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1

Generation IV Nuclear Energy Systems ...  

E-Print Network [OSTI]

Generation IV Nuclear Energy Systems ... The U.S. Department of Energy's Office of Nuclear Energy enhance safety and security, and develop nuclear power as an energy source for industrial applications Information ... U.S. Department of Energy www.energy.gov DOE Office of Nuclear Energy www.nuclear

Kemner, Ken

2

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

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

3

Observations on A Technology Roadmap for Generation IV Nuclear Energy  

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

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

4

An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems  

SciTech Connect (OSTI)

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

5

Generation IV International Forum Updates Technology Roadmap...  

Office of Environmental Management (EM)

nuclear energy Generation IV International Forum Signs Agreement to Collaborate on Sodium Cooled Fast Reactors China and Russia to Join the Generation IV International Forum...

6

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 (OSTI)

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

7

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

SciTech Connect (OSTI)

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

8

EVALUATION METHODOLOGY FOR PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION OF GENERATION IV NUCLEAR ENERGY SYSTEMS: AN OVERVIEW.  

SciTech Connect (OSTI)

This paper provides an overview of the methodology approach developed by the Generation IV International Forum Expert Group on Proliferation Resistance & Physical Protection for evaluation of Proliferation Resistance and Physical Protection robustness of Generation IV nuclear energy systems options. The methodology considers a set of alternative systems and evaluates their resistance or robustness to a collection of potential threats. For the challenges considered, the response of the system to these challenges is assessed and expressed in terms of outcomes. The challenges to the system are given by the threats posed by potential proliferant States and sub-national adversaries on the nuclear systems. The characteristics of the Generation IV systems, both technical and institutional, are used to evaluate their response to the threats and determine their resistance against the proliferation threats and robustness against sabotage and theft threats. System response encompasses three main elements: (1) System Element Identification. The nuclear energy system is decomposed into smaller elements (subsystems) at a level amenable to further analysis. (2) Target Identification and Categorization. A systematic process is used to identify and select representative targets for different categories of pathways, within each system element, that actors (proliferant States or adversaries) might choose to use or attack. (3) Pathway Identification and Refinement. Pathways are defined as potential sequences of events and actions followed by the proliferant State or adversary to achieve its objectives (proliferation, theft or sabotage). For each target, individual pathway segments are developed through a systematic process, analyzed at a high level, and screened where possible. Segments are connected into full pathways and analyzed in detail. The outcomes of the system response are expressed in terms of PR&PP measures. Measures are high-level characteristics of a pathway that include information important to the evaluation methodology users and to the decisions of a proliferant State or adversary. They are first evaluated for segments and then aggregated for complete pathways. Results are aggregated as appropriate to permit pathway comparisons and system assessment. The paper highlights the current achievements in the development of the Proliferation Resistance and Physical Protection Evaluation Methodology. The way forward is also briefly presented together with some conclusions.

BARI, R.; ET AL.

2006-03-01T23:59:59.000Z

9

Safeguards Licensing Aspects of a Future Generation IV Demonstration Facility.  

E-Print Network [OSTI]

?? Generation IV (Gen IV) is a developing new generation of nuclear power reactors which is foreseen to bring about a safer and more sustainable (more)

berg Lindell, Matilda

2010-01-01T23:59:59.000Z

10

Generation -IV Reactor Concepts  

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

Generation-IV Reactor Concepts Generation-IV Reactor Concepts Thomas H. Fanning Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439, USA The Generation-IV International Forum (GIF) is a multi-national research and development (R&D) collaboration. The GIF pursues the development of advanced, next generation reactor technology with goals to improve: a) sustainability (effective fuel utilization and minimization of waste) b) economics (competitiveness with respect to other energy sources) c) safety and reliability (e.g., no need for offsite emergency response), and d) proliferation resistance and physical protection The GIF Technology Roadmap exercise selected six generic systems for further study: the Gas- cooled Fast Reactor (GFR), the Lead-cooled Fast Reactor (LFR), the Molten Salt Reactor (MSR),

11

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

SciTech Connect (OSTI)

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

12

Generation IV International Forum | Department of Energy  

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

Forum Forum Generation IV International Forum January 14, 2005 - 9:50am Addthis Remarks of Secretary of Energy Spencer Abraham National Press Club It is a pleasure to be here today, to welcome the representatives of the Generation IV International Forum to their first Washington, D.C., meeting. Very early in my tenure as U.S. Secretary of Energy, I took part in the formation of the Generation IV initiative, and the signing of the organization's charter - which provided the framework for international cooperative research on advanced nuclear energy systems that are safe, reliable, economical and proliferation resistant... to help ensure that nuclear power has a vital and viable role in the world's energy future. I last met with the Generation IV International Forum two years ago in

13

Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems  

SciTech Connect (OSTI)

This project will use proton irradiation to further understand the microstructural stability of ceramics being considered as matrix material for advanced nuclear fuels.

Todd R. Allen

2009-06-30T23:59:59.000Z

14

Outlook on Generation IV Nuclear Systems and Related Materials R&D Challenges  

Science Journals Connector (OSTI)

Preoccupations of energy security and concerns about of the role that future reactors should play for minimizing long-lived radioactive ... that gives first priority to developing a new generation of fast neutron...

F. Carr; C. Renault; P. Anzieu; P. Brossard

2008-01-01T23:59:59.000Z

15

Roadmap Integration Team Presentation Generation IV Roadmap Overview  

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

Presentation Presentation Generation IV Roadmap Overview NERAC Meeting: Washington, D.C. April 15, 2002 Roadmap Integration Team Presentation Definition - Generation IV Generation IV is: "...the next generation of nuclear energy systems that can be licensed, constructed, and operated in a manner that will provide a competitively priced and reliable supply of energy to the country where such systems are deployed, while addressing nuclear safety, waste, proliferation and public perception concerns." Roadmap Integration Team Presentation Objective - Gen IV Technology Roadmap The Technology Roadmap: * Describes systems deployable by 2030 or earlier * Determines which systems offer significant advances towards:

16

The U.S. Generation IV Implementation Strategy  

SciTech Connect (OSTI)

This report has been prepared by the U.S. Department of Energy (DOE) to respond to Congressional direction contained in Senate Report 107-220 from the Senate Committee on Appropriations regarding the Energy and Water Development Appropriations for 2003. In that report, the Committee instructed the Department to prepare a report regarding how it intends to carry out the results of the Generation IV Roadmap. This report is the U.S. Department of Energy's response to the Congressional directive. It summarizes results from the Generation IV Technology Roadmap and the strategy for implementing of the Generation IV program in the United States. Planning for the implementation of the Generation IV program is based on (1) the long-term outlook for nuclear energy in the United States, (2) the advice of the Nuclear Energy Research Advisory Committee during the two-year development of the Generation IV Technology Roadmap, and (3) the need for the Generation IV program to be integrated with other nuclear energy research programs of the Department. Considerable emphasis is given to developing the priorities and necessary timelines for the U.S. Generation IV Program, as well as developing international R&D cooperation that will benefit the program and strengthen U.S. leadership in nuclear technology R&D.

None

2003-09-01T23:59:59.000Z

17

Development of Modeling Techniques for A Generation IV Gas Fast Reactor  

E-Print Network [OSTI]

Worldwide, multiple countries are investing a great deal of time and energy towards developing a new class of technologically advanced nuclear reactors. These new reactors have come to be known as the Generation IV (Gen IV) class of nuclear...

Dercher, Andrew Steven

2012-10-19T23:59:59.000Z

18

Investigation of a Novel NDE Method for Monitoring Thermomechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems  

SciTech Connect (OSTI)

The main goal of the proposed project is the development of validated nondestructive evaluation (NDE) techniques for in situ monitoring of ferritic-martensitic steels like Grade 91 9Cr-1Mo, which are candidate materials for Generation IV nuclear energy structural components operating at temperatures up to ~650{degree}C and for steam-generator tubing for sodium-cooled fast reactors. Full assessment of thermomechanical damage requires a clear separation between thermally activated microstructural evolution and creep damage caused by simultaneous mechanical stress. Creep damage can be classified as "negligible" creep without significant plastic strain and "ordinary" creep of the primary, secondary, and tertiary kind that is accompanied by significant plastic deformation and/or cavity nucleation and growth. Under negligible creep conditions of interest in this project, minimal or no plastic strain occurs, and the accumulation of creep damage does not significantly reduce the fatigue life of a structural component so that low-temperature design rules, such as the ASME Section III, Subsection NB, can be applied with confidence. The proposed research project will utilize a multifaceted approach in which the feasibility of electrical conductivity and thermo-electric monitoring methods is researched and coupled with detailed post-thermal/creep exposure characterization of microstructural changes and damage processes using state-of-the-art electron microscopy techniques, with the aim of establishing the most effective nondestructive materials evaluation technique for particular degradation modes in high-temperature alloys that are candidates for use in the Next Generation Nuclear Plant (NGNP) as well as providing the necessary mechanism-based underpinnings for relating the two. Only techniques suitable for practical application in situ will be considered. As the project evolves and results accumulate, we will also study the use of this technique for monitoring other GEN IV materials. Through the results obtained from this integrated materials behavior and NDE study, new insight will be gained into the best nondestructive creep and microstructure monitoring methods for the particular mechanisms identified in these materials. The proposed project includes collaboration with a national laboratory partner and the results will also serve as a foundation to guide the efforts of scientists in the DOE laboratory, university, and industrial communities concerned with the technological challenges of monitoring creep and microstructural evolution in materials planned to be used in Generation IV Nuclear Energy Systems.

Nagy, Peter

2013-09-30T23:59:59.000Z

19

Generation IV International Forum Updates Technology Roadmap and Builds  

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

Generation IV International Forum Updates Technology Roadmap and Generation IV International Forum Updates Technology Roadmap and Builds Future Collaboration Generation IV International Forum Updates Technology Roadmap and Builds Future Collaboration December 31, 2013 - 12:14pm Addthis GIF Policy Group Meeting in Brussels, Belgium, November 2013 GIF Policy Group Meeting in Brussels, Belgium, November 2013 Deputy Assistant Secretary Kelly Deputy Assistant Secretary Kelly Deputy Assistant Secretary for Nuclear Reactor Technologies The Generation IV International Forum (GIF) held its 36th Policy Group (PG) meeting on November 21-22 in Brussels, Belgium. The PG reviewed progress on a number of on-going actions and received progress reports from the GIF Experts Group (EG) and the GIF Senior Industry Advisory Panel (SIAP).

20

13 - Generation IV reactor designs, operation and fuel cycle  

Science Journals Connector (OSTI)

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

N. Cerullo; G. Lomonaco

2012-01-01T23:59:59.000Z

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

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

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

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

22

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

SciTech Connect (OSTI)

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

23

Generating the Option of a Two-Stage Nuclear Renaissance  

Science Journals Connector (OSTI)

...resources. However, the technology has not been demonstrated...nonrenewable natural gas), although various measures...energy. Outlook Nuclear technology is at a crossroads. The...International Forum, A Technology Roadmap for Generation IV Nuclear...

Robin W. Grimes; William J. Nuttall

2010-08-13T23:59:59.000Z

24

China and Russia to Join the Generation IV International Forum | Department  

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

China and Russia to Join the Generation IV International Forum China and Russia to Join the Generation IV International Forum China and Russia to Join the Generation IV International Forum July 13, 2006 - 3:03pm Addthis International Scope of Nuclear Nations Pursuing Advanced Reactors Broadens WASHINGTON, DC - U.S. Department of Energy Assistant Secretary for Nuclear Energy Dennis Spurgeon today announced that China and Russia are expected to join the Generation IV International Forum (GIF), a group of the world's leading nuclear nations who are working together to develop more efficient and less waste-intensive advanced reactors to meet future energy challenges. Earlier today, the GIF Policy Group voted unanimously to extend an offer of membership to China and Russia. China and Russia's formal entry into GIF is expected to be finalized by November 2006.

25

China and Russia to Join the Generation IV International Forum | Department  

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

China and Russia to Join the Generation IV International Forum China and Russia to Join the Generation IV International Forum China and Russia to Join the Generation IV International Forum July 13, 2006 - 3:03pm Addthis International Scope of Nuclear Nations Pursuing Advanced Reactors Broadens WASHINGTON, DC - U.S. Department of Energy Assistant Secretary for Nuclear Energy Dennis Spurgeon today announced that China and Russia are expected to join the Generation IV International Forum (GIF), a group of the world's leading nuclear nations who are working together to develop more efficient and less waste-intensive advanced reactors to meet future energy challenges. Earlier today, the GIF Policy Group voted unanimously to extend an offer of membership to China and Russia. China and Russia's formal entry into GIF is expected to be finalized by November 2006.

26

GEN-IV Reactors  

Science Journals Connector (OSTI)

Generation-IV reactors are a set of nuclear reactors currently being developed under international collaborations targeting ... economics, proliferation resistance, and physical protection of nuclear energy. Nuclear

Taek K. Kim

2013-01-01T23:59:59.000Z

27

Generation IV International Forum Signs Agreement to Collaborate...  

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

and Japan Increase Cooperation on Sodium-Cooled Fast Reactor Prototypes China and Russia to Join the Generation IV International Forum Renewed energy and enhanced coordination...

