuclear grade graphite are understood, historical “nuclear” grades no longer exist. New grades must be fabricated, characterized, and irradiated to demonstrate that current grades of graphite exhibit acceptable non-irradiated and irradiated properties upon which the thermo-mechanical design of the structural graphite in NGNP is based. The NGNP graphite R&D program has selected a handful of commercially available types for research and development activities necessary to qualify this nuclear grade graphite for use within the NGNP reactor. These activities fall within five primary areas; 1) material property characterization, 2) irradiated material property characterization, 3) modeling, and 4) ASTM test development, and 5) ASME code development efforts. Individual research and development activities within each area are being pursued with the ultimate goal of obtaining a commercial operating license for the nuclear graphite from the US NRC.

William E. Windes; Timothy D. Burchell; Robert L. Bratton

2008-09-01T23:59:59.000Z

70

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

which steam is raised. nuclear fuel generates heat that isattention to nuclear and fossil-fuel plants, and these areFor all the fossil-fuel and nuclear (However, categories,

Nero, A.V.

2010-01-01T23:59:59.000Z

71

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

... (kWh). There were 65 nuclear power plants with 104 operating nuclear reactors that generated a total of 790 billion kilowatt-hours (kWh), ...

72

Preventing Biogas Generation in Low Level Waste: Interim Report  

Science Conference Proceedings (OSTI)

This interim report describes actions that can be taken to control and prevent biogas generation in waste containers and plant systems. In addition, it describes additional work in progress that will form the basis for the final report. This research was undertaken in response to nuclear power stations experiencing biogas generation from plant systems and low level waste containers.

1997-11-11T23:59:59.000Z

73

Nuclear Maintenance Applications Center: Emergency Diesel Generator Single Component Vulnerability Review Guidance.  

Science Conference Proceedings (OSTI)

This report provides guidance to owners and operators of nuclear power plants on performing emergency diesel generator (EDG) system single component vulnerability reviews. This guidance was developed based on a recommendation from the nuclear industry’s EDG Technical Advisory Committee (TAC) that plants perform a single component vulnerability review as discussed in the Institute of Nuclear Power Operations’ Industry Experience Report ...

2013-11-01T23:59:59.000Z

74

Nuclear Georeactor Generation of Earth's Geomagnetic Field  

E-Print Network (OSTI)

The purpose of this communication is to suggest that the mechanism for generating the geomagnetic field and the energy source for powering it are one and the same, a nuclear georeactor at the center of the Earth. Toward this end, I: i) Present evidence that the nuclear georeactor fission-product sub-shell is fluid; ii)Suggest that the geomagnetic field is generated within the georeactor sub-shell, rather than within Earth's iron-alloy fluid core; iii) Describe why convection appears more feasible within the georeactor sub-shell than within the iron-alloy core; iv) Disclose additional relative physical advantages for georeactor sub-shell dynamo operation; and, v) Outline briefly the research that should be conducted to advance the state of knowledge of georeactor-geomagnetic field generation. The concept of geomagnetic field production by the nuclear georeactor is presented specifically for the Earth. The concepts and principles, however, are generally applicable to planetary magnetic field production.

Herndon, J Marvin

2007-01-01T23:59:59.000Z

75

Nuclear Georeactor Generation of Earth's Geomagnetic Field  

E-Print Network (OSTI)

The purpose of this communication is to suggest that the mechanism for generating the geomagnetic field and the energy source for powering it are one and the same, a nuclear georeactor at the center of the Earth. Toward this end, I: i) Present evidence that the nuclear georeactor fission-product sub-shell is fluid; ii)Suggest that the geomagnetic field is generated within the georeactor sub-shell, rather than within Earth's iron-alloy fluid core; iii) Describe why convection appears more feasible within the georeactor sub-shell than within the iron-alloy core; iv) Disclose additional relative physical advantages for georeactor sub-shell dynamo operation; and, v) Outline briefly the research that should be conducted to advance the state of knowledge of georeactor-geomagnetic field generation. The concept of geomagnetic field production by the nuclear georeactor is presented specifically for the Earth. The concepts and principles, however, are generally applicable to planetary magnetic field production.

J. Marvin Herndon

2007-07-19T23:59:59.000Z

76

Steam Generator Group Project. Annual report, 1982  

SciTech Connect

The Steam Generator Group Project (SGGP) is an NRC program joined by additional sponsors. The SGGP utilizes a steam generator removed from service at a nuclear plant (Surry 2) as a vehicle for research on a variety of safety and reliability issues. This report is an annual summary of progress of the program for 1982. Information is presented on the Steam Generator Examination Facility (SGEF), especially designed and constructed for this research. Loading of the generator into the SGEF is then discussed. The report then presents radiological field mapping results and personnel exposure monitoring. This is followed by information on field reduction achieved by channel head decontaminations. The report then presents results of a secondary side examination through shell penetrations placed prior to transport, confirming no change in generator condition due to transport. Decontamination of the channel head is discussed followed by plans for eddy current testing and removal of the plugs placed during service. Results of a preliminary profilometry examination are then provided.

Clark, R.A.; Lewis, M.

1984-02-01T23:59:59.000Z

77

NIST Processes to Help Build Next-Generation Nuclear Power ...  

Science Conference Proceedings (OSTI)

NIST Processes to Help Build Next-Generation Nuclear Power Plants. From NIST Tech Beat: June 2, 2009. ...

2011-04-04T23:59:59.000Z

78

Arizona Public Service Co., Palo Verde Nuclear Generating ...  

Science Conference Proceedings (OSTI)

Arizona Public Service Co., Palo Verde Nuclear Generating Station. NVLAP Lab Code: 100536-0. Address and Contact Information: ...

2013-08-23T23:59:59.000Z

79

Mechanical Performance for Current and Next-Generation Nuclear ...  

Science Conference Proceedings (OSTI)

About this Symposium. Meeting, 2010 TMS Annual Meeting & Exhibition. Symposium, Mechanical Performance for Current and Next-Generation Nuclear ...

80

NMMSS Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Reports | National Nuclear Security Administration Reports | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog NMMSS Reports Home > About Us > Our Programs > Nuclear Security > Nuclear Materials Management & Safeguards System > NMMSS Information, Reports & Forms > NMMSS Reports NMMSS Reports U.S. Department of Energy / U.S. Nuclear Regulatory Commission

Note: This page contains sample records for the topic "nuclear generation reported" 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

January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE The ANTT Subcommittee met in Washington on Dec 4-5, 2002 to review progress in the transmutation program, and to learn about major organizational changes that affect the management of the program. The NE's new Advanced Nuclear Research Office (NE-20) now oversees both the transmutation program (ANTT) and the Generation-IV program (GEN-IV). antt14Jan_03.pdf More Documents & Publications October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE

82

International Nuclear Energy Research Initiative: 2012 Annual Report |  

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

International Nuclear Energy Research Initiative: 2012 Annual International Nuclear Energy Research Initiative: 2012 Annual Report International Nuclear Energy Research Initiative: 2012 Annual Report Nuclear energy represents the single largest carbon-free baseload source of energy in the United States, accounting for nearly 20 percent of the electricity generated and over 60 percent of our low-carbon production. Worldwide, nuclear power generates 14 percent of global electricity. Continually increasing demand for clean energy both domestically and across the globe, combined with research designed to make nuclear power ever-safer and more cost-effective, will keep nuclear in the energy mix for the foreseeable future. U.S. researchers are collaborating with nuclear scientists and engineers around the world to develop new technologies that will lower costs,

83

Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana) |  

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

You are here You are here Home » Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana) Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana) < Back Eligibility Commercial Construction Industrial Utility Program Info State Louisiana Program Type Fees Generating Facility Rate-Making Provider Louisiana Public Service Commission The Incentive Cost Recovery Rule for Nuclear Power Generation establishes guidelines for any utility seeking to develop a nuclear power plant in Louisiana. The rule clarifies, as well as supplements the Louisiana Public Service Commission's 1983 General Order for the acquisition of nuclear generation resources. The goal of the rule is to provide a transparent process that identifies the responsibilities parties in the regulatory

84

Nuclear Power Generating Facilities (Maine) | Department of Energy  

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

Nuclear Power Generating Facilities (Maine) Nuclear Power Generating Facilities (Maine) Nuclear Power Generating Facilities (Maine) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Maine Program Type Siting and Permitting Provider Radiation Control Program The first subchapter of the statute concerning Nuclear Power Generating Facilities provides for direct citizen participation in the decision to construct any nuclear power generating facility in Maine. The Legislature

85

NNSA Next Generation Safeguards Initiative | National Nuclear...  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

86

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

and Related Standards for Fossil-Fuel and Geo- thermal Powerposed Nuclear, Geothermal, and Fossil-Fuel Sites and Facili-NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN

Nero, A.V.

2010-01-01T23:59:59.000Z

87

The Next Generation Nuclear Plant (NGNP) Project  

DOE Green Energy (OSTI)

The Next Generation Nuclear Power (NGNP) Project will demonstrate emissions-free nuclearassisted electricity and hydrogen production by 2015. The NGNP reactor will be a helium-cooled, graphite moderated, thermal neutron spectrum reactor with a design goal outlet temperature of 1000 C or higher. The reactor thermal power and core configuration will be designed to assure passive decay heat removal without fuel damage during hypothetical accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. This paper provides a description of the project to build the NGNP at the Idaho National Engineering and Environmental Laboratory (INEEL). The NGNP Project includes an overall reactor design activity and four major supporting activities: materials selection and qualification, NRC licensing and regulatory support, fuel development and qualification, and the hydrogen production plant. Each of these activities is discussed in the paper. All the reactor design and construction activities will be managed under the DOE’s project management system as outlined in DOE Order 413.3. The key elements of the overall project management system discussed in this paper include the client and project management organization relationship, critical decisions (CDs), acquisition strategy, and the project logic and timeline. The major activities associated with the materials program include development of a plan for managing the selection and qualification of all component materials required for the NGNP; identification of specific materials alternatives for each system component; evaluation of the needed testing, code work, and analysis required to qualify each identified material; preliminary selection of component materials; irradiation of needed sample materials; physical, mechanical, and chemical testing of unirradiated and irradiated materials; and documentation of final materials selections. The NGNP will be licensed by the NRC under 10 CFR 50 or 10 CFR 52, for the purpose of demonstrating the suitability of high-temperature gas-cooled reactors for commercial electric power and hydrogen production. Products that will support the licensing of the NGNP include the environmental impact statement, the preliminary safety analysis report, the NRC construction permit, the final safety analysis report, and the NRC operating license. The fuel development and qualification program consists of five elements: development of improved fuel manufacturing technologies, fuel and materials irradiations, safety testing and post-irradiation examinations, fuel performance modeling, and fission product transport and source term modeling. Two basic approaches will be explored for using the heat from the high-temperature helium coolant to produce hydrogen. The first technology of interest is the thermochemical splitting of water into hydrogen and oxygen. The most promising processes for thermochemical splitting of water are sulfur-based and include the sulfur-iodine, hybrid sulfur-electrolysis, and sulfur-bromine processes. The second technology of interest is thermally assisted electrolysis of water. The efficiency of this process can be substantially improved by heating the water to high-temperature steam before applying electrolysis.

F. H. Southworth; P. E. MacDonald

2003-11-01T23:59:59.000Z

88

Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Workshop  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory (PNL) evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume II, reports the results of an industry-wide workshop held on May 28 and 29, 1986, to discuss the technical issues associated with aging of nuclear service emergency diesel generators. The technical issues discussed most extensively were: man/machine interfaces, component interfaces, thermal gradients of startup and cooldown and the need for an accurate industry database for trend analysis of the diesel generator system.

Hoopingarner, K.R.; Vause, J.W.

1987-08-01T23:59:59.000Z

89

Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant  

SciTech Connect

Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

Nathan V. Hoffer; Piyush Sabharwall; Nolan A. Anderson

2011-01-01T23:59:59.000Z

90

NNSA Launches Next Generation Safeguards Initiative | National Nuclear  

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

Next Generation Safeguards Initiative | National Nuclear Next Generation Safeguards Initiative | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > NNSA Launches Next Generation Safeguards Initiative NNSA Launches Next Generation Safeguards Initiative September 09, 2008 Washington, DC NNSA Launches Next Generation Safeguards Initiative

91

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

~ ties Surrounding Nuclear Power Plants. LBlr5921, Lawrencein U. S. Commercial Nuclear Power Plants. WASH-1400. Octoberand Content of for Nuclear Power Plants. Regulatory Guide

Yen, W.W.S.

2010-01-01T23:59:59.000Z

92

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Commission. Office of Nuclear Reactor Licens- ing. StandardCommission. Office of Nuclear Reactor Regula- tion.Nuclear Regulatory Commission Standard Review Plan for Light Water Reactor

Nero, jA.V.

2010-01-01T23:59:59.000Z

93

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Commission. Office of Nuclear Reactor Reg- ulation.Commission. Office of Nuclear Reactor Licen- sing. StandardCommission. Office of Nuclear Reactor Regulation. Standard

Yen, W.W.S.

2010-01-01T23:59:59.000Z

94

Nuclear Science Division: 1993 Annual report  

Science Conference Proceedings (OSTI)

This report describes the activities of the Nuclear Science Division for the 1993 calendar year. This was another significant year in the history of the Division with many interesting and important accomplishments. Activities for the following programs are covered here: (1) nuclear structure and reactions program; (2) the Institute for Nuclear and Particle Astrophysics; (3) relativistic nuclear collisions program; (4) nuclear theory program; (5) nuclear data evaluation program, isotope project; and (6) 88-inch cyclotron operations.

Myers, W.D. [ed.

1994-06-01T23:59:59.000Z

95

International Nuclear Energy Research Initiative: 2012 Annual Report |  

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

2 Annual 2 Annual Report International Nuclear Energy Research Initiative: 2012 Annual Report Nuclear energy represents the single largest carbon-free baseload source of energy in the United States, accounting for nearly 20 percent of the electricity generated and over 60 percent of our low-carbon production. Worldwide, nuclear power generates 14 percent of global electricity. Continually increasing demand for clean energy both domestically and across the globe, combined with research designed to make nuclear power ever-safer and more cost-effective, will keep nuclear in the energy mix for the foreseeable future. U.S. researchers are collaborating with nuclear scientists and engineers around the world to develop new technologies that will lower costs, maximize safety, minimize proliferation risk, and handle used fuel and

96

Power generation from nuclear reactors in aerospace applications  

SciTech Connect

Power generation in nuclear powerplants in space is addressed. In particular, the states of technology of the principal competitive concepts for power generation are assessed. The possible impact of power conditioning on power generation is also discussed. For aircraft nuclear propulsion, the suitability of various technologies is cursorily assessed for flight in the Earth's atmosphere. A program path is suggested to ease the conditions of first use of aircraft nuclear propulsion.

English, R.E.

1982-01-01T23:59:59.000Z

97

Power generation from nuclear reactors in aerospace applications  

SciTech Connect

Power generation in nuclear powerplants in space is addressed. In particular, the states of technology of the principal competitive concepts for power generation are assessed. The possible impact of power conditioning on power generation is also discussed. For aircraft nuclear propulsion, the suitability of various technologies is cursorily assessed for flight in the Earth's atmosphere. A program path is suggested to ease the conditions of first use of aircraft nuclear propulsion.

English, R.E.

1982-01-01T23:59:59.000Z

98

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

population growth surrounding a nuclear power plant once thegrowth by requiring that certification of nuclear power plant

Yen, W.W.S.

2010-01-01T23:59:59.000Z

99

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Population Evaluation Emergency Planning for Nuclear PowerPotential Definition of Nuclear Emergencies Developingan Emergency Plan . . . . Regulatory Review of Utilities!

Yen, W.W.S.

2010-01-01T23:59:59.000Z

100

Bush Administration Moves Forward to Develop Next Generation Nuclear Energy  

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

Moves Forward to Develop Next Generation Moves Forward to Develop Next Generation Nuclear Energy Systems Bush Administration Moves Forward to Develop Next Generation Nuclear Energy Systems February 28, 2005 - 10:33am Addthis WASHINGTON, DC-The Bush Administration today took a major step in advancing international efforts to develop the next generation of clean, safe nuclear energy systems. Secretary of Energy Samuel W. Bodman joined representatives from Canada, France, Japan, and the United Kingdom to sign the first multilateral agreement in history aimed at the development of next generation nuclear energy systems. The work of the Generation IV International Forum (GIF) is essential to advancing an important component of the Bush Administration's comprehensive energy strategy in the development of next generation nuclear energy technologies.

Note: This page contains sample records for the topic "nuclear generation reported" 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

Figure 38. Levelized costs of nuclear electricity generation in ...  

U.S. Energy Information Administration (EIA)

Sheet3 Sheet2 Sheet1 Figure 38. Levelized costs of nuclear electricity generation in two cases, 2025 (2011 dollars per megawatthour) Reference Small Modular Reactor

102

Some noise control problems peculiar to nuclear generating facilities  

Science Conference Proceedings (OSTI)

The ability to confidently predict the noise environment in a nuclear generating facility presently under construction is complicated by the design constraints of physical layout

Robert A. Putnam

1977-01-01T23:59:59.000Z

103

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

How much electricity does a typical nuclear power plant generate? ... tariff, and demand charge data? How is electricity used in U.S. homes?

104

Spark Plasma Sintering of Next Generation Nuclear Materials  

Science Conference Proceedings (OSTI)

... Spark Plasma Sintering of Next Generation Nuclear Materials. Author(s), Daniel Osterberg, Jeff Perkins, Matt Luke, Brian Jaques, Michael F Hurley, Darryl Butt.

105

Energy Department Invests $60 Million to Train Next Generation Nuclear  

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

60 Million to Train Next Generation 60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology Energy Department Invests $60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology September 20, 2013 - 1:00pm Addthis News Media Contact (202) 586-4940 WASHINGTON - Building on President Obama's Climate Action Plan to continue America's leadership in clean energy innovation, the Energy Department announced today more than $60 million in nuclear energy research awards and improvements to university research reactors and infrastructure. The 91 awards announced today will help train and educate the next generation of leaders in America's nuclear industry as well as support new and advanced nuclear technologies from reactor materials to innovative

106

Energy Department Invests $60 Million to Train Next Generation Nuclear  

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

Energy Department Invests $60 Million to Train Next Generation Energy Department Invests $60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology Energy Department Invests $60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology September 20, 2013 - 1:00pm Addthis News Media Contact (202) 586-4940 WASHINGTON - Building on President Obama's Climate Action Plan to continue America's leadership in clean energy innovation, the Energy Department announced today more than $60 million in nuclear energy research awards and improvements to university research reactors and infrastructure. The 91 awards announced today will help train and educate the next generation of leaders in America's nuclear industry as well as support new and advanced nuclear technologies from reactor materials to innovative

107

Industry Participation Sought for Design of Next Generation Nuclear Plant |  

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

Industry Participation Sought for Design of Next Generation Nuclear Industry Participation Sought for Design of Next Generation Nuclear Plant Industry Participation Sought for Design of Next Generation Nuclear Plant June 29, 2006 - 2:41pm Addthis Gen IV Reactor Capable of Producing Electricity and/or Hydrogen WASHINGTON, DC - The U.S. Department of Energy (DOE) is seeking expressions of interest from prospective industry teams interested in participating in the development and conceptual design for the Next Generation Nuclear Plant (NGNP), a very high temperature gas-cooled nuclear reactor prototype with the capability to produce process heat, electricity and/or hydrogen. The very high temperature reactor is based on research and development activities supported by DOE's Generation IV nuclear energy systems initiative.

108

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |  

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

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the estimated resources required to license an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process heat for any number of industrial applications including electricity production, hydrogen production, coal-to-liquids, shale oil

109

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |  

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

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the estimated resources required to license an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process heat for any number of industrial applications including electricity production, hydrogen production, coal-to-liquids, shale oil

110

Figure 9.1 Nuclear Generating Units - U.S. Energy Information ...  

U.S. Energy Information Administration (EIA)

Figure 9.1 Nuclear Generating Units Operable Units,1 1957-2011 Nuclear Net Summer Capacity Change, 1950-2011 Status of All Nuclear Generating Units, ...

111

Salt disposal of heat-generating nuclear waste.  

SciTech Connect

This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

2011-01-01T23:59:59.000Z

112

NUCLEAR ENERGY RESEARCH INITIATIVE (NERI) PROGRAM GRANT NUMBER DE-FG03-00SF22168 TECHNICAL PROGRESS REPORT (Nov. 15, 2001 - Feb. 15,2002) ''Design and Layout Concepts for Compact, Factory-Produced, Transportable, Generation IV Reactor Systems''  

SciTech Connect

The objectives of this project are to develop and evaluate nuclear power plant designs and layout concepts to maximize the benefits of compact modular Generation IV reactor concepts including factory fabrication and packaging for optimal transportation and siting. Three nuclear power plant concepts are being studied representing water, helium and lead-bismuth coolants. This is the sixth quarterly progress report.

Fred R. Mynatt; Andy Kadak; Marc Berte; Larry Miller; Mohammed Khan; Joe McConn; Lawrence Townsend; Wesley Williams; Martin Williamson

2002-03-15T23:59:59.000Z

113

NUCLEAR CHEMISTRY ANNUAL REPORT 1970  

E-Print Network (OSTI)

Letters 24, 1507 (1970); Nuclear Data B4, 663 (1970). 5. R.S. Hager and E. C. Seltzer, Nuclear Data A4, 1 (1968). 6. H.J. Nijgh, and R. Van Lieshout, Nuclear Spectroscopy Tables (

Authors, Various

2011-01-01T23:59:59.000Z

114

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.

Nero, jA.V.

2010-01-01T23:59:59.000Z

115

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Response Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, jA.V.

2010-01-01T23:59:59.000Z

116

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Power Plant Reliability-Availability and State Regulation,"Report on Equipment Availability: Fossil and NuclearBasic Definitions* Availability: Reliability: Base Loading:

Nero, A.V.

2010-01-01T23:59:59.000Z

117

Nuclear Power Plant Emergency Diesel Generator Tanks 1  

E-Print Network (OSTI)

Nuclear power provides about 20 % of the total electricity generated in the United States. In 2005, this was about 782 Billion kWh of the total electricity generation (EIA 2006). 2 As with fossil-fueled electricity generating plants, electricity in a nuclear power plant is produced by heated steam that drives a turbine generator. In a nuclear power plant, however, nuclear fission reactions in the core produce heat that is absorbed by a liquid that flows through the system and is converted to steam. Nuclear power plants are highly efficient and have become more so over the last 25 years. Operational efficiency (also referred to as plant performance or electricity production) can be measured by the capacity factor. The capacity factor is the ratio of the actual amount of electricity generated to the maximum possible amount that could be generated in a given period of time – usually a year. Today, nuclear power plants operate at an average 90 % capacity factor (compared to 56 % in 1980) (EIA 2006a). Thus, although nuclear generating capacity has remained roughly constant since 1990, at about 99 gigawatts (or about 10 % of the total U.S. electric generating capacity), the amount of electricity produced has increased 33 % since that time because of increased capacity utilization. Nuclear plants have the highest capacity factors of

unknown authors

2006-01-01T23:59:59.000Z

118

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSING PROCESSPlanning for Nuclear Power Plants Determination of Accidentnuclear power plants . . . . . . . . . • . . . . .2.2.4.3.

Yen, W.W.S.

2010-01-01T23:59:59.000Z

119

Washington Nuclear Profile - Columbia Generating Station  

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

Columbia Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

120

Illinois Nuclear Profile - Braidwood Generation Station  

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

Braidwood Generation Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

Note: This page contains sample records for the topic "nuclear generation reported" 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

Kansas Nuclear Profile - Wolf Creek Generating Station  

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

April 2012" "Next Release Date: February 2013" "Wolf Creek Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor...

122

Illinois Nuclear Profile - Byron Generating Station  

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

Byron Generating Station" ,"Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

123

Illinois Nuclear Profile - Dresden Generating Station  

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

Dresden Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

124

Dairy methane generator. Final report  

Science Conference Proceedings (OSTI)

Details of the work completed under this contract are presented. During the winter of 1979-80 three students enrolled, in the Mechanical Design Engineering Technology program at the Pennsylvania State University's Capitol Campus (Middletown, PA), undertook a feasibility study for the utilization of the manure generated by the dairy cows located on Mr. Thomas B. Williams farm for the generation and use of methane gas. The results of their effort was the design of an Anaerobic Digester/Electric Generation System. This preliminary designed system was later changed and improved by another group of P.S.U. MDET students in the spring of 1980. The final design included working drawings and an economic analysis of the estimated investment necessary to complete the Methane Generator/Electric Power Generation System.

Williams, T.B.

1981-09-30T23:59:59.000Z

125

NUCLEAR CHEMISTRY ANNUAL REPORT 1970  

SciTech Connect

Papers are presented for the following topics: (1) Nuclear Structure and Nuclear Properties - (a) Nuclear Spectroscopy and Radioactivity; (b) Nuclear Reactions and Scattering; (c) Nuclear Theory; and (d) Fission. (2) Chemical and Atomic Physics - (a) Atomic and Molecular Spectroscopy; and (b) Hyperfine Interactions. (3) Physical, Inorganic, and Analytical Chemistry - (a) X-Ray Crystallography; (b) Physical and Inorganic Chemistry; (c) Radiation Chemistry; and (d) Chemical Engineering. (4) Instrumentation and Systems Development.

Authors, Various

1971-05-01T23:59:59.000Z

126

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

2004-06-01T23:59:59.000Z

127

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER  

SciTech Connect

OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could

BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-06-01T23:59:59.000Z

128

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER  

DOE Green Energy (OSTI)

OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could benefit, in terms of efficien

BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-06-01T23:59:59.000Z

129

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

Science Conference Proceedings (OSTI)

Feb 12, 2007... Nuclear Power Background, Trends in Nuclear Power, The Nuclear ... Science: Application to Fusion and Generation IV Fission Reactors

130

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect

Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

Lynne M. Stevens

2010-07-01T23:59:59.000Z

131

Institutional Research & Development Reports | National Nuclear...  

National Nuclear Security Administration (NNSA)

Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Institutional Research & Development Reports Home > About Us > Our...