28

Generation IV International Forum Signs Agreement to Collaborate on Sodium  

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

Forum Signs Agreement to Collaborate on Forum Signs Agreement to Collaborate on Sodium Cooled Fast Reactors Generation IV International Forum Signs Agreement to Collaborate on Sodium Cooled Fast Reactors February 17, 2006 - 11:58am Addthis FUKUI , JAPAN - The Department of Energy today announced that the United States signed a sodium-cooled fast reactor systems arrangement with France and Japan, providing the framework for collaboration among these countries on the research and development of these advanced nuclear reactors. The signing of the agreement took place on February 16, 2006. This arrangement will support the development of technologies associated with the U.S.-led Global Nuclear Energy Partnership (GNEP), announced earlier this month by Secretary of Energy Samuel W. Bodman. GNEP is a

29

Next Generation Nuclear Plant Phenomena  

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

5 ORNLTM-2007147, Vol. 5 Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs Office of Nuclear Regulatory Research...

30

Generation IV PR and PP Methods and Applications  

SciTech Connect (OSTI)

This paper presents an evaluation methodology for proliferation resistance and physical protection (PR&PP) of Generation IV nuclear energy systems (NESs). For a proposed NES design, the methodology defines a set of challenges, analyzes system response to these challenges, and assesses outcomes. The challenges to the NES are the threats posed by potential actors (proliferant States or sub-national adversaries). The characteristics of Generation IV systems, both technical and institutional, are used to evaluate the response of the system and determine its resistance against proliferation threats and robustness against sabotage and terrorism threats. The outcomes of the system response are expressed in terms of six measures for PR and three measures for PP, which are the high-level PR&PP characteristics of the NES. The methodology is organized to allow evaluations to be performed at the earliest stages of system design and to become more detailed and more representative as design progresses. Uncertainty of results are recognized and incorporated into the evaluation at all stages. The results are intended for three types of users: system designers, program policy makers, and external stakeholders. Particular current relevant activities will be discussed in this regard. The methodology has been illustrated in a series of demonstration and case studies and these will be summarized in the paper.

Bari,R.A.

2008-10-13T23:59:59.000Z

31

Synergies Between Generation-IV and Advanced  

E-Print Network [OSTI]

to these changes · Requires experimental data for validation Limited resources require careful selection both recognize potential risk to environment and public health Safety goals and requirements Waste minimization Regulatory reform #12;9/14/2004 16th TOFE: Gen IV + ARIES 11/17 Safety Common safety goal

32

Industry Participation Sought for Design of Next Generation Nuclear Plant |  

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

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.

33

DEVELOPMENT OF A METHODOLOGY TO ASSESS PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION FOR GENERATION IV SYSTEMS  

SciTech Connect (OSTI)

Enhanced proliferation resistance and physical protection (PR&PP) is one of the technology goals for advanced nuclear concepts, such as Generation IV systems. Under the auspices of the Generation IV International Forum, the Office of Nuclear Energy, Science and Technology of the U.S. DOE, the Office of Nonproliferation Policy of the National Nuclear Security Administration, and participating organizations from six other countries are sponsoring an international working group to develop an evaluation methodology for PR&PP. This methodology will permit an objective PR&PP comparison between alternative nuclear systems (e.g., different reactor types or fuel cycles) and support design optimization to enhance robustness against proliferation, theft and sabotage. The paper summarizes the proposed assessment methodology including the assessment framework, measures used to express the PR&PP characteristics of the system, threat definition, system element and target identification, pathway identification and analysis, and estimation of the measures.

Nishimura, R.; Bari, R.; Peterson, P.; Roglans-Ribas, J.; Kalenchuk, D.

2004-10-06T23:59:59.000Z

34

CONSTRUCTION OF WEB-ACCESSIBLE MATERIALS HANDBOOK FORGENERATION IV NUCLEAR REACTORS  

SciTech Connect (OSTI)

The development of a web-accessible materials handbook in support of the materials selection and structural design for the Generation IV nuclear reactors is being planned. Background of the reactor program is briefly introduced. Evolution of materials handbooks for nuclear reactors over years is reviewed in light of the trends brought forth by the rapid advancement in information technologies. The framework, major features, contents, and construction considerations of the web-accessible Gen IV Materials Handbook are discussed. Potential further developments and applications of the handbook are also elucidated.

Ren, Weiju [ORNL

2005-01-01T23:59:59.000Z

35

A nuclear magnetic resonance probe of group IV clathrates  

E-Print Network [OSTI]

A NUCLEAR MAGNETIC RESONANCE PROBE OF GROUP IV CLATHRATES A Dissertation by WEIPING GOU Submitted to the Oce of Graduate Studies of Texas A&M University in partial fulflllment of the requirements for the degree of DOCTOR OF PHILOSOPHY August 2008... Major Subject: Physics A NUCLEAR MAGNETIC RESONANCE PROBE OF GROUP IV CLATHRATES A Dissertation by WEIPING GOU Submitted to the Oce of Graduate Studies of Texas A&M University in partial fulflllment of the requirements for the degree of DOCTOR...

Gou, Weiping

2008-10-10T23:59:59.000Z

36

Generating the Option of a Two-Stage Nuclear Renaissance  

Science Journals Connector (OSTI)

...inhomogeneously distributed fission gas bubbles and oxides, and noble metal precipitates...conventional island (the turbine and generator). At the end of its...coproduct of nonrenewable natural gas), although various measures such as cooling...International Forum, A Technology Roadmap for Generation IV Nuclear Energy...

Robin W. Grimes; William J. Nuttall

2010-08-13T23:59:59.000Z

37

Automatic generation and analysis of solar cell IV curves  

SciTech Connect (OSTI)

A photovoltaic system includes multiple strings of solar panels and a device presenting a DC load to the strings of solar panels. Output currents of the strings of solar panels may be sensed and provided to a computer that generates current-voltage (IV) curves of the strings of solar panels. Output voltages of the string of solar panels may be sensed at the string or at the device presenting the DC load. The DC load may be varied. Output currents of the strings of solar panels responsive to the variation of the DC load are sensed to generate IV curves of the strings of solar panels. IV curves may be compared and analyzed to evaluate performance of and detect problems with a string of solar panels.

Kraft, Steven M.; Jones, Jason C.

2014-06-03T23:59:59.000Z

38

Bush Administration Moves Forward to Develop Next Generation Nuclear Energy  

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

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.

39

Generating the Option of a Two-Stage Nuclear Renaissance  

Science Journals Connector (OSTI)

...capacity of waste repositories for decommissioning waste in the second half of the century will...is returned to the manufacturer for decommissioning and disposal. Because fuel handling is avoided at the...International Forum, A Technology Roadmap for Generation IV Nuclear Energy Systems...

Robin W. Grimes; William J. Nuttall

2010-08-13T23:59:59.000Z

40

COMPUTATIONS OF NUCLEAR RESPONSE FUNCTIONS WITH MACK-IV M. A. Abdou and Y. Gohar  

E-Print Network [OSTI]

on The Technology of Controlled Nuclear Fusion May 9-11f 1978 Santa Fer NM UofGAUAUSQOE ARGONNE NATIONAL LABORATORY OF NUCLEAR RESPONSE FUNCTIONS WITH MACK-IV M. A. Abdou and Y. Gohar APPLIED PHYSICS DIVISION, ARGONNECOMPUTATIONS OF NUCLEAR RESPONSE FUNCTIONS WITH MACK-IV M. A. Abdou and Y. Gohar Ttm ttpait * i

Abdou, Mohamed

Note: This page contains sample records for the topic "generation iv nuclear" 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 power eyed to generate industrial heat  

Science Journals Connector (OSTI)

Nuclear power eyed to generate industrial heat ... The American Nuclear Society has called for "an aggresssive national policy aimed at demonstrating specific capabilities and providing incentives for the application of nuclear power to meeting industrial energy needs." ...

1983-10-24T23:59:59.000Z

42

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...

43

A Project Management and Systems Engineering Structure for a Generation IV Very High Temperature Reactor  

SciTech Connect (OSTI)

The Very High Temperature Reactor (VHTR) will be an advanced, very high temperature (approximately 1000o C. coolant outlet temperature), gas cooled nuclear reactor and is the nearest term of six Generation IV reactor technologies for nuclear assisted hydrogen production. In 2001, the Generation IV International Forum (GIF), a ten nation international forum working together with the Department of Energys (DOE) Nuclear Energy Research Advisory Committee (NERAC), agreed to proceed with the development of a technology roadmap and identified the next generation of nuclear reactor systems for producing new sources of power. Since a new reactor has not been licensed in the United States since the 1970s, the risks are too large for a single utility to assume in the development of an unprecedented Generation IV reactor. The government must sponsor and invest in the research to resolve major first of a kind (FOAK) issues through a full-scale demonstration prior to industry implementation. DOEs primary mission for the VHTR is to demonstrate nuclear reactor assisted cogeneration of electricity and hydrogen while meeting the Generation IV goals for safety, sustainability, proliferation resistance and physical security and economics. The successful deployment of the VHTR as a demonstration project will aid in restarting the now atrophied U.S. nuclear power industry infrastructure. It is envisioned that VHTR project participants will include DOE Laboratories, industry partners such as designers, constructors, manufacturers, utilities, and Generation IV international countries. To effectively mange R&D, engineering, procurement, construction, and operation for this multi-organizational and technologically complex project, systems engineering will be used extensively to ensure delivery of the final product. Although the VHTR is an unprecedented FOAK system, the R&D, when assessed using the Office of Science and Technology Gate Model, falls primarily in the 3rd - Exploratory Development, 4th Advanced Development, and 5th- Engineering Development stages of maturity rather than in the basic and viability stages. Therefore the R&D must be controlled and project driven from the top down to address specific issues of feasibility, proof of design or support of engineering. The design evolution must be through the systems approach including an iterative process of high-level requirements definition, engineering to focus R&D to verify feasibility, requirements development and conceptual design, R&D to verify design and refine detailed requirements for final detailed design. This paper will define a framework for project management and application of systems engineering at the Idaho National Engineering and Environmental Laboratory (INEEL). The VHTR Project includes an overall reactor design and construction activity and four major supporting activities: fuel development and qualification, materials selection and qualification, NRC licensing and regulatory support, and the hydrogen production plant.

Ed Gorski; Dennis Harrell; Finis Southworth

2004-09-01T23:59:59.000Z

44

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

45

U.S. Nuclear Generation of Electricity  

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

U.S. Nuclear Generation and Generating Capacity Data Released: September 26, 2014 Data for: July 2014 Next Release: October 2014 Year Capacity and Generation by State and Reactor...

46

Status of advanced fuel candidates for Sodium Fast Reactor within the Generation IV International Forum  

SciTech Connect (OSTI)

The main challenge for fuels for future Sodium Fast Reactor systems is the development and qualification of a nuclear fuel sub-assembly which meets the Generation IV International Forum goals. The Advanced Fuel project investigates high burn-up minor actinide bearing fuels as well as claddings and wrappers to withstand high neutron doses and temperatures. The R&D outcome of national and collaborative programs has been collected and shared between the AF project members in order to review the capability of sub-assembly material and fuel candidates, to identify the issues and select the viable options. Based on historical experience and knowledge, both oxide and metal fuels emerge as primary options to meet the performance and the reliability goals of Generation IV SFR systems. There is a significant positive experience on carbide fuels but major issues remain to be overcome: strong in-pile swelling, atmosphere required for fabrication as well as Pu and Am losses. The irradiation performance database for nitride fuels is limited with longer term R&D activities still required. The promising core material candidates are Ferritic/Martensitic (F/M) and Oxide Dispersed Strengthened (ODS) steels.

F. Delage; J. Carmack; C. B. Lee; T. Mizuno; M. Pelletier; J. Somers

2013-10-01T23:59:59.000Z

47

"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

48

THE BIRTH OF NUCLEAR-GENERATED ELECTRICITY  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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 National Nuclear Security Administration's Neutron Generator...  

Energy Savers [EERE]

National Nuclear Security Administration's Neutron Generator Activities OAS-L-14-11 August 2014 U.S. Department of Energy Office of Inspector General Office of Audits and...

50

Fostering the Next Generation of Nuclear Energy Technology |...  

Office of Environmental Management (EM)

Fostering the Next Generation of Nuclear Energy Technology Fostering the Next Generation of Nuclear Energy Technology September 29, 2014 - 11:06am Addthis Fostering the Next...

51

Fusionfission hybrids for nuclear waste transmutation: A synergistic step between Gen-IV fission and fusion reactors  

Science Journals Connector (OSTI)

Energy demand and GDP per capita are strongly correlated, while public concern over the role of energy in climate change is growing. Nuclear power plants produce 16% of world electricity demands without greenhouse gases. Generation-IV advanced nuclear energy systems are being designed to be safe and economical. Minimizing the handling and storage of nuclear waste is important. NIF and ITER are bringing sustainable fusion energy closer, but a significant gap in fusion technology development remains. Fusionfission hybrids could be a synergistic step to a pure fusion economy and act as a technology bridge. We discuss how a pulsed power-driven Z-pinch hybrid system producing only 20MW of fusion yield can drive a sub-critical transuranic blanket that transmutes 1280kg of actinide wastes per year and produces 3000MW. These results are applicable to other inertial and magnetic fusion energy systems. A hybrid system could be introduced somewhat sooner because of the modest fusion yield requirements and can provide both a safe alternative to fast reactors for nuclear waste transmutation and a maturation path for fusion technology. The development and demonstration of advanced materials that withstand high-temperature, high-irradiation environments is a fundamental technology issue that is common to both fusionfission hybrids and Generation-IV reactors.

T.A. Mehlhorn; B.B. Cipiti; C.L. Olson; G.E. Rochau

2008-01-01T23:59:59.000Z

52

Fusion-fission hybrids for nuclear waste transmutation : a synergistic step between Gen-IV fission and fusion reactors.  