132

Generation IV (Gen IV) - Nuclear Engineering Division (Argonne)  

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

Generation IV (Gen Generation IV (Gen IV) Generation IV Overview Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Major Programs Generation IV (Gen IV) Development of next generation nuclear systems featuring significant advances in sustainability, economics, safety, reliability, proliferation resistance and physical protection. Bookmark and Share Generation IV Fact Sheet (73 KB) Overview Generation IV nuclear energy systems target significant advances over current-generation and evolutionary systems in the areas of sustainability, safety and reliability, and economics. These systems are to be deployable by 2030 in both industrialized and developing countries. Development of Generation IV systems is an international initiative. A

133

Annual Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Annual Reports | National Nuclear Security Administration Annual Reports | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Annual Reports Home > Our Mission > Powering the Nuclear Navy > Annual Reports Annual Reports NNSA's Naval Reactors is committed to providing information about its operations. Environmental Monitoring Report NT-12-1 - May 2012 - ENVIRONMENTAL MONITORING AND DISPOSAL OF

134

Report on Distributed Generation Penetration Study  

Science Conference Proceedings (OSTI)

This report documents part of a multiyear research program dedicated to the development of requirements to support the definition, design, and demonstration of a distributed generation-electric power system interconnection interface concept. The report focuses on the dynamic behavior of power systems when a significant portion of the total energy resource is distributed generation. It also focuses on the near-term reality that the majority of new DG relies on rotating synchronous generators for energy conversion.

Miller, N.; Ye, Z.

2003-08-01T23:59:59.000Z

135

Training the Next Generation of Nuclear Energy Leaders | Department of  

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

Training the Next Generation of Nuclear Energy Leaders Training the Next Generation of Nuclear Energy Leaders Training the Next Generation of Nuclear Energy Leaders May 8, 2012 - 3:06pm Addthis University of Idaho professor Supathorn Phongikaroon works with a graduate student in the radiochemistry lab at the Center for Advanced Energy Studies in Idaho Falls, Idaho. Phongikaroon has received $820,000 from DOE to study an applied technology to remotely analyze spent nuclear fuel. | Photo courtesy of the University of Idaho. University of Idaho professor Supathorn Phongikaroon works with a graduate student in the radiochemistry lab at the Center for Advanced Energy Studies in Idaho Falls, Idaho. Phongikaroon has received $820,000 from DOE to study an applied technology to remotely analyze spent nuclear fuel. | Photo

136

Training the Next Generation of Nuclear Energy Leaders | Department of  

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

the Next Generation of Nuclear Energy Leaders the Next Generation of Nuclear Energy Leaders Training the Next Generation of Nuclear Energy Leaders May 8, 2012 - 3:06pm Addthis University of Idaho professor Supathorn Phongikaroon works with a graduate student in the radiochemistry lab at the Center for Advanced Energy Studies in Idaho Falls, Idaho. Phongikaroon has received $820,000 from DOE to study an applied technology to remotely analyze spent nuclear fuel. | Photo courtesy of the University of Idaho. University of Idaho professor Supathorn Phongikaroon works with a graduate student in the radiochemistry lab at the Center for Advanced Energy Studies in Idaho Falls, Idaho. Phongikaroon has received $820,000 from DOE to study an applied technology to remotely analyze spent nuclear fuel. | Photo

137

Theoretical studies in nuclear reactions and nuclear structure. Progress report  

Science Conference Proceedings (OSTI)

Research in the Maryland Nuclear Theory Group focusses on problems in four basic areas of current relevance. Hadrons in nuclear matter; the structure of hadrons; relativistic nuclear physics and heavy ion dynamics and related processes. The section on hadrons in nuclear matter groups together research items which are aimed at exploring ways in which the properties of nucleons and the mesons which play a role in the nuclear force are modified in the nuclear medium. A very interesting result has been the finding that QCD sum rules supply a new insight into the decrease of the nucleon`s mass in the nuclear medium. The quark condensate, which characterizes spontaneous chiral symmetry breaking of the late QCD vacuum, decreases in nuclear matter and this is responsible for the decrease of the nucleon`s mass. The section on the structure of hadrons contains progress reports on our research aimed at understanding the structure of the nucleon. Widely different approaches are being studied, e.g., lattice gauge calculations, QCD sum rules, quark-meson models with confinement and other hedgehog models. A major goal of this type of research is to develop appropriate links between nuclear physics and QCD. The section on relativistic nuclear physics represents our continuing interest in developing an appropriate relativistic framework for nuclear dynamics. A Lorentz-invariant description of the nuclear force suggests a similar decrease of the nucleon`s mass in the nuclear medium as has been found from QCD sum rules. Work in progress extends previous successes in elastic scattering to inelastic scattering of protons by nuclei. The section on heavy ion dynamics and related processes reports on research into the e{sup +}e{sup {minus}} problem and heavy ion dynamics.

Not Available

1992-05-01T23:59:59.000Z

138

Reports to the DOE Nuclear Data Committee  

Science Conference Proceedings (OSTI)

The report in this document were submitted to the Department of Energy, Nuclear Data Committee (DOE-NDC) in April 1988. The reporting laboratories are those with a substantial program for the measurement of neutron and nuclear cross sections of relevance to the US applied nuclear energy program. Appropriate subjects are microscopic neutron cross sections relevant to the nuclear energy program, including shielding. Inverse reactions where pertinent are included; charged-particle cross sections where relevant to developing and testing nuclear models; gamma ray production, radioactive decay, and theoretical developments in nuclear structure which are applicable to nuclear energy programs; and proton and alpha-particle cross sections, at energies of up to 1 GeV, which are of interest to the space program.

Not Available

1988-05-01T23:59:59.000Z

139

Program on Technology Innovation: The Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

This Technology Update documents the Next Generation Nuclear Plant (NGNP) project, which will demonstrate the design, licensing, construction, and operation of a new nuclear energy source using high-temperature gas-cooled reactor (HTGR) technology. This new non-emitting energy source is applicable to a broad range of uses, from generating electricity to providing high-temperature industrial process heat to producing hydrogen. The NGNP project is sponsored as part of the Energy Policy Act of 2005 and envi...

2008-12-15T23:59:59.000Z

140

NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER  

SciTech Connect

The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) plant capable of producing the electricity and high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) application process, as recommended in the Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy. NRC licensing of the NGNP plant utilizing this process will demonstrate the efficacy of licensing future HTGRs for commercial industrial applications. This white paper is one in a series of submittals that will address key generic issues of the COL priority licensing topics as part of the process for establishing HTGR regulatory requirements.

Mark Holbrook

2010-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

to the nuclear power plant, the Marine Corps base, thePower Plant Emergency Response Plan, July 1975. United States Marine

Yen, W.W.S.

2010-01-01T23:59:59.000Z

142

Washington Nuclear Profile - Columbia Generating Station  

U.S. Energy Information Administration (EIA)

snpt3wa371 1,097 9,241 96.2 BWR Columbia Generating Station Unit Type Data for 2010 BWR = Boiling Water Reactor. Note: Totals may not equal sum of components due to ...

143

Kansas Nuclear Profile - Wolf Creek Generating Station  

U.S. Energy Information Administration (EIA)

snpt3ks210 1,160 9,556 94.0 PWR Wolf Creek Generating Station Unit Type Data for 2010 PWR = Pressurized Light Water Reactor. Note: Totals may not ...

144

Nuclear Data and Measurements Series Reports - Nuclear Data Program -  

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

REPORTS REPORTS Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Group 1 (ANL/NDM-1 - ANL/NDM-20) Group 2 (ANL/NDM-21 - ANL/NDM-40) Group 3 (ANL/NDM-41 - ANL/NDM-60) Group 4 (ANL/NDM-61 - ANL/NDM-80) Group 5 (ANL/NDM-81 - ANL/NDM-100) Group 6 (ANL/NDM-101 - ANL/NDM-120) Group 7 (ANL/NDM-121 - ANL/NDM-140) Group 8 (ANL/NDM-141 - ANL/NDM-160) Group 9 (ANL/NDM-161 - ANL/NDM-180) Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program NUCLEAR DATA AND MEASUREMENTS REPORTS Bookmark and Share Contents Information on the Nuclear Data and Measurements Series Reports and

145

Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators.

Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

1987-08-01T23:59:59.000Z

146

NUCLEAR DATA AND MEASUREMENTS REPORTS 161-180 - Nuclear Data...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

147

Method and apparatus for generating low energy nuclear particles  

DOE Patents (OSTI)

A particle accelerator (12) generates an input particle beam having an initial energy level above a threshold for generating secondary nuclear particles. A thin target (14) is rotated in the path of the input beam for undergoing nuclear reactions to generate the secondary particles and correspondingly decrease energy of the input beam to about the threshold. The target (14) produces low energy secondary particles and is effectively cooled by radiation and conduction. A neutron scatterer (44) and a neutron filter (42) are also used for preferentially degrading the secondary particles into a lower energy range if desired.

Powell, James R. (Shoreham, NY); Reich, Morris (Flushing, NY); Ludewig, Hans (Brookhaven, NY); Todosow, Michael (Miller Place, NY)

1999-02-09T23:59:59.000Z

148

Method and apparatus for generating low energy nuclear particles  

DOE Patents (OSTI)

A particle accelerator generates an input particle beam having an initial energy level above a threshold for generating secondary nuclear particles. A thin target is rotated in the path of the input beam for undergoing nuclear reactions to generate the secondary particles and correspondingly decrease energy of the input beam to about the threshold. The target produces low energy secondary particles and is effectively cooled by radiation and conduction. A neutron scatterer and a neutron filter are also used for preferentially degrading the secondary particles into a lower energy range if desired. 18 figs.

Powell, J.R.; Reich, M.; Ludewig, H.; Todosow, M.

1999-02-09T23:59:59.000Z

149

An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems  

SciTech Connect

The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated “toolkit” consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

Timothy J. Leahy

2010-06-01T23:59:59.000Z

150

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Power Plants. WASH~1400 (NUREG 75/014). October 1975. S.Power Plants -LWR Edison." NUREG-75! 094, October 1975. NRCof Fixed Nuclear Facilities, NUREG-75/l1l (Reprint of WASH-

Yen, W.W.S.

2010-01-01T23:59:59.000Z

151

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

and Related Standards for Fossil-Fuel and Geo- thermal Powerposed Nuclear, Geothermal, and Fossil-Fuel Sites and Facili-and RelatedStandards for Fossil-Fuel and Geothermal Power

Nero, jA.V.

2010-01-01T23:59:59.000Z

152

POWER GENERATION FROM LIQUID METAL NUCLEAR FUEL  

DOE Patents (OSTI)

A nuclear reactor system is described wherein the reactor is the type using a liquid metal fuel, such as a dispersion of fissile material in bismuth. The reactor is designed ln the form of a closed loop having a core sectlon and heat exchanger sections. The liquid fuel is clrculated through the loop undergoing flssion in the core section to produce heat energy and transferrlng this heat energy to secondary fluids in the heat exchanger sections. The fission in the core may be produced by a separate neutron source or by a selfsustained chain reaction of the liquid fuel present in the core section. Additional auxiliary heat exchangers are used in the system to convert water into steam which drives a turbine.

Dwyer, O.E.

1958-12-23T23:59:59.000Z

153

MONTHLY UPDATE TO ANNUAL ELECTRIC GENERATOR REPORT  

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

REPORT REPORT INSTRUCTIONS|Year: 2013 No. 1905-0129 Approval Expires: 12/31/2015 Burden: 0.3 Hours| |PURPOSE|Form EIA-860M collects data on the status of: Proposed new generators scheduled to begin commercial operation within the subsequent 12 months; Existing generators scheduled to retire from service within the subsequent 12 months; and Existing generators that have proposed modifications that are scheduled for completion within one month. The data collected on this form appear in the EIA publication Electric Power Monthly. They are also used to monitor the current status and trends of the electric power industry and to evaluate the future of the industry.| |REQUIRED RESPONDENTS|Respondents to the Form EIA-860M who are required to complete this form are all Form EIA-860, ANNUAL ELECTRIC GENERATOR REPORT,

154

Nuclear Separations Technologies Workshop Report 2011  

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

i i NUCLEAR SEPARATIONS TECHNOLOGIES WORKSHOP REPORT November 7, 2011 FINAL TABLE OF CONTENTS Acronyms and Initialisms............................................................................................................ iii Executive Summary ...................................................................................................................... 1 1. Introduction ............................................................................................................................. 9 1.1 Overview .......................................................................................................................... 9 1.2 Background .................................................................................................................... 10

155

New Generation of Nuclear Physics at RIKEN  

Science Conference Proceedings (OSTI)

I report present status and perspectives of RIBF ''RI Beam Factory (RIBF)'' at RIKEN. RIBF is a top world-class in-flight RIB facility. Emphasis is given to on-going and future programs at the new facility through introducing experimental devices and recent highlights.

Sakurai, H. [2-1 Hirosawa, Wako, Saitama, 351-0198 (Japan)

2011-05-06T23:59:59.000Z

156

Audit Report on "The National Nuclear Security Administration...  

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

Report on "The National Nuclear Security Administration's B61 Spin Rocket Motor Project," DOEIG-0740 Audit Report on "The National Nuclear Security Administration's B61 Spin...

157

Nuclear steam-generator transplant total rises  

Science Conference Proceedings (OSTI)

Several utilities with pressurized water reactors (PWRs) are replacing leaking and corroded steam generators. Over half the PWRs face corrosion problems that will cost $50 million to $100 million per unit to correct. An alternative approach of installing new tube sleeves has only had one application. Corrosion prevention still eludes utilities, whose problems differ. Westinghouse units were the first to experience corrosion problems because they have almost all operated for a decade or more. Some advances in condenser and steam-generator technology should extend the component life of younger units, and some leaking PWR tubes can be plugged. Operating differences may explain why PWRs have operated for over 20 years on submarines using phosphate water chemistry, while the use of de-aerators in the secondary-systems of foreign PWRs may explain their better performance. Among the corrective steps recommended by Stone and Webster are tighter chemistry control, better plant layup practices, revamping secondary-system hardware, condensate polishing, and de-aerators. Research continues to find the long-term preventative. 2 tables. (DCK)

Smock, R.

1982-09-01T23:59:59.000Z

158

ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS  

SciTech Connect

Rising global energy demands coupled with increased environmental concerns point to one solution; they must reduce their dependence on fossil fuels that emit greenhouse gases. As the global community faces the challenge of maintaining sovereign nation security, reducing greenhouse gases, and addressing climate change nuclear power will play a significant and likely growing role. In the US, nuclear energy already provides approximately one-fifth of the electricity used to power factories, offices, homes, and schools with 104 operating nuclear power plants, located at 65 sites in 31 states. Additionally, 19 utilities have applied to the US Nuclear Regulatory Commission (NRC) for construction and operating licenses for 26 new reactors at 17 sites. This planned growth of nuclear power is occurring worldwide and has been termed the 'nuclear renaissance.' As major industrial nations craft their energy future, there are several important factors that must be considered about nuclear energy: (1) it has been proven over the last 40 years to be safe, reliable and affordable (good for Economic Security); (2) its technology and fuel can be domestically produced or obtained from allied nations (good for Energy Security); and (3) it is nearly free of greenhouse gas emissions (good for Environmental Security). Already an important part of worldwide energy security via electricity generation, nuclear energy can also potentially play an important role in industrial processes and supporting the nation's transportation sector. Coal-to-liquid processes, the generation of hydrogen and supporting the growing potential for a greatly increased electric transportation system (i.e. cars and trains) mean that nuclear energy could see dramatic growth in the near future as we seek to meet our growing demand for energy in cleaner, more secure ways. In order to address some of the prominent issues associated with nuclear power generation (i.e., high capital costs, waste management, and proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

Marra, J.

2010-09-29T23:59:59.000Z

159

Field Examination and Hot Cell Post-Irradiation Examination of Fuel Channels from Monticello Nuclear Generating Plant  

Science Conference Proceedings (OSTI)

On January 20, 2007, Monticello Nuclear Generating Plant observed an unexpected no-settle condition at the 00 position in peripheral cell 42-11. Publication OE24588, "Control Rod Blade did not Move Normally at Monticello Nuclear Generating Plant," documented this event. This report gives field examination results of four symmetric channels including cell 42-11. Researchers sectioned channel coupons from two channels in cell 42-11 and sent them to Vallecitos Nuclear Center (VNC), Sunol, California for mor...

2009-04-22T23:59:59.000Z

160

Assessment of next generation nuclear plant intermediate heat exchanger design.  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made an assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. A detailed thermal hydraulic analysis, using models developed at ANL, was performed to calculate heat transfer, temperature distribution, and pressure drop. Two IHX designs namely, shell and straight tube and compact heat exchangers were considered in an earlier assessment. Helical coil heat exchangers were analyzed in the current report and the results were compared with the performance features of designs from industry. In addition, a comparative analysis is presented between the shell and straight tube, helical, and printed circuit heat exchangers from the standpoint of heat exchanger volume, primary and secondary sides pressure drop, and number of tubes. The IHX being a high temperature component, probably needs to be designed using ASME Code Section III, Subsection NH, assuming that the IHX will be classified as a class 1 component. With input from thermal hydraulic calculations performed at ANL, thermal conduction and stress analyses were performed for the helical heat exchanger design and the results were compared with earlier-developed results on shell and straight tube and printed circuit heat exchangers.

Majumdar, S.; Moisseytsev, A.; Natesan, K.; Nuclear Engineering Division

2008-10-17T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

BRUSLIB and NETGEN: the Brussels nuclear reaction rate library and nuclear network generator for astrophysics  

E-Print Network (OSTI)

Nuclear reaction rates are quantities of fundamental importance in astrophysics. Substantial efforts have been devoted in the last decades to measure or calculate them. The present paper presents for the first time a detailed description of the Brussels nuclear reaction rate library BRUSLIB and of the nuclear network generator NETGEN so as to make these nuclear data packages easily accessible to astrophysicists for a large variety of applications. BRUSLIB is made of two parts. The first one contains the 1999 NACRE compilation based on experimental data for 86 reactions with (mainly) stable targets up to Si. The second part of BRUSLIB concerns nuclear reaction rate predictions calculated within a statistical Hauser-Feshbach approximation, which limits the reliability of the rates to reactions producing compound nuclei with a high enough level density. These calculations make use of global and coherent microscopic nuclear models for the quantities entering the rate calculations. The use of such models is utterly important, and makes the BRUSLIB rate library unique. A description of the Nuclear Network Generator NETGEN that complements the BRUSLIB package is also presented. NETGEN is a tool to generate nuclear reaction rates for temperature grids specified by the user. The information it provides can be used for a large variety of applications, including Big Bang nucleosynthesis, the energy generation and nucleosynthesis associated with the non-explosive and explosive hydrogen to silicon burning stages, or the synthesis of the heavy nuclides through the s-, alpha- and r-, rp- or p-processes.

M. Aikawa; M. Arnould; S. Goriely; A. Jorissen; K. Takahashi

2005-06-24T23:59:59.000Z

162

Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

and stockpile stewardship. Some of these reports are listed below: Advancing the Science of High Energy Density Laboratory Plasmas, U.S. Department of Energy, Office of...

163

Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Office of Defense Science Reports Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Research and...

164

NUCLEAR CHEMISTRY ANNUAL REPORT 1970  

E-Print Network (OSTI)

and Jordan 4 reported the observation of solar cor- onal lines corresponding to the ls2s 3S 1 -1s 2 lS0 energy

Authors, Various

2011-01-01T23:59:59.000Z

165

Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Stewardship Academic Alliance Reports Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Research and Development...

166

Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Office of Defense Science Reports Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Research and Development >...

167

Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Test Capabilities and Evaluation > Reports...

168

Nuclear Maintenance Applications Center: Clearance and Tagging Guideline for Nuclear Electric Generating Stations, Revision 1  

Science Conference Proceedings (OSTI)

Clearance and tagging programs at nuclear electric generating facilities serve to protect personnel from injury and to protect equipment from damage. These programs are thus of vital importance from both a worker safety standpoint and an operations and maintenance cost standpoint. This guideline presents a clearance and tagging approach, developed with broad industry input, that nuclear electric generating companies can use as a basis for comparison with their own programs.

2010-02-01T23:59:59.000Z

169

Regional comparison of nuclear and fossil electric power generation costs  

SciTech Connect

Nuclear's main disadvantages are its high capital investment cost and uncertainty in schedule compared with alternatives. Nuclear plant costs continue to rise whereas coal plant investment costs are staying relative steady. Based on average experience, nuclear capital investment costs are nearly double those of coal-fired generation plants. The capital investment cost disadvantage of nuclear is balanced by its fuel cost advantages. New base load nuclear power plants were projected to be competitive with coal-fired plants in most regions of the country. Nuclear power costs wre projected to be significantly less (10% or more) than coal-fired power costs in the South Atlantic region. Coal-fired plants were projected to have a significant economic advantage over nuclear plants in the Central and North Central regions. In the remaining seven regions, the levelized cost of power from either option was projected to be within 10%. Uncertainties in future costs of materials, services, and financing affect the relative economics of the nuclear and coal options significantly. 10 figures.

Bowers, H.I.

1984-01-01T23:59:59.000Z

170

Life Cycle Management Plan for Main Generator and Exciter at Callaway Nuclear Plant: Generic Version  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This report provides Ameren UE with an optimized LCM plan for the main generator and exciter at Callaway Plant.

2003-09-30T23:59:59.000Z

171

Active Interrogation Using Electronic Neutron Generators for Nuclear Safeguards Applications  

SciTech Connect

Active interrogation, a measurement technique which uses a radiation source to probe materials and generate unique signatures useful for characterizing those materials, is a powerful tool for assaying special nuclear material. The most commonly used technique for performing active interrogation is to use an electronic neutron generator as the probe radiation source. Exploiting the unique operating characteristics of these devices, including their monoenergetic neutron emissions and their ability to operate in pulsed modes, presents a number of options for performing prompt and delayed signature analyses using both photon and neutron sensors. A review of literature in this area shows multiple applications of the active neutron interrogation technique for performing nuclear nonproliferation measurements. Some examples include measuring the plutonium content of spent fuel, assaying plutonium residue in spent fuel hull claddings, assaying plutonium in aqueous fuel reprocessing process streams, and assaying nuclear fuel reprocessing facility waste streams to detect and quantify fissile material. This paper discusses the historical use of this technique and examines its context within the scope and challenges of next-generation nuclear fuel cycles and advanced concept nuclear fuel cycle facilities.

David L. Chichester; Edward H. Seabury

2008-08-01T23:59:59.000Z

172

Hazard Analysis Reports for Nuclear Explosive Operations  

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

NA-STD-3016-2006 NA-STD-3016-2006 May 2006 DOE LIMITED STANDARD HAZARD ANALYSIS REPORTS FOR NUCLEAR EXPLOSIVE OPERATIONS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii Available on the Department of Energy Technical Standards Program web site at http://www.eh.doe.gov/techstds/ DOE-NA-STD-3016-2006 iii FORWARD This Department of Energy (DOE)/National Nuclear Security Administration (NNSA) technical standard is approved for use by the Assistant Deputy Administrator for Military Application and Stockpile Operations (NA-12), and is available for use to prepare Nuclear Explosive Operation (NEO) Hazard Analysis Reports (HARs) as required by 10 CFR 830, "Nuclear Safety Management." This Standard is

173

Nuclear Maintenance Applications Center: Emergency Diesel Generator Condition- Based Maintenance  

Science Conference Proceedings (OSTI)

Condition-based maintenance practices that were developed in the United States in the 1990s for emergency diesel generators (EDGs) have not been fully adopted by international nuclear plant operators. To encourage broader use of such practices, NMAC formed a technical advisory group of international utilities interested in learning more about condition-based EDG maintenance practices.

2008-12-19T23:59:59.000Z

174

Hydrogen Production from the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) is a high temperature gas-cooled reactor that will be capable of producing hydrogen, electricity and/or high temperature process heat for industrial use. The project has initiated the conceptual design phase and when completed will demonstrate the viability of hydrogen generation using nuclear produced process heat. This paper explains how industry and the U.S. Government are cooperating to advance nuclear hydrogen technology. It also describes the issues being explored and the results of recent R&D including materials development and testing, thermal-fluids research, and systems analysis. The paper also describes the hydrogen production technologies being considered (including various thermochemical processes and high-temperature electrolysis).

M. Patterson; C. Park

2008-03-01T23:59:59.000Z

175

Nuclear Science Division Annual Report 1984-85  

E-Print Network (OSTI)

3. Nuclear Collisions at Relativistic Energies The theory6 Nuclear Theory 1. Hadronic and Quark Matter at High Energytheory group to calculate whether such energy densities could be generated in nuclear collisions at ultra-relativistic energies.

Mahoney Editor, Jeannette

2010-01-01T23:59:59.000Z

176

Wind-powered generator. Final report  

DOE Green Energy (OSTI)

Completion of a wind energy conversion system for a private home is reported. The system included three blades constructed of an aluminum center with marine plywood sandwiched between the aluminum center and the fiberglass outer covering. The wind turbine drives a 1800 rpm generator by a chain drive mechanism. Battery storage is included. (LEW)

Whitesides, R E

177

First Report from New Nuclear Energy Standards Group ...  

Science Conference Proceedings (OSTI)

First Report from New Nuclear Energy Standards Group Released. For Immediate Release: August 11, 2009. ...

2010-12-29T23:59:59.000Z

178

JPRS report: Nuclear developments, [June 28, 1989  

Science Conference Proceedings (OSTI)

Partial contents include: Nuclear Power; Qinshan Plant; Nuclear Weapons; Nuclear Power Plants; Nuclear Waste; Nuclear Policy; Decontamination Devices; and Environmental Protection.

NONE

1989-06-28T23:59:59.000Z

179

Executive Summary: Research in Nuclear Power—Workshop on the Needs of the Next Generation of Nuclear Power Technology  

Science Conference Proceedings (OSTI)

Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor

A. David Rossin; Kunmo Chung; K. L. Peddicord

180

Potential growth of nuclear and coal electricity generation in the US  

SciTech Connect

Electricity demand should continue to grow at about the same rate as GNP, creating a need for large amounts of new generating capacity over the next fifty years. Only coal and nuclear at this time have the abundant domestic resources and assured technology to meet this need. However, large increase in both coal and nuclear usage will require solutions to many of the problems that now deter their increased usage. For coal, the problems center around the safety and environmental impacts of increased coal mining and coal combustion. For nuclear, the problems center around reactor safety, radioactive waste disposal, financial risk, and nuclear materials safeguards. This report assesses the impacts associated with a range of projected growth rates in electricity demand over the next 50 years. The resource requirements and waste generation resulting from pursuing the coal and nuclear fuel options to meet the projected growth rates are estimated. The fuel requirements and waste generation for coal plants are orders of magnitude greater than for nuclear. Improvements in technology and waste management practices must be pursued to mitigate environmental and safety concerns about electricity generation from both options. 34 refs., 18 figs., 14 tabs.

Bloomster, C.H.; Merrill, E.T.

1989-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network (OSTI)

Uncertainty can be either an opportunity or a risk. Every construction project begins with the expectation of project performance. To meet the expectation, construction projects need to be managed through sound risk assessment and management beginning with the front-end of the project life cycle to check the feasibility of a project. The Construction Industry Institute’s (CII) International Project Risk Assessment (IPRA) tool has been developed, successfully used for a variety of heavy industry sector projects, and recently elevated to Best Practice status. However, its current format is inadequate to address the unique challenges of constructing the next generation of nuclear power plants (NPP). To understand and determine the risks associated with NPP projects, the goal of this thesis is to develop tailored risk framework for NPP projects that leverages and modifies the existing IPRA process. The IPRA has 82 elements to assess the risks associated with international construction projects. The modified IPRA adds five major issues (elements) to consider the unique risk factors of typical NPP projects based upon a review of the literature and an evaluation of the performance of previous nuclear-related facilities. The modified IPRA considers the sequence of NPP design that ultimately impacts the risks associated with plant safety and operations. Historically, financial risks have been a major chronic problem with the construction of NPPs. This research suggests that unstable regulations and the lack of design controls and oversight are significant risk issues. This thesis includes a consistency test to initially validate whether the asserted risks exist in actual conditions. Also, an overall risk assessment is performed based on the proposed risk framework for NPP and the list of assessed risk is proposed through a possible scenario. After the assessment, possible mitigation strategies are also provided against the major risks as a part of this thesis. This study reports on the preliminary findings for developing a new risk framework for constructing nuclear power plants. Future research is needed for advanced verification of the proposed elements. Follow-on efforts should include verification and validation of the proposed framework by industry experts and methods to quantify and evaluate the performance and risks associated with the multitude of previous NPP projects.

Yeon, Jaeheum 1981-

2012-12-01T23:59:59.000Z

182

National need for utilizing nuclear energy for process heat generation  

DOE Green Energy (OSTI)

Nuclear reactors are potential sources for generating process heat, and their applications for such use economically competitive. They help satisfy national needs by helping conserve and extend oil and natural gas resources, thus reducing energy imports and easing future international energy concerns. Several reactor types can be utilized for generating nuclear process heat; those considered here are light water reactors (LWRs), heavy water reactors (HWRs), gas-cooled reactors (GCRs), and liquid metal reactors (LMRs). LWRs and HWRs can generate process heat up to 280/sup 0/C, LMRs up to 540/sup 0/C, and GCRs up to 950/sup 0/C. Based on the studies considered here, the estimated process heat markets and the associated energy markets which would be supplied by the various reactor types are summarized.

Gambill, W.R.; Kasten, P.R.

1984-01-01T23:59:59.000Z

183

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

G.O. Hayner; R.L. Bratton; R.N. Wright

2005-09-01T23:59:59.000Z

184

Coal based electric generation comparative technologies report  

Science Conference Proceedings (OSTI)

Ohio Clean Fuels, Inc., (OCF) has licensed technology that involves Co-Processing (Co-Pro) poor grade (high sulfur) coal and residual oil feedstocks to produce clean liquid fuels on a commercial scale. Stone Webster is requested to perform a comparative technologies report for grassroot plants utilizing coal as a base fuel. In the case of Co-Processing technology the plant considered is the nth plant in a series of applications. This report presents the results of an economic comparison of this technology with other power generation technologies that use coal. Technologies evaluated were:Co-Processing integrated with simple cycle combustion turbine generators, (CSC); Co-Processing integrated with combined cycle combustion turbine generators, (CCC); pulverized coal-fired boiler with flue gas desulfurization and steam turbine generator, (PC) and Circulating fluidized bed boiler and steam turbine generator, (CFB). Conceptual designs were developed. Designs were based on approximately equivalent net electrical output for each technology. A base case of 310 MWe net for each technology was established. Sensitivity analyses at other net electrical output sizes varying from 220 MWe's to 1770 MWe's were also performed. 4 figs., 9 tabs.

Not Available

1989-10-26T23:59:59.000Z

185

Space Nuclear Safety Program. Progress report, November 1983  

DOE Green Energy (OSTI)

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Topics discussed include: safety-verification impact tests; explosion test; fragment test; leaking fueled clads; effects of fresh water and seawater or PuO/sub 2/ pellets; and impact tests of 5 watt radioisotope thermoelectric generator.

Bronisz, S.E. (comp.)

1984-06-01T23:59:59.000Z

186

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect

The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

R. Doug Hamelin; G. O. Hayner

2004-11-01T23:59:59.000Z

187

Next Generation Nuclear Plant Materials Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

G. O. Hayner; E.L. Shaber

2004-09-01T23:59:59.000Z

188

2010 Inspection and Status Report for the Boiling Nuclear Superheater...  

Office of Legacy Management (LM)

3 Annual Inspection - Boiling Nuclear Superheat (BONUS) Site, Rincn, Puerto Rico October 2013 Page 1 2013 Inspection and Status Report for the Former Boiling Nuclear Superheater...

189

Space Nuclear Safety Program. Progress report  

DOE Green Energy (OSTI)

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.

Bronisz, S.E. (comp.)

1984-01-01T23:59:59.000Z

190

Nuclear Physics Laboratory 1980 annual report  

SciTech Connect

Research progress is reported in the following areas: astrophysics and cosmology, fundamental symmetries, nuclear structure and reactions, radiative capture, medium energy physics, heavy ion reactions, research by outside users, accelerators and ion sources, instrumentation and experimental techniques, and computers and computing. Publications are listed. (WHK)

Adelberger, E.G. (ed.) [ed.

1980-09-01T23:59:59.000Z

191

[Experimental nuclear physics]. Annual report 1988  

Science Conference Proceedings (OSTI)

This is the May 1988 annual report of the Nuclear Physics Laboratory of the University of Washington. It contains chapters on astrophysics, giant resonances, heavy ion induced reactions, fundamental symmetries, polarization in nuclear reactions, medium energy reactions, accelerator mass spectrometry (AMS), research by outside users, Van de Graaff and ion sources, the Laboratory`s booster linac project work, instrumentation, and computer systems. An appendix lists Laboratory personnel, Ph.D. degrees granted in the 1987-88 academic year, and publications. Refs., 27 figs., 4 tabs.

NONE

1988-05-01T23:59:59.000Z

192

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in  

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

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Nuclear power plants in the United States currently produce about 20 percent of the nation's electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit greenhouse gases. Continued and expanded reliance on nuclear energy is one key to meeting future demand for electricity in the U.S. and is called for in the National Energy Policy. Nevertheless, no new nuclear plants have been built in the U.S. in many years, and none are currently slated for construction. The U.S. Department of Energy (DOE) has been working with the nuclear

193

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in  

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

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Nuclear power plants in the United States currently produce about 20 percent of the nation's electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit greenhouse gases. Continued and expanded reliance on nuclear energy is one key to meeting future demand for electricity in the U.S. and is called for in the National Energy Policy. Nevertheless, no new nuclear plants have been built in the U.S. in many years, and none are currently slated for construction. The U.S. Department of Energy (DOE) has been working with the nuclear

194

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Summary of Nuclear Power Plant Operating Experience forResponse Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, A.V.

2010-01-01T23:59:59.000Z

195

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

OUTAGES COMPONENT NUCLEAR REACTOR General Primary CoolingAsh Disposal Trouble NUCLEAR REACTOR COMPONENT OUTAGE CAUSESconsisting of a Nuclear units use a reactor in which burner

Nero, A.V.

2010-01-01T23:59:59.000Z

196

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

been restricted core. Nuclear tests are not scheduled untilnuclear NRC, the non-nuclear tests are proceedingInstitute test reactor - megawatts - megawatts - Nuclear

Nero, A.V.

2010-01-01T23:59:59.000Z

197

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

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

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

198

Technological Transfer from Research Nuclear Reactors to New Generation Nuclear Power Reactors  

SciTech Connect

The goal of this paper is the analysis of the technological transfer role in the nuclear field, with particular emphasis on nuclear reactors domain. The presentation is sustained by historical arguments. In this frame, it is very important to start with the achievements of the first nuclear systems, for instant those with natural uranium as fuel and heavy water as moderator, following in time through the history until the New Generation Nuclear Power Reactors.Starting with 1940, the accelerated development of the industry has implied the increase of the global demand for energy. In this respect, the nuclear energy could play an important role, being essentially an unlimited source of energy. However, the nuclear option faces the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide, a significant amount of experience has been accumulated during development, licensing, construction, and operation of nuclear power reactors. The experience gained is a strong basis for further improvements. Actually, the nuclear programs of many countries are addressing the development of advanced reactors, which are intended to have better economics, higher reliability, improved safety, and proliferation-resistant characteristics in order to overcome the current concerns about nuclear power. Advanced reactors, now under development, may help to meet the demand for energy power of both developed and developing countries as well as for district heating, desalination and for process heat.The paper gives historical examples that illustrate the steps pursued from first research nuclear reactors to present advanced power reactors. Emphasis was laid upon the fact that the progress is due to the great discoveries of the nuclear scientists using the technological transfer.

Radulescu, Laura ['Horia Hulubei' National Institute of Nuclear Physics and Engineering, PO BOX MG-6, Bucharest 077125 (Romania); Pavelescu, Margarit [Academy of Romanian Scientists, Bucharest (Romania)

2010-01-21T23:59:59.000Z

199

NMMSS Information, Reports & Forms | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Information, Reports & Forms | National Nuclear Security Information, Reports & Forms | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog NMMSS Information, Reports & Forms Home > About Us > Our Programs > Nuclear Security > Nuclear Materials Management & Safeguards System > NMMSS Information, Reports & Forms NMMSS Information, Reports & Forms

200

Generation IV Nuclear Energy Systems Construction Cost Reductions Through the Use of Virtual Environments  

SciTech Connect

The objective of this multi-phase project is to demonstrate the feasibility and effectiveness of using full-scale virtual reality simulation in the design, construction, and maintenance of future nuclear power plants. The project will test the suitability of immersive virtual reality technology to aid engineers in the design of the next generation nuclear power plant and to evaluate potential cost reductions that can be realized by optimization of installation and construction sequences. The intent is to see if this type of information technology can be used in capacities similar to those currently filled by full-scale physical mockups. This report presents the results of the completed project.

Timothy Shaw; Vaugh Whisker

2004-02-28T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Human Reliability for the Next Generation of Nuclear Experts  

Science Conference Proceedings (OSTI)

As the nuclear renaissance progresses and today s nuclear and radiological experts retire, a new generation of experts will ultimately be recruited, trained, and replace the old guard. Selecting individuals who have the attitudes and values appropriate to work in the nuclear industry and who have the best qualifications for the position will be a key to the success of this renaissance. In a world with deep divisions on political and social issues; how a State, agency, or company assures that those hired can be trusted with the access to, and responsibilities for, nuclear and/or radiological materials is an important consideration. Human interactions invariably rely on the offering of assurance and the receipt of trust. A fundamental element in any human relationship is knowing when to trust and when to doubt. When are assurances to be believed or questioned? Human reliability programs (HRP) are used to assure a person s truthfulness and loyalty to the State. An HRP program has a number of elements and may not fit all cultures in the same form. An HRP can vary in scope from simple background checks of readily available data to full field investigations and testing. This presentation discusses possible elements for an HRP from regulation to implementation and the issues related to each element. The effects of an HRP on potential recruits will be discussed.

Coates, Cameron W [ORNL; Eisele, Gerhard R [ORNL

2010-01-01T23:59:59.000Z

202

Draft Report Chapter 2: Generation Adequacy | Department of Energy  

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

Chapter 2: Generation Adequacy More Documents & Publications Draft Report: Chapter 2 Generation Adequacy. Keeping The Lights On In the New World Electricity Advisory Committee...

203

NUCLEAR SCIENCE ANNUAL REPORT 1977-1978  

E-Print Network (OSTI)

A Relation Between Nuclear Dynamics and the RenormalizationMultiplicity Distributions in Nuclear Collision M. GyulassyHigh Energy Nuclear Collisions in the Resonance Dominated

Schroeder, L.S.

2011-01-01T23:59:59.000Z

204

Nuclear Maintenance Applications Center: Emergency Diesel Generator Control Systems  

Science Conference Proceedings (OSTI)

Emergency diesel generators (EDGs) have been a subject of industry attention since the 1980s because of their importance to plant safety, and a key point of focus has been their control systems. To support long-term reliability and availability of EDG control systems, the Electric Power Research Institute (EPRI) has developed this report, which highlights maintenance tasks and strategies that can reduce failures of control system components. The report draws from the knowledge of industry EDG experts and...

2012-08-06T23:59:59.000Z

205

Report of the Nuclear Energy Research Advisory Committee, Subcommittee on  

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

Nuclear Energy Research Advisory Committee, Nuclear Energy Research Advisory Committee, Subcommittee on Nuclear Laboratory Requirements Report of the Nuclear Energy Research Advisory Committee, Subcommittee on Nuclear Laboratory Requirements As an element of its plans to return the U.S. Department of Energy (DOE) site in eastern Idaho to its historic mission of nuclear technology development, the DOE asked its Nuclear Energy Research Advisory Committee (NERAC) to establish a Subcommittee on Nuclear Laboratory Requirements. The Subcommittee was charged with identifying the "characteristics, capabilities, and attributes a world-class nuclear laboratory would possess". It was also asked "to become familiar with the practices, culture, and facilities of other world-class laboratories - not

206

Nuclear Chemistry Division annual report FY83  

Science Conference Proceedings (OSTI)

The purpose of the annual reports of the Nuclear Chemistry Division is to provide a timely summary of research activities pursued by members of the Division during the preceding year. Throughout, details are kept to a minimum; readers desiring additional information are encouraged to read the referenced documents or contact the authors. The Introduction presents an overview of the Division's scientific and technical programs. Next is a section of short articles describing recent upgrades of the Division's major facilities, followed by sections highlighting scientific and technical advances. These are grouped under the following sections: nuclear explosives diagnostics; geochemistry and environmental sciences; safeguards technology and radiation effect; and supporting fundamental science. A brief overview introduces each section. Reports on research supported by a particular program are generally grouped together in the same section. The last section lists the scientific, administrative, and technical staff in the Division, along with visitors, consultants, and postdoctoral fellows. It also contains a list of recent publications and presentations. Some contributions to the annual report are classified and only their abstracts are included in this unclassified portion of the report (UCAR-10062-83/1); the full article appears in the classified portion (UCAR-10062-83/2).

Struble, G. (ed.)

1983-01-01T23:59:59.000Z

207

March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE The Global Nuclear Energy Partnership (GNEP) marks a major change in the direction of the DOE's nuclear energy R&D program. It is a coherent plan to test technologies that promise to markedly reduce the problem of nuclear waste treatment and to reduce the proliferation risk in a world with a greatly expanded nuclear power program. It brings the U.S. program into much closer alignment with that of the other major nuclear energy states. GNEP proposes to take spent fuel from existing light water reactors (LWRs),

208

2009 Annual Reports Issued for Nuclear Energy Research Initiative and  

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

2009 Annual Reports Issued for Nuclear Energy Research Initiative 2009 Annual Reports Issued for Nuclear Energy Research Initiative and International Nuclear Energy Research Initiative 2009 Annual Reports Issued for Nuclear Energy Research Initiative and International Nuclear Energy Research Initiative July 2, 2010 - 11:49am Addthis On July 2, 2010, the Department of Energy's (DOE) Office of Nuclear Energy (NE) issued annual reports for its Nuclear Energy Research Initiative (NERI) andInternational Nuclear Energy Research Initiative (I-NERI), describing accomplishments achieved in 2009. The NERI and I-NERI programs have furthered DOE goals for the past decade, conducting research into many of the key technical issues that impact the expanded use of advanced nuclear energy systems. Researchers have fostered innovative ideas

209

Impact of U.S. Nuclear Generation on Greenhouse Gas Emissions  

Gasoline and Diesel Fuel Update (EIA)

Impact of U.S. Nuclear Generation Impact of U.S. Nuclear Generation on Greenhouse Gas Emissions Ronald E. Hagen, John R. Moens, and Zdenek D. Nikodem Energy Information Administration U.S. Department of Energy International Atomic Energy Agency Vienna, Austria November 6-9, 2001 iii Energy Information Administration/ Impact of U.S. Nuclear Generation on Greenhouse Gas Emissions Contents Page I. The Electric Power Industry and the Greenhouse Gas Issue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 II. The Current Role of the U.S. Nuclear Industry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 III. The Future Role of the U.S. Nuclear Industry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 IV. Factors That Affect Nuclear Expansion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 V. Conclusion

210

A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats  

Science Conference Proceedings (OSTI)

This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the range of possibilities. Once an object is generated, its radiation signature is calculated using a 1-dimensional deterministic transport code. Objects that do not make sense based on physics principles or other constraints are rejected. Thus, the model can be used to generate a population of spectral signatures that spans a large space, including smuggled nuclear material and nuclear weapons.

Nelson, K; Sokkappa, P

2008-10-29T23:59:59.000Z

211

Dependable Hydrogen and Industrial Heat Generation from the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Department of Energy is working with industry to develop a next generation, high-temperature gas-cooled nuclear reactor (HTGR) as a part of the effort to supply the US with abundant, clean and secure energy. The Next Generation Nuclear Plant (NGNP) project, led by the Idaho National Laboratory, will demonstrate the ability of the HTGR to generate hydrogen, electricity, and high-quality process heat for a wide range of industrial applications. Substituting HTGR power for traditional fossil fuel resources reduces the cost and supply vulnerability of natural gas and oil, and reduces or eliminates greenhouse gas emissions. As authorized by the Energy Policy Act of 2005, industry leaders are developing designs for the construction of a commercial prototype producing up to 600 MWt of power by 2021. This paper describes a variety of critical applications that are appropriate for the HTGR with an emphasis placed on applications requiring a clean and reliable source of hydrogen. An overview of the NGNP project status and its significant technology development efforts are also presented.

Charles V. Park; Michael W. Patterson; Vincent C. Maio; Piyush Sabharwall

2009-03-01T23:59:59.000Z

212

Approach for enhancing nuclear materials tracking and reporting in waste  

SciTech Connect

Recent policy from the Department of Energy/Office of Safeguards and Security (DOE/OSS) has identified the need to report nuclear materials in waste in a manner that is consistent with the Department of Energy's Nuclear Materials Information System (NMIS), which uses Form 471 as its official record. NMIS is used to track nuclear material inventories while they are subject to safeguards. This requirement necessitates the reevaluation of existing business practices that are used to track and report these nuclear materials. This paper provides a methodology for applying a systems approach to the evaluation of the flow of nuclear waste materials from a generating facility through to permanent disposal. This methodology can be used to integrate existing systems and leverage data already gathered that support both the waste reporting requirements and the NMIS requirements. In order to consider an active waste reporting system that covers waste management through to final disposal, the requirements for characterization, certification, and transportation for disposal at the Waste Isolation Pilot Plant (WIPP) are used as an example. These requirements are found in the WIPP Waste Acceptance Criteria (WIPP/WAC) and associated requirement documents. This approach will prevent inconsistencies in reported data and address current and future needs. For example, spent fuel (which the U.S. intends to dispose of as high-level waste) has not been viewed as particularly attractive in terms of proliferation in comparison to materials associated with other parts of the nuclear fuel cycle. However, collecting high-level waste (or some types of defense waste) in one location where it will be left for hundreds or thousands of years presents proliferation and safeguards issues that need to be considered as part of a systems evaluation. This paper brings together information on domestic and international safeguards practices and considers the current system of documentation used by the U.S. Department of Energy for radioactive waste disposal. The information presented represents current practices, and we recognize that the practices were designed to address different goals. After providing an overview of these areas, some steps that may help develop safeguards systems for geologic repositories in the U.S. context are discussed.

Longmire, V. L. (Victoria L.); Seitz, S. L. (Sharon L.); Sinkule, B. J. (Barbara J.)

2001-06-01T23:59:59.000Z

213

Nuclear Science Division annual report for 1991  

Science Conference Proceedings (OSTI)

This paper discusses research being conducted under the following programs: Low energy research program; bevalac research program; ultrarelativistic research program; nuclear theory program; nuclear theory program; nuclear data evaluation program; and 88-inch cyclotron operations.

Myers, W.D. (ed.)

1992-04-01T23:59:59.000Z

214

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

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

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

215

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

without steam gen. ) Steam generator Control Rods Refuelingcooling system, steam generator, and auxiliary coolingcooling system and steam generator. A brief look at tables

Nero, A.V.

2010-01-01T23:59:59.000Z

216

Steam generator tube integrity program: Phase II, Final report  

SciTech Connect

The Steam Generator Tube Integrity Program (SGTIP) was a three phase program conducted for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL). The first phase involved burst and collapse testing of typical steam generator tubing with machined defects. The second phase of the SGTIP continued the integrity testing work of Phase I, but tube specimens were degraded by chemical means rather than machining methods. The third phase of the program used a removed-from-service steam generator as a test bed for investigating the reliability and effectiveness of in-service nondestructive eddy-current inspection methods and as a source of service degraded tubes for validating the Phase I and Phase II data on tube integrity. This report describes the results of Phase II of the SGTIP. The object of this effort included burst and collapse testing of chemically defected pressurized water reactor (PWR) steam generator tubing to validate empirical equations of remaining tube integrity developed during Phase I. Three types of defect geometries were investigated: stress corrosion cracking (SCC), uniform thinning and elliptical wastage. In addition, a review of the publicly available leak rate data for steam generator tubes with axial and circumferential SCC and a comparison with an analytical leak rate model is presented. Lastly, nondestructive eddy-current (EC) measurements to determine accuracy of defect depth sizing using conventional and alternate standards is described. To supplement the laboratory EC data and obtain an estimate of EC capability to detect and size SCC, a mini-round robin test utilizing several firms that routinely perform in-service inspections was conducted.

Kurtz, R.J.; Bickford, R.L.; Clark, R.A.; Morris, C.J.; Simonen, F.A.; Wheeler, K.R.

1988-08-01T23:59:59.000Z

217

Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators - Interim Report for FY 2013  

Science Conference Proceedings (OSTI)

The Light Water Reactor Sustainability program at Idaho National Laboratory is actively conducting research to develop and demonstrate online monitoring capabilities for active components in existing nuclear power plants. Idaho National Laboratory and the Electric Power Research Institute are working jointly to implement a pilot project to apply these capabilities to emergency diesel generators and generator step-up transformers. The Electric Power Research Institute Fleet-Wide Prognostic and Health Management Software Suite will be used to implement monitoring in conjunction with utility partners: Braidwood Generating Station (owned by Exelon Corporation) for emergency diesel generators, and Shearon Harris Nuclear Generating Station (owned by Duke Energy Progress) for generator step-up transformers. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for emergency diesel generators. Emergency diesel generators provide backup power to the nuclear power plant, allowing operation of essential equipment such as pumps in the emergency core coolant system during catastrophic events, including loss of offsite power. Technical experts from Braidwood are assisting Idaho National Laboratory and Electric Power Research Institute in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the Fleet-Wide Prognostic and Health Management Software Suite and tested using data from Braidwood. Parallel research on generator step-up transformers was summarized in an interim report during the fourth quarter of fiscal year 2012.

Binh T. Pham; Nancy J. Lybeck; Vivek Agarwal

2012-12-01T23:59:59.000Z

218

Property exempt from taxation: nuclear generation facility property...  

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

legislation would exempt from state property taxes any property purchased, constructed or installed to expand capacity at an existing nuclear plant or to build a new nuclear plant....

219

Global nuclear generation capacity totaled more than 370 gigawatts ...  

U.S. Energy Information Administration (EIA)

China—where plans for large increases in nuclear capacity had been announced—instituted a temporary moratorium on new approvals for nuclear power ...

220

Employee Concerns Reporting Form | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Reporting Form | National Nuclear Security Administration Reporting Form | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our Operations > Management and Budget > Human Resources > Employee Concerns Program > How Do You Report A Concern? > Employee Concerns Reporting Form Employee Concerns Reporting Form Employee Concerns Program Policy Statement

Note: This page contains sample records for the topic "nuclear generation reported" 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

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.Fuel and Geo- thermal Power Plants," by G.D. Case, T.A.

Nero, A.V.

2010-01-01T23:59:59.000Z

222

Investing in the Next Generation of U.S. Nuclear Energy Leaders |  

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

the Next Generation of U.S. Nuclear Energy Leaders the Next Generation of U.S. Nuclear Energy Leaders Investing in the Next Generation of U.S. Nuclear Energy Leaders August 9, 2011 - 5:12pm Addthis Assistant Secretary Lyons Assistant Secretary Lyons Assistant Secretary for Nuclear Energy As part of the Energy Department's Nuclear Energy University Programs (NEUP) annual workshop, I met today with professors from across the country and announced awards of up to $39 million for research projects aimed at developing cutting-edge nuclear energy technologies. The awards will also help train and educate the next generation of nuclear industry leaders in the U.S. These projects, led by 31 universities in more than 20 states, will help to enable the safe, secure and sustainable expansion of nuclear energy in the United States.

223

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Nuclear Power Reactors PROTECTION AGAINST SABOTAGE Protection Against Industrial Sabotage I1C-4 Decominarion and Decommissioning

Nero, A.V.

2010-01-01T23:59:59.000Z

224

Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)  

SciTech Connect

The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01T23:59:59.000Z

225

Institutional Research & Development Reports | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Reports | National Nuclear Security Reports | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Institutional Research & Development Reports Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing and

226

Nuclear Nonproliferation Ontology Assessment Team Final Report  

SciTech Connect

Final Report for the NA22 Simulations, Algorithm and Modeling (SAM) Ontology Assessment Team's efforts from FY09-FY11. The Ontology Assessment Team began in May 2009 and concluded in September 2011. During this two-year time frame, the Ontology Assessment team had two objectives: (1) Assessing the utility of knowledge representation and semantic technologies for addressing nuclear nonproliferation challenges; and (2) Developing ontological support tools that would provide a framework for integrating across the Simulation, Algorithm and Modeling (SAM) program. The SAM Program was going through a large assessment and strategic planning effort during this time and as a result, the relative importance of these two objectives changed, altering the focus of the Ontology Assessment Team. In the end, the team conducted an assessment of the state of art, created an annotated bibliography, and developed a series of ontological support tools, demonstrations and presentations. A total of more than 35 individuals from 12 different research institutions participated in the Ontology Assessment Team. These included subject matter experts in several nuclear nonproliferation-related domains as well as experts in semantic technologies. Despite the diverse backgrounds and perspectives, the Ontology Assessment team functioned very well together and aspects could serve as a model for future inter-laboratory collaborations and working groups. While the team encountered several challenges and learned many lessons along the way, the Ontology Assessment effort was ultimately a success that led to several multi-lab research projects and opened up a new area of scientific exploration within the Office of Nuclear Nonproliferation and Verification.