SciTech Connect (OSTI)

Energy demand and GDP per capita are strongly correlated, while public concern over the role of energy in climate change is growing. Nuclear power plants produce 16% of world electricity demands without greenhouse gases. Generation-IV advanced nuclear energy systems are being designed to be safe and economical. Minimizing the handling and storage of nuclear waste is important. NIF and ITER are bringing sustainable fusion energy closer, but a significant gap in fusion technology development remains. Fusion-fission hybrids could be a synergistic step to a pure fusion economy and act as a technology bridge. We discuss how a pulsed power-driven Z-pinch hybrid system producing only 20 MW of fusion yield can drive a sub-critical transuranic blanket that transmutes 1280 kg of actinide wastes per year and produces 3000 MW. These results are applicable to other inertial and magnetic fusion energy systems. A hybrid system could be introduced somewhat sooner because of the modest fusion yield requirements and can provide both a safe alternative to fast reactors for nuclear waste transmutation and a maturation path for fusion technology. The development and demonstration of advanced materials that withstand high-temperature, high-irradiation environments is a fundamental technology issue that is common to both fusion-fission hybrids and Generation-IV reactors.

Olson, Craig Lee; Mehlhorn, Thomas Alan; Cipiti, Benjamin B.; Rochau, Gary Eugene

2007-09-01T23:59:59.000Z

53

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

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

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

54

Electric generating prospects for nuclear power  

Science Journals Connector (OSTI)

Most of the nuclear power plants in the U.S. today are of the light-water variety. In many parts of the U.S. these plants are competitive with plants burning coal, but the electricity that they generate will be more costly in the future as uranium supplies ...

Manson Benedict

1970-07-01T23:59:59.000Z

55

Nuclear theory for high-energy nuclear reactions of biomedical relevance  

Science Journals Connector (OSTI)

......Presentations Nuclear theory for high-energy nuclear reactions of biomedical relevance...Nuclear Data Needs for Generation IV Nuclear Energy Systems, April 5-7, 2005...2005. Nuclear theory for high-energy nuclear reactions of biomedical relevance......

A. J. Koning; M. C. Duijvestijn

2007-08-01T23:59:59.000Z

56

World Net Nuclear Electric Power Generation, 1980-2007 - Datasets...  

Open Energy Info (EERE)

U.S. Energy Information ... World Net Nuclear Electric ... Dataset Activity Stream World Net Nuclear Electric Power Generation, 1980-2007 International data showing world net...

57

Microstructural Characterization of Next Generation Nuclear Graphites  

SciTech Connect (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

58

Future Trends in Nuclear Power Generation [and Discussion  

Science Journals Connector (OSTI)

...Future Trends in Nuclear Power Generation [and Discussion...the Calder Hall reactors were ordered...building and operating nuclear power stations...situations, a high nuclear share of new capacity...1980s. The fast reactor, prototypes of...

1974-01-01T23:59:59.000Z

59

Suez SNC-Lavalin Nuclear to replace US steam generator  

Science Journals Connector (OSTI)

SNC-Lavalin Nuclear (USA) has signed a contract with Xcel Energy to replace the Unit #2 steam generators at the Prairie Island Nuclear Generating Plant (PINGP) in Welch, Minnesota.

2010-01-01T23:59:59.000Z

60

TABLE 1. Nuclear Reactor, State, Type, Net Capacity, Generation...  

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

TABLE 1. Nuclear Reactor, State, Type, Net Capacity, Generation, and Capacity Factor " "PlantReactor Name","Generator ID","State","Type","2009 Summer Capacity"," 2010 Annual...

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

Climate Change, Nuclear Power and Nuclear  

E-Print Network [OSTI]

Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters Rob Goldston MIT IAP biomass wind hydro coal CCS coal nat gas CCS nat gas nuclear Gen IV nuclear Gen III nuclear Gen II 5-1 Electricity Generation: CCS and Nuclear Power Technology Options Available Global Electricity Generation WRE

62

validation and Enhancement of Computational Fluid Dynamics and Heat Transfer Predictive Capabilities for Generation IV Reactor Systems  

SciTech Connect (OSTI)

Nationwide, the demand for electricity due to population and industrial growth is on the rise. However, climate change and air quality issues raise serious questions about the wisdom of addressing these shortages through the construction of additional fossil fueled power plants. In 1997, the President's Committee of Advisors on Science and Technology Energy Research and Development Panel determined that restoring a viable nuclear energy option was essential and that the DOE should implement a R&D effort to address principal obstacles to achieving this option. This work has addressed the need for improved thermal/fluid analysis capabilities, through the use of computational fluid dynamics, which are necessary to support the design of generation IV gas-cooled and supercritical water reactors.

Robert E. Spall; Barton Smith; Thomas Hauser

2008-12-08T23:59:59.000Z

63

Nuclear Power Generating Facilities (Maine) | Department of Energy  

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

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

64

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

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

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

65

NNSA Launches Next Generation Safeguards Initiative | National Nuclear  

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

66

Power generation from nuclear reactors in aerospace applications  

SciTech Connect (OSTI)

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

67

Water generator replaces bottled water in nuclear power plant  

Science Journals Connector (OSTI)

WaterPure International Incorporated of Doylestown, Pennsylvania, USA, has announced that it has placed its atmospheric water generator (AWG) inside a selected nuclear power plant.

2007-01-01T23:59:59.000Z

68

Energy Department Invests $60 Million to Train Next Generation Nuclear  

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

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

69

Energy Department Invests $60 Million to Train Next Generation Nuclear  

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

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

70

R. Shane Johnson, Associate Director Office of Advanced Nuclear Research  

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

Advanced Nuclear Research Advanced Nuclear Research September 30, 2002 Generation IV International Forum Generation IV International Forum Presentation to the Nuclear Energy Research Advisory Committee Office of Nuclear Energy, Science and Technology Generation IV International Forum Generation IV International Forum 6 Government-sanctioned organization working together to plan the future of nuclear energy * Chartered in July 2002 * Conduct joint R&D on next-generation nuclear energy systems * Voluntary member participation in specific projects 6 Observer Organizations * OECD-NEA * IAEA * Euratom South Korea U.S.A. Argentina Brazil Canada France Japan South Africa United Kingdom Switzerland Office of Nuclear Energy, Science and Technology

71

Advanced ceramic materials for next-generation nuclear applications  

Science Journals Connector (OSTI)

The nuclear industry is at the eye of a 'perfect storm' with fuel oil and natural gas prices near record highs, worldwide energy demands increasing at an alarming rate, and increased concerns about greenhouse gas (GHG) emissions that have caused many to look negatively at long-term use of fossil fuels. This convergence of factors has led to a growing interest in revitalization of the nuclear power industry within the United States and across the globe. Many are surprised to learn that nuclear power provides approximately 20% of the electrical power in the US and approximately 16% of the world-wide electric power. With the above factors in mind, world-wide over 130 new reactor projects are being considered with approximately 25 new permit applications in the US. Materials have long played a very important role in the nuclear industry with applications throughout the entire fuel cycle; from fuel fabrication to waste stabilization. As the international community begins to look at advanced reactor systems and fuel cycles that minimize waste and increase proliferation resistance, materials will play an even larger role. Many of the advanced reactor concepts being evaluated operate at high-temperature requiring the use of durable, heat-resistant materials. Advanced metallic and ceramic fuels are being investigated for a variety of Generation IV reactor concepts. These include the traditional TRISO-coated particles, advanced alloy fuels for 'deep-burn' applications, as well as advanced inert-matrix fuels. In order to minimize wastes and legacy materials, a number of fuel reprocessing operations are being investigated. Advanced materials continue to provide a vital contribution in 'closing the fuel cycle' by stabilization of associated low-level and high-level wastes in highly durable cements, ceramics, and glasses. Beyond this fission energy application, fusion energy will demand advanced materials capable of withstanding the extreme environments of high-temperature plasma systems. Fusion reactors will likely depend on lithium-based ceramics to produce tritium that fuels the fusion plasma, while high-temperature alloys or ceramics will contain and control the hot plasma. All the while, alloys, ceramics, and ceramic-related processes continue to find applications in the management of wastes and byproducts produced by these processes.

John Marra

2011-01-01T23:59:59.000Z

72

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...

73

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"...

74

Uncertainty Quantification in the Reliability and Risk Assessment of Generation IV Reactors: Final Scientific/Technical Report  

SciTech Connect (OSTI)

The project entitled, Uncertainty Quantification in the Reliability and Risk Assessment of Generation IV Reactors, was conducted as a DOE NERI project collaboration between Texas A&M University and The Ohio State University between March 2006 and June 2009. The overall goal of the proposed project was to develop practical approaches and tools by which dynamic reliability and risk assessment techniques can be used to augment the uncertainty quantification process in probabilistic risk assessment (PRA) methods and PRA applications for Generation IV reactors. This report is the Final Scientific/Technical Report summarizing the project.

Vierow, Karen; Aldemir, Tunc

2009-09-10T23:59:59.000Z

75

Training the Next Generation of Nuclear Energy Leaders | Department of  

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

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

76

Training the Next Generation of Nuclear Energy Leaders | Department of  

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

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

77

Validation of Nuclear Criticality Safety Software and 27 energy group ENDF/B-IV cross sections  

SciTech Connect (OSTI)

The validation documented in this report is based on calculations that were executed during June through August 1992, and was completed in June 1993. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Martin Marietta Nuclear Criticality Safety Software. The first portion of the document outlines basic information in regard to validation of NCSS using ENDF/B-IV 27-group cross sections on the IBM 3090 at ORNL. A basic discussion of the NCSS system is provided, some discussion on the validation database and validation in general. Then follows a detailed description of the statistical analysis which was applied. The results of this validation indicate that the NCSS software may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant. When the validation results are treated as a single group, there is 95% confidence that 99.9% of future calculations of similar critical systems will have a calculated K{sub eff} > 0.9616. Based on this result the Portsmouth Nuclear Criticality Safety Department has adopted the calculational acceptance criteria that a k{sub eff} + 2{sigma} {le} 0.95 is safety subcritical. The validation of NCSS on the IBM 3090 at ORNL was extended to include NCSS on the IBM 3090 at K-25.

Lee, B.L. Jr.

1994-08-01T23:59:59.000Z

78

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network [OSTI]

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...

Yeon, Jaeheum 1981-

2012-12-11T23:59:59.000Z

79

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

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

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

80

Managing Model Data Introduced Uncertainties in Simulator Predictions for Generation IV Systems via Optimum Experimental Design  

SciTech Connect (OSTI)

An optimization technique has been developed to select optimized experimental design specifications to produce data specifically designed to be assimilated to optimize a given reactor concept. Data from the optimized experiment is assimilated to generate posteriori uncertainties on the reactor concepts core attributes from which the design responses are computed. The reactor concept is then optimized with the new data to realize cost savings by reducing margin. The optimization problem iterates until an optimal experiment is found to maximize the savings. A new generation of innovative nuclear reactor designs, in particular fast neutron spectrum recycle reactors, are being considered for the application of closing the nuclear fuel cycle in the future. Safe and economical design of these reactors will require uncertainty reduction in basic nuclear data which are input to the reactor design. These data uncertainty propagate to design responses which in turn require the reactor designer to incorporate additional safety margin into the design, which often increases the cost of the reactor. Therefore basic nuclear data needs to be improved and this is accomplished through experimentation. Considering the high cost of nuclear experiments, it is desired to have an optimized experiment which will provide the data needed for uncertainty reduction such that a reactor design concept can meet its target accuracies or to allow savings to be realized by reducing the margin required due to uncertainty propagated from basic nuclear data. However, this optimization is coupled to the reactor design itself because with improved data the reactor concept can be re-optimized itself. It is thus desired to find the experiment that gives the best optimized reactor design. Methods are first established to model both the reactor concept and the experiment and to efficiently propagate the basic nuclear data uncertainty through these models to outputs. The representativity of the experiment to the design concept is quantitatively determined. A technique is then established to assimilate this data and produce posteriori uncertainties on key attributes and responses of the design concept. Several experiment perturbations based on engineering judgment are used to demonstrate these methods and also serve as an initial generation of the optimization problem. Finally, an optimization technique is developed which will simultaneously arrive at an optimized experiment to produce an optimized reactor design. Solution of this problem is made possible by the use of the simulated annealing algorithm for solution of optimization problems. The optimization examined in this work is based on maximizing the reactor cost savings associated with the modified design made possible by using the design margin gained through reduced basic nuclear data uncertainties. Cost values for experiment design specifications and reactor design specifications are established and used to compute a total savings by comparing the posteriori reactor cost to the a priori cost plus the cost of the experiment. The optimized solution arrives at a maximized cost savings.

Paul J. Turinsky; Hany S.Abdel-Khalik; Tracy E. Stover

2011-03-31T23:59:59.000Z

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


81

The Next Generation Nuclear Plant (NGNP) Project  

SciTech Connect (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 DOEs 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

82

Fourth Generation Nuclear Weapons: Military effectiveness and collateral effects  

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 charged jets and forged fragments, enhanced prompt radiation effects, reduced collateral damage and residual radioactivity, etc.

Gsponer, A

2005-01-01T23:59:59.000Z

83

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:

84

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

85

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

86

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

87

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

SciTech Connect (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

88

Methane generation at Grand Gulf Nuclear Station  

SciTech Connect (OSTI)

The methane generation at Grand Gulf has been brought to light twice. The initial event occurred in February 1990 and the second in December 1993. Both events involved the receipt of a cask at Barnwell Waste Management Facility that when opened indicated a gas escaping. The gas was subsequently sampled and indicated a percentage of explosive gas. Both events involved powdered resin and indicated that the generation was from a bacterial attack of the organic materials (cellulose in the powdered resin mixture). The first event occurred and was believed to be isolated in a particular waste stream. The situation was handled and a biocide was found to be effective in treatment of liners until severe cross contamination of another waste stream occurred. This allowed the shipment of a liner that was required to be sampled for explosive gases. The biocide used by GGNS was allowed reintroduction into the floor drains and this allowed the buildup of immunity of the bacterial population to this particular biocide. The approval of a new biocide has currently allowed GGNS to treat liners and ship them offsite.

Carver, M.L. [Entergy Operations, Inc., Grand Gulf Nuclear Station, Port Gibson, MS (United States)

1995-09-01T23:59:59.000Z

89

Roadmap to NRC Approval of Ceramic Matrix Composites in Generation IV Reactors  

SciTech Connect (OSTI)

This report provides an initial roadmap to obtain Nuclear Regulatory Commission (NRC) approval for using these material systems in a nuclear application. The possible paths taken to achieving NRC approval are necessarily subject to change as this is an on-going process that shifts as more data and a clearer understanding of the nuclear regulations are gathered.

M. G. Jenkins; E. Lara-Curzio; W. Windes

2006-05-01T23:59:59.000Z

90

Generating the Option of a Two-Stage Nuclear Renaissance  

Science Journals Connector (OSTI)

...be refueled while remaining online (LWRs have...distributed fission gas bubbles and oxides, and...long-term storage. Life extension. This...16) (which have remaining design work to be...the fueled-for-life core, that is, a nuclear...island (the turbine and generator...

Robin W. Grimes; William J. Nuttall

2010-08-13T23:59:59.000Z

91

Hydrogen Production from the Next Generation Nuclear Plant  

SciTech Connect (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

92

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect (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 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

93

Salt disposal of heat-generating nuclear waste.  

SciTech Connect (OSTI)

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

94

Innovative systems for sustainable nuclear energy generation and waste management  

Science Journals Connector (OSTI)

The limited amount of fossil resources, the impact of green-house gas emissions on the world climate, the rising demand of primary energy projected to 2050, lead to a potentially critical situation for the world energy supply. The need for alternative (to fossil energies) massive energy production is evaluated to 10 Gtoe. The potential of Nuclear Energy generation at the level of 5 Gtoe is examined. Such a sustainable production can only be met by a breeder reactor fleet for which a deployment scenario is described with the associated constraints. Waste management is discussed in connection with different nuclear energy development scenarios according to the point in time when breeder reactors are started. At the world level, it appears that the optimal handling of today's wastes rests on an early decision to develop tomorrow's breeder reactors.

Jm Loiseaux; S David

2006-01-01T23:59:59.000Z

95

Alternative similarity renormalization group generators in nuclear structure calculations  

E-Print Network [OSTI]

The similarity renormalization group (SRG) has been successfully applied to soften interactions for ab initio nuclear calculations. In almost all practical applications in nuclear physics, an SRG generator with the kinetic energy operator is used. With this choice, a fast convergence of many-body calculations can be achieved, but at the same time substantial three-body interactions are induced even if one starts from a purely two-nucleon (NN) Hamiltonian. Three-nucleon (3N) interactions can be handled by modern many-body methods. However, it has been observed that when including initial chiral 3N forces in the Hamiltonian, the SRG transformations induce a non-negligible four-nucleon interaction that cannot be currently included in the calculations for technical reasons. Consequently, it is essential to investigate alternative SRG generators that might suppress the induction of many-body forces while at the same time might preserve the good convergence. In this work we test two alternative generators with oper...

Dicaire, Nuiok M; Navratil, Petr

2014-01-01T23:59:59.000Z

96

Alternative similarity renormalization group generators in nuclear structure calculations  

Science Journals Connector (OSTI)

The similarity renormalization group (SRG) has been successfully applied to soften interactions for ab initio nuclear calculations. In almost all practical applications in nuclear physics, an SRG generator with the kinetic energy operator is used. With this choice, a fast convergence of many-body calculations can be achieved, but at the same time substantial three-body interactions are induced even if one starts from a purely two-nucleon (NN) Hamiltonian. Three-nucleon (3N) interactions can be handled by modern many-body methods. However, it has been observed that when including initial chiral 3N forces in the Hamiltonian, the SRG transformations induce a non-negligible four-nucleon interaction that cannot be currently included in the calculations for technical reasons. Consequently, it is essential to investigate alternative SRG generators that might suppress the induction of many-body forces while at the same time might preserve the good convergence. In this work we test two alternative generators with operators of block structure in the harmonic oscillator basis. In the no-core shell model calculations for 3H, 4He, and 6Li with chiral NN force, we demonstrate that their performances appear quite promising.

Nuiok M. Dicaire; Conor Omand; Petr Navrtil

2014-09-04T23:59:59.000Z

97

Alternative similarity renormalization group generators in nuclear structure calculations  

E-Print Network [OSTI]

The similarity renormalization group (SRG) has been successfully applied to soften interactions for ab initio nuclear calculations. In almost all practical applications in nuclear physics, an SRG generator with the kinetic energy operator is used. With this choice, a fast convergence of many-body calculations can be achieved, but at the same time substantial three-body interactions are induced even if one starts from a purely two-nucleon (NN) Hamiltonian. Three-nucleon (3N) interactions can be handled by modern many-body methods. However, it has been observed that when including initial chiral 3N forces in the Hamiltonian, the SRG transformations induce a non-negligible four-nucleon interaction that cannot be currently included in the calculations for technical reasons. Consequently, it is essential to investigate alternative SRG generators that might suppress the induction of many-body forces while at the same time might preserve the good convergence. In this work we test two alternative generators with operators of block structure in the harmonic oscillator basis. In the no-core shell model calculations for 3H, 4He and 6Li with chiral NN force, we demonstrate that their performances appear quite promising.

Nuiok M. Dicaire; Conor Omand; Petr Navratil

2014-08-22T23:59:59.000Z

98

Removal of deposited copper from nuclear steam generators  

SciTech Connect (OSTI)

A review of the copper-removal process implemented during the cleaning of the NPD nuclear steam generator in Ontario revealed that major shortcomings in the process were depletion of the strong ammonia solution and relatively poor copper removal. Tests have shown that the concentration of the ammonia solution can be preserved close to its initial value, and high concentrations of complexed copper obtained, by sparging the ammonia solution with oxygen recirculating through a gas recirculation loop. Using recirculating oxygen for sparging at ambient air temperature, approximately 11 g/l of copper were dissolved by 100 g/l ammonia solution while the gaseous ammonia content of the recirculating gas remained well below the lower flammability limit. The corrosion rates of mild steel and commonly used nuclear steam generator tube materials in oxygenated ammonia solution were less than 30 mil/yr and no intergranular attack of samples was observed during tests. A second technique studied for the removal of copper is to ammoniate the spent iron-removal solvent to approximately pH 9.5 and sparge with recirculating oxygen. Complexed ferric iron in the spent iron-removal solvent was found to be the major oxidizing agent for metallic copper. The ferric iron can be derived from oxidation of dissolved ferrous iron to the ferric state or from dissolved oxides of iron directly. To extract copper from the secondary sides of nuclear steam generators, strong ammonia solution sparged with recirculating oxygen is recommended as the first stage, while ammoniated spent iron-removal solvent sparged with recirculating oxygen may be used to remove the copper freshly exposed during the removal of iron.

McSweeney, P.

1982-05-01T23:59:59.000Z

99

Generating Unstructured Nuclear Reactor Core Meshes in Parallel  

Science Journals Connector (OSTI)

Abstract Recent advances in supercomputers and parallel solver techniques have enabled users to run large simulations problems using millions of processors. Techniques for multiphysics nuclear reactor core simulations are under active development in several countries. Most of these techniques require large unstructured meshes that can be hard to generate in a standalone desktop computers because of high memory requirements, limited processing power, and other complexities. We have previously reported on a hierarchical lattice-based approach for generating reactor core meshes. Here, we describe efforts to exploit coarse-grained parallelism during reactor assembly and reactor core mesh generation processes. We highlight several reactor core examples including a very high temperature reactor, a full-core model of the Korean MONJU reactor, a pressurized water reactor core, the fast reactor Experimental Breeder Reactor-II core with a XX09 assembly, and an advanced breeder test reactor core. The times required to generate large mesh models, along with speedups obtained from running these problems in parallel, are reported. A graphical user interface to the tools described here has also been developed.

Rajeev Jain; Timothy J. Tautges

2014-01-01T23:59:59.000Z

100

NNSA Administrator Addresses the Next Generation of Nuclear Security Professionals: Part 1  

ScienceCinema (OSTI)

Administrator Thomas DAgostino of the National Nuclear Security Administration addressed the next generation of nuclear security professionals during the opening session of todays 2009 Department of Energy (DOE) Computational Science Graduate Fellowship Annual Conference. Administrator DAgostino discussed NNSAs role in implementing President Obamas nuclear security agenda and encouraged the computing science fellows to consider careers in nuclear security.

Thomas D'Agostino

2010-09-01T23:59:59.000Z

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101

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

SciTech Connect (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

102

NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER  

SciTech Connect (OSTI)

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

103

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect (OSTI)

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

104

Event generator for nuclear collisions at intermediate energies  

Science Journals Connector (OSTI)

An event generator, HIPSE (heavy-ion phase-space exploration), dedicated to the description of nuclear collisions in the intermediate energy range is presented. Based on the sudden approximation and on geometrical hypothesis, it can conveniently simulate heavy-ion interactions at all impact parameters and thus can constitute a valuable tool for the understanding of processes such as neck emission or multifragmentation in peripheral or?and central collisions. After a detailed description of the ingredients of the model, first comparisons with experimental data collected by the INDRA Collaboration are shown. Special emphasis is put on the kinematical characteristics of fragments and light particles observed at all impact parameters for Xe+Sn reactions at 25 and 50MeV?nucleon and Ni+Ni at 82MeV?nucleon.

Denis Lacroix; Aymeric Van Lauwe; Dominique Durand

2004-05-12T23:59:59.000Z

105

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

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

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.

106

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

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

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.

107

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

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

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.

108

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential  

SciTech Connect (OSTI)

This volume of the Nonproliferation Alternative Systems Assessment Program (NASAP) report provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest.

Not Available

1980-06-01T23:59:59.000Z

109

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

SciTech Connect (OSTI)

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

110

Applications of Extraction Chromatography in the Development of Radionuclide Generator Systems for Nuclear Medicine  

Science Journals Connector (OSTI)

Applications of Extraction Chromatography in the Development of Radionuclide Generator Systems for Nuclear Medicine ... Chemistry Division, Argonne National Laboratory, Argonne, Illinois 60439 ...

Mark L. Dietz; E. Philip Horwitz

2000-08-12T23:59:59.000Z

111

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

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

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)

112

The Evolution of Nuclear Power Generation for Mars  

Science Journals Connector (OSTI)

Among the available energy alternatives nuclear power offers important advantages and in many cases is the only viable alternative given actual operation conditions on Mars. We know that nuclear is the most co...

Liviu Popa-Simil

2009-01-01T23:59:59.000Z

113

Generating the Option of a Two-Stage Nuclear Renaissance  

Science Journals Connector (OSTI)

...system using battery energy storage. The widespread...intermittent renewable energies and might restore the cost benefits of nuclear energy in the 2030s. Nuclear...plant and appropriate grid infrastructure, economic considerations...

Robin W. Grimes; William J. Nuttall

2010-08-13T23:59:59.000Z

114

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

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

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

115

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

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

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

116

Why the IBEW supports expanding nuclear power generation in the USA  

Science Journals Connector (OSTI)

The International Brotherhood of Electrical Workers (IBEW) represents workers, many who work in the utility and power generation industries. The IBEW has been and continues to be a vocal supporter of the expansion of nuclear power generation in the USA. Five years ago, there was a general expectation that nuclear capacity would expand greatly. It did not, and in part the absence of more new nuclear construction is the natural outcome of a misguided energy market regulation system. We close with a set of priorities for rebuilding the energy regulatory scheme that would benefit our members and ratepayers and would, at the same time, lead to and require an expansion of nuclear power. The article describes the state of nuclear power in the USA today, the IBEW's role in the utility industry and nuclear power generation; the IBEW's priorities for the US energy market and why those priorities lead the IBEW to call for the expansion of nuclear power in the USA.

William Bill Riley

2013-01-01T23:59:59.000Z

117

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

SciTech Connect (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

118

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...

119

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...

120

Monthly Nuclear Utility Generation by State and Reactor, 2004  

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

194,1095428,1211897,1374523,1347985,1262403,1340639,1347577,1387346,15503218 "Arkansas Nuclear One 1",840,,639800,598183,639443,403029,346066,489260,629320,629209,610996,637714,619...

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

Monthly Nuclear Utility Generation by State and Reactor, 2008  

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

2889,1359120,1330655,1334646,1369191,1335231,1264610,725939,1043730,14168091 "Arkansas Nuclear One 1",842,,640210,332640,639812,611739,611473,610763,626182,625966,612739,514485,-32...