Strasburg, Jana D.; Hohimer, Ryan E.

2012-01-01T23:59:59.000Z

227

Nuclear Nonproliferation Ontology Assessment Team Final Report  

SciTech Connect

Final Report for the NA22 Simulations, Algorithm and Modeling (SAM) Ontology Assessment Team's efforts from FY09-FY11. The Ontology Assessment Team began in May 2009 and concluded in September 2011. During this two-year time frame, the Ontology Assessment team had two objectives: (1) Assessing the utility of knowledge representation and semantic technologies for addressing nuclear nonproliferation challenges; and (2) Developing ontological support tools that would provide a framework for integrating across the Simulation, Algorithm and Modeling (SAM) program. The SAM Program was going through a large assessment and strategic planning effort during this time and as a result, the relative importance of these two objectives changed, altering the focus of the Ontology Assessment Team. In the end, the team conducted an assessment of the state of art, created an annotated bibliography, and developed a series of ontological support tools, demonstrations and presentations. A total of more than 35 individuals from 12 different research institutions participated in the Ontology Assessment Team. These included subject matter experts in several nuclear nonproliferation-related domains as well as experts in semantic technologies. Despite the diverse backgrounds and perspectives, the Ontology Assessment team functioned very well together and aspects could serve as a model for future inter-laboratory collaborations and working groups. While the team encountered several challenges and learned many lessons along the way, the Ontology Assessment effort was ultimately a success that led to several multi-lab research projects and opened up a new area of scientific exploration within the Office of Nuclear Nonproliferation and Verification.

Strasburg, Jana D.; Hohimer, Ryan E.

2012-01-01T23:59:59.000Z

228

NEXT GENERATION MELTER OPTIONEERING STUDY - INTERIM REPORT  

SciTech Connect

The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D{sub 2}0 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.

GRAY MF; CALMUS RB; RAMSEY G; LOMAX J; ALLEN H

2010-10-19T23:59:59.000Z

229

Nuclear Separations Technologies Workshop Report | Department of Energy  

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

Nuclear Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report The Department of Energy (DOE) sponsored a workshop on nuclear separations technologies in Bethesda, Maryland, on July 27 and 28, 2011, to (1) identify common needs and potential requirements in separations technologies and opportunities for program partnerships, and (2) evaluate the need for a DOE nuclear separations center of knowledge to improve cross- program collaboration in separations technology. The workshop supported Goal 3 of the DOE Strategic Plan1 to enhance nuclear security through defense, nonproliferation, and environmental management. The Office of Environmental Management (EM), Office of Nuclear Energy (NE), and National Nuclear Security Administration (NNSA) jointly sponsored the workshop. The Office of Science

230

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology  

SciTech Connect

We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good agreement for simulations of highly enriched uranium assemblies is preserved; (d) The underprediction of fast criticality of {sup 233,235}U and {sup 239}Pu assemblies is removed; and (e) The intermediate spectrum critical assemblies are predicted more accurately. We anticipate that the new library will play an important role in nuclear technology applications, including transport simulations supporting national security, nonproliferation, advanced reactor and fuel cycle concepts, criticality safety, medicine, space applications, nuclear astrophysics, and nuclear physics facility design. The ENDF/B-VII.0 library is archived at the National Nuclear Data Center, BNL. The complete library, or any part of it, may be retrieved from www.nndc.bnl.gov.

Chadwick, M B; Oblozinsky, P; Herman, M; Greene, N M; McKnight, R D; Smith, D L; Young, P G; MacFarlane, R E; Hale, G M; Haight, R C; Frankle, S; Kahler, A C; Kawano, T; Little, R C; Madland, D G; Moller, P; Mosteller, R; Page, P; Talou, P; Trellue, H; White, M; Wilson, W B; Arcilla, R; Dunford, C L; Mughabghab, S F; Pritychenko, B; Rochman, D; Sonzogni, A A; Lubitz, C; Trumbull, T H; Weinman, J; Brown, D; Cullen, D E; Heinrichs, D; McNabb, D; Derrien, H; Dunn, M; Larson, N M; Leal, L C; Carlson, A D; Block, R C; Briggs, B; Cheng, E; Huria, H; Kozier, K; Courcelle, A; Pronyaev, V; der Marck, S

2006-10-02T23:59:59.000Z

231

Nuclear Waste Management. Semiannual progress report, October 1984-March 1985  

Science Conference Proceedings (OSTI)

Progress reports are presented for the following studies on radioactive waste management: defense waste technology; nuclear waste materials characterization center; and supporting studies. 19 figs., 29 tabs.

McElroy, J.L.; Powell, J.A. (comps.)

1985-06-01T23:59:59.000Z

232

FY 2012 Annual Report National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

2 Annual Report National Nuclear Security Administration ENERGY U.S. DEPARTMENT OF Table of Contents Executive Message Meeting National Policy Objectives The Four Pillars of NIS...

233

Long-term outlook for nuclear generation depends on lifetime of ...  

U.S. Energy Information Administration (EIA)

These projects are currently under construction. Overall generation from nuclear power grows by 14.3% from 2011 through 2040 (see chart below).

234

Annual report of waste generation and pollution prevention progress 1995  

Science Conference Proceedings (OSTI)

This fourth Annual Report presents and analyzes 1995 DOE complex-wide waste generation and pollution prevention activities at 40 reporting sites in 25 States, and trends DOE waste generation from 1991 through 1995. DOE has established a 50% reduction goal (relative to the 1993 baseline) for routine operations radioactive and hazardous waste generation, due by December 31, 1999. Routine operations waste generation decreased 37% from 1994 to 1995, and 43% overall from 1993--1995.

NONE

1997-02-01T23:59:59.000Z

235

11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation  

E-Print Network (OSTI)

-2% to 60-70%; and third step is the employment of nuclear fusion. However, a report by Zhongguo Dianli Wang thermonuclear experimental reactors (ITER) by International Atomic Energy Agency (IAEA), says, are meant to utilize the energy generated in the fusion of hydrogen, as in the explosion of a hydrogen bomb

236

October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

6, Report of the ADVANCED NUCLEAR TRANSFORMATION 6, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE The Global Nuclear Energy Partnership (GNEP) program is still evolving. Since our report of March 22, 2006 the DOE has sought to gauge industry interest in participation in the program from its very beginning. At the time the ANTT committee met, August 30- 31, 2006, responses had not yet been received from industry to the DOE's request for Expressions of Interest. This report is based on the assumption that the program outlined recently, which does not include an Advanced Burner Test Reactor, is what

237

Main Generator Seal Oil Supply Reliability Improvements at Southern California Edison's San Onofre Nuclear Generating Station  

Science Conference Proceedings (OSTI)

This paper presents the justification for the approach, details and results of the Main Generator Seal Oil System reliability enhancements on the San Onofre Nuclear Generating Station, SONGS. The SONGS, Unit 3 experienced substantial turbine damage in early 2001 after the turbine bearings lubrication oil supply failed. During a loss of off-site power incident, power was lost to the two AC powered turbine lubrication oil pumps due to a breaker failure in the switchgear and the DC powered emergency bearing lubricating oil pump failed to start due to a breaker trip. The SONGS turbine generators coasted down from full speed to a full stop without lubricating oil. This resulted in significant bearing, journal and steam path damage that required a four-month duration repair outage during a time period where electricity was in short supply in the State of California. The generator hydrogen sealing system remained operable during this event, however it was recognized during the event follow up investigation that this system had vulnerabilities to failure similar to the bearing lubrication system. In order to prevent a reoccurrence of this extremely costly event, SONGS has taken actions to modify both of these critical turbine generator systems by adding additional, continuously operating pumps with a new, independent power source and independently routed cables. The main challenge was to integrate the additional equipment into the existing lubrication and seal oil systems. The lubrication Oil System was the first system to be retro-fitted and these results already have been presented. Reference 2. This paper provides the result of the reliability enhancements for the Main Generator Seal Oil System, which concludes the turbine/generator critical oil systems reliability improvements, performed by SONGS. It is worth noting that the design team discovered and corrected a number of other significant operational issues, which had been present from the early days and also learned a great deal of detailed information about this vital system during the project. The SONGS approach and findings are discussed in this paper, as well as a summary of the work performed. This technical paper will be of interest to utilities with a need to improve turbine generator reliability issues. (authors)

Simma, Fred Y.; Chetwynd, Russell J. [Southern California Edison, P.O. Box 800, Rosemead, CA 91770 (United States); Rowe, Stuart A. [Alstom Power Service (United States)

2006-07-01T23:59:59.000Z

238

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

None

2005-01-01T23:59:59.000Z

239

A Vision for Nuclear Theory: Report to NSAC  

E-Print Network (OSTI)

This is the report of the NSAC Subcommittee on Nuclear Theory in response to a charge by the funding agencies to review and evaluate current NSF and DOE supported efforts in nuclear theory and identify strategic plans to ensure a strong U.S. nuclear theory program under various funding scenarios.

J. Carlson; B. Holstein; X. D. Ji; G. McLaughlin; B. Müller; W. Nazarewicz; K. Rajagopal; W. Roberts; X. -N. Wang

2003-11-18T23:59:59.000Z

240

Paving the path for next-generation nuclear energy | Department of Energy  

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

Paving the path for next-generation nuclear energy Paving the path for next-generation nuclear energy Paving the path for next-generation nuclear energy May 6, 2013 - 2:26pm Addthis Renewed energy and enhanced coordination are on the horizon for an international collaborative that is advancing new, safer nuclear energy systems. Renewed energy and enhanced coordination are on the horizon for an international collaborative that is advancing new, safer nuclear energy systems. Deputy Assistant Secretary Kelly Deputy Assistant Secretary Kelly Deputy Assistant Secretary for Nuclear Reactor Technologies Nuclear power reactors currently under construction worldwide boast modern safety and operational enhancements that were designed by the global nuclear energy industry and enhanced through research and development (R&D)

Note: This page contains sample records for the topic "nuclear generation reported" 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

Nuclear technology programs; Semiannual progress report, October 1989--March 1990  

Science Conference Proceedings (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

Harmon, J.E. [ed.

1992-01-01T23:59:59.000Z

242

Nuclear technology programs semiannual progress report, April--September 1989  

SciTech Connect

This document reports on the work done by the Nuclear Technology Program of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1989. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with developing a process for separating the organic and inorganic constitutents of the red-water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories. 154 refs., 154 figs., 100 tabs.

Harmon, J.E. (ed.)

1991-08-01T23:59:59.000Z

243

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site  

Science Conference Proceedings (OSTI)

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

L.E. Demick

2011-10-01T23:59:59.000Z

244

International Nuclear Energy Research Initiative: 2010 Annual Report |  

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

10 Annual 10 Annual Report International Nuclear Energy Research Initiative: 2010 Annual Report The International Nuclear Energy Research Initiative (I-NERI) is a research-oriented collaborative program that supports the advancement of nuclear science and technology in the United States and the world. Innovative research performed under the I-NERI umbrella addresses key issues affecting the future use of nuclear energy and its global deployment. The 2010 Nuclear Energy Research and Development Roadmap issued by the U.S. Department of Energy, Office of Nuclear Energy (DOE-NE), identifies these issues as high capital costs, safety, high-level nuclear waste management, and non-proliferation. Projects under the I-NERI program investigate ways to address these challenges and support future nuclear

245

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-12-01T23:59:59.000Z

246

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2007-01-01T23:59:59.000Z

247

Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-09-01T23:59:59.000Z

248

A knowledge representation model for the nuclear power generation domain  

Science Conference Proceedings (OSTI)

A knowledge representation model for the nuclear power field is proposed. The model is a generalized production rule function inspired by a neural network approach that enables the representation of physical systems of nuclear power plants. The article ... Keywords: Knowledge representation, Nuclear power plant, Physical systems, Production rules

Thiago Tinoco Pires

2007-11-01T23:59:59.000Z

249

Report of the Nuclear Energy Research Advisory Committee, Subcommittee on  

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

of the Nuclear Energy Research Advisory Committee, of the Nuclear Energy Research Advisory Committee, Subcommittee on Nuclear Laboratory Requirements Report of the Nuclear Energy Research Advisory Committee, Subcommittee on Nuclear Laboratory Requirements As an element of its plans to return the U.S. Department of Energy (DOE) site in eastern Idaho to its historic mission of nuclear technology development, the DOE asked its Nuclear Energy Research Advisory Committee (NERAC) to establish a Subcommittee on Nuclear Laboratory Requirements. The Subcommittee was charged with identifying the "characteristics, capabilities, and attributes a world-class nuclear laboratory would possess". It was also asked "to become familiar with the practices, culture, and facilities of other world-class laboratories - not

250

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Fuel and Geo­ thermal Power Plants," by G.D. Case, T.A.produces thermal energy, from the nuclear power plant, whichthermal, or the study "large" plants about one about 1000 sixth MW size of current The large nuclear power plants (

Nero, A.V.

2010-01-01T23:59:59.000Z

251

Wind electric generator project. Final report  

Science Conference Proceedings (OSTI)

The wind generator is installed and connected at Iowa Western Community College. It is heating water through four hot water tanks and has proven to be an excellent demonstration project for the community. The college gets frequent inquiries about the wind mill and has been very cooperative in informing the public about the success. The windmill generates more electricity than is needed to heat four hot water heaters and future plans are to hook up more. The project requires very little maintenance. Attached is a date sheet on the project.

Not Available

1983-09-23T23:59:59.000Z

252

Report on interim storage of spent nuclear fuel  

SciTech Connect

The report on interim storage of spent nuclear fuel discusses the technical, regulatory, and economic aspects of spent-fuel storage at nuclear reactors. The report is intended to provide legislators state officials and citizens in the Midwest with information on spent-fuel inventories, current and projected additional storage requirements, licensing, storage technologies, and actions taken by various utilities in the Midwest to augment their capacity to store spent nuclear fuel on site.

1993-04-01T23:59:59.000Z

253

2010 Report Released | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Our History > NNSA Timeline > 2010 Report Released 2010 Report Released January 12, 1987 Washington, DC 2010 Report Released White House releases "2010 Report," projecting...

254

Working Group Report on - Space Nuclear Power Systems and Nuclear Waste  

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

Working Group Report on - Space Nuclear Power Systems and Nuclear Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even though one cannot anticipate the answers in basic research, the return on the public's investment can be maximized through long-range planning of the most promising avenues to explore and the resources needed to explore them." (p. v) "Pursuit of this goal entails developing new technologies and advanced facilities, educating young scientists, training a technical workforce, and contributing to the broader science and technology enterprise?." (p. vi) Ref:: "Nuclear Science: A Long Range Plan", DOE/NSF, Feb. 1996. The purpose of this effort is to develop the first iteration of a

255

Working Group Report on - Space Nuclear Power Systems and Nuclear Waste  

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

Working Group Report on - Space Nuclear Power Systems and Nuclear Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even though one cannot anticipate the answers in basic research, the return on the public's investment can be maximized through long-range planning of the most promising avenues to explore and the resources needed to explore them." (p. v) "Pursuit of this goal entails developing new technologies and advanced facilities, educating young scientists, training a technical workforce, and contributing to the broader science and technology enterprise?." (p. vi) Ref:: "Nuclear Science: A Long Range Plan", DOE/NSF, Feb. 1996. The purpose of this effort is to develop the first iteration of a

256

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

P. E. MacDonald

2005-01-01T23:59:59.000Z

257

Annual report of waste generation and pollution prevention progress 1999  

SciTech Connect

This Annual Report summarizes and highlights waste generation, waste reduction, pollution prevention accomplishments, and cost avoidance for 44 U.S. Department of Energy reporting sites for Calendar Year 1999. This section summarizes Calendar Year 1999 Complex-wide waste generation and pollution prevention accomplishments.

NONE

2000-09-01T23:59:59.000Z

258

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

generate steam to drive a steam turbine, giving rise to theValves and Pi~ing STEAM TURBINE COMPONENT OUTAGE CAUSESbasically of a steam-driven turbine, an electric generator

Nero, A.V.

2010-01-01T23:59:59.000Z

259

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

a. b. c. Pump Ap S(WDB) OK NT(NC) W(WDB) Steam generatorsuperheat Steam generator tube leaks D. Core thermaland radial models Steam generator tube leaks Critical heat

Nero, A.V.

2010-01-01T23:59:59.000Z

260

International Nuclear Energy Research Initiative: 2007 Annual Report |  

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

International Nuclear Energy Research Initiative: 2007 Annual International Nuclear Energy Research Initiative: 2007 Annual Report International Nuclear Energy Research Initiative: 2007 Annual Report The International Nuclear Energy Research Initiative (I-NERI) supports the National Energy Policy by pursuing international collaborations to conduct research that will advance the state of nuclear science and technology in the United States. I-NERI promotes bilateral and multilateral scientific and engineering research and development (R&D) with other nations. Innovative research performed under the I-NERI umbrella addresses key issues affecting the future of nuclear energy and its global deployment by improving cost performance, enhancing safety, and increasing proliferation resistance of future nuclear energy systems. Information on the program

Note: This page contains sample records for the topic "nuclear generation reported" 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

Illinois Nuclear Profile - LaSalle Generating Station  

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

LaSalle Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

262

New Jersey Nuclear Profile - PSEG Salem Generating Station  

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

PSEG Salem Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

263

New Jersey Nuclear Profile - PSEG Hope Creek Generating Station  

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

PSEG Hope Creek Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

264

Letter to NEAC to Review the Next Generation Nuclear Plant Activities |  

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

to NEAC to Review the Next Generation Nuclear Plant to NEAC to Review the Next Generation Nuclear Plant Activities Letter to NEAC to Review the Next Generation Nuclear Plant Activities The Next Generation Nuclear Plant (NGNP) project was established under the Energy Policy Act in August 2005 (EPACT-2005). EPACT-2005 defined an overall plan and timetable for NGNP research, design, licensing, construction and operation by the end of FY 2021. At the time that EPACT-2005 was passed, it was envisioned that key aspects of the project included: NGNP is based on R&D activities supported by the Gen-IV Nuclear Energy initiative;  NGNP is to be used to generate electricity, to produce hydrogen or (to do) both;  The Idaho National Laboratory (INL) will be the lead national lab for the project;  NGNP will be sited at the INL in

265

A Technology Roadmap for Generation IV Nuclear Energy Systems Executive Summary  

SciTech Connect

To meet future energy needs, ten countries--Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, Switzerland, the United Kingdom, and the United States--have agreed on a framework for international cooperation in research for an advanced generation of nuclear energy systems, known as Generation IV. These ten countries have joined together to form the Generation IV International Forum (GIF) to develop future-generation nuclear energy systems that can be licensed, constructed, and operated in a manner that will provide competitively priced and reliable energy products while satisfactorily addressing nuclear safety, waste, proliferation, and public perception concerns. The objective for Generation IV nuclear energy systems is to be available for international deployment before the year 2030, when many of the world's currently operating nuclear power plants will be at or near the end of their operating licenses.

2003-03-01T23:59:59.000Z

266

Nuclear Separations Technologies Workshop Report | Department of Energy  

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

Separations Technologies Workshop Report Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report The Department of Energy (DOE) sponsored a workshop on nuclear separations technologies in Bethesda, Maryland, on July 27 and 28, 2011, to (1) identify common needs and potential requirements in separations technologies and opportunities for program partnerships, and (2) evaluate the need for a DOE nuclear separations center of knowledge to improve cross- program collaboration in separations technology. The workshop supported Goal 3 of the DOE Strategic Plan1 to enhance nuclear security through defense, nonproliferation, and environmental management. The Office of Environmental Management (EM), Office of Nuclear Energy (NE), and National Nuclear Security Administration (NNSA) jointly sponsored the workshop. The Office of Science

267

October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

3, Report of the ADVANCED NUCLEAR TRANSFORMATION 3, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE The committee met in Washington in Sept 16-17 to review progress in the program with respect to a changed set of mission priorities. Our last meeting took place in Dec 2002 after the reorganization that had place the Advanced Fuel Cycle Initiative (AFCI) and GEN IV program together in the Advanced Nuclear Reserach Office (AN-20). Since mission priorities have been evolving, the committee felt that it should wait unti they have settled down before we met again. We have kept in touch during the process,

268

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

prevent serious damage to the nuclear fuel, since it is thetransportation: for nuclear plants, fuel handling is carriedSpecific Fossil Fuel Geothermal Nuclear Solid Waste Disposal

Nero, A.V.

2010-01-01T23:59:59.000Z

269

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Commission Report WASH-1400 (NUREG-75/014), in 9 volumes,Commission Report WASH-1400 (NUREG-75/014), in 9 volumes,Commission Report WASH-1400 (NUREG-75/014), in 9 volumes,

Nero, A.V.

2010-01-01T23:59:59.000Z

270

How Do You Report A Concern? | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Report A Concern? | National Nuclear Security Administration Report A Concern? | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog How Do You Report A Concern? Home > About Us > Our Operations > Management and Budget > Human Resources > Employee Concerns Program > How Do You Report A Concern? How Do You Report A Concern? DOE/NNSA Federal, contractor and subcontractor employees may report their

271

EEO Plans and Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plans and Reports | National Nuclear Security Administration Plans and Reports | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog EEO Plans and Reports Home > About Us > Our Operations > Management and Budget > Office of Civil Rights > EEO Plans and Reports EEO Plans and Reports FY 13 Disabled Veterans Affirmative Action Program Report (pdf, 668kb)

272

Nuclear Science Division 1994 annual report  

Science Conference Proceedings (OSTI)

This report describes the activities of the Nuclear Science Division for the period of January 1, 1994, to December 31, 1994. This was a time of significant accomplishment for all of the programs in the Division. Assembly of the solar neutrino detector at the Sudbury Neutrino Observatory is well under way. All of the components fabricated by LBL were shipped to Sudbury early in the year and our efforts are now divided between assisting the assembly of the detector and preparing software for data analysis once the detector is operational in 1996. Much of the activity at the 88-Inch Cyclotron centered on Gammasphere. The {open_quotes}early implementation{close_quotes} phase of the detector ended in September. This phase was extremely successful, involving over 60 experiments with nearly 200 users from 37 institutions worldwide. The mechanical structure was installed and the final electronic system is expected to operate in March 1995. The Division concurrently hosted a conference on physics for large {gamma}-ray detector arrays at the Clark Kerr Campus at UC Berkeley in August. This was a very successful meeting, reflecting the enthusiasm for this field worldwide. Also at the Cyclotron, the progress toward weak interaction experiments using ultra-thin sources passed a major milestone with the trapping of radioactive {sup 21}Na atoms. We are now engaged in a major upgrade of the experimental area and the outlook is very promising for these novel experiments. Another highlight of research at the Cyclotron was the confirmation of element 106. This development allowed the original LLNL/LBL discovery team to move forward with their proposal to name this element seaborgium.

Myers, W.D. [ed.

1995-06-01T23:59:59.000Z

273

White paper report on using nuclear reactors to search for a value of theta13  

E-Print Network (OSTI)

PAPER REPORT on Using Nuclear Reactors to Search for a valuetimely new experiment at a nuclear reactor sensitive to theand judicious choice of a nuclear reactor. The dominant

2004-01-01T23:59:59.000Z

274

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

MWe l. l. l. l. l. l. l. CONDENSER o. o. o. o. GENERATOR o.Code BOILER TURBINE CONDENSER MWe MWe MWe 600 & Above MWe O.3) pE rcentage of total CONDENSER l. 23l. O. GENERATOR l.

Nero, A.V.

2010-01-01T23:59:59.000Z

275

DOE Seeks Additional Input on Next Generation Nuclear Plant | Department of  

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

Seeks Additional Input on Next Generation Nuclear Plant Seeks Additional Input on Next Generation Nuclear Plant DOE Seeks Additional Input on Next Generation Nuclear Plant April 17, 2008 - 10:49am Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) today announced it is seeking public and industry input on how to best achieve the goals and meet the requirements for the Next Generation Nuclear Plant (NGNP) demonstration project work at DOE's Idaho National Laboratory. DOE today issued a Request for Information and Expressions of Interest from prospective participants and interested parties on utilizing cutting-edge high temperature gas reactor technology in the effort to reduce greenhouse gas emissions by enabling nuclear energy to replace fossil fuels used by industry for process heat. "This is an opportunity to advance the development of safe, reliable, and

276

The development and use of radionuclide generators in nuclear medicine -- recent advances and future perspectives  

SciTech Connect

Although the trend in radionuclide generator research has declined, radionuclide generator systems continue to play an important role in nuclear medicine. Technetium-99m obtained from the molybdenum-99/technetium-99m generator system is used in over 80% of all diagnostic clinical studies and there is increasing interest and use of therapeutic radioisotopes obtained from generator systems. This paper focuses on a discussion of the major current areas of radionuclide generator research, and the expected areas of future research and applications.

Knapp, F.F. Jr.

1998-03-01T23:59:59.000Z

277

International Nuclear Energy Research Initiative: 2008 Annual Report |  

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

8 Annual 8 Annual Report International Nuclear Energy Research Initiative: 2008 Annual Report The International Nuclear Energy Research Initiative (I-NERI) is an international, research-oriented initiative that supports the advancement of nuclear science and technology in the United States and the world. I-NERI promotes bilateral scientific and engineering research and development (R&D) with other nations. Innovative research performed under the I-NERI umbrella addresses key issues affecting the future use of nuclear energy and its global deployment by improving cost performance, enhancing safety, and increasing proliferation resistance of future nuclear energy systems. A link to the program can be found at the U.S. Department of Energy, Office of Nuclear Energy (DOE-NE) website:

278

International Nuclear Energy Research Initiative: 2009 Annual Report |  

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

9 Annual 9 Annual Report International Nuclear Energy Research Initiative: 2009 Annual Report The International Nuclear Energy Research Initiative (I-NERI) is an international, research-oriented collaboration that supports advancement of nuclear science and technology in the United States and the world. I-NERI promotes bilateral scientific and engineering research and development (R&D) with other nations. Innovative research performed under the I-NERI umbrella addresses key issues affecting the future use of nuclear energy and its global deployment by improving cost performance, enhancing safety, and increasing proliferation resistance of future nuclear energy systems. A link to the program can be found at the U.S. Department of Energy Office of Nuclear Energy website.