122

Monthly Nuclear Utility Generation by State and Reactor, 2005  

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

049398,1385659,1329546,1365357,1364550,1315097,826104,724688,842506,13689571 "Arkansas Nuclear One 1",836,,642446,580408,640573,616442,635753,607660,621404,622382,608955,74815,-336...

123

Monthly Nuclear Utility Generation by State and Reactor, 2003  

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

0183,1370443,1333879,1333266,1232981,970683,1026829,1008188,1033852,14689416 "Arkansas Nuclear One 1",840,,638732,576736,637898,614123,622312,611199,598045,569278,582588,637484,278...

124

Monthly Nuclear Utility Generation by State and Reactor, 2007  

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

2613,979493,1330868,1372259,1363174,1328057,1383098,1348837,1393879,15486102 "Arkansas Nuclear One 1",843,,642145,579996,631611,425625,233279,610804,629284,623738,610379,634652,620...

125

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

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

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

126

Generating the Option of a Two-Stage Nuclear Renaissance  

Science Journals Connector (OSTI)

...in the 2030s. Nuclear power could also be widely used for desalination, another efficient way to use surplus power in an electricity...country of origin would have access to the spent fuel. The economics of small and fueled-for-life reactors versus large reactors...

Robin W. Grimes; William J. Nuttall

2010-08-13T23:59:59.000Z

127

Program generator for experiments in nuclear magnetic resonance  

SciTech Connect (OSTI)

This paper describes a programmable pulse-train generator for experiments in relaxation analysis. The generator produces up to eight pulses, whose durations and spacings can be varied from 0.5 sec to 160 sec in 0.1-usec steps. The maximum number of pulse-train repetitions is 160. An individual program provides a Carr-Percell train. A clock pulse for the measuring and recording devices is established after any pulse of a compiled program or after the last 180 degree pulse in a Carr train. The generator is implemented by integrated circuits of series 155.

Babkin, A.F.; Kuznetsov, V.K.; Makarenko, V.L.; Rusanov, A.V.

1986-07-01T23:59:59.000Z

128

Structural materials issues for the next generation fission reactors  

Science Journals Connector (OSTI)

Generation-IV reactor design concepts envisioned thus far cater to ... longer lasting, proliferation-resistant, and economically viable nuclear power plants. The foremost consideration in the successful developme...

I. Chant; K. L. Murty

2010-09-01T23:59:59.000Z

129

Next Generation Nuclear Plant Project 2009 Status Report  

SciTech Connect (OSTI)

The mission of the NGNP Project is to broaden the environmental and economic benefits of nuclear energy technology to the United States and other economies by demonstrating its applicability to market sectors not served by light water reactors (LWRs). Those markets typically use fossil fuels to fulfill their energy needs, and high temperature gas-cooled reactors (HTGRs) like the NGNP can reduce this dependence and the resulting carbon footprint.

Larry Demick; Jim Kinsey; Keith Perry; Dave Petti

2010-05-01T23:59:59.000Z

130

Next Generation CANDU Technology: Competitive Design for the Nuclear Renaissance  

SciTech Connect (OSTI)

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

131

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

SciTech Connect (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

132

Nuclear theory for high-energy nuclear reactions of biomedical relevance  

Science Journals Connector (OSTI)

......as MCNP(X), activation and reactor codes rely on a complete description of a nuclear reaction in a data file, and not...of the International Workshop on Nuclear Data Needs for Generation IV Nuclear Energy Systems, April 5-7......

A. J. Koning; M. C. Duijvestijn

2007-08-01T23:59:59.000Z

133

Bruce Nuclear Generating Station B rapid cooldown test and validation of simulation model  

SciTech Connect (OSTI)

The SOPHT code was assessed against Bruce Nuclear Generating Station B commissioning data from a heat transport system rapid cooldown. It was found that (a) under a rapid upstream depressurization, the steam relief valves, like orifices, had a lower discharge coefficient than the corresponding steadystate value and (b) the flashing of water in the steam generators during depressurization causes the at-power boiling heat transfer correlations to overpredict the steam generator heat transfer.

Chang, Y.F.; Langan, M.D.; Sermer, P.; Watson, P.C.

1985-09-01T23:59:59.000Z

134

New Materials for NGNP/Gen IV  

SciTech Connect (OSTI)

The bounding conditions were briefly summarized for the Next Generation Nuclear Plant (NGNP) that is the leading candidate in the Department of Energy Generation IV reactor program. Metallic materials essential to the successful development and proof of concept for the NGNP were identified. The literature bearing on the materials technology for high-temperature gas-cooled reactors was reviewed with emphasis on the needs identified for the NGNP. Several materials were identified for a more thorough study of their databases and behavioral features relative to the requirements ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NH.

Robert W. Swindeman; Douglas L. Marriott

2009-12-18T23:59:59.000Z

135

Informing the next nuclear generation - how does the Ginna plant branch do it?  

SciTech Connect (OSTI)

Most of us are familiar with the latest advertising phrase, ``Our children are our future.`` This phrase has been used in so many instances - from concerns about waste, Social Security, and the federal deficit to drug abuse and violence. One more area can be added to the list and advertised nuclear power. Since the establishment of the Ginna plant branch (GPB) in 1992, our target audience has been the next nuclear generation (our children), but our vehicle for dissemination has been the current generation (the adults). Have you ever thought about how often your opinions affect the children you come in contact with? One of GPB`s goals is to provide as much information as possible to teachers, neighbors, and civic organizations of our community so that there is a nuclear future that can be carried on by the next generation.

Saavedra, A. [Rochester Gas and Electric Corporation, Ontario, NY (United States)

1995-12-31T23:59:59.000Z

136

F POWER MEASUREMENT FOR GENERATION IV SODIUM FAST R. COULON, S. NORMAND, M. MICHEL, L. BARBOT, T. DOMENECH,  

E-Print Network [OSTI]

.F-84500 Bollène, France. ABSTRACT The Phénix nuclear power plant has been a French Sodium Fast Reactor. Drift between the measured ex-core neutron flux and the instant released thermal power (fission rate the research of power tagging agents. Then, simulation study has been done to evaluate measurability using high

Boyer, Edmond

137

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

138

The B61-based "Robust Nuclear Earth Penetrator:" Clever retrofit or headway towards fourth-generation nuclear weapons?  

E-Print Network [OSTI]

It is scientifically and technically possible to build an earth penetrating device that could bury a B61-7 warhead 30 meters into concrete, or 150 meters into earth, before detonating it. The device (based on knowledge and technology that is available since 50 years) would however by large and cumbersome. Better penetrator materials, components able to withstand larger stresses, higher impact velocities, and/or high-explosive driven penetration aids, can only marginally improve the device. It is conclude that the robust nuclear earth penetrator (RNEP) program may be as much motivated by the development of new technology directly applicable to next generation nuclear weapons, and by the political necessity to periodically reasses the role and utility of nuclear weapons, then by the perceived military need of a weapon able to destroy deeply buried targets.

Gsponer, A

2005-01-01T23:59:59.000Z

139

The costs of generating electricity and the competitiveness of nuclear power  

Science Journals Connector (OSTI)

Abstract This paper provides an analysis on the costs of generating electricity from nuclear and fossil sources (coal and natural gas) based on the most recent technical data available in literature. The aim is to discuss the competitiveness of nuclear power in a liberalized market context by considering the impact on the generating costs of the main factors affecting the viability of the nuclear option. Particular attention will be devoted to study the variability of the generating costs regarding the level of risk perceived by investors through a sensitivity analysis of the generating costs with respect to the cost of capital and the debt fraction of initial investment. The impact of environment policies is also considered by including a tax on carbon emissions. The analysis reveals that nuclear power could have ample potentiality also in a competitive market, particularly if the level of risk perceived by the investors keeps standing low. For low values of the cost of capital, nuclear power seems to be the most viable solution. Uncertainty about environmental policies and unpredictability of carbon emissions costs might offer further margins of competitiveness.

Carlo Mari

2014-01-01T23:59:59.000Z

140

D.McNew/GettyIMaGes San Onofre Nuclear Generating Station, California.  

E-Print Network [OSTI]

D.McNew/GettyIMaGes San Onofre Nuclear Generating Station, California. CORRESPONDENCE Checklist be supplied by solar power plants covering about 36,000 square kilometres of land in the desert southwest,theycanberampedupquickly.Annualinstallationofwind- energy capacity in the United States has quadrupled from Counterpoint Not wanted, not needed J. Doyne

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

Decommissioning of Large Components as an Example of Steam Generator from PWR Nuclear Power Plants  

SciTech Connect (OSTI)

This paper describes the procedure for the qualification of large components (Steam Generators) as an IP-2 package, the ship transport abroad to Sweden and the external treatment of this components to disburden the Nuclear Power Plant from this task, to assure an accelerated the deconstruction phase and to minimize the amount of waste. In conclusion: The transport of large components to an external treatment facility is linked with many advantages for a Nuclear Power Plant: - Disburden of the Nuclear Power Plant from the treatment of such components, - no timely influence on the deconstruction phase of the power reactor and therewith an accelerated deconstruction phase and - minimization of the waste to be returned and therewith less demand of required waste storage capacity. (authors)

Beverungen, M. [GNS Gesellschaft fur Nuklear-Service mbH, Hollestrabe 7A (Germany)

2008-07-01T23:59:59.000Z

142

Power conversion system design for supercritical carbon dioxide cooled indirect cycle nuclear reactors  

E-Print Network [OSTI]

The supercritical carbon dioxide (S-CO?) cycle is a promising advanced power conversion cycle which couples nicely to many Generation IV nuclear reactors. This work investigates the power conversion system design and ...

Gibbs, Jonathan Paul

2008-01-01T23:59:59.000Z

143

A Roadmap to Deploy New Nuclear Power Plants in the United States...  

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

will also serve as input for a longer term and broader scope Generation IV Nuclear Technology Roadmap being prepared by DOE, as discussed below. In order to meet this...

144

Survey of insulation used in nuclear power plants and the potential for debris generation. Technical report  

SciTech Connect (OSTI)

In support of Unresolved Safety Issue A-43, 'Containment Emergency Sump Performance,' 11 nuclear power plants representative of different U.S. reactor manufacturers and architect-engineers were surveyed to identify and document the types and amounts of insulation used, location within containment, components insulated, material characteristics, and methods of installation and attachment. A preliminary assessment was made of the potential effects of insulation debris generated as the result of a loss-of-coolant accident (pipe break).

Reyer, R.; Gahan, E.; Riddington, J.W.

1981-10-01T23:59:59.000Z

145

The Future of Nuclear Energy: Facts and Fiction Chapter IV: Energy from Breeder Reactors and from Fusion?  

E-Print Network [OSTI]

The accumulated knowledge and the prospects for commercial energy production from fission breeder and fusion reactors are analyzed in this report. The publicly available data from past experimental breeder reactors indicate that a large number of unsolved technological problems exist and that the amount of "created" fissile material, either from the U238 --> Pu239 or from the Th232 --> U233 cycle, is still far below the breeder requirements and optimistic theoretical expectations. Thus huge efforts, including many basic research questions with an uncertain outcome, are needed before a large commercial breeder prototype can be designed. Even if such efforts are undertaken by the technologically most advanced countries, it will take several decades before such a prototype can be constructed. We conclude therefore, that ideas about near-future commercial fission breeder reactors are nothing but wishful thinking. We further conclude that, no matter how far into the future we may look, nuclear fusion as an energy ...

Dittmar, Michael

2009-01-01T23:59:59.000Z

146

EnvWiltonIV-EIS  

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

Wilton IV Wind Energy Center Draft EIS Wilton IV Wind Energy Center Draft EIS Western Area Power Administration (Western) prepared this draft environmental impact statement (DEIS) in response to a request from NextEra Energy Resources, LLC (NextEra), on behalf of its subsidiary Wilton Wind IV, LLC (Wilton IV), to interconnect its proposed Wilton IV Wind Energy Center (Project) to Western's power transmission system. The proposed Project is a wind turbine generation facility located in Burleigh County, North Dakota. It would consist of 62 wind turbine generators, with a total nameplate capacity of approximately 99 MW. NextEra has also requested that the existing interconnection contracts for the Wilton Wind I Energy Center (formerly known as Burleigh County Wind), Wilton Wind II Energy Center, and the Baldwin Wind Energy Center (together called the Existing Projects) be modified to lift their administrative 50 average annual MW production caps.

147

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

148

Composite Materials under Extreme Radiation and Temperature Environments of the Next Generation Nuclear Reactors  

SciTech Connect (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

149

Nuclear Energy Research Advisory Subcommittee Meeting  

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

to the Minutes for the to the Minutes for the Nuclear Energy Research Advisory Subcommittee Meeting September 30 to October 1, 2002 MEMORANDUM To: Chairman, Nuclear Energy Research Advisory Committee (NERAC) From: Thomas B. Cochran, Member of NERAC Date: October 16, 2002 Subject: "A Technology Roadmap on Generation IV Nuclear Energy Systems," a report of the NERAC Subcommittee on Generation IV Technology Planning Please include these additional remarks in your transmittal of the subject report to DOE's Office of Nuclear Energy, Science and Technology. Perhaps the greatest security threat to the United States today, and of paramount concern to American citizens since September 11, 2001, is that nuclear weapon- usable materials will be stolen, seized, or secretly diverted from nuclear facilities and then used by

150

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

SciTech Connect (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

151

Financial valuation of investments in future power generation technologies: nuclear fusion and CCS in an emissions trading system  

Science Journals Connector (OSTI)

This paper outlines a model approach for the financial valuation of future power generation technologies, such as nuclear fusion or carbon capture and storage (CCS) under an emissions trading regime. Since on imp...

Heinz Eckart Klingelhfer; Peter Kurz

2011-12-01T23:59:59.000Z

152

CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor  

E-Print Network [OSTI]

Very High Temperature Rector (VHTR) had been designated as one of those promising reactors for the Next Generation (IV) Nuclear Plant (NGNP). For a prismatic core VHTR, one of the most crucial design considerations is the bypass flow and crossflow...

Wang, Huhu 1985-

2012-12-13T23:59:59.000Z

153

Automatic code generation enables nuclear gradient computations for fully internally contracted multireference theory  

E-Print Network [OSTI]

Analytical nuclear gradients for fully internally contracted complete active space second-order perturbation theory (CASPT2) are reported. This implementation has been realized by an automated code generator that can handle spin-free formulas for the CASPT2 energy and its derivatives with respect to variations of molecular orbitals and reference coefficients. The underlying complete active space self-consistent field and the so-called Z-vector equations are solved using density fitting. With full internal contraction the size of first-order wave functions scales polynomially with the number of active orbitals. The CASPT2 gradient program and the code generator are both publicly available. This work enables the CASPT2 geometry optimization of molecules as complex as those investigated by respective single-point calculations.

MacLeod, Matthew K

2015-01-01T23:59:59.000Z

154

Update report on the performance of 400 megawatt and larger nuclear and coal-fired generating units. Performance through 1977  

SciTech Connect (OSTI)

Forty-seven nuclear generating units and 125 coal-fired generating plants that have had at least one full year of commercial operation are covered in this report. Their performances are evaluated using the capacity factor, availability factor, equivalent availability, and forced outage rate. The data are arranged by state and utility. (DLC)

None

1981-01-01T23:59:59.000Z

155

Method and apparatus for steam mixing a nuclear fueled electricity generation system  

DOE Patents [OSTI]

A method and apparatus for improving the efficiency and performance of a nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a micro-jet high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life. An additional advantage is the reduction in erosion/corrosion of secondary system components including turbine blades and diaphragms. The gas turbine generator used in the instant invention can also replace or augment existing peak or emergency power needs. Another benefit of the instant invention is the extension of plant life and the reduction of downtime due to refueling.

Tsiklauri, Georgi V. (Richland, WA); Durst, Bruce M. (Kennewick, WA)

1996-01-01T23:59:59.000Z

156

Nuclear Energy Research Advisory Committee Meeting  

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

10/03/02 10/03/02 Appendix A to the Minutes for the Nuclear Energy Research Advisory Committee Meeting September 30 to October 1, 2002 Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report October 3, 2002 The Roadmap Context 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

157

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

SciTech Connect (OSTI)

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

158

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report  

SciTech Connect (OSTI)

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

John Saurwein

2011-07-15T23:59:59.000Z

159

January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

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

160

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

SciTech Connect (OSTI)

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

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

2009-01-01T23:59:59.000Z

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

A critical study on Kennedys Cost-Benefit-Analysis New nuclear power generation in the UK.  

E-Print Network [OSTI]

?? The demand for energy is forever growing. The technology of extracting power from uranium through nuclear facilities is rather old. Core melting, nuclear bombs, (more)

Strng, Jonathan

2011-01-01T23:59:59.000Z

162

Considerations Associated with Reactor Technology Selection for the Next Generation Nuclear Plant Project  

SciTech Connect (OSTI)

At the inception of the Next Generation Nuclear Plant Project and during predecessor activities, alternative reactor technologies have been evaluated to determine the technology that best fulfills the functional and performance requirements of the targeted energy applications and market. Unlike the case of electric power generation where the reactor performance is primarily expressed in terms of economics, the targeted energy applications involve industrial applications that have specific needs in terms of acceptable heat transport fluids and the associated thermodynamic conditions. Hence, to be of interest to these industrial energy applications, the alternative reactor technologies are weighed in terms of the reactor coolant/heat transport fluid, achievable reactor outlet temperature, and practicality of operations to achieve the very high reliability demands associated with the petrochemical, petroleum, metals and related industries. These evaluations have concluded that the high temperature gas-cooled reactor (HTGR) can uniquely provide the required ranges of energy needs for these target applications, do so with promising economics, and can be commercialized with reasonable development risk in the time frames of current industry interest i.e., within the next 10-15 years.

L.E. Demick

2010-09-01T23:59:59.000Z

163

Argonne Chemical Sciences & Engineering - Nuclear & Environmental Processes  

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

Nuclear Technology Nuclear Technology * Members * Contact * Publications * Overview * Pyrochemical Process Research * Closing the Nuclear Fuel Cycle Nuclear & Environmental Processes Home Pyrochemical Process Research Our department is also interested in pyrochemical process research and its development and demonstration for the U.S. Department of Energy's Generation IV (GEN IV) and Advanced Fuel Cycle Initiative (AFCI) programs. Through these initiatives, we are working to contribute to the development of next generation of advanced nuclear systems, to meet future needs for safe, economic, proliferation-resistant and environmentally responsible fuel cycles and energy production. Argonne research efforts in this area include: developing a novel electrochemical method for the conversion of spent oxide nuclear fuel to its metallic form for subsequent treatment by pyrochemical methods

164

From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the Worlds First nuclear power plant  

Science Journals Connector (OSTI)

Successful commissioning in the 1954 of the Worlds First nuclear power plant constructed at the Institute for Physics ... center for training Soviet and foreign specialists on nuclear power plants, the personnel...

V. I. Rachkov; S. G. Kalyakin; O. F. Kukharchuk; Yu. I. Orlov

2014-05-01T23:59:59.000Z

165

High Energy Utilization, Co-Generation Nuclear power Plants With Static Energy Conversion  

SciTech Connect (OSTI)

In addition to being cost effective, very small nuclear power plants with static energy conversion could meet the needs and the energy mix in underdeveloped countries and remote communities, which may include electricity, residential and industrial space heating, seawater desalination, and/or high temperature process heat or steam for industrial uses. These plants are also an attractive option in naval, marine, and undersea applications, when the absence of a sound signature is highly desirable. An Analysis is performed of Gas Cooled Reactor (CGR) and Liquid Metal Cooled Reactor (LMR), very small nuclear power plants with static energy conversion, using a combination of options. These include Alkali Metal Thermal-to-Electric Converters (AMTECs) and both single segment and segmented thermoelectric converters. The total energy utilization of these plants exceeds 88%. It includes the fraction of the reactor's thermal power converted into electricity and delivered to the Grid at 6.6 kVA and those used for residential and industrial space heating at {approx}370 K, seawater desalination at 400 K, and/or high temperature process heat or steam at {approx}850 K. In addition to its inherently high reliability, modularity, low maintenance and redundancy, static energy conversion used in the present study could deliver electricity to the Grid at a net efficiency of 29.5%. A LMR plant delivers 2-3 times the fraction of the reactor thermal power converted into electricity in a GCR plant, but could not provide for both seawater desalination and high temperature process heat/steam concurrently, which is possible in GCR plants. The fraction of the reactor's thermal power used for non-electrical power generation in a GCR plant is {approx} 10 - 15% higher than in a LMR plant. (authors)

El-Genk, Mohamed S.; Tournier, Jean-Michel P. [Institute for Space and Nuclear Power Studies and Chemical and Nuclear Engineering Department, The University of New Mexico, Albuquerque, NM (United States)

2002-07-01T23:59:59.000Z

166

PHYSICAL REVIEW A 90, 063412 (2014) Effect of nuclear vibration on high-order-harmonic generation of aligned H2  

E-Print Network [OSTI]

PHYSICAL REVIEW A 90, 063412 (2014) Effect of nuclear vibration on high-order-harmonic generation of aligned H2 + molecules Dmitry A. Telnov,1,* John Heslar,2, and Shih-I Chu2,3, 1 Department of Physics, St. Petersburg State University, St. Petersburg 198504, Russia 2 Department of Physics, Center for Quantum

Chu, Shih-I

167

Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)  

SciTech Connect (OSTI)

The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. 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 Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2Cr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

168

Property exempt from taxation: nuclear generation facility property: K.S.A. 79-230 (Kansas)  

Broader source: Energy.gov [DOE]

This 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. A...

169

Monitoring attosecond dynamics of coherent electron-nuclear wave packets by molecular high-order-harmonic generation  

SciTech Connect (OSTI)

A pump-probe scheme for preparing and monitoring electron-nuclear motion in a dissociative coherent electron-nuclear wave packet is explored from numerical solutions of a non-Born-Oppenheimer time-dependent Schroedinger equation. A mid-ir intense few-cycle probe pulse is used to generate molecular high-order-harmonic generation (MHOHG) from a coherent superposition of two or more dissociative coherent electronic-nuclear wave packets, prepared by a femtosecond uv pump pulse. Varying the time delay between the intense ir probe pulse and the uv pump pulse by a few hundreds of attoseconds, the MHOHG signal intensity is shown to vary by orders of magnitude, thus showing the high sensitivity to electron-nuclear dynamics in coherent electron-nuclear wave packets. We relate this high sensitivity of MHOHG spectra to opposing electron velocities (fluxes) in the electron wave packets of the recombining (recolliding) ionized electron and of the bound electron in the initial coherent superposition of two electronic states.

Bredtmann, Timm [Laboratoire de Chimie Theorique, Faculte des Sciences, Universite de Sherbrooke, Sherbrooke, Quebec, J1K 2R1 (Canada); Institut fuer Chemie und Biochemie, Freie Universitaet Berlin, Takustrasse 3, D-14195 Berlin (Germany); Chelkowski, Szczepan; Bandrauk, Andre D. [Laboratoire de Chimie Theorique, Faculte des Sciences, Universite de Sherbrooke, Sherbrooke, Quebec, J1K 2R1 (Canada)

2011-08-15T23:59:59.000Z

170

Nuclear Energy Program  

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

September 30, 2002 September 30, 2002 NERAC Fall 2002 Meeting Office of Nuclear Energy, Science and Technology Major Program Developments Major Program Developments 6 June 2002: Department selects three U.S. electric utilities (Dominion Energy, Entergy, and Exelon) to participate in joint government/ industry projects to demonstrate NRC's Early Site Permit (ESP) process and seek NRC approval by mid-decade 6 July 2002: Secretary Abraham announces transition of management of the Idaho National Engineering and Environmental Laboratory to Nuclear Energy and revitalization of its nuclear R&D mission 6 September 2002: Generation IV International Forum reaches agreement on six advanced reactor and fuel cycle technologies for joint development Office of Nuclear Energy, Science and Technology

171

STARLIB: A NEXT-GENERATION REACTION-RATE LIBRARY FOR NUCLEAR ASTROPHYSICS  

SciTech Connect (OSTI)

STARLIB is a next-generation, all-purpose nuclear reaction-rate library. For the first time, this library provides the rate probability density at all temperature grid points for convenient implementation in models of stellar phenomena. The recommended rate and its associated uncertainties are also included. Currently, uncertainties are absent from all other rate libraries, and, although estimates have been attempted in previous evaluations and compilations, these are generally not based on rigorous statistical definitions. A common standard for deriving uncertainties is clearly warranted. STARLIB represents a first step in addressing this deficiency by providing a tabular, up-to-date database that supplies not only the rate and its uncertainty but also its distribution. Because a majority of rates are lognormally distributed, this allows the construction of rate probability densities from the columns of STARLIB. This structure is based on a recently suggested Monte Carlo method to calculate reaction rates, where uncertainties are rigorously defined. In STARLIB, experimental rates are supplemented with: (1) theoretical TALYS rates for reactions for which no experimental input is available, and (2) laboratory and theoretical weak rates. STARLIB includes all types of reactions of astrophysical interest to Z = 83, such as (p, {gamma}), (p, {alpha}), ({alpha}, n), and corresponding reverse rates. Strong rates account for thermal target excitations. Here, we summarize our Monte Carlo formalism, introduce the library, compare methods of correcting rates for stellar environments, and discuss how to implement our library in Monte Carlo nucleosynthesis studies. We also present a method for accessing STARLIB on the Internet and outline updated Monte Carlo-based rates.

Sallaska, A. L. [National Institute of Standards and Technology, Gaithersburg, MD 20899-8462 (United States); Iliadis, C.; Champange, A. E. [University of North Carolina at Chapel Hill, Chapel Hill, NC 27599-3255 (United States); Goriely, S. [Institut d'Astronomie et d'Astrophysique, Universite Libre de Bruxelles, C.P. 226, B-1050 Brussels (Belgium); Starrfield, S.; Timmes, F. X., E-mail: anne.sallaska@nist.gov [Arizona State University, Tempe, AZ 85287-1504 (United States)

2013-07-15T23:59:59.000Z

172

Economic and environmental analysis of power generation expansion in Japan considering Fukushima nuclear accident using a multi-objective optimization model  

Science Journals Connector (OSTI)

Nuclear power has long been a cornerstone of energy policy in Japan, a country with few natural resources of its own. However, following on from the Fukushima Daiichi accident, the Japanese government is now in the throes of reviewing its nuclear power policy. On the other hand, under continuing policies of greenhouse gas reduction, it is crucial to consider scenarios for the country to realize an economic, safe and low-carbon power generation system in the future. Therefore, in the present study, economic and environmental analysis was conducted on the power generation system in Japan up to 2030 using a multi-objective optimization methodology. Four nuclear power scenarios were proposed in light of the nuclear accident: (1) actively anti-nuclear; (2) passively negative towards nuclear; (3) conservative towards nuclear; and (4) active expansion of nuclear power. The obtained capacity mix, generation mix, generation cost, CO2 emissions and fuel consumption of the scenarios were compared and analysed. The obtained results show that the large scale penetration of PV (photovoltaic), wind and LNG (Liquefied Natural Gas) power can partly replace nuclear power, however, removing nuclear power entirely was not suggested from economic, environmental and energy security perspectives.