279

Microsoft Word - spent nuclear fuel report.doc  

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

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

280

Membranes for H2 generation from nuclear powered thermochemical cycles.  

DOE Green Energy (OSTI)

In an effort to produce hydrogen without the unwanted greenhouse gas byproducts, high-temperature thermochemical cycles driven by heat from solar energy or next-generation nuclear power plants are being explored. The process being developed is the thermochemical production of Hydrogen. The Sulfur-Iodide (SI) cycle was deemed to be one of the most promising cycles to explore. The first step of the SI cycle involves the decomposition of H{sub 2}SO{sub 4} into O{sub 2}, SO{sub 2}, and H{sub 2}O at temperatures around 850 C. In-situ removal of O{sub 2} from this reaction pushes the equilibrium towards dissociation, thus increasing the overall efficiency of the decomposition reaction. A membrane is required for this oxygen separation step that is capable of withstanding the high temperatures and corrosive conditions inherent in this process. Mixed ionic-electronic perovskites and perovskite-related structures are potential materials for oxygen separation membranes owing to their robustness, ability to form dense ceramics, capacity to stabilize oxygen nonstoichiometry, and mixed ionic/electronic conductivity. Two oxide families with promising results were studied: the double-substituted perovskite A{sub x}Sr{sub 1-x}Co{sub 1-y}B{sub y}O{sub 3-{delta}} (A=La, Y; B=Cr-Ni), in particular the family La{sub x}Sr{sub 1-x}Co{sub 1-y}Mn{sub y}O{sub 3-{delta}} (LSCM), and doped La{sub 2}Ni{sub 1-x}M{sub x}O{sub 4} (M = Cu, Zn). Materials and membranes were synthesized by solid state methods and characterized by X-ray and neutron diffraction, SEM, thermal analyses, calorimetry and conductivity. Furthermore, we were able to leverage our program with a DOE/NE sponsored H{sub 2}SO{sub 4} decomposition reactor study (at Sandia), in which our membranes were tested in the actual H{sub 2}SO{sub 4} decomposition step.

Nenoff, Tina Maria; Ambrosini, Andrea; Garino, Terry J.; Gelbard, Fred; Leung, Kevin; Navrotsky, Alexandra (University of California, Davis, CA); Iyer, Ratnasabapathy G. (University of California, Davis, CA); Axness, Marlene

2006-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Report of the State of Nevada Commission on Nuclear Projects  

SciTech Connect

This third biennial Report of the Nevada Commission on Nuclear Projects has been prepared in fulfillment of the requirements of NRS 459.0092, which stipulates that the Commission shall report to the Governor and Legislature on any matter relating to radioactive waste disposal the Commission deems appropriate and advise and make recommendations on the policy of the State concerning nuclear waste disposal projects. Chapter One of the Report presents a brief overview of the Commission`s functions and statutory charges. It also contains a summary of developments which have affected the overall nuclear waste disposl issue since the last Commission Report was published in November, 1988. Chapter Two contains a synthesis of Commission activities and reports on the findings of the Commission relative to the geotechnical, environmental, socioeconomic, transportation, intergovernmental and legal aspects of federal and State nuclear waste program efforts.

1990-12-01T23:59:59.000Z

282

Nuclear science. Annual report, July 1, 1980-June 30, 1981  

Science Conference Proceedings (OSTI)

This annual report describes the scientific research carried out within the Nuclear Science Division between July 1, 1980 and June 30, 1981. The principal activity of the division continues to be the experimental and theoretical investigation of the interaction of heavy ions with target nuclei. Complementary research programs in light-ion nuclear science, in nuclear data evaluations, and in the development of advanced instrumentation are also carried out.

Friedlander, E.M. (ed.)

1982-06-01T23:59:59.000Z

283

Institute of Nuclear Power Operations 1994 annual report  

SciTech Connect

This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1994 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

NONE

1994-12-31T23:59:59.000Z

284

Institute of Nuclear Power Operations annual report, 1993  

SciTech Connect

This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1993 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry.

NONE

1993-12-31T23:59:59.000Z

285

Table 9.1 Nuclear Generating Units, 1955-2011  

U.S. Energy Information Administration (EIA)

1 Data in columns 1–3 are based on the U.S. Nuclear Regulatory Commission (NRC) regulation 10 CFR Part 50. Data in columns 4–6 are based on the NRC regulation 10 ...

286

Observations on A Technology Roadmap for Generation IV Nuclear...  

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

the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new installations in the short term. DOE needs to...

287

Nuclear economics 2000: Deterministic and probabilistic projections of nuclear and coal electric power generation costs for the year 2000  

SciTech Connect

The total busbar electric generating costs were estimated for locations in ten regions of the United States for base-load nuclear and coal-fired power plants with a startup date of January 2000. For the Midwest region a complete data set that specifies each parameter used to obtain the comparative results is supplied. When based on the reference set of input variables, the comparison of power generation costs is found to favor nuclear in most regions of the country. Nuclear power is most favored in the northeast and western regions where coal must be transported over long distances; however, coal-fired generation is most competitive in the north central region where large reserves of cheaply mineable coal exist. In several regions small changes in the reference variables could cause either option to be preferred. The reference data set reflects the better of recent electric utility construction cost experience (BE) for nuclear plants. This study assumes as its reference case a stable regulatory environment and improved planning and construction practices, resulting in nuclear plants typically built at the present BE costs. Today's BE nuclear-plant capital investment cost model is then being used as a surrogate for projected costs for the next generation of light-water reactor plants. An alternative analysis based on today's median experience (ME) nuclear-plant construction cost experience is also included. In this case, coal is favored in all ten regions, implying that typical nuclear capital investment costs must improve for nuclear to be competitive.

Williams, K.A.; Delene, J.G.; Fuller, L.C.; Bowers, H.I.

1987-06-01T23:59:59.000Z

288

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs  

DOE Green Energy (OSTI)

Here we report the outcome of the application of the Nuclear Regulatory Commission (NRC) Phenomena Identification and Ranking Table (PIRT) process to the issue of nuclear-grade graphite for the moderator and structural components of a next generation nuclear plant (NGNP), considering both routine (normal operation) and postulated accident conditions for the NGNP. The NGNP is assumed to be a modular high-temperature gas-cooled reactor (HTGR), either a gas-turbine modular helium reactor (GTMHR) version [a prismatic-core modular reactor (PMR)] or a pebble-bed modular reactor (PBMR) version [a pebble bed reactor (PBR)] design, with either a direct- or indirect-cycle gas turbine (Brayton cycle) system for electric power production, and an indirect-cycle component for hydrogen production. NGNP design options with a high-pressure steam generator (Rankine cycle) in the primary loop are not considered in this PIRT. This graphite PIRT was conducted in parallel with four other NRC PIRT activities, taking advantage of the relationships and overlaps in subject matter. The graphite PIRT panel identified numerous phenomena, five of which were ranked high importance-low knowledge. A further nine were ranked with high importance and medium knowledge rank. Two phenomena were ranked with medium importance and low knowledge, and a further 14 were ranked medium importance and medium knowledge rank. The last 12 phenomena were ranked with low importance and high knowledge rank (or similar combinations suggesting they have low priority). The ranking/scoring rationale for the reported graphite phenomena is discussed. Much has been learned about the behavior of graphite in reactor environments in the 60-plus years since the first graphite rectors went into service. The extensive list of references in the Bibliography is plainly testament to this fact. Our current knowledge base is well developed. Although data are lacking for the specific grades being considered for Generation IV (Gen IV) concepts, such as the NGNP, it is fully expected that the behavior of these graphites will conform to the recognized trends for near isotropic nuclear graphite. Thus, much of the data needed is confirmatory in nature. Theories that can explain graphite behavior have been postulated and, in many cases, shown to represent experimental data well. However, these theories need to be tested against data for the new graphites and extended to higher neutron doses and temperatures pertinent to the new Gen IV reactor concepts. It is anticipated that current and planned future graphite irradiation experiments will provide the data needed to validate many of the currently accepted models, as well as providing the needed data for design confirmation.

Burchell, Timothy D [ORNL; Bratton, Rob [Idaho National Laboratory (INL); Marsden, Barry [University of Manchester, UK; Srinivasan, Makuteswara [U.S. Nuclear Regulatory Commission; Penfield, Scott [Technology Insights; Mitchell, Mark [PBMR (Pty) Ltd.; Windes, Will [Idaho National Laboratory (INL)

2008-03-01T23:59:59.000Z

289

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

entry are u Table 4-6 GAS TURBINE FOR 1965-1974 (OUTAGES)AVERAGE utage Cause Code GAS TURBINE GENERATOR FORCED OUTAGEof fossil units, and for gas turbine units, the basic data

Nero, A.V.

2010-01-01T23:59:59.000Z

290

Nuclear Waste Programs semiannual progress report, April--September 1992  

Science Conference Proceedings (OSTI)

This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period April--September 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

Bates, J.K.; Bradley, C.R.; Buck, E.C. [and others

1994-05-01T23:59:59.000Z

291

Nuclear waste programs; Semiannual progress report, October 1991--March 1992  

SciTech Connect

This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Finn, P.A.; Gerding, T.J.; Hoh, J.C. [and others

1993-11-01T23:59:59.000Z

292

Microsoft Word - Power Generation in Pipeline Report.doc  

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

correctness. LA-UR-05-6354 Approved for public release; distribution is unlimited. Title: Power Generation in Pipeline: Report Author(s): Dipen N. Sinha Submitted to: Gas...

293

Alternative electric generation impact simulator : final summary report  

E-Print Network (OSTI)

This report is a short summary of three related research tasks that were conducted during the project "Alternative Electric Generation Impact Simulator." The first of these tasks combines several different types of ...

Gruhl, Jim

1981-01-01T23:59:59.000Z

294

Radioactive Effluents from Nuclear Power Plants Annual Report 2008  

SciTech Connect

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

295

Radioactive Effluents from Nuclear Power Plants Annual Report 2007  

SciTech Connect

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

296

Interim report on long range plan for nuclear physics  

SciTech Connect

The interim report on the updated NSAC Long Range Plan for Nuclear Physics will be presented to the community for discussion and comment before submission to the funding agencies. The presentation will be coordinated by E. Moniz chair of NSAC.

1995-04-01T23:59:59.000Z

297

NUCLEAR DATA AND MEASUREMENTS REPORTS 21-40 - Nuclear Data Program (Argonne  

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

21 - 40 21 - 40 Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Group 1 (ANL/NDM-1 - ANL/NDM-20) Group 2 (ANL/NDM-21 - ANL/NDM-40) Group 3 (ANL/NDM-41 - ANL/NDM-60) Group 4 (ANL/NDM-61 - ANL/NDM-80) Group 5 (ANL/NDM-81 - ANL/NDM-100) Group 6 (ANL/NDM-101 - ANL/NDM-120) Group 7 (ANL/NDM-121 - ANL/NDM-140) Group 8 (ANL/NDM-141 - ANL/NDM-160) Group 9 (ANL/NDM-161 - ANL/NDM-180) Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program NUCLEAR DATA AND MEASUREMENTS REPORTS Bookmark and Share Reports 21-40

298

NUCLEAR DATA AND MEASUREMENTS REPORTS 101-120 - Nuclear Data Program  

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

01 - 120 01 - 120 Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Group 1 (ANL/NDM-1 - ANL/NDM-20) Group 2 (ANL/NDM-21 - ANL/NDM-40) Group 3 (ANL/NDM-41 - ANL/NDM-60) Group 4 (ANL/NDM-61 - ANL/NDM-80) Group 5 (ANL/NDM-81 - ANL/NDM-100) Group 6 (ANL/NDM-101 - ANL/NDM-120) Group 7 (ANL/NDM-121 - ANL/NDM-140) Group 8 (ANL/NDM-141 - ANL/NDM-160) Group 9 (ANL/NDM-161 - ANL/NDM-180) Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program NUCLEAR DATA AND MEASUREMENTS REPORTS Bookmark and Share Reports 101-120

299

NUCLEAR DATA AND MEASUREMENTS REPORTS 121-140 - Nuclear Data Program  

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

21 - 140 21 - 140 Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Group 1 (ANL/NDM-1 - ANL/NDM-20) Group 2 (ANL/NDM-21 - ANL/NDM-40) Group 3 (ANL/NDM-41 - ANL/NDM-60) Group 4 (ANL/NDM-61 - ANL/NDM-80) Group 5 (ANL/NDM-81 - ANL/NDM-100) Group 6 (ANL/NDM-101 - ANL/NDM-120) Group 7 (ANL/NDM-121 - ANL/NDM-140) Group 8 (ANL/NDM-141 - ANL/NDM-160) Group 9 (ANL/NDM-161 - ANL/NDM-180) Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program NUCLEAR DATA AND MEASUREMENTS REPORTS Bookmark and Share Reports 121-140

300

NUCLEAR DATA AND MEASUREMENTS REPORTS 141-160 - Nuclear Data Program  

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

41 - 160 41 - 160 Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Group 1 (ANL/NDM-1 - ANL/NDM-20) Group 2 (ANL/NDM-21 - ANL/NDM-40) Group 3 (ANL/NDM-41 - ANL/NDM-60) Group 4 (ANL/NDM-61 - ANL/NDM-80) Group 5 (ANL/NDM-81 - ANL/NDM-100) Group 6 (ANL/NDM-101 - ANL/NDM-120) Group 7 (ANL/NDM-121 - ANL/NDM-140) Group 8 (ANL/NDM-141 - ANL/NDM-160) Group 9 (ANL/NDM-161 - ANL/NDM-180) Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program NUCLEAR DATA AND MEASUREMENTS REPORTS Bookmark and Share Reports 141-160

Note: This page contains sample records for the topic "nuclear generation reported" 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

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

NP-263, October 1976. Edison Electric Institute, "Report onREGULATION Data from the Edison Electric Institute annualpower plants. However, the Edison Electric Institute, in its

Nero, A.V.

2010-01-01T23:59:59.000Z

302

Ris Energy Report 4 Distributed generation 1 What is distributed generation?  

E-Print Network (OSTI)

Risø Energy Report 4 Distributed generation 1 5 What is distributed generation? Distributed as distributed energy resources (DERs). It appears that there is no consensus on precise defi- nitions of DG. Wind energy is presently the fastest growing and largest contributor to distributed genera- tion from

303

Report to Congress on Plan for Interim Storage of Spent Nuclear...  

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

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from...

304

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

E-Print Network (OSTI)

U. S. Conunercial Nuclear Power Plants", Report WASH-1400 (for Light-Water Cooled Nuclear Power Plants to Assess PlantStandards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

305

International Nuclear Energy Research Initiative: Annual Report 2005 |  

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

5 5 International Nuclear Energy Research Initiative: Annual Report 2005 The International Nuclear Energy Research Initiative (I-NERI) supports the National Energy Policy by conducting research to advance the state of nuclear science and technology in the United States. I-NERI sponsors innovative scientific and engineering research and development (R&D) in cooperation with participating countries. The research performed under the I-NERI umbrella addresses the key issues affecting the future of nuclear energy and its global deployment. I-NERI research is directed towards improving cost performance, increasing proliferation resistance, enhancing safety, and improving the waste management of future nuclear energy systems. This I-NERI 2005 Annual Report serves to inform interested parties about

306

Mathematical model of steam generator feed system at power unit of nuclear plant  

Science Conference Proceedings (OSTI)

A mathematical model of a steam generator feed system at a power unit of a nuclear plant with variable values of transfer function coefficients is presented. The model is realized in the MATLAB/Simulink/Stateflow event-driven simulation.

E. M. Raskin; L. A. Denisova; V. P. Sinitsyn; Yu. V. Nesterov

2011-05-01T23:59:59.000Z

307

Maintenance practices for emergency diesel generator engines onboard United States Navy Los Angeles class nuclear submarines  

E-Print Network (OSTI)

The United States Navy has recognized the rising age of its nuclear reactors. With this increasing age comes increasing importance of backup generators. In addition to the need for decay heat removal common to all (naval ...

Hawks, Matthew Arthur

2006-01-01T23:59:59.000Z

308

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward  

SciTech Connect

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

John Collins

2009-01-01T23:59:59.000Z

309

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

310

Strategic Nuclear Research Collaboration - FY99 Annual Report  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) has created the Strategic Nuclear Research Collaboration. The SNRC brings together some of America's finest laboratory and university nuclear researchers in a carefully focused research program intended to produce ''breakthrough'' solutions to the difficult issues of nuclear economics, safety, non-proliferation, and nuclear waste. This integrated program aims to address obstacles that stand in the way of nuclear power development in the US These include fuel cycle concerns related to waste and proliferation, the need for more efficient regulatory practices, and the high cost of constructing and operating nuclear power plants. Funded at an FY99 level of $2.58M, the SNRC is focusing the efforts of scientists and engineers from the INEEL and the Massachusetts Institute of Technology to solve complex nuclear energy challenges in a carefully chosen, integrated portfolio of research topics. The result of this collaboration will be research that serves as a catalyst for future direct-funded nuclear research and technology development and which preserves and enhances the INEEL's role as America's leading national laboratory for nuclear power research. In its first year, the SNRC has focused on four research projects each of which address one or more of the four issues facing further nuclear power development (economics, safety, waste disposition and proliferation-resistance). This Annual Report describes technical work and accomplishments during the first year of the SNRC's existence.

T. J. Leahy

1999-07-01T23:59:59.000Z

311

Life Cycle Greenhouse Gas Emissions of Nuclear Electricity Generation: Systematic Review and Harmonization  

SciTech Connect

A systematic review and harmonization of life cycle assessment (LCA) literature of nuclear electricity generation technologies was performed to determine causes of and, where possible, reduce variability in estimates of life cycle greenhouse gas (GHG) emissions to clarify the state of knowledge and inform decision making. LCA literature indicates that life cycle GHG emissions from nuclear power are a fraction of traditional fossil sources, but the conditions and assumptions under which nuclear power are deployed can have a significant impact on the magnitude of life cycle GHG emissions relative to renewable technologies. Screening 274 references yielded 27 that reported 99 independent estimates of life cycle GHG emissions from light water reactors (LWRs). The published median, interquartile range (IQR), and range for the pool of LWR life cycle GHG emission estimates were 13, 23, and 220 grams of carbon dioxide equivalent per kilowatt-hour (g CO{sub 2}-eq/kWh), respectively. After harmonizing methods to use consistent gross system boundaries and values for several important system parameters, the same statistics were 12, 17, and 110 g CO{sub 2}-eq/kWh, respectively. Harmonization (especially of performance characteristics) clarifies the estimation of central tendency and variability. To explain the remaining variability, several additional, highly influential consequential factors were examined using other methods. These factors included the primary source energy mix, uranium ore grade, and the selected LCA method. For example, a scenario analysis of future global nuclear development examined the effects of a decreasing global uranium market-average ore grade on life cycle GHG emissions. Depending on conditions, median life cycle GHG emissions could be 9 to 110 g CO{sub 2}-eq/kWh by 2050.

Warner, E. S.; Heath, G. A.

2012-04-01T23:59:59.000Z

312

International Nuclear Energy Research Initiative 2010 Annual Report  

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

2010 I-NERI Annual Report 2010 I-NERI Annual Report  | i Foreword The U.S. Department of Energy, Office of Nuclear Energy (DOE-NE), established the International Nuclear Energy Research Initiative (I-NERI) in fiscal year (FY) 2001 to conduct advanced nuclear energy systems research in collaboration with international partners. This annual report provides an update on research and development (R&D) accomplishments which the I-NERI program achieved during FY 2010. I-NERI supports bilateral scientific and engineering collaboration in advanced reactor systems and the nuclear fuel cycle and is linked to two of DOE-NE's primary research programs: Reactor Concepts Research, Development and Demonstration and the Fuel Cycle Research and Development program. I-NERI is designed to foster international partnerships to address key issues

313

Compendium of Nuclear Reactor Containment Experiments and Reports  

Science Conference Proceedings (OSTI)

This CD-ROM contains 36 reports and papers about the structural integrity of steel-lined concrete and steel shell containments subjected to internal pressurization. Most were published in the period 1981–1990, following the Three Mile Island 2 (TMI-2) accident, but work continued during the following decade. There is a listing of the report numbers and titles. The Electric Power Research Institute (EPRI) reports are complete, but the journal articles and Nuclear Regulatory Commission (NRC) reports are li...

2011-10-11T23:59:59.000Z

314

Institutional Research & Development Reports | National Nuclear...  

National Nuclear Security Administration (NNSA)

Development Reports Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing Institutional Research...

315

Employee Concerns Reporting Form | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

subcontractor fulfilling the DOENNSA's mission have the right and responsibility to report concerns relating to the environment, safety, health, security, fraud, waste, abuse or...

316

NUCLEAR BATTERY-THERMOCOUPLE TYPE SUMMARY REPORT  

SciTech Connect

The potential usefulness of approximately 1300 radioactive isotopes as a heat source for the thermoelectric generator was investigated. Only 47 were found to have the proper characteristics of high specific activity and usable haif-life combined with an easily absorbable radiation. These isotopes are discussed showing possible sources of supply, the hazards involved, and the expected performance. Three large Po/sup 210/ heat sources were designed and constructed (for battery use), including one for the SNAP III generator. One small Tl/sup 204/ test heat source was made by irradiation. Eight thermoelectric generators were developed and two of these were used as thermoelectric batteries. Theoretical equations for non-semiconductor thermoelectric materials and experimental measurements to verify the Thompson and Peltier effects are given. (auth)

Blanke, B.C.; Birden, J.H.; Jordan, K.C.; Murphy, E.L.

1960-10-01T23:59:59.000Z

317

Nuclear Science Division, 1995--1996 annual report  

Science Conference Proceedings (OSTI)

This report describes the activities of the Nuclear Science Division (NSD) for the two-year period, January 1, 1995 to January 1, 1997. This was a time of major accomplishments for all research programs in the Division-many of which are highlighted in the reports of this document.

Poskanzer, A.M. [ed.

1997-02-01T23:59:59.000Z

318

Nuclear materials 1993 annual report. Volume 8, No. 2  

Science Conference Proceedings (OSTI)

This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC`s Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ``Nonreactors`` to ``Nuclear Materials.`` Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993.

NONE

1995-05-01T23:59:59.000Z

319

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

E-Print Network (OSTI)

Report LBL-5287. "Power Plant Reliability-Availability andConunercial Nuclear Power Plants", Report WASH-1400 (NUREG-Standards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

320

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Fossil-Fuel-Fired Steam Generators," U.S. Environmentalbasin Boiler or PWR Steam Generator Blowdown Transmissionreactor coolant pumps, steam generators, piping, main stream

Nero, A.V.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Final MTI Data Report: Pilgrim Nuclear Station  

Science Conference Proceedings (OSTI)

During the period from May 2000 to September 2001, ocean surface water temperature data was collected at the Pilgrim Nuclear Power Station near Plymouth, MA. This effort was led by the Savannah River Technology Center (SRTC) with the assistance of a local sub-contractor, Marine BioControl Corporation of Sandwich, MA. Permission for setting up the monitoring system was granted by Energy Corporation, which owns the plant site. This work was done in support of SRTC's ground truth mission for the U.S. Department of Energy's Multispectral Thermal Imager (MTI) satellite.

Parker, M.J.

2003-03-17T23:59:59.000Z

322

Next Generation CANDU Technology: Competitive Design for the Nuclear Renaissance  

SciTech Connect

AECL has developed the design for a next generation of CANDU{sup R} plants by marrying a set of enabling technologies to well-established successful CANDU features. The basis for the design is to replicate or adapt existing CANDU components for a new core design. By adopting slightly enriched uranium fuel, a core design with light water coolant, heavy water moderator and reflector has been defined, based on the existing CANDU fuel channel module. This paper summarizes the main features and characteristics of the reference next-generation CANDU design. The progress of the next generation of CANDU design program in meeting challenging cost, schedule and performance targets is described. AECL's cost reduction methodology is summarized as an integral part of the design optimization process. Examples are given of cost reduction features together with enhancement of design margins. (authors)

Hopwood, J.M.; Hedges, K.R.; Pakan, M. [Atomic Energy of Canada Ltd., Ontario (Canada)

2002-07-01T23:59:59.000Z

323

Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 1. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California  

DOE Green Energy (OSTI)

This report presents an overview of a project on the health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. In addition to presenting an executive summary of the project, it sets forth the main results of the four tasks of the project: to review the health impacts (and related standards) of these forms of power generation, to review the status of standards related to plant safety (with an emphasis on nuclear power), to consider the role of the California Energy Resources Conservation and Development Commission in selection of standards, and to set forth methodologies whereby that Commission may review the health and safety aspects of proposed sites and facilities.

Nero, A.V. Jr.

1977-01-01T23:59:59.000Z

324

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

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

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

325

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

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

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

326

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

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

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

327

International Nuclear Energy Research Initiative: Annual Report 2006 |  

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

6 6 International Nuclear Energy Research Initiative: Annual Report 2006 The International Nuclear Energy Research Initiative (I-NERI) supports the National Energy Policy by conducting research to advance the state of nuclear science and technology in the United States. I-NERI sponsors innovative scientific and engineering research and development (R&D) in cooperation with participating countries. The research performed under the I-NERI umbrella addresses key issues affecting the future of nuclear energy and its global deployment. A link to the program can be found at the NE website. This I-NERI 2006 Annual Report serves to inform interested parties about the program's organization, progress of collaborative research projects undertaken since FY 2003, and future plans for the program. Following is an

328

International Nuclear Energy Research Initiative: 2011 Annual Report |  

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

1 Annual 1 Annual Report International Nuclear Energy Research Initiative: 2011 Annual Report Fiscal year (FY) 2011 marks the ten-year anniversary of the founding of the International Nuclear Energy Research Initiative, or I-NERI. Designed to foster international partnerships that address key issues affecting the future global use of nuclear energy, I-NERI is perhaps even more relevant today than at its establishment. In the face of increasing energy demands coupled with clean energy imperatives, we must clear the hurdles to expanding the role of nuclear power in our energy portfolio. And in an increasingly global society, the importance of international cooperation in these efforts has escalated. For ten years, I-NERI has been a vehicle for establishing bilateral

329

Temporary Grounding and Bonding Practices in Nuclear Electric Generating Stations  

Science Conference Proceedings (OSTI)

Correct written temporary grounding practices inside generating stations are an important industrial safety issue, as well as an important plant status control issue. An extraordinary amount of regulations, standards, and information is available for temporary grounding practices in transmission and delivery (T&D), but very little is written about inside plant practices.