Qi Zhang; Benjamin C. Mclellan; Tetsuo Tezuka; Keiichi N. Ishihara

2012-01-01T23:59:59.000Z

173

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...

Hackemack, Michael Wayne

2013-04-15T23:59:59.000Z

174

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

E-Print Network [OSTI]

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

Burns, Jonathan

2012-10-02T23:59:59.000Z

175

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]

On other hand, accidents at nuclear facilities could nott ed expos ur e from a nuclear accident which would warrantresulting from accidents at nuclear facilities. Average

Nero, A.V.

2010-01-01T23:59:59.000Z

176

Analysis of ground motions at San Onofre Nuclear Generating Station April 9, 1968  

Science Journals Connector (OSTI)

...concrete mat foundation. The turbine generator, the plant auxiliary...transferred to the secondary turbine steam system by the steam generators...has resulted in a bothersome maintenance problem which requires replacement...self-sustMned Wineharger wind-generator to charge the batteries...

G. W. Housner; P. J. West; C. G. Johnson

177

The state and prospects of coal and nuclear power generation in Russia (review)  

Science Journals Connector (OSTI)

Data on the modern state and development trends for coal and nuclear power engineering in Russia up to 2030 are generalized. It is emphasized that from the viewpoint of strategy, coal and uranium fuel will be ...

V. V. Salomatov

2009-12-01T23:59:59.000Z

178

Multi-Objective Optimization Analysis of Post-Fukushima Power Generation Planning in Japan with Considering Nuclear Powers Risk Cost  

Science Journals Connector (OSTI)

In the present study, multi-objective optimization analysis was conducted on the post-Fukushima power generation planning in Japan up to 2030 from economic and environmental perspectives with considering nuclear

Qi Zhang; Tetsuo Tezuka; Keiichi Ishihara

2013-01-01T23:59:59.000Z

179

Restoration of the graphite memory of a reactor in the third power-generating unit of the Leningrad nuclear power plant  

Science Journals Connector (OSTI)

The restoration of the graphite masonry of cell 52-16 in the reactor in the third power-generating unit of the Leningrad nuclear power plant is described. The process reduces to moving...

V. I. Lebedev; Yu. V. Garusov; M. A. Pavlov; A. N. Peunov; E. P. Kozlov

1999-11-01T23:59:59.000Z

180

Michelangelo Network recommendations on nuclear hydrogen production  

Science Journals Connector (OSTI)

The Michelangelo Network (MICANET) was started within the 5th EURATOM Framework Programme (FP5) with the objective to elaborate a general European R&D strategy for the further development of the nuclear industry in the short, medium, and long term. To broaden the application range of nuclear power beyond dedicated electricity generation, the network proposed an orientation for future EURATOM R&D programmes including new industrial aspects of nuclear energy, such as combined heat and power and, particularly, the production of hydrogen or other fuels as a link to CO2-free energy sources. MICANET is acting as the European counterpart and partner to the Generation IV International Forum. The MICANET project ended in November 2005. Goals achieved related to nuclear hydrogen production and other non-electrical nuclear applications are outlined in this paper.

Karl Verfondern; Werner Von Lensa

2006-01-01T23:59:59.000Z

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

Acoustic monitoring and signature analysis in nuclear and fossil energy generation  

Science Journals Connector (OSTI)

Acoustic monitoring and analysis in nuclear and fossil energy plants has been accompanied by transducer development for the hot environment. The Nuclear Regulatory Commission requires acoustic monitoring systems on nuclear reactors for detecting potential failures. Accelerometers are attached at critical points and their output is automatically analyzed to give warnings of loose parts or excessive vibration. In addition to providing a warning the system can monitor arrival time to be used for fault location. For use as a potential boiling detector of breeder reactors the acoustic signature of the sodium coolant boiling has been compared with background noise level. High temperature sodium?immersible microphones and waveguides for smooth energy transfer were developed for this investigation. High?temperature acoustic sensors have been used in a coal gasification plant. The presence of solids in a steam?char line has been automatically determined using passive monitoring of relative sound intensities of different frequency bands.

Henry B. Karplus

1982-01-01T23:59:59.000Z

182

A comparison of delayed radiobiological effects of depleted-uranium munitions versus fourth-generation nuclear weapons  

E-Print Network [OSTI]

It is shown that the radiological burden due to the battle-field use of circa 400 tons of depleted-uranium munitions in Iraq (and of about 40 tons in Yugoslavia) is comparable to that arising from the hypothetical battle-field use of more than 600 kt (respectively 60 kt) of high-explosive equivalent pure-fusion fourth-generation nuclear weapons. Despite the limited knowledge openly available on existing and future nuclear weapons, there is sufficient published information on their physical principles and radiological effects to make such a comparison. In fact, it is shown that this comparison can be made with very simple and convincing arguments so that the main technical conclusions of the paper are undisputable -- although it would be worthwhile to supplement the hand calculations presented in the paper by more detailed computer simulations in order to consolidate the conclusions and refute any possible objections.

Gsponer, A; Vitale, B; Gsponer, Andre; Hurni, Jean-Pierre; Vitale, Bruno

2002-01-01T23:59:59.000Z

183

Electronic constant current and current pulse signal generator for nuclear instrumentation testing  

DOE Patents [OSTI]

Circuitry is described for testing the ability of an intermediate range nuclear instrument to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on. 1 figures.

Brown, R.A.

1994-04-19T23:59:59.000Z

184

Electronic constant current and current pulse signal generator for nuclear instrumentation testing  

DOE Patents [OSTI]

Circuitry for testing the ability of an intermediate range nuclear instrut to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on.

Brown, Roger A. (Amsterdam, NY)

1994-01-01T23:59:59.000Z

185

Carbon emission and mitigation cost comparisons between fossil fuel, nuclear and renewable energy resources for electricity generation  

Science Journals Connector (OSTI)

A study was conducted to compare the electricity generation costs of a number of current commercial technologies with technologies expected to become commercially available within the coming decade or so. The amount of greenhouse gas emissions resulting per kWh of electricity generated were evaluated. A range of fossil fuel alternatives (with and without physical carbon sequestration), were compared with the baseline case of a pulverised coal, steam cycle power plant. Nuclear, hydro, wind, bioenergy and solar generating plants were also evaluated. The objectives were to assess the comparative costs of mitigation per tonne of carbon emissions avoided, and to estimate the total amount of carbon mitigation that could result from the global electricity sector by 2010 and 2020 as a result of fuel switching, carbon dioxide sequestration and the greater uptake of renewable energy. Most technologies showed potential to reduce both generating costs and carbon emission avoidance by 2020 with the exception of solar power and carbon dioxide sequestration. The global electricity industry has potential to reduce its carbon emissions by over 15% by 2020 together with cost saving benefits compared with existing generation.

Ralph E.H. Sims; Hans-Holger Rogner; Ken Gregory

2003-01-01T23:59:59.000Z

186

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

E-Print Network [OSTI]

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

Nero, A.V.

2010-01-01T23:59:59.000Z

187

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]

in U. S. Conunercial Nuclear Power Plants", Report WASH-Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"

Nero, A.V.

2010-01-01T23:59:59.000Z

188

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

Nero, A.V.

2010-01-01T23:59:59.000Z

189

Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design  

SciTech Connect (OSTI)

Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design & performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program implementation as LANL moves forward into production and use of the SAVY-3000 will all be addressed. The SAVY-3000 is intended as a work horse package for the DOE complex as a vented storage container primarily for plutonium in solid form.

Stone, Timothy Amos [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

190

New technology for purging the steam generators of nuclear power plants  

SciTech Connect (OSTI)

A technology for removal of undissolved impurities from a horizontal steam generator using purge water is developed on the basis of a theoretical analysis. A purge with a maximal flow rate is drawn off from the zone with the highest accumulation of sludge in the lower part of the steam generator after the main circulation pump of the corresponding loop is shut off and the temperatures of the heat transfer medium at the inlet and outlet of the steam generator have equilibrated. An improved purge configuration is used for this technology; it employs shutoff and regulator valves, periodic purge lines separated by a cutoff fixture, and a D{sub y} 100 drain union as a connector for the periodic purge. Field tests show that the efficiency of this technology for sludge removal by purge water is several times that for the standard method.

Budko, I. O.; Kutdjusov, Yu. F.; Gorburov, V. I. [Scientific-Research Center for Energy Technology 'NICE Centrenergo' (Russian Federation); Rjasnyj, S. I. [JSC 'The All-Rissia Nuklear Power Engineering Research and Development Institute' (VNIIAM) (Russian Federation)

2011-07-15T23:59:59.000Z

191

The Transmutation of Nuclear Waste in the Two-Zone Subcritical System Driven by High- Intensity Neutron Generator - 12098  

SciTech Connect (OSTI)

The main problems of transmutation of high-level radioactive waste (minor actinides and long-lived fission products) are considered in our work. The range of radioactive waste of nuclear power is analyzed. The conditions under which the transmutation of radioactive waste will be most effective are analyzed too. The modeling results of a transmutation of the main radioactive isotopes are presented and discussed. The transmutation of minor actinides and long-lived fission products are modeled in our work (minor actinides - Np-237, Am-241, Am-242, Am-243, Cm-244, Cm-245; long-lived fission products - I-129, Tc-99). The two-zone subcritical system is calculated with help of different neutron-physical codes (MCNP, Scale, Montebarn, Origen). The ENDF/B-VI nuclear data library used in above calculations. Thus, radioactive wastes can be divided into two main groups that need to be transmuted. The minor actinides form the first group and the long-lived fission products form the second one. For the purpose of effective transmutation these isotopes must be extracted from the spent nuclear fuel with the help of either PUREX technology or pyrometallurgical technology. The two-zone reactor system with fast and thermal regions is more effective for nuclear waste transmutation than the one-zone reactor. Modeling results show that nearly all radioactive wastes can be transmuted in the two-zone subcritical system driven by a high-intensity neutron generator with the external neutron source strength of 1.10{sup 13} n/sec. Obviously, transmutation rate will increase with a rise of the external neutron source strength. From the results above we can also see that the initial loading of radioactive isotopes into the reactor system should exceed by mass those isotopes that are finally produced. (authors)

Babenko, V.O. [Bogolyubov Institute for Theoretical Physics, Metrolohichna str. 14-b, Kiev, 03680 (Ukraine); Gulik, V.I.; Pavlovych, V.M. [Institute for Nuclear Research, pr. Nauky 47, Kyiv, 03680 (Ukraine)

2012-07-01T23:59:59.000Z

192

Evaluation Metrics for Intermediate Heat Exchangers for Next Generation Nuclear Reactors  

SciTech Connect (OSTI)

The Department of Energy (DOE) is working with industry to develop a next generation, high-temperature gas-cooled reactor (HTGR) as a part of the effort to supply the United States with abundant, clean, and secure energy as initiated by the Energy Policy Act of 2005 (EPAct; Public Law 109-58,2005). The NGNP Project, led by the Idaho National Laboratory (INL), will demonstrate the ability of the HTGR to generate hydrogen, electricity, and/or high-quality process heat for a wide range of industrial applications.

Piyush Sabharwall; Eung Soo Kim; Nolan Anderson

2011-06-01T23:59:59.000Z

193

Fiscal year 1985 Department of Energy authorization (nuclear fission R and D and waste management). Volume IV. Hearings before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Eighth Congress, Second Session, February 7, 8, 9, 1984  

SciTech Connect (OSTI)

Volume IV of the DOE authorization hearings covers material relating to research and development on nuclear fission and on waste management during three days of testimony. The 29 witnesses included nuclear scientists in both the private and public sector, as well as specialists in energy policy, electric power, and the nuclear industry. Among the issues covered were the distribution of resources for nuclear research to ensure the development of innovative technology, problems within the nuclear industry, regulatory reform, the progress on spent fuel research and development, and funding for the light water reactor extended burnup program. Chairman Lloyd noted the problems associated with a 50% decline in federal funding during the Reagan administration. An appendix with supplemental questions and answers for the record follows the testimony.

Not Available

1984-01-01T23:59:59.000Z

194

Model of sludge behavior in nuclear plant steam generators. Final report  

SciTech Connect (OSTI)

The accumulation of large amounts of sludge in pressurized water reactor steam generators is thought to be a cause of accelerated corrosion by trace impurities which concentrate in such deposits. Based on fundamental principles, this study develops a mathematical model for predicting the behavior (e.g., deposition and reentrainment) of sludge in steam generators. The calculated sludge behavior shows good agreement with the limited amount of experimental data available. The results suggest that the continued accumulation of sludge on the tubesheet might be preventable, and that if it could be, the incoming sludge would be removed by blowdown. An analysis of the uncertainties in the model led to suggested priorities for further analytical and experimental work to gain a better understanding of sludge behavior. 29 refs., 12 figs., 15 tabs.

Beal, S.K.; Chen, J.H.