2008-12-22T23:59:59.000Z

330

Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

Ian McKirdy

2011-07-01T23:59:59.000Z

331

Solar nuclear energy generation and the chlorine solar neutrino experiment  

E-Print Network (OSTI)

The study of solar neutrinos may provide important insights into the physics of the central region of the Sun. Four solar neutrino experiments have confirmed the solar neutrino problem but do not clearly indicate whether solar physics, nuclear physics, or neutrino physics have to be improved to solve it. Nonlinear relations among the different neutrino fluxes are imposed by two coupled systems of differential equations governing the internal structure and time evolution of the Sun. We assume that the results of the four neutrino experiments are correct and are concerned not with the discrepancy between the average rate and the predicted rate, but with a possible time dependence of the argon production rate as revealed in the Homestake experiment over a time period of 20 years. Based on the subtlety of the solar neutrino problem we review here quantitatively the physical laws employed for understanding the internal solar structure and conjecture that the interlink between specific nuclear reactions of the PPIII-branch of the proton-proton chain may allow the high-energy solar neutrino flux to vary over time.

H. J. Haubold; A. M. Mathai

1994-05-18T23:59:59.000Z

332

SOLAR NUCLEAR ENERGY GENERATION AND THE CHLORINE SOLAR NEUTRINO EXPERIMENT  

E-Print Network (OSTI)

The study of solar neutrinos may provide important insights into the physics of the central region of the Sun. Four solar neutrino experiments have confirmed the solar neutrino problem but do not clearly indicate whether solar physics, nuclear physics, or neutrino physics have to be improved to solve it. Nonlinear relations among the different neutrino fluxes are imposed by two coupled systems of differential equations governing the internal structure and time evolution of the Sun. We assume that the results of the four neutrino experiments are correct and are concerned not with the discrepancy between the average rate and the predicted rate, but with a possible time dependence of the argon production rate as revealed in the Homestake experiment over a time period of 20 years. Based on the subtlety of the solar neutrino problem we review here qualitatively the physical laws employed for understanding the internal solar structure and conjecture that the interlink between specific nuclear reactions of the PPIII-branch of the proton-proton chain may allow

H. J. Haubold

1994-01-01T23:59:59.000Z

333

Nuclear waste management. Quarterly progress report, January-March, 1981  

SciTech Connect

Reports and summaries are provided for the following programs: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclide in soils; low-level waste generation reduction handbook; waste management system studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

Chikalla, T.D.; Powell, J.A. (comp.)

1981-06-01T23:59:59.000Z

334

Labor Market Trends for Nuclear Engineers Through 2005, 1999 Update Report  

SciTech Connect

This report summarizes the labor market trends for nuclear engineers predicted through the year 2005.

Larry Blair

1999-10-28T23:59:59.000Z

335

Establishing a Groundwater Protection Program for New Nuclear Generating Units: Appendix to the EPRI Groundwater Protection Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

New nuclear power plants should plan for groundwater protection early in the planning process. The construction project team should be made aware of the need to establish the groundwater protection program prior to the construction planning process. This document provides guidance for establishing Groundwater Protection Programs for new nuclear generating units. It applies to new nuclear generating units on both new and existing nuclear power plant ...

2013-03-27T23:59:59.000Z

336

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

1 runoff - co;il pile Geothermal wells Waste Disposal: WaterLiquid-Dominated Fields Geothermal Nuclear Water EmissionsOil 1. 2. 3. L 3 Gas Geothermal Nuclear Section 1.3 Noise

Nero, A.V.

2010-01-01T23:59:59.000Z

337

NUCLEAR DATA AND MEASUREMENTS REPORTS 61-80 - Nuclear Data Program...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

338

NUCLEAR DATA AND MEASUREMENTS REPORTS 81-100 - Nuclear Data Program...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

339

Procedure for Generating Data Quality Reports for SIRS Radiometric Measurements  

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

Procedure for Generating Data Quality Reports Procedure for Generating Data Quality Reports for SIRS Radiometric Measurements M. H. L. Anderberg, F. P. Rael, and T. L. Stoffell National Renewable Energy Laboratory Golden, Colorado Introduction The Atmospheric Radiation Measurement (ARM) Program needs high-quality broadband shortwave (SW) (solar) and longwave (LW) irradiance information for the development and validation of atmospheric circulation and climate models. To this end, the National Renewable Energy Laboratory (NREL) performs a quality assessment of the data from 22 Solar Infrared Stations (SIRS) in the Southern Great Plains (SGP). Data quality reports (DQRs) are instrumental in passing the resultant information to the scientific community. The value of these reports depends on clear and consistent

340

The Need for Deployment of the Next Generation Nuclear Plant Project Position Statement  

E-Print Network (OSTI)

research, development, design, construction, and operation of a prototype nuclear reactor to produce electricity and hydrogen. The NGNP is intended to be a collaborative effort among the U.S. Department of Energy, the Idaho National Laboratory, and appropriate industrial partners. It is also intended to include international technology exchanges. The NGNP will utilize what is commonly referred to as a Generation IV design. Generation III designs are the latest reactor designs licensed or certified by the U.S. Nuclear Regulatory Commission (NRC). Generation III+ includes the new designs currently under review by the NRC and anticipated to begin operation during the next 10 to 20 years. Generation IV designs are more advanced and are expected to be ready for commercial construction after 2020. The Generation IV designs may include new or additional features such as the following: • capability for hydrogen production 2 • use of recycled fuel • use of plutonium and other fission by-products • a more efficient fuel cycle with lower generation of waste products • higher safety and physical protection levels • higher reliability • better economic performance. The ANS also supports the federal government efforts in support of a robust Generation IV development program in parallel with current Generation III+ efforts. 3 Sequential utilization of new or different designs and technologies will ensure ever-increasing safety levels and will help nuclear energy fulfill its vital role in worldwide electricity generation.

unknown authors

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Advanced nuclear reactor public opinion project. Interim report  

SciTech Connect

This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

Benson, B.

1991-07-25T23:59:59.000Z

342

Guidance for identifying, reporting and tracking nuclear safety noncompliances  

SciTech Connect

This document provides Department of Energy (DOE) contractors, subcontractors and suppliers with guidance in the effective use of DOE`s Price-Anderson nuclear safety Noncompliance Tracking System (NTS). Prompt contractor identification, reporting to DOE, and correction of nuclear safety noncompliances provides DOE with a basis to exercise enforcement discretion to mitigate civil penalties, and suspend the issuance of Notices of Violation for certain violations. Use of this reporting methodology is elective by contractors; however, this methodology is intended to reflect DOE`s philosophy on effective identification and reporting of nuclear safety noncompliances. To the extent that these expectations are met for particular noncompliances, DOE intends to appropriately exercise its enforcement discretion in considering whether, and to what extent, to undertake enforcement action.

NONE

1995-12-01T23:59:59.000Z

343

Milliwatt Generator Project. Progress report, April-September 1980  

DOE Green Energy (OSTI)

This formal biannual report covers the effort related to the Milliwatt Generator Project (MWG) carried out for the Department of Energy, Office of Military Applications, by the Los Alamos Scientific Laboratory (LASL). Most of the studies discussed here are of a continuing nature. Results and conclusions may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

Maraman, W.J. (comp.)

1981-01-01T23:59:59.000Z

344

Milliwatt Generator Project. Progress report, October 1980-March 1981  

DOE Green Energy (OSTI)

This formal biannual report covers the effort related to the Milliwatt Generator Project (MWG) carried out for the Department of Energy, Office of Military Application by the Los Alamos National Laboratory. Most of the studies discussed here are of a continuing nature. Results and conclusions may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

Maraman, W.J. (comp.)

1981-06-01T23:59:59.000Z

345

Short-term hydroelectric generation model. Model documentation report  

DOE Green Energy (OSTI)

The purpose of this report is to define the objectives of the Energy Information Administration`s (EIA) Short-Term Hydroelectric Generation Model (STHGM), describe its basic approach, and to provide details on the model structure. This report is intended as a reference document for model analysts, users, and the general public. Documentation of the model is in accordance with the EIA`s legal obligation to provide adequate documentation in support of its models.

NONE

1996-12-01T23:59:59.000Z

346

Present and future nuclear power generation as a reflection of individual countries' resources and objectives  

SciTech Connect

The nuclear reactor industry has been in a state of decline for more than a decade in most of the world. The reasons are numerous and often unique to the energy situation of individual countries. Two commonly cited issues influence decisions relating to construction of reactors: costs and the need, or lack thereof, for additional generating capacity. Public concern has ''politicized'' the nuclear industry in many non-communist countries, causing a profound effect on the economics of the option. The nuclear installations and future plans are reviewed on a country-by-country basis for 36 countries in the light of the resources and objectives of each. Because oil and gas for power production throughout the world are being phased out as much as possible, coal-fired generation currently tends to be the chosen alternative to nuclear power production. Exceptions occur in many of the less developed countries that collectively have a very limited operating experience with nuclear reactors. The Chernobyl accident in the USSR alarmed the public; however, national strategies and plans to build reactors have not changed markedly in the interim. Assuming that the next decade of nuclear power generation is uneventful, additional electrical demand would cause the nuclear power industry to experience a rejuvenation in Europe as well as in the US. 80 refs., 3 figs., 22 tabs.

Borg, I.Y.

1987-06-26T23:59:59.000Z

347

Framing Scenarios of Electricity Generation and Gas Use: EPRI Report Series on Gas Demands for Power Generation  

Science Conference Proceedings (OSTI)

This report provides a systematic appraisal of trends in electric generation and demands for gas for power generation. Gas-fired generation is the leading driver of forecasted growth in demand for natural gas in the United States, and natural gas is a leading fuel for planned new generating capacity. The report goes behind the numbers and forecasts to quantify key drivers and uncertainties.

1996-08-28T23:59:59.000Z

348

Aerospace nuclear safety report for August 1967  

SciTech Connect

The AEC Safety Branch advised that the present outlook for a potential mission using four modified SNAP-3 type generators is rather negative. Drop tests of four SNAP-19 intact reentry heat source capsules were conducted at the Tonopah Test Range. A preliminary GE SNAP-27 safety analysis was reviewed. Three arc tunnel tests were conducted at low heat fluxes. Debris were collected on downrange impactors from all tests. The rapid helium depressurization test on fuel microspheres was conducted by Battelle; preliminary examination of the fuel revealed no obvious change in microsphere characteristics.

Illing, R.G. (comp.)

1967-09-01T23:59:59.000Z

349

Annual report of waste generation and pollution prevention progress 1998  

SciTech Connect

This seventh Annual Report presents and analyzes DOE Complex-wide waste generation and pollution prevention activities at 45 reporting sites from 1993 through 1998. This section summarizes Calendar Year 1998 Complex-wide waste generation and pollution prevention accomplishments. More detailed information follows this section in the body of the Report. In May 1996, the Secretary of Energy established a 50 percent Complex-Wide Waste Reduction Goal (relative to the 1993 baseline) for routine operations radioactive, mixed, and hazardous waste generation, to be achieved by December31, 1999. DOE has achieved its Complex-Wide Waste Reduction Goals for routine operations based upon a comparison of 1998 waste generation to the 1993 baseline. Excluding sanitary waste, routine operations waste generation decreased 67 percent overall from 1993 to 1998. However, for the first time since 1994, the total amount of materials recycled by the Complex decreased from 109,600 metric tons in 1997 to 92,800 metric tons in 1998. This decrease is attributed to the fact that in 1997, several large ''one-time only'' recycling projects were conducted throughout the Complex. In order to demonstrate commitment to DOE's Complex-wide recycling goal, it is important for sites to identify all potential large-scale recycling/reuse opportunities.

NONE

1999-09-01T23:59:59.000Z

350

Form EIA-860 Annual Electric Generator Report | OpenEI  

Open Energy Info (EERE)

761 761 Varnish cache server Browse Upload data GDR 429 Throttled (bot load) Error 429 Throttled (bot load) Throttled (bot load) Guru Meditation: XID: 2142263761 Varnish cache server Form EIA-860 Annual Electric Generator Report Dataset Summary Description The Form EIA-860 is a generator-level survey that collects specific information about existing and planned generators and associated environmental equipment at electric power plants with 1 megawatt or greater of combined nameplate capacity. The survey data is summarized in reports such as the Electric Power Annual. The survey data is also available for download here. The data are compressed into a self-extracting (.exe) zip folder containing .XLS data files and record layouts. The current file structure (starting with 2009 data) consists

351

Impact of Nuclear Power Plant Operations on Carbon-14 Generation, Chemical Forms, and Release  

Science Conference Proceedings (OSTI)

As nuclear power plants continue to implement best practices to reduce the total radioactivity in plant effluents, other radionuclides that were not previously significant fractions of the effluent streams will need to be quantified and reported. Carbon-14 can become a principal radionuclide for the gaseous effluent pathway as the concentrations of other radionuclides decrease. This report documents the potential opportunities for further understanding the impact of nuclear power plant operations on Carb...

2011-12-08T23:59:59.000Z

352

Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings  

DOE Green Energy (OSTI)

Two of the major challenges the U.S. energy sector faces are greenhouse gas emissions and oil that is both imported and potentially reaching a peak (the point at which maximum extraction is reached). Interest in development of both renewable and nuclear energy has been strong because both have potential for overcoming these challenges. Research in both energy sources is ongoing, but relatively little research has focused on the potential benefits of combining nuclear and renewable energy. In September 2011, the Joint Institute for Strategic Energy Analysis (JISEA) convened the Nuclear and Renewable Energy Synergies Workshop at the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to identify potential synergies and strategic leveraging opportunities between nuclear energy and renewable energy. Industry, government, and academic thought leaders gathered to identify potential broad categories of synergies and brainstorm topic areas for additional analysis and research and development (R&D). This report records the proceedings and outcomes of the workshop.

Ruth, M.; Antkowiak, M.; Gossett, S.

2011-12-01T23:59:59.000Z

353

Nuclear materials research progress reports for 1977  

DOE Green Energy (OSTI)

Research is reported concerning radiation enhancement of stress corrosion cracking of Zircaloy, surface chemistry of epitaxial Si deposited by thermal cracking of silane, thermal gradient migration of metallic inclusions in UO/sub 2/, molecular beam studies of atomic H and reduction of oxides, mass transfer and reduction of UO/sub 2/, kinetics of laser pulse vaporization of UO/sub 2/, retention and release of water by UO/sub 2/ pellets, and solubility of H in UO/sub 2/. (FS)

Olander, D.R.

1977-12-01T23:59:59.000Z

354

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux  

DOE Patents (OSTI)

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

Bowman, Charles D. (Los Alamos, NM)

1992-01-01T23:59:59.000Z

355

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux  

DOE Patents (OSTI)

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

Bowman, C.D.

1992-11-03T23:59:59.000Z

356

ECONOMIC FACTORS OF MFP THERMOELECTRIC GENERATORS. Interim Report  

SciTech Connect

Mixed Fission Products (MFP) for use as a heat source for thermoelectric generators will become increasingly available in the coming years. The Atomic Energy Conamission sponsored program on solidification of nuclear wastes is now entering the hot-bench scale test phase. During this phase approximately 5000 thermal watts of two year old MFP could be produced monthly. Two different types of hot calcination pilot plants are planned for installation at the Hanford National Laboratories in the 1964 to 1966 time period. Each of these plants should be able to produce 160,000 thermal watts of two year MFP and 16,000 thermal watts of ten year MFP on a monthly basis. During this phase, MFP costs should be less than 15 per ihermal watt for two year MFP and 50 for ten year MFP. This cost includes operation of the plant solely to obtain heat sources and sealing the MFP into fuel containers. A full scale plant for a 15,000 Mw(e) nuclear economy is estimated to produce four to five times as much MFP as either of the pilot plants. Costs will be dependent upon AEC policy in effect at the time the plant is operating. lf the policy indicates that the full cost be paid by the user, the prices will approximate that obtained from the pilot plant operation. A conceptual design has been made for MFP fueled generators at several output power levels up to 1000 watts. These are for use at great underwater depths and contain an integral biological shield. A low cost biological shield of high density concrete or cast iron is considered. Economic studies indicate that, in production quantities, a 10 watt generator will cost one tenth an equivalent Strontium90 generator. Because of the low cost for MFP heat sources, radionuclide generators at the hundred and thousand watt level can be reasonably postulated for the first time. At the kilowatt level costs of per watt year are achievable while to 0 are estimated at the ten watt level. Currently available ocean-going craft can handle the placement of MFP generators up to the hundreds of watts level. Investigation of other available vessels is continuing. (auth)

Barmat, M.

1962-06-01T23:59:59.000Z

357

Research in theoretical nuclear physics. Progress report, November 1, 1989--September 1992  

SciTech Connect

This report discusses topics in the following areas: Low energy nuclear reactions induced by light and heavy ions; medium energy physics; and nuclear structure. (LSP)

Udagawa, T.

1992-09-01T23:59:59.000Z

358

Nuclear Theory and Applications progress report, January 1, 1989-- April 1, 1990  

Science Conference Proceedings (OSTI)

This report contains brief papers on the following topics: data evaluation and libraries; data processing; nuclear applications; reactions; fission; and nuclear structure.

Strottman, D.D.; Mutschlecner, A.D. (comps.)

1990-12-01T23:59:59.000Z

359

Annual report of waste generation and pollution prevention progress, 1994  

SciTech Connect

This Report summarizes the waste generation and pollution prevention activities of the major operational sites in the Department of Energy (DOE). We are witnessing progress in waste reduction from routine operations that are the focus of Department-wide reduction goals set by the Secretary on May 3,1996. The goals require that by the end of 1999, we reduce, recycle, reuse, and otherwise avoid waste generation to achieve a 50 percent reduction over 1993 levels. This Report provides the first measure of our progress in waste reduction and recycling against our 1993 waste generation baseline. While we see progress in reducing waste from our normal operations, we must begin to focus attention on waste generated by cleanup and facilities stabilization activities that are the major functions of the Office of Environmental Management. Reducing the generation of waste is one of the seven principles that I have established for the Office of Environmental Management Ten Year Plan. As part of our vision to complete a major portion of the environmental cleanup at DOE sites over the next ten years, we must utilize the potential of the pollution prevention program to reduce the cost of our cleanup program. We have included the Secretarial goals as part of the performance measures for the Ten Year Plan, and we are committed to implementing pollution prevention ideas. Through the efforts of both Federal and contractor employees, our pollution prevention program has reduced waste and the cost of our operations. I applaud their efforts and look forward to reporting further waste reduction progress in the next annual update of this Report.

NONE

1996-09-01T23:59:59.000Z

360

Nuclear Maintenance Applications Center: Post-Trip Voltage Prediction at Nuclear and Other Generating Stations  

Science Conference Proceedings (OSTI)

The objective of this Electric Power Research Institute (EPRI) project is to investigate the possibility of predicting the switchyard voltage in a nuclear power plant (NPP) following a trip of a nuclear unit. Two methods of post-trip voltage prediction are investigated. The first method, called the V-Q method, uses minimal local plant information (such as unit operating conditionsactive and reactive power output and pre-trip voltage) to predict post-trip voltage based on the sensitivity of voltage to the...

2009-06-30T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Spent nuclear fuel Canister Storage Building CDR Review Committee report  

SciTech Connect

The Canister Storage Building (CSB) is a subproject under the Spent Nuclear Fuels Major System Acquisition. This subproject is necessary to design and construct a facility capable of providing dry storage of repackaged spent fuels received from K Basins. The CSB project completed a Conceptual Design Report (CDR) implementing current project requirements. A Design Review Committee was established to review the CDR. This document is the final report summarizing that review

Dana, W.P.

1995-12-01T23:59:59.000Z

362

Space nuclear safety program: Progress report, July--September 1987  

SciTech Connect

This quarterly report describes studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems, carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. The studies discussed are ongoing; the results and conclusions described may change as the work progresses. 20 figs., 4 tabs.

George, T.G. (comp.)

1989-02-01T23:59:59.000Z

363

Delays in nuclear power plant construction. Volume II. Final report  

SciTech Connect

The report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts which should minimize or eliminate the identified barriers. The identified barriers include (1) Design and Construction Interfacing Problems; (2) Problems Relating to the Selection and Use of Permanent Materials and Construction Methods; (3) Construction Coordination and Communication Problems; and (4) Problems Associated with Manpower Availability and Productivity.

Mason, G.E.; Larew, R.E.; Borcherding, J.D.; Okes, S.R. Jr.; Rad, P.F.

1977-12-14T23:59:59.000Z

364

BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Final Summary Design Report  

SciTech Connect

The design and construction of the Boiling Nuclear Superheater (BONUS) Power Station at Punta Higuera on the seacoast at the westernmost tip of Puerto Rico are described. The reactor has an output of 17.5 Mw(e). This report will serve as a source of information for personnel engaged in management, evaluation, and training. (N.W.R.)

1962-05-01T23:59:59.000Z

365

Space Nuclear Space Program. Progress report, December 1983  

DOE Green Energy (OSTI)

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Results from safety-verification tests including impact tests are presented.

Bronisz, S.E. (comp.)

1984-06-01T23:59:59.000Z

366

Risk perception & strategic decision making :general insights, a framework, and specific application to electricity generation using nuclear energy.  

SciTech Connect

The objective of this report is to promote increased understanding of decision making processes and hopefully to enable improved decision making regarding high-consequence, highly sophisticated technological systems. This report brings together insights regarding risk perception and decision making across domains ranging from nuclear power technology safety, cognitive psychology, economics, science education, public policy, and neural science (to name a few). It forms them into a unique, coherent, concise framework, and list of strategies to aid in decision making. It is suggested that all decision makers, whether ordinary citizens, academics, or political leaders, ought to cultivate their abilities to separate the wheat from the chaff in these types of decision making instances. The wheat includes proper data sources and helpful human decision making heuristics; these should be sought. The chaff includes ''unhelpful biases'' that hinder proper interpretation of available data and lead people unwittingly toward inappropriate decision making ''strategies''; obviously, these should be avoided. It is further proposed that successfully accomplishing the wheat vs. chaff separation is very difficult, yet tenable. This report hopes to expose and facilitate navigation away from decision-making traps which often ensnare the unwary. Furthermore, it is emphasized that one's personal decision making biases can be examined, and tools can be provided allowing better means to generate, evaluate, and select among decision options. Many examples in this report are tailored to the energy domain (esp. nuclear power for electricity generation). The decision making framework and approach presented here are applicable to any high-consequence, highly sophisticated technological system.

Brewer, Jeffrey D.

2005-11-01T23:59:59.000Z

367

Summary for the Next Generation Nuclear Plant Project in Review  

Science Conference Proceedings (OSTI)

This paper reports on the major progress that the NGNP Project has made toward developing and commercializing the HTGR technology. Significant R&D progress has been made in addressing key technical issues for qualification of the HTGR fuel and graphite, codification of high temperature materials and verification and validation of design codes. Work is also progressing in heat transfer/transport design and testing and in development of the high temperature steam electrolysis hydrogen production process. A viable licensing strategy has been formulated in coordination with the NRC and DOE. White papers covering key licensing issues have been and will continue to be submitted and necessary discussions of these key issues have begun with the NRC. Continued government support is needed to complete the Project objectives as established in the 2005 Energy Policy Act.

L.E. Demick

2010-09-01T23:59:59.000Z

368

Nuclear electric generation: Political, social, and economic cost and benefit to Indonesia. Master`s thesis  

SciTech Connect

Indonesia, the largest archipelagic country with a population the fourth biggest in the world, is now in the process of development. It needs a large quantity of energy electricity to meet the industrial and household demands. The currently available generating capacity is not sufficient to meet the electricity demand for the rapidly growing industries and the increasing population. In order to meet the future demand for electricity, new generating capacity is required to be added to the current capacity. Nuclear electricity generation is one possible alternative to supplement Indonesia`s future demand of electricity. This thesis investigates the possibility of developing nuclear electricity generation in Indonesia, considering the political, social, and economic cost and benefit to Indonesia.

Waliyo

1994-12-01T23:59:59.000Z

369

Nuclear Physics Science Network Requirements Workshop, May 2008 - Final Report  

E-Print Network (OSTI)

Requirements Workshop Nuclear Physics Program Office, DOEDOE Nuclear Physics Programs .. 6 Nuclear Physics Network Requirementsbandwidth and services requirements. 3 DOE Nuclear Physics

Tierney, Ed., Brian L

2008-01-01T23:59:59.000Z

370

Replacement energy costs for nuclear electricity-generating units in the United States: 1997--2001. Volume 4  

Science Conference Proceedings (OSTI)

This report updates previous estimates of replacement energy costs for potential short-term shutdowns of 109 US nuclear electricity-generating units. This information was developed to assist the US Nuclear Regulatory Commission (NRC) in its regulatory impact analyses, specifically those that examine the impacts of proposed regulations requiring retrofitting of or safety modifications to nuclear reactors. Such actions might necessitate shutdowns of nuclear power plants while these changes are being implemented. The change in energy cost represents one factor that the NRC must consider when deciding to require a particular modification. Cost estimates were derived from probabilistic production cost simulations of pooled utility system operations. Factors affecting replacement energy costs, such as random unit failures, maintenance and refueling requirements, and load variations, are treated in the analysis. This report describes an abbreviated analytical approach as it was adopted to update the cost estimates published in NUREG/CR-4012, Vol. 3. The updates were made to extend the time frame of cost estimates and to account for recent changes in utility system conditions, such as change in fuel prices, construction and retirement schedules, and system demand projects.

VanKuiken, J.C.; Guziel, K.A.; Tompkins, M.M.; Buehring, W.A. [Argonne National Lab., IL (United States)

1997-09-01T23:59:59.000Z

371

Report on aging of nuclear power plant reinforced concrete structures  

Science Conference Proceedings (OSTI)

The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs.

Naus, D.J.; Oland, C.B. [Oak Ridge National Lab., TN (United States); Ellingwood, B.R. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

1996-03-01T23:59:59.000Z

372

Main Generator and Exciter Life Cycle Management Plans at STARS Nuclear Plants  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This CD is a compilation of six optimum LCM plans for the main generators and exciters at the six STARS plants and also contains a generic LCM information "sourcebook" for generators.

2003-09-30T23:59:59.000Z

373

Model documentation report: Short-Term Hydroelectric Generation Model  

DOE Green Energy (OSTI)

The purpose of this report is to define the objectives of the Short- Term Hydroelectric Generation Model (STHGM), describe its basic approach, and to provide details on the model structure. This report is intended as a reference document for model analysts, users, and the general public. Documentation of the model is in accordance with the Energy Information Administration`s (AYE) legal obligation to provide adequate documentation in support of its models (Public Law 94-385, Section 57.b.2). The STHGM performs a short-term (18 to 27- month) forecast of hydroelectric generation in the United States using an autoregressive integrated moving average (UREMIA) time series model with precipitation as an explanatory variable. The model results are used as input for the short-term Energy Outlook.

Not Available

1993-08-01T23:59:59.000Z

374

Milliwatt Generator Project: April 1988--September 1996. Progress report  

DOE Green Energy (OSTI)

This report covers progress on the Milliwatt Generator (MWG) Project from April 1988 to September 1996. Manufacturing of heat sources for the project ended by September 1990. Beginning in October 1990, the major activities of the project have been surveillance and testing of MWGs, disposal of excess MWGs, and reclamation of the PuO{sub 2} from excess MWG heat sources. Reported activities include fuel processing and characterization, production of heat sources, compatibility studies, impact testing, examination and electrical testing of surveillance units, and recovery of PuO{sub 2} from heat sources.

Latimer, T.W.

1997-07-01T23:59:59.000Z

375

Low cost high performance generator technology program. Addendum report  

DOE Green Energy (OSTI)

The results of a system weight, efficiency, and size analysis which was performed on the 500 W(e) low cost high performance generator (LCHPG) are presented. The analysis was performed in an attempt to improve system efficiency and specific power over those presented in June 1975, System Design Study Report TES-SNSO-3-25. Heat source volume, configuration, and safety as related to the 500 W(e) LCHPG are also discussed. (RCK)

Not Available

1975-09-01T23:59:59.000Z

376

Microsoft Word - Nuclear Safety Reporting Criteria.docx  

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

Safety Noncompliance Reporting Criteria (as of January 1, 2012) Safety Noncompliance Reporting Criteria (as of January 1, 2012) Nuclear Safety Noncompliances Associated With Occurrences (DOE Order 232.2) Consult the DOE Order for the full text of each occurrence criterion 1 Reporting Criteria Group Subgroup Occurrence Category and Summary Description 2 1. Operational Emergencies 3 N/A (1) Operational Emergency (2) Alert (3) Site Area Emergency (4) General Emergency 2. Personnel Safety and Health C. Fires (1) Fire within primary confinement/containment (2d) Self-extinguishing fires D. Explosions (1) Unplanned explosion within primary confinement/containment 3. Nuclear Safety Basis A. Technical Safety Requirement (TSR) Violations (1) Violation of TSR/Operational Safety Requirement (OSR) Safety Limit (2) Violation of other TSR/OSR requirement

377

Isotope and Nuclear Chemistry Division annual report, FY 1983  

Science Conference Proceedings (OSTI)

This report describes progress in the major research and development programs carried out in FY 1983 by the Isotope and Nuclear Chemistry Division. It covers radiochemical diagnostics of weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production, separation, and applications (including biomedical applications); element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced analytical techniques; development and applications; atmospheric chemistry and transport; and earth and planetary processes.

Heiken, J.H.; Lindberg, H.A. (eds.)

1984-05-01T23:59:59.000Z

378

Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper  

SciTech Connect

This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

Pete Jordan

2010-09-01T23:59:59.000Z

379

Spent Nuclear Fuel project photon heat deposition calculation for hygrogen generation within MCO  

DOE Green Energy (OSTI)

Three types of water conditions are analyzed for nuclear heat deposition in a MCO: fully flooded, thick film, and thin film. These heat deposition rates within water can be used to determine gas generation during the different phases of Spent Fuel removal and processing for storage.

Lan, J.S.

1996-08-01T23:59:59.000Z

380

Generation IV Nuclear Energy Systems Ten-Year Program Plan Fiscal Year 2005, Volume 1  

SciTech Connect

As reflected in the U.S. ''National Energy Policy'', nuclear energy has a strong role to play in satisfying our nation's future energy security and environmental quality needs. The desirable environmental, economic, and sustainability attributes of nuclear energy give it a cornerstone position, not only in the U.S. energy portfolio, but also in the world's future energy portfolio. Accordingly, on September 20, 2002, U.S. Energy Secretary Spencer Abraham announced that, ''The United States and nine other countries have agreed to develop six Generation IV nuclear energy concepts''. The Secretary also noted that the systems are expected to ''represent significant advances in economics, safety, reliability, proliferation resistance, and waste minimization''. The six systems and their broad, worldwide research and development (R&D) needs are described in ''A Technology Roadmap for Generation IV Nuclear Energy Systems'' (hereafter referred to as the Generation IV Roadmap). The first 10 years of required U.S. R&D contributions to achieve the goals described in the Generation IV Roadmap are outlined in this Program Plan.

None

2005-03-01T23:59:59.000Z

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


381

Audit Report on "The Department's Management of Nuclear Materials Provided to Domestic Licensees"  

Science Conference Proceedings (OSTI)

The objective if to determine whether the Department of Energy (Department) was adequately managing its nuclear materials provided to domestic licensees. The audit was performed from February 2007 to September 2008 at Department Headquarters in Washington, DC, and Germantown, MD; the Oak Ridge Office and the Oak Ridge National Laboratory in Oak Ridge, TN. In addition, we visited or obtained data from 40 different non-Departmental facilities in various states. To accomplish the audit objective, we: (1) Reviewed Departmental and Nuclear Regulatory Commission (NRC) requirements for the control and accountability of nuclear materials; (2) Analyzed a Nuclear Materials Management and Safeguards System (NMMSS) report with ending inventory balances for Department-owned nuclear materials dated September 30, 2007, to determine the amount and types of nuclear materials located at non-Department domestic facilities; (3) Held discussions with Department and NRC personnel that used NMMSS information to determine their roles and responsibilities related to the control and accountability over nuclear materials; (4) Selected a judgmental sample of 40 non-Department domestic facilities; (5) Met with licensee officials and sent confirmations to determine whether their actual inventories of Department-owned nuclear materials were consistent with inventories reported in the NMMSS; and, (6) Analyzed historical information related to the 2004 NMMSS inventory rebaselining initiative to determine the quantity of Department-owned nuclear materials that were written off from the domestic licensees inventory balances. This performance audit was conducted in accordance with generally accepted Government auditing standards. Those standards require that we plan and perform the audit to obtain sufficient, appropriate evidence to provide a reasonable basis for our findings and conclusions based on our audit objective. We believe that the evidence obtained provides a reasonable basis for our findings and conclusions based on our audit objectives. The audit included tests of controls and compliance with laws and regulations related to managing the Department-owned nuclear materials provided to non-Departmental domestic licensees. Because our review was limited it would not necessarily have disclosed all internal control deficiencies that may have existed at the time of our audit. We examined the establishment of performance measures in accordance with Government Performance and Results Act of 1993, as they related to the audit objective. We found that the Department had established performance measures related to removing or disposing of nuclear materials and radiological sources around the world. We utilized computer generated data during our audit and performed procedures to validate the reliability of the information as necessary to satisfy our audit objective. As noted in the report, we questioned the reliability of the NMMSS data.

None

2009-02-01T23:59:59.000Z

382

Nuclear science. Annual report, July 1, 1979-June 30, 1980  

SciTech Connect

This annual report describes the scientific research carried out within the Nuclear Science Division (NSD) during the period between July 1, 1979 and June 30, 1980. The principal objective of the division continues to be the experimental and theoretical investigation of the interactions of heavy ions with target nuclei, complemented with programs in light ion nuclear science, in nuclear data compilations, and in advanced instrumentation development. The division continues to operate the 88 Inch Cyclotron as a major research facility that also supports a strong outside user program. Both the SuperHILAC and Bevalac accelerators, operated as national facilities by LBL's Accelerator and Fusion Research Division, are also important to NSD experimentalists. (WHK)

Myers, W.D.; Friedlander, E.M.; Nitschke, J.M.; Stokstad, R.G. (eds.)

1981-03-01T23:59:59.000Z

383

Evaluation of Next Generation Nuclear Power Plant (NGNP) Intermediate Heat Exchanger (IHX) Operating Conditions  

DOE Green Energy (OSTI)

This report summarizes results of a preliminary evaluation to determine the operating conditions for the Next Generation Nuclear Plant (NGNP) Intermediate Heat Exchanger (IHX) that will transfer heat from the reactor primary system to the demonstration hydrogen production plant(s). The Department of Energy is currently investigating two primary options for the production of hydrogen using a high temperature reactor as the power source. These options are the High Temperature Electrolysis (HTE) and Sulfur-Iodine (SI) thermochemical hydrogen production processes. However, since the SI process relies entirely on process heat from the reactor, while the HTE process relies primarily on electrical energy with only a small amount of process heat required, the design of the IHX is dictated by the SI process heat requirements. Therefore, the IHX operating conditions were defined assuming 50 MWt is available for the production of hydrogen using the SI process. Three configurations for the intermediate loop were evaluated, including configurations for both direct and indirect power conversion systems. The HYSYS process analysis software was used to perform sensitivity studies to determine the influence of reactor outlet temperatures, intermediate loop working fluids (helium and molten salt), intermediate loop pressures, and intermediate loop piping lengths on NGNP performance and IHX operating conditions. The evaluation of NGNP performance included assessments of overall electric power conversion efficiency and estimated hydrogen production efficiency. Based on these evaluations, recommended IHX operating conditions are defined.

E. A. Harvego

2006-04-01T23:59:59.000Z

384

Nuclear waste treatment program: Annual report for FY 1987  

SciTech Connect

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs.

Brouns, R.A.; Powell, J.A. (comps.)

1988-09-01T23:59:59.000Z

385

Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.  

DOE Green Energy (OSTI)

In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for both the PBMR and prismatic design. The main focus of this report is the RPV for both design concepts with emphasis on material selection.

Natesan, K.; Majumdar, S.; Shankar, P. S.; Shah, V. N.; Nuclear Engineering Division

2007-03-21T23:59:59.000Z

386

Magnetic Field Generation in Planets and Satellites by Natural Nuclear Fission Reactors  

E-Print Network (OSTI)

One of the most fundamental problems in physics has been to understand the nature of the mechanism that generates the geomagnetic field and the magnetic fields of other planets and satellites. For decades, the dynamo mechanism, thought to be responsible for generating the geomagnetic field and other planetary magnetic fields, has been ascribed to convection in each planet's iron-alloy core. Recently, I described the problems inherent in Earth-core convection and proposed instead that the geomagnetic field is produced by a dynamo mechanism involving convection, not in the fluid core, but in the electrically conductive, fluid, fission-product sub-shell of a natural nuclear fission reactor at the center of the Earth, called the georeactor. Here I set forth in detail the commonality in the Solar System of the matter like that of the inside of the Earth, which is my basis for generalizing the concept of planetary magnetic field generation by natural planetocentric nuclear fission reactors.

J. Marvin Herndon

2007-07-27T23:59:59.000Z

387

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

SciTech Connect

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube`s inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

Palmrose, D.E.; Herring, J.S.

1993-05-01T23:59:59.000Z

388

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

Science Conference Proceedings (OSTI)

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube's inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

Palmrose, D.E.; Herring, J.S.

1993-01-01T23:59:59.000Z

389

Energy Storage and Distributed Energy Generation Project, Final Project Report  

Science Conference Proceedings (OSTI)

This report serves as a Final Report under the “Energy Storage and Distribution Energy Generation Project” carried out by the Transportation Energy Center (TEC) at the University of Michigan (UM). An interdisciplinary research team has been working on fundamental and applied research on: -distributed power generation and microgrids, -power electronics, and -advanced energy storage. The long-term objective of the project was to provide a framework for identifying fundamental research solutions to technology challenges of transmission and distribution, with special emphasis on distributed power generation, energy storage, control methodologies, and power electronics for microgrids, and to develop enabling technologies for novel energy storage and harvesting concepts that can be simulated, tested, and scaled up to provide relief for both underserved and overstressed portions of the Nation’s grid. TEC’s research is closely associated with Sections 5.0 and 6.0 of the DOE "Five-year Program Plan for FY2008 to FY2012 for Electric Transmission and Distribution Programs, August 2006.”

Schwank, Johannes; Mader, Jerry; Chen, Xiaoyin; Mi, Chris; Linic, Suljo; Sastry, Ann Marie; Stefanopoulou, Anna; Thompson, Levi; Varde, Keshav

2008-03-31T23:59:59.000Z

390

Characterization of nuclear reactor containment penetrations. Final report  

SciTech Connect

This report concludes a preliminary report prepared by ANL for Sandia, published as NUREG/CR-3855, in June 1984. The preliminary report, NUREG/CR-3855, presented the results of a survey of nuclear reactor containment penetrations, covering the number of plants surveyed at that time (22 total). Since that time, an additional 26 plants have been included in the survey. This final report serves two purposes: (1) to add the summary data sheets and penetration details for the additional plants now included in the survey; and (2) to confirm, revise, or add to analyses and discussions presented in the first report which, of course, were based solely on the earlier sample of 22 plants. This final report follows the outline and format of the preliminary survey report. In general, changes and additions to the preliminary report are implied, rather than stated as such to avoid repeated reference to that report. If no changes have been made in a section the title of the section of the previous report is simply repeated followed by ''No Changes''. Some repetition is used for continuity and clarity.

Shackelford, M.H.; Bump, T.R.; Seidensticker, R.W.

1985-02-01T23:59:59.000Z

391

Nuclear waste management. Quarterly progress report, October-December 1979  

SciTech Connect

Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-04-01T23:59:59.000Z

392

1 hour, 59 minutes ago President Jacques Chirac announced plans to build a prototype fourth-generation nuclear reactor by 2020 as well as symbolic targets  

E-Print Network (OSTI)

-generation nuclear reactor by 2020 as well as symbolic targets for cutting France's reliance on oil in the coming and is conducting research into several new models of nuclear reactor. Business leaders in the French energy sector-generation nuclear reactor 1/5/06 3:19 PMPrint Story: France to develop fourth-generation nuclear reactor on Yahoo

393

Characterization of nuclear reactor containment penetrations. Preliminary report  

Science Conference Proceedings (OSTI)

This report summarizes the survey work conducted by Argonne National Laboratory on the design and details of major penetrations in 22 nuclear power plants. The survey includes all containment types and materials in current use. It also includes details of all types of penetrations (except for electrical penetration assemblies and valves) and the seals and gaskets used in them. The report provides a test matrix for testing major penetrations and for testing seals and gaskets in order to evaluate their leakage potential under severe accident conditions.

Bump, T.R.; Seidensticker, R.W.; Shackelford, M.A.; Gambhir, V.K.; McLennan, G.L.

1984-06-01T23:59:59.000Z

394

RESTRUCTURING RELAP5-3D FOR NEXT GENERATION NUCLEAR PLANT ANALYSIS  

Science Conference Proceedings (OSTI)

RELAP5-3D is used worldwide for analyzing nuclear reactors under both operational transients and postulated accident conditions. Development of the RELAP code series began in 1975 and since that time the code has been continuously improved, enhanced, verified and validated [1]. Since RELAP5-3D will continue to be the premier thermal hydraulics tool well into the future, it is necessary to modernize the code to accommodate the incorporation of additional capabilities to support the development of the next generation of nuclear reactors [2]. This paper discusses the reengineering of RELAP5-3D into structured code.

Donna Post Guillen; George L. Mesina; Joshua M. Hykes

2006-06-01T23:59:59.000Z

395

Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Second technical progress report  

Science Conference Proceedings (OSTI)

OAK-B135 Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Second technical progress report

Ulm, Franz-Josef

1999-12-31T23:59:59.000Z

396

Worldwide assessment of steam-generator problems in pressurized-water-reactor nuclear power plants  

Science Conference Proceedings (OSTI)

Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of PWR plant operations, plant types, and materials used in PWR plants. A review of the worldwide distribution of PWR plants is also given. The report describes in detail the degradation problems discovered in PWR steam generators: their causes, their impacts on the performance of steam generators, and the actions to mitigate and avoid them. One chapter is devoted to operating experience of PWR steam generators in foreign countries. Another discusses the improvements in future steam generator design.

Woo, H.H.; Lu, S.C.

1981-09-15T23:59:59.000Z

397

A Systems Engineering Framework for Design, Construction and Operation of the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

Not since the International Space Station has a project of such wide participation been proposed for the United States. Ten countries, the European Union, universities, Department of Energy (DOE) laboratories, and industry will participate in the research and development, design, construction and/or operation of the fourth generation of nuclear power plants with a demonstration reactor to be built at a DOE site and operational by the middle of the next decade. This reactor will be like no other. The Next Generation Nuclear Plant (NGNP) will be passively safe, economical, highly efficient, modular, proliferation resistant, and sustainable. In addition to electrical generation, the NGNP will demonstrate efficient and cost effective generation of hydrogen to support the President’s Hydrogen Initiative. To effectively manage this multi-organizational and technologically complex project, systems engineering techniques and processes will be used extensively to ensure delivery of the final product. The technological and organizational challenges are complex. Research and development activities are required, material standards require development, hydrogen production, storage and infrastructure requirements are not well developed, and the Nuclear Regulatory Commission may further define risk-informed/performance-based approach to licensing. Detailed design and development will be challenged by the vast cultural and institutional differences across the participants. Systems engineering processes must bring the technological and organizational complexity together to ensure successful product delivery. This paper will define the framework for application of systems engineering to this $1.5B - $1.9B project.

Edward J. Gorski; Charles V. Park; Finis H. Southworth

2004-06-01T23:59:59.000Z

398

NUCLEAR CHEMISTRY DIV. ANNUAL REPORT 1980-81  

E-Print Network (OSTI)

Polarization Phenomena in Nuclear Physics-1980, AIP Conf.Barrett and D.F. Jackson, Nuclear Sizes and Structure, (K Production in Relativistic Nuclear Collisions A. Shor, K.

Cerny, J.

2010-01-01T23:59:59.000Z

399

Selenide isotope generator for the Galileo Mission. Program final report  

SciTech Connect

This final report for the Selenide Isotope Generator for the Galileo Mission (SIG/GM) documents the work performed by Teledyne Energy Systems (TES) under US Department of Energy (DOE) Contract No. DE-AC01-78ET33009 (formerly ET-78-C-01-2865) during the period April 10, 1978 to June 30, 1979. Because of technical difficulties with the thermoelectric converter being developed by the 3M Company under separate DOE contract, a Stop Work Order, dated January 29, 1979, was issued by DOE. The TES effort up to the receipt of the Stop Work Order as well as limited technical activities up to the contract conclusion on June 30, 1979 are reported.

1979-06-01T23:59:59.000Z

400

DOE Statement on UK Government's "Road to 2010" Report on Nuclear Security  

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

Statement on UK Government's "Road to 2010" Report on Nuclear Statement on UK Government's "Road to 2010" Report on Nuclear Security DOE Statement on UK Government's "Road to 2010" Report on Nuclear Security July 17, 2009 - 12:00am Addthis WASHINGTON, DC - Thomas P. D'Agostino, the Department of Energy's Under Secretary for Nuclear Security and Administrator of the National Nuclear Security Administration, today applauded the British government's new report on advancing the global nuclear security agenda. Issued yesterday, "The Road to 2010 - Addressing the Nuclear Question in the Twenty First Century" outlines a strategy for addressing the threat posed by the proliferation of nuclear weapons ahead of the 2010 Nuclear Non-Proliferation Treaty (NPT) Review Conference. Among other steps, it includes the creation of a UK Center for Nuclear

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401

Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings  

SciTech Connect

Two of the major challenges the U.S. energy sector faces are greenhouse gas emissions and oil that is both imported and potentially reaching a peak (the point at which maximum extraction is reached). Interest in development of both renewable and nuclear energy has been strong because both have potential for overcoming these challenges. Research in both energy sources is ongoing, but relatively little research has focused on the potential benefits of combining nuclear and renewable energy. In September 2011, the Joint Institute for Strategic Energy Analysis (JISEA) convened the Nuclear and Renewable Energy Synergies Workshop at the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to identify potential synergies and strategic leveraging opportunities between nuclear energy and renewable energy. Industry, government, and academic thought leaders gathered to identify potential broad categories of synergies and brainstorm topic areas for additional analysis and research and development (R&D). This report records the proceedings and outcomes of the workshop.

Ruth, M.; Antkowiak, M.; Gossett, S.

2011-12-01T23:59:59.000Z

402

Milliwatt Generator Project. Progress report, April 1986--March 1988  

DOE Green Energy (OSTI)

This report covers progress on the Milliwatt Generator Project from April 1986 through March 1988. Activities included fuel processing and characterization, production of heat sources, fabrication of pressure-burst test units, compatibility studies, impact testing, and examination of surveillance units. The major task of the Los Alamos Milliwatt Generator Project is to fabricate MC2893A heat sources (4.0 W) for MC2730A radioisotope thermoelectric generators (RTGS) and MC3599 heat sources (4.5 W) for MC3500 RTGs. The MWG Project interfaces with the following contractors: Sandia National Laboratories, Albuquerque (designer); E.I. du Pont de Nemours and Co. (Inc.), Savannah River Plant (fuel); Monsanto Research Corporation, Mound Facility (metal hardware); and General Electric Company, Neutron Devices Department (RTGs). In addition to MWG fabrication activities, Los Alamos is involved in (1) fabrication of pressure-burst test units, (2) compatibility testing and evaluation, (3) examination of surveillance units, and (4) impact testing and subsequent examination of compatibility and surveillance units.

Latimer, T.W.; Rinehart, G.H.

1992-05-01T23:59:59.000Z

403

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

plants fly ash h. Coal-fired plants 1. fly ash 2. bottom ashthan those from a coal-fired plant. They are: Particulatevaries with fuel type: Coal-fired plants Oil-fired generate

Nero, A.V.

2010-01-01T23:59:59.000Z

404

Steam generator tube integrity program: Annual report, August 1995--September 1996. Volume 2  

Science Conference Proceedings (OSTI)

This report summarizes work performed by Argonne National Laboratory on the Steam Generator Tube Integrity Program from the inception of the program in August 1995 through September 1996. The program is divided into five tasks: (1) assessment of inspection reliability, (2) research on ISI (inservice-inspection) technology, (3) research on degradation modes and integrity, (4) tube removals from steam generators, and (5) program management. Under Task 1, progress is reported on the preparation of facilities and evaluation of nondestructive evaluation techniques for inspecting a mock-up steam generator for round-robin testing, the development of better ways to correlate failure pressure and leak rate with eddy current (EC) signals, the inspection of sleeved tubes, workshop and training activities, and the evaluation of emerging NDE technology. Results are reported in Task 2 on closed-form solutions and finite-element electromagnetic modeling of EC probe responses for various probe designs and flaw characteristics. In Task 3, facilities are being designed and built for the production of cracked tubes under aggressive and near-prototypical conditions and for the testing of flawed and unflawed tubes under normal operating, accident, and severe-accident conditions. Crack behavior and stability are also being modeled to provide guidance for test facility design, develop an improved understanding of the expected rupture behavior of tubes with circumferential cracks, and predict the behavior of flawed and unflawed tubes under severe accident conditions. Task 4 is concerned with the acquisition of tubes and tube sections from retired steam generators for use in the other research tasks. Progress on the acquisition of tubes from the Salem and McGuire 1 nuclear plants is reported.

Diercks, D.R.; Bakhtiari, S.; Kasza, K.E.; Kupperman, D.S.; Majumdar, S.; Park, J.Y.; Shack, W.J. [Argonne National Lab., IL (United States)

1998-02-01T23:59:59.000Z

405

Confirmatory Survey Results for the Reactor Building Dome Upper Surfaces, Rancho Saco Nuclear Generating Station  

SciTech Connect

Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006.

Wade C. Adams

2006-10-25T23:59:59.000Z

406

Marginal cost of electricity 1980-1995: an approximation based on the cost of new coal and nuclear generating plants  

SciTech Connect

This report presents estimates of the costs of new coal and nuclear base-load generating capacity which is either currently under construction or planned by utilities to meet their load-growth expectations during the period from 1980 to 1995. These capacity cost estimates are used in conjunction with announced plant capacities and commercial-operation dates to develop state-level estimates of busbar costs of electricity. From these projected busbar costs, aggregated estimates of electricity costs at the retail level are developed for DOE Regions. The introductory chapter explains the rationale for using the cost of electricity from base-load plants to approximate the marginal cost of electricity. The next major section of the report outlines the methodology and major assumptions used. This is followed by a detailed description of the empirical analysis, including the equations used for each of the cost components. The fourth section presents the resultant marginal cost estimates.

Nieves, L.A.; Patton, W.P.; Harrer, B.J.; Emery, J.C.

1980-07-01T23:59:59.000Z

407

Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program  

SciTech Connect

Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

1994-02-01T23:59:59.000Z

408

Preliminary issues associated with the next generation nuclear plant intermediate heat exchanger design.  

SciTech Connect

The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made a preliminary assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. Two IHX designs namely, shell and tube and compact heat exchangers were considered in the assessment. Printed circuit heat exchanger, among various compact heat exchanger (HX) designs, was selected for the analysis. Irrespective of the design, the material considerations for the construction of the HX are essentially similar, except may be in the fabrication of the units. As a result, we have reviewed in detail the available information on material property data relevant for the construction of HX and made a preliminary assessment of several relevant factors to make a judicious selection of the material for the IHX. The assessment included four primary candidate alloys namely, Alloy 617 (UNS N06617), Alloy 230 (UNS N06230), Alloy 800H (UNS N08810), and Alloy X (UNS N06002) for the IHX. Some of the factors addressed in this report are the tensile, creep, fatigue, creep fatigue, toughness properties for the candidate alloys, thermal aging effects on the mechanical properties, American Society of Mechanical Engineers (ASME) Code compliance information, and performance of the alloys in helium containing a wide range of impurity concentrations. A detailed thermal hydraulic analysis, using a model developed at ANL, was performed to calculate heat transfer, temperature distribution, and pressure drop inside both printed circuit and shell-and-tube heat exchangers. The analysis included evaluation of the role of key process parameters, geometrical factors in HX designs, and material properties. Calculations were performed for helium-to-helium, helium-to-helium/nitrogen, and helium-to-salt HXs. The IHX being a high temperature component, probably needs to be designed using ASME Code Section III, Subsection NH, assuming that the IHX will be classified as a class 1 component. With input from thermal hydraulic calculations performed at ANL, thermal conduction and stress analyses for both compact and shell-and-tube HXs were performed.

Natesan, K.; Moisseytsev, A.; Majumdar, S.; Shankar, P. S.; Nuclear Engineering Division

2007-04-05T23:59:59.000Z

409

Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory  

SciTech Connect

One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

J. D. Bess; J. B. Briggs; A. S. Garcia

2011-09-01T23:59:59.000Z

410

Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory  

SciTech Connect

One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

J. D. Bess; J. B. Briggs; A. S. Garcia

2011-09-01T23:59:59.000Z

411

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 6: Process Heat and Hydrogen Co-Generation PIRTs  

DOE Green Energy (OSTI)

A Phenomena Identification and Ranking Table (PIRT) exercise was conducted to identify potential safety-0-related physical phenomena for the Next Generation Nuclear Plant (NGNP) when coupled to a hydrogen production or similar chemical plant. The NGNP is a very high-temperature reactor (VHTR) with the design goal to produce high-temperature heat and electricity for nearby chemical plants. Because high-temperature heat can only be transported limited distances, the two plants will be close to each other. One of the primary applications for the VHTR would be to supply heat and electricity for the production of hydrogen. There was no assessment of chemical plant safety challenges. The primary application of this PIRT is to support the safety analysis of the NGNP coupled one or more small hydrogen production pilot plants. However, the chemical plant processes to be coupled to the NGNP have not yet been chosen; thus, a broad PIRT assessment was conducted to scope alternative potential applications and test facilities associated with the NGNP. The hazards associated with various chemicals and methods to minimize risks from those hazards are well understood within the chemical industry. Much but not all of the information required to assure safe conditions (separation distance, relative elevation, berms) is known for a reactor coupled to a chemical plant. There is also some experience with nuclear plants in several countries that have produced steam for industrial applications. The specific characteristics of the chemical plant, site layout, and the maximum stored inventories of chemicals can provide the starting point for the safety assessments. While the panel identified events and phenomena of safety significance, there is one added caveat. Multiple high-temperature reactors provide safety-related experience and understanding of reactor safety. In contrast, there have been only limited safety studies of coupled chemical and nuclear plants. The work herein provides a starting point for those studies; but, the general level of understanding of safety in coupling nuclear and chemical plants is less than in other areas of high-temperature reactor safety.

Forsberg, Charles W [ORNL; Gorensek, M. B. [Savannah River National Laboratory (SRNL); Herring, S. [Idaho National Laboratory (INL); Pickard, P. [Sandia National Laboratories (SNL)

2008-03-01T23:59:59.000Z

412

Locating hot and cold-legs in a nuclear powered steam generation system  

DOE Patents (OSTI)

A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet. 2 figures.

Ekeroth, D.E.; Corletti, M.M.

1993-11-16T23:59:59.000Z

413

Locating hot and cold-legs in a nuclear powered steam generation system  

SciTech Connect

A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet.

Ekeroth, Douglas E. (Delmont, PA); Corletti, Michael M. (New Kensington, PA)

1993-01-01T23:59:59.000Z

414

MHD generator component development. Quarterly report, October 1979-December 1979  

DOE Green Energy (OSTI)

Progress is reported on the following tasks: (1) perform experimental investigations related to MHD channel design and performance by testing existing channel hardware and by fabricating and testing new channel hardware; perform complementary analytical investigations; (2) perform experimental investigations related to MHD channel performance and lifetime, with the principal aim of systematically obtaining data on the prototype electrodes for the coal-fired, subsonic, long-duration CDIF Generator 1B3; (3) perform testing on channel loading and control utilizing the supersonic Reference channel No. 4 and other appropriate channels and/or test modules, at magnetic fields to 4 Tesla; and (4) provide for facility operation and maintenance of the Mk VI and Mk VII test bays. (WHK)

Not Available

1980-05-01T23:59:59.000Z

415

MHD generator component development. Quarterly report, July 1983-September 1983  

DOE Green Energy (OSTI)

The overall objectives of this program are two-fold: (1) To contribute, by appropriate systematic experimental and analytical investigations, to the engineering data base necessary for the design and construction of MHD generators at CDIF-scale (50 MW/sub th/) and baseload scale (2000 MW/sub th/). (2) To design and fabricate specific hardware items to be tested at the CDIF site in Butte, Montana. The program consists of a series of related tasks: (1) MHD channel design and performance; (2) MHD channel construction and lifetime; (3) MHD channel loading and control; (4) facility operation; (5) CDIF related hardware; and (6) high interaction tests of a supersonic channel. Progress is reported. (WHK)

Not Available

1983-11-01T23:59:59.000Z

416

Key contributions in MHD power generation. Semi-annual report, December 1, 1978-May 31, 1979  

DOE Green Energy (OSTI)

Research and development on open-cycle coal-fired MHD generators at MIT is reported. Separate abstracts were prepared for progress reported on the four tasks. (WHK)

Louis, J F

1979-06-01T23:59:59.000Z

417

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

particles report of the NRC Reactor Safety Study ANSI APCDFDA FR GRID Hz IEEE mrem NOI NRC OSHA PAH P.L. ppb ppbv ppbw20 arc applied; refer to the NRC procedures for determining

Nero, A.V.

2010-01-01T23:59:59.000Z

418

Nuclear technology programs. Semiannual progress report, April--September 1991  

Science Conference Proceedings (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April through September 1991. These programs involve R & D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

Not Available

1993-07-01T23:59:59.000Z

419

Nuclear Technology Programs semiannual progress report, April-- September 1990  

Science Conference Proceedings (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

Harmon, J.E. (ed.)

1992-06-01T23:59:59.000Z

420

Nuclear Technology Programs semiannual progress report, April-- September 1990  

SciTech Connect

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

Harmon, J.E. [ed.

1992-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Nuclear Technology Programs semiannual progress report, October 1988--March 1989  

Science Conference Proceedings (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1988--March 1989. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories. 127 refs., 76 figs., 103 tabs.

Harmon, J.E. [ed.

1990-12-01T23:59:59.000Z

422

Nuclear Technology Programs semiannual progress report, October 1990--March 1991  

SciTech Connect

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1990--March 1991. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transpose of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

1992-12-01T23:59:59.000Z

423

Nuclear Science Division annual report, October 1, 1984-September 30, 1985  

SciTech Connect

This report summarizes the activities of the Nuclear Science Division during the period October 1, 1984 to September 30, 1985. As in previous years, experimental research has for the most part been carried out using three local accelerators, the Bevalac, the SuperHILAC and the 88-Inch Cyclotron. However, during this time, preparations began for a new generation of relativistic heavy-ion experiments at CERN. The Nuclear Science Division is involved in three major experiments at CERN and several smaller ones. The report is divided into 5 sections. Part I describes the research programs and operations, and Part II contains condensations of experimental papers arranged roughly according to program and in order of increasing energy, without any further subdivisions. Part III contains condensations of theoretical papers, again ordered according to program but in order of decreasing energy. Improvements and innovations in instrumentation and in experimental or analytical techniques are presented in Part IV. Part V consists of appendices, the first listing publications by author for this period, in which the LBL report number only is given for papers that have not yet appeared in journals; the second contains abstracts of PhD theses awarded during this period; and the third gives the titles and speakers of the NSD Monday seminars, the Bevatron Research Meetings and the theory seminars that were given during the report period. The last appendix is an author index for this report.

Mahoney, J. (ed.)

1986-09-01T23:59:59.000Z

424

Composite Materials under Extreme Radiation and Temperature Environments of the Next Generation Nuclear Reactors  

Science Conference Proceedings (OSTI)

In the nuclear energy renaissance, driven by fission reactor concepts utilizing very high temperatures and fast neutron spectra, materials with enhanced performance that exceeds are expected to play a central role. With the operating temperatures of the Generation III reactors bringing the classical reactor materials close to their performance limits there is an urgent need to develop and qualify new alloys and composites. Efforts have been focused on the intricate relations and the high demands placed on materials at the anticipated extreme states within the next generation fusion and fission reactors which combine high radiation fluxes, elevated temperatures and aggressive environments. While nuclear reactors have been in operation for several decades, the structural materials associated with the next generation options need to endure much higher temperatures (1200 C), higher neutron doses (tens of displacements per atom, dpa), and extremely corrosive environments, which are beyond the experience on materials accumulated to-date. The most important consideration is the performance and reliability of structural materials for both in-core and out-of-core functions. While there exists a great body of nuclear materials research and operating experience/performance from fission reactors where epithermal and thermal neutrons interact with materials and alter their physio-mechanical properties, a process that is well understood by now, there are no operating or even experimental facilities that will facilitate the extreme conditions of flux and temperature anticipated and thus provide insights into the behaviour of these well understood materials. Materials, however, still need to be developed and their interaction and damage potential or lifetime to be quantified for the next generation nuclear energy. Based on material development advances, composites, and in particular ceramic composites, seem to inherently possess properties suitable for key functions within the operating envelope of both fission and fusion reactors. In advanced fission reactors composite materials are being designed in an effort to extend the life and improve the reliability of fuel rod cladding as well as structural materials. Composites are being considered for use as core internals in the next generation of gas-cooled reactors. Further, next-generation plasma-fusion reactors, such as the International Thermonuclear Experimental Reactor (ITER) will rely on the capabilities of advanced composites to safely withstand extremely high neutron fluxes while providing superior thermal shock resistance.

Simos, N.

2011-05-01T23:59:59.000Z

425

Characterization of a Stochastic Procedure for the Generation and Transport of Fission Fragments within Nuclear Fuels  

E-Print Network (OSTI)

With the ever-increasing demands of the nuclear power community to extend fuel cycles and overall core-lifetimes in a safe and economic manner, it is becoming more necessary to extend the working knowledge of nuclear fuel performance. From the atomistic to the macroscopic level, great morphological changes occur within the fuel over its lifetime. The main initial damaging events produced by fuel recoils from fast neutrons and fission fragment spiking leads to the onset of grain growths and fuel restructuring. Therefore, it is desirable to have a more detailed understanding of the initial events leading to fuel morphology changes at the atomistic level. However, this is difficult to achieve with the fission fragments due to the wide variability of their species (charge, mass, and energy) and the large averaging of their relative yields in the nuclear data files. This work is our first iteration at developing a general methodology to characterize a procedure, based on Monte Carlo principles, for generating individual fission event result channels and analyzing their specific response in the fuel. We utilized the nuclear reaction simulation tool, TALYS, to generate energy-dependent fission fragment yield distributions for different fissile/fissionable isotopes. These distributions can then be used in conjunction with fuel isotopics and a neutron energy spectrum to generate a fission-reaction-rate-averaged distribution of the fission fragment yields. We then used Monte Carlo sampling to generate the result channels from individual fission events, using the Q-value of the prompt fission system to either accept or reject. The simulation tool: Transport of Ions in Matter (TRIM) was used to characterize the general response of the fission fragment species within Uranium Dioxide (UO2), including the range, energy loss, displacements, recoils, etc. These responses were then correlated which allowed for the quick calculation of the response of the individual fission fragment species generated from the Monte Carlo sampling. As an example of this strategy, we calculated the response on a PWR fuel pin where MCNP was used to generate a high-fidelity neutron energy spectrum.

Hackemack, Michael Wayne

2013-05-01T23:59:59.000Z

426

Hydrogen generation rates in Savannah River Site high-level nuclear waste  

DOE Green Energy (OSTI)

High-level nuclear waste (HLW) is stored at the Savannah River Site (SRS) as alkaline, high-nitrate slurries in underground carbon steel tanks. Hydrogen is continuously generated in the waste tanks as a result of the radiolysis of water. Hydrogen generation rates have recently been measured in several waste tanks containing different types of waste. The measured rates ranged from 1.1 to 6.7 cubic feet per million Btu of decay heat. The measured rates are consistent with laboratory data which show that the hydrogen generation rate depends on the nitrate concentration and the decay heat content of the waste. Sampling at different locations indicated that the hydrogen is uniformly distributed radially within the tank.

Hobbs, D.T.; Norris, P.W.; Pucko, S.A.; Bibler, N.E.; Walker, D.D.; d'Entremont, P.D.

1992-01-01T23:59:59.000Z

427

Ontology-based Software for Generating Scenarios for Characterizing Searches for Nuclear Materials  

Science Conference Proceedings (OSTI)

A software environment was created in which ontologies are used to significantly expand the number and variety of scenarios for special nuclear materials (SNM) detection based on a set of simple generalized initial descriptions. A framework was built that combined advanced reasoning from ontologies with geographical and other data sources to generate a much larger list of specific detailed descriptions from a simple initial set of user-input variables. This presentation shows how basing the scenario generation on a process of inferencing from multiple ontologies, including a new SNM Detection Ontology (DO) combined with data extraction from geodatabases, provided the desired significant variability of scenarios for testing search algorithms, including unique combinations of variables not previously expected. The various components of the software environment and the resulting scenarios generated will be discussed.

Ward, Richard C [ORNL; Sorokine, Alexandre [ORNL; Schlicher, Bob G [ORNL; Wright, Michael C [ORNL; Kruse, Kara L [ORNL

2011-01-01T23:59:59.000Z

428

Letter Report: Looking Ahead at Nuclear Fuel Resources  

SciTech Connect

The future of nuclear energy and its ability to fulfill part of the world’s energy needs for centuries to come depend on a reliable input of nuclear fuel, either thorium or uranium. Obviously, the present nuclear fuel cycle is completely dependent on uranium. Future thorium cycles will also depend on 235U or fissile isotopes separated from used fuel to breed 232Th into fissile 233U. This letter report discusses several emerging areas of scientific understanding and technology development that will clarify and enable assured supplies of uranium and thorium well into the future. At the most fundamental level, the nuclear energy community needs to appreciate the origins of uranium and thorium and the processes of planetary accretion by which those materials have coalesced to form the earth and other planets. Secondly, the studies of geophysics and geochemistry are increasing understanding of the processes by which uranium and thorium are concentrated in various locations in the earth’s crust. Thirdly, the study of neutrinos and particularly geoneutrinos (neutrinos emitted by radioactive materials within the earth) has given an indication of the overall global inventories of uranium and thorium, though little indication for those materials’ locations. Crustal temperature measurements have also given hints of the vertical distribution of radioactive heat sources, primarily 238U and 232Th, within the continental crust. Finally, the evolving technologies for laser isotope separation are indicating methods for reducing the energy input to uranium enrichment but also for tailoring the isotopic vectors of fuels, burnable poisons and structural materials, thereby adding another tool for dealing with long-term waste management.

J. Stephen Herring

2013-09-01T23:59:59.000Z

429

Theoretical studies in high energy nuclear physics. Progress report  

SciTech Connect

This paper is a progress report for the period 1-1-93 to 6-30-95 on a project primarily directed at the application of high energy physics techniques to nuclear structure studies, and the ability to study hadron dynamics through interactions with nuclear targets. This work has included the first legitimate QCD calculations of hard coherent diffractive processes off nucleon (nuclear) targets which established novel features of color transparency phenomenon not anticipated in the previous intuitive or QCD inspired model calculations and predicted the fast increase of the cross section for electroproduction of {rho}-mesons with increase of the energy, which was confirmed very recently by the first HERA data on this reaction. First theoretical demonstration that color transparency phenomenon for the hard diffractive processes follow from QCD in the kinematics when both x{yields}0 and Q{sup 2}{yields}{infinity}. Establishing the pattern of color (cross section) fluctuations in hadrons. Confirmed by the FNAL inelastic diffraction data. Finding that in realistic quark, skyrmion models of a hadron large momentum transfer elastic lepton-hadron scattering occurs through formation of small spatial size configurations. Discovering a novel class of color transparency sensitive double interaction processes which is complementary to quasielastic reactions originally suggested by S. Brodsky and A. Mueller. Adopting ideas suggested elsewhere for hadron initiated reactions they developed a method for taking into account nuclear correlations in (e,e{prime}p) reactions. Such an approach gives practical possibility to overcome ambiguities of optical model approximation used before and to reliably interpret color transparency effects at intermediate Q{sup 2}.

1995-08-01T23:59:59.000Z

430

Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect  

DOE Green Energy (OSTI)

Corrosion of steel canisters, stored in a repository for spent fuel and high-level nuclear wastes, leads to the generation and accumulation of hydrogen gas in the backfilled emplacement tunnels, which may significantly affect long-term repository safety. Previous studies used H{sub 2} generation rates based on the volume of the waste or canister material and the stoichiometry of the corrosion reaction. However, iron corrosion and H{sub 2} generation rates vary with time, depending on factors such as amount of iron, water availability, water contact area, and aqueous and solid chemistry. To account for these factors and feedback mechanisms, we developed a chemistry model related to iron corrosion, coupled with two-phase (liquid and gas) flow phenomena that are driven by gas-pressure buildup associated with H{sub 2} generation and water consumption. Results indicate that by dynamically calculating H{sub 2} generation rates based on a simple model of corrosion chemistry, and by coupling this corrosion reaction with two-phase flow processes, the degree and extent of gas pressure buildup could be much smaller compared to a model that neglects the coupling between flow and reactive transport mechanisms. By considering the feedback of corrosion chemistry, the gas pressure increases initially at the canister, but later decreases and eventually returns to a stabilized pressure that is slightly higher than the background pressure. The current study focuses on corrosion under anaerobic conditions for which the coupled hydrogeochemical model was used to examine the role of selected physical parameters on the H{sub 2} gas generation and corresponding pressure buildup in a nuclear waste repository. The developed model can be applied to evaluate the effect of water and mineral chemistry of the buffer and host rock on the corrosion reaction for future site-specific studies.

Xu, T.; Senger, R.; Finsterle, S.

2008-10-15T23:59:59.000Z

431

Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings  

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

Joint Institute for Strategic Energy Analysis is operated by the Alliance Joint Institute for Strategic Energy Analysis is operated by the Alliance for Sustainable Energy, LLC, on behalf of the U.S. Department of Energy's National Renewable Energy Laboratory, the University of Colorado-Boulder, the Colorado School of Mines, the Colorado State University, the Massachusetts Institute of Technology, and Stanford University. Contract No. DE-AC36-08GO28308 Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings Mark Ruth, Mark Antkowiak, and Scott Gossett Technical Report NREL/TP-6A30-52256 December 2011 The Joint Institute for Strategic Energy Analysis is operated by the Alliance for Sustainable Energy, LLC, on behalf of the U.S. Department of Energy's National Renewable Energy Laboratory, the University of Colorado-Boulder,

432

Environmental radiological studies in 1989 near the Rancho Seco Nuclear Power Generating Station  

SciTech Connect

In December 1988, the Sacramento Municipal Utilities District (SMUD) asked the Lawrence Livermore National Laboratory's (LLNL) Environmental Sciences Division (ENV) to collect sediment, water,and fish samples downstream from the Rancho Seco Nuclear Power Generating Station for analysis of radionuclides to compare with results from earlier surveys in 1984 through 1987 (1--8). ENV was, however, asked to reduce the total number of sample collections to a minimum in this study because of financial constraints. The proposal ENV submitted for the 1989 Environmental Radiological Studies downstream of the Rancho Seco Nuclear Power Generating Station reflected this reduction, but we believe, nevertheless, the 1989 efforts do allow us to make some meaningful comparisons with the previous studies. Cesium-137 is the most significant radionuclide still observed downstream from the Rancho Seco Nuclear Power Plant. Only occasionally is {sup 134}Cs or {sup 60}CO observed. In 1989, the concentration of {sup 137}Cs in the water and fish decreased with distance from the plant to the same level that is was in 1987, and was lower than it had been from 1984 through 1986. The concentration ratio (CR) for {sup 137}Cs in fish is between 1000 and 1500, which is below the NRC default value of 2000. Physical mixing in the creek environment has moved the {sup 137}Cs deeper into the sediment column, thereby reducing the concentration in the top 12 cm relative to that in previous years. 8 refs., 18 figs., 9 tabs.

Robison, W.L.; Wong, Kai M.; Jones, H.E.

1990-11-01T23:59:59.000Z

433

CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS  

SciTech Connect

The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and attempts to answer this question: What type of SNF cask would be produced if we were to start over and design SNF casks based on today's requirements? The characteristics for a next-generation SNF cask system are examined and are found to be essentially the same in Russia and the United States. It appears that the new depleted uranium dioxide (DUO2)-steel cermet material will enable these requirements to be met. Depleted uranium (DU) is uranium in which a portion of the 235U isotope has been removed during a uranium enrichment process. The DUO2-steel cermet material is described. The United States and Russia are cooperating toward the development of a next-generation, dual-purpose, storage and transport SNF system.

Haire, M.J.; Forsberg, C.W.; Matveev, V.Z.; Shapovalov, V.I.

2004-10-03T23:59:59.000Z

434

Nuclear Science Division Annual Report 1995-1996  

E-Print Network (OSTI)

Times in 3He Induced Nuclear Fission Th. Rubehn, K.X. Jing,of the discovery of nuclear fission. Many review papers andtimes in 3He induced nuclear fission* Th. Rubehn, K.X. Jing,

Authors, Various

2010-01-01T23:59:59.000Z

435

Nuclear Science Division Annual Report 1984-85  

E-Print Network (OSTI)

and J.R. Huizenga, Nuclear Fission (Academic, New York,and J.R. Huizenga, Nuclear Fission (Academic, N.Y. , 1973).is well known from nuclear fission where it can be related

Mahoney Editor, Jeannette

2010-01-01T23:59:59.000Z

436

NUCLEAR SCIENCE DIVISION ANNUAL REPORT 1979-1980  

E-Print Network (OSTI)

high energy nuclear collisions. Application of HFB theory totheory that accounts for the known bulk properties of nuclear matter, i t s saturation energyenergy options. Sane neutron star physics involving nuclear theory.

Cerny, J.

2010-01-01T23:59:59.000Z

437

Nuclear Science Division Annual Report 1995-1996  

E-Print Network (OSTI)

Nuclear Theory Study of Medium-induced Parton Energy LossTransport theory With a view towards high-energy nuclearNuclear Theory Study of Medium-induced Parton Energy Loss

Authors, Various

2010-01-01T23:59:59.000Z

438

NUCLEAR CHEMISTRY DIV. ANNUAL REPORT 1980-81  

E-Print Network (OSTI)

Correlations in High-Energy Nuclear Colli­ sions, LBL-11418,Effects in High-Energy Nuclear Collisions: Implications onLarge Angles in High-Energy Nuclear Collisions, LBL-12123,

Cerny, J.

2010-01-01T23:59:59.000Z

439

NUCLEAR SCIENCE DIVISION ANNUAL REPORT 1979-1980  

E-Print Network (OSTI)

1979). {Laboratory for Nuclear Studies, Osaka University,D. Loveland, and G. T. Seaborg, Nuclear Science Div. AnnualBohr and B. R. Hottel son. Nuclear Structure Vol. 1 (W. A.

Cerny, J.

2010-01-01T23:59:59.000Z

440

Nuclear Science Division Annual Report 1995-1996  

E-Print Network (OSTI)

Saladin5, and C.H. Yu6 Nuclear Science Division, LawrenceMoretto, G.J. Wozniak, Nuclear Science Division, LawrenceComment on “Probing the Nuclear Liquid-Gas Phase Transition”

Authors, Various

2010-01-01T23:59:59.000Z

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


441

Nuclear Science Division Annual Report 1984-85  

E-Print Network (OSTI)

M. Xcssi. and W. Wolf. Nuclear-Reaction-Time Studies of U +K° Produced in Relativistic Nuclear Collisions Phys. Lett.Momentum Distributions of Nuclear Fragments in im Collisions

Mahoney Editor, Jeannette

2010-01-01T23:59:59.000Z

442

The Coming Nuclear Renaissance for Next Generation Safeguards Specialists--Maximizing Potential and Minimizing the Risks  

SciTech Connect

This document is intended to provide an overview of the workshop entitled 'The Coming Nuclear Renaissance for the Next Generation Safeguards Experts-Maximizing Benefits While Minimizing Proliferation Risks', conducted at Oak Ridge National Laboratory (ORNL) in partnership with the Y-12 National Security Complex (Y-12) and the Savannah River National Laboratory (SRNL). This document presents workshop objectives; lists the numerous participant universities and individuals, the nuclear nonproliferation lecture topics covered, and the facilities tours taken as part of the workshop; and discusses the university partnership sessions and proposed areas for collaboration between the universities and ORNL for 2009. Appendix A contains the agenda for the workshop; Appendix B lists the workshop attendees and presenters with contact information; Appendix C contains graphics of the evaluation form results and survey areas; and Appendix D summarizes the responses to the workshop evaluation form. The workshop was an opportunity for ORNL, Y-12, and SRNL staff with more than 30 years combined experience in nuclear nonproliferation to provide a comprehensive overview of their expertise for the university professors and their students. The overall goal of the workshop was to emphasize nonproliferation aspects of the nuclear fuel cycle and to identify specific areas where the universities and experts from operations and national laboratories could collaborate.

Eipeldauer, Mary D [ORNL

2009-01-01T23:59:59.000Z

443

Nuclear Science Division, Annual report, October 1, 1988--December 31, 1990  

Science Conference Proceedings (OSTI)

This report contains short papers of research conducted in the following areas: Low energy research program; bevalac research program; ultrarelativistic research program; nuclear theory program; nuclear data evaluation; and, 88-inch cyclotron operations.

Poskanzer, A.M.; Deleplanque, M.A.; Firestone, R.B.; Lofdahl, J.B. (eds.)

1991-04-01T23:59:59.000Z

444

Advanced Nuclear Technology: Impact of EPRI Pre-Operational and Operational Configuration Management Report (1022684) on the Nuclear Industry  

Science Conference Proceedings (OSTI)

EPRI Technical Report 1022684, Elements of Pre-Operational and Operational Configuration Management for a New Nuclear Facility, was developed by an EPRI Advanced Nuclear Technology (ANT) technical advisory group whose mission was to develop guidance for establishing a comprehensive configuration management (CM) program for the unique challenges of a new nuclear facility. The program elements developed for the pre-operation phase would then be in place to manage the configuration for the ...

2013-03-20T23:59:59.000Z

445

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

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

safeguards and nonproliferation, environmental management and waste cleanup, and Navy nuclear propulsion systems development resides outside the Office of Nuclear Energy, Science...

446

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

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... A resource document for the Workshop on Basic Research Needs for Advanced Nuclear Energy Systems. Includes an overview of nuclear ...

447

Assessment of DC Backup Power Technology Options for Nuclear Power Generation Stations  

Science Conference Proceedings (OSTI)

The March 2011 Fukushima nuclear power plant accident in Japan created a renewed industry interest in examining potential improvements for backup power options to support plant accident scenarios in both near-term and long-term implementation time periods. This report assesses technology options that can be considered in improving DC backup power. Options with near-term applicability were considered and reviewed. Certain energy storage systems and hydrogen power fuel cells were identified that could ...

2013-10-15T23:59:59.000Z

448