1986-06-01T23:59:59.000Z

195

Temperature and thermal stress distributions for the HFIR permanent reflector generated by nuclear heating  

SciTech Connect (OSTI)

The beryllium permanent reflector of the High Flux Isotope Reactor has the main functions for slowing down and reflecting the neutrons and housing the experimental facilities. The reflector is heated as a result of the nuclear reaction. Heat is removed mainly by the cooling water passing through the densely distributed coolant holes along the vertical or axial direction of the reflector. The reflector neutronic distribution and its heating rate are calculated by J.C. Gehin of the Oak Ridge National Laboratory by applying the Monte Carlo Code MCNP. The heat transfer boundary conditions along several reflector interfaces are estimated to remove additional heat from the reflector. The present paper is to report the calculation results of the temperature and the thermal stress distributions of the permanent reflector by applying the computer aided design code I-DEAS and the finite element code ABAQUS. The present calculation is to estimate the high stress areas as a result of the new beam tube cutouts along the horizontal mid-plane of the reflector of the recent reactor upgrade project. These high stresses were not able to be calculated in the preliminary design analysis in earlier 60`s. The heat transfer boundary conditions are used in this redesigned calculation. The material constants and the acceptance criteria for the allowable stresses are mainly based on that assumed in the preliminary design report.

Chang, S.J.

1998-04-01T23:59:59.000Z

196

Evaluation of the Effectiveness of a New Technology for Extraction of Insoluble Impurities from Nuclear Power Plant Steam Generators with Purge Water  

SciTech Connect (OSTI)

An experimental technology for the removal of insoluble impurities from a horizontal steam generator with purge water during planned shutdowns of the power generating unit is improved through a more representative determination of the concentration of impurities in the purge water ahead of the water cleanup facility and a more precise effective time for the duration of the purge process. Tests with the improved technique at power generating unit No. 1 of the Rostov Nuclear Power Plant show that the efficiency with which insoluble impurities are removed from the steam generator volume was more than two orders of magnitude greater than under the standard regulations.

Bud'ko, I. O. [JSC NIITsE 'Tsentrenergo' (Russian Federation)] [JSC NIITsE 'Tsentrenergo' (Russian Federation); Zhukov, A. G. [Rostov Nuclear Power Plant (Russian Federation)] [Rostov Nuclear Power Plant (Russian Federation)

2013-11-15T23:59:59.000Z

197

Nuclear power can reduce emissions and maintain a strong economy: Rating Australias optimal future electricity-generation mix by technologies and policies  

Science Journals Connector (OSTI)

Abstract Legal barriers currently prohibit nuclear power for electricity generation in Australia. For this reason, published future electricity scenarios aimed at policy makers for this country have not seriously considered a full mix of energy options. Here we addressed this deficiency by comparing the life-cycle sustainability of published scenarios using multi-criteria decision-making analysis, and modeling the optimized future electricity mix using a genetic algorithm. The published CSIRO e-future scenario under its default condition (excluding nuclear) has the largest aggregate negative environmental and economic outcomes (score=4.51 out of 8), followed by the Australian Energy Market Operators 100% renewable energy scenario (4.16) and the Greenpeace scenario (3.97). The e-future projection with maximum nuclear-power penetration allowed yields the lowest negative impacts (1.46). After modeling possible future electricity mixes including or excluding nuclear power, the weighted criteria recommended an optimized scenario mix where nuclear power generated >40% of total electricity. The life-cycle greenhouse-gas emissions of the optimization scenarios including nuclear power were nuclear power is an effective and logical option for the environmental and economic sustainability of a future electricity network in Australia.

Sanghyun Hong; Corey J.A. Bradshaw; Barry W. Brook

2014-01-01T23:59:59.000Z

198

Mountain View IV | Open Energy Information  

Open Energy Info (EERE)

IV IV Facility Mountain View IV Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner AES Wind Generation Developer AES Wind Generation Energy Purchaser Southern California Edison Co Location White Water CA Coordinates 33.95475187°, -116.7015839° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":33.95475187,"lon":-116.7015839,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

199

Maintaining a Technology-Neutral Approach to Hydrogen Production Process Development through Conceptual Design of the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

The Next Generation Nuclear Plant (NGNP) project was authorized in the Energy Policy Act of 2005 (EPAct), tasking the U.S. Department of Energy (DOE) with demonstrating High Temperature Gas-Cooled Reactor (HTGR) technology. The demonstration is to include the technical, licensing, operational, and commercial viability of HTGR technology for the production of electricity and hydrogen. The Nuclear Hydrogen Initiative (NHI), a component of the DOE Hydrogen Program managed by the Office of Nuclear Energy, is also investigating multiple approaches to cost effective hydrogen production from nuclear energy. The objective of NHI is development of the technology and information basis for a future decision on commercial viability. The initiatives are clearly intertwined. While the objectives of NGNP and NHI are generally consistent, NGNP has progressed to the project definition phase and the project plan has matured. Multiple process applications for the NGNP require process heat, electricity and hydrogen in varied combinations and sizes. Coupling these processes to the reactor in multiple configurations adds complexity to the design, licensing and demonstration of both the reactor and the hydrogen production process. Commercial viability of hydrogen production may depend on the specific application and heat transport configuration. A component test facility (CTF) is planned by the NGNP to support testing and demonstration of NGNP systems, including those for hydrogen production, in multiple configurations. Engineering-scale demonstrations in the CTF are expected to start in 2012 to support scheduled design and licensing activities leading to subsequent construction and operation. Engineering-scale demonstrations planned by NHI are expected to start at least two years later. Reconciliation of these schedules is recommended to successfully complete both initiatives. Hence, closer and earlier integration of hydrogen process development and heat transport systems is sensible. For integration purposes, an analysis comparing the design, cost and schedule impact of maintaining a technology neutral approach through conceptual design or making an early hydrogen process technology selection was performed. Early selection does not specifically eliminate a technology, but rather selects the first hydrogen technology for demonstration. A systems-engineering approach was taken to define decision-making criteria for selecting a hydrogen technology. The relative technical, cost and schedule risks of each approach were analyzed and risk mitigation strategies were recommended, including provisions to maintain close collaboration with the NHI. The results of these analyses are presented here.

Michael W. Patterson

2008-05-01T23:59:59.000Z

200

he students, faculty, and research staff of the MIT Department of Nuclear Science and Engineering (NSE) generate, control, and apply nuclear  

E-Print Network [OSTI]

T he students, faculty, and research staff of the MIT Department of Nuclear Science and Engineering and technology. Professor Richard K. Lester Head, Department of Nuclear Science & Engineering rklester contact Professor Richard K. Lester, Head Department of Nuclear Science & Engineering rklester

Polz, Martin

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201

On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers, Volumes 1, 2.  

SciTech Connect (OSTI)

The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001 ???????????????????????????????? September 2004. ???????????????????????????????· Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. ???????????????????????????????· Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. ???????????????????????????????· Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. ???????????????????????????????· Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. ???????????????????????????????· Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. ???????????????????????????????· Development and implementation of a new nonlinear and non-stationary signal processing method, called the Hilbert-Huang transform (HHT), for flaw detection and location. This is a more robust and adaptive approach compared to the wavelet transform

Upadhyaya, Belle R.; Hines, J. Wesley; Lu, Baofu; Huang, Xuedong; Penha, Rosani, L.; Perillo, Sergio, R.; Zhao, Ke

2005-06-03T23:59:59.000Z

202

On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers.  

SciTech Connect (OSTI)

The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001-September 2004. (1) Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. (2) Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. (3) Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. (4) Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. (5) Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. (6) Development and implementation of a new nonlinear and non-stationary signal processing method, called the Hilbert-Huang transform (HHT), for flaw detection and location. This is a more robust and adaptive approach compared to the wavelet transform. (7) Implementation of a moving-window technique in the time domain for detecting and quantifying flaw types in tubular structures. A window zooming technique was also developed for flaw location in tubes. (8) Theoretical study of elastic wave propagation (longitudinal and shear waves) in metallic flat plates and tubing with and without flaws. (9) Simulation of the Lamb wave propagation using the finite-element code ABAQUS. This enabled the verification of the experimental results. The research tasks included both analytical research and experimental studies. The experimental results helped to enhance the robustness of fault monitoring methods and to provide a systematic verification of the analytical results. The results of this research were disseminated in scientific meetings. A journal manuscript was submitted for publication. The new findings of this research have potential applications in aerospace and civil structures. The report contains a complete bibliography that was developed during the course of the project.

Belle R. Upadhyaya; J. Wesley Hines

2004-09-27T23:59:59.000Z

203

Monthly/Annual Energy Review - nuclear section  

Reports and Publications (EIA)

Monthly and latest annual statistics on nuclear electricity capacity, generation, and number of operable nuclear reactors.

2015-01-01T23:59:59.000Z

204

Secondary wastes and high explosive residues generated during production of main high explosive charges for nuclear weapons. Revision 1  

SciTech Connect (OSTI)

This study identifies the sources of high-explosive (HE) residues and hazardous and nonhazardous wastes generated during the production of the main HE charges for nuclear weapons, and estimates their quantities and characteristics. The results can be used as a basis for design of future handling and treatment systems for solid and liquid HE residues and wastes at any proposed new HE production facilities. This paper outlines a general methodology for documenting and estimating the volumes and characteristics of the solid and liquid HE residues and hazardous and nonhazardous wastes. To facilitate the estimating, we separated the HE main-charge production process into ten discrete unit operations and four support operations, and identified the corresponding solid and liquid HE residues and waste quantities. Four different annual HE main-charge production rates of 100, 500, 1000, and 2000 HE units/yr were assumed to develop the volume estimates and to establish the sensitivity of the estimates to HE production rates. The total solids (HE residues and hazardous and nonhazardous wastes) estimated range from 800 to 2800 ft{sup 3}/yr and vary uniformly with the assumed HE production rate. The total liquids estimated range from 73,000 to 1,448.000 gal/yr and also vary uniformly with the assumed production rate. Of the estimated solids, the hazardous wastes (e.g., electrical vehicle batteries and light tubes) were about 2% of the total volumes. The generation of solid HE residues varied uniformly with the HE production rates and ranged from about 20% of the total solids volume for the 100 HE units/yr case to about 60% for the 2000 units/yr case. The HE machining operations generated 60 to 80% of the total solid HE residues, depending on the assumed production rate, and were also the sources of the most concentrated HE residues.

Jardine, L.J.; McGee, J.T.

1995-01-01T23:59:59.000Z

205

Department of Energy Announces 24 Nuclear Energy Research Awards to U.S.  

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

4 Nuclear Energy Research Awards to 4 Nuclear Energy Research Awards to U.S. Universities Department of Energy Announces 24 Nuclear Energy Research Awards to U.S. Universities December 15, 2005 - 4:46pm Addthis $12 Million in Support to Be Provided for Innovative R&D Projects WASHINGTON, D.C. - The U.S. Department of Energy (DOE) today announced 24 research awards totaling $12 million over three years to U.S. universities to engage students and professors in DOE's advanced nuclear energy research and development programs, including the Advanced Fuel Cycle Initiative, Generation IV Nuclear Energy Systems Initiative and Nuclear Hydrogen Initiative. "These awards support the department's advanced nuclear technology development efforts and foster the education and training of the next generation of scientists and engineers needed to move this vital industry

206

Department of Energy Awards $5.7 Million to U.S. Universities for Nuclear  

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

7 Million to U.S. Universities for 7 Million to U.S. Universities for Nuclear Energy Research Department of Energy Awards $5.7 Million to U.S. Universities for Nuclear Energy Research February 2, 2007 - 10:15am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced it will award $5.7 million to nine universities for research grants under the Nuclear Energy Research Initiative (NERI). These grants are designed to engage U.S. university professors and students in advanced nuclear energy research and development (R&D), in an effort to strengthen and focus DOE's research for the Generation IV Nuclear Energy Systems Initiative and the Nuclear Hydrogen Initiative. "These awards demonstrate our commitment to pursuing nuclear research, and we are eager for our next generation of scientists and engineers to

207

Secondary wastes and high explosive residues generated during production of main high explosive charges for nuclear weapons  

SciTech Connect (OSTI)

This study identifies the sources of high-explosive (HE) residues and hazardous and nonhazardous wastes generated during the production of the main HE charges for nuclear weapons, and estimates their quantities and characteristics. The results can be used as a basis for design of future handling and treatment systems for solid and liquid HE residues and wastes at any proposed new HE production facilities. This paper outlines a general methodology for documenting and estimating the volumes and characteristics of the solid and liquid HE residues and hazardous and nonhazardous wastes. We prepared volume estimates by applying this method to actual past Pantex plant HE production operations. To facilitate the estimating, we separated the HE main-charge production process into ten discrete unit operations and four support operations, and identified the corresponding solid and liquid HE residues and waste quantities. Four different annual HE main-charge production rates of 100, 500, 1000, and 2000 HE units/yr were assumed to develop the volume estimates and to establish the sensitivity of the estimates to HE production rates. The total solids (HE residues and hazardous and nonhazardous wastes) estimated range from 800 to 2800 ft{sup 3}/yr and vary uniformly with the assumed HE production rate. The total liquids estimated range from 73,000 to 1,448,000 gal/yr and also vary uniformly with the assumed production rate.

Jardine, L.J.; McGee, J.T.

1994-02-01T23:59:59.000Z

208

Tennessee Nuclear Profile - Power Plants  

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

Tennessee nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

209

Minnesota Nuclear Profile - Power Plants  

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

Minnesota nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

210

Massachusetts Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

211

Kansas Nuclear Profile - Power Plants  

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

Kansas nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

212

Missouri Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

213

Nebraska Nuclear Profile - Power Plants  

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

Nebraska nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

214

Arizona Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

215

Georgia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

216

Texas Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

217

Wisconsin Nuclear Profile - Power Plants  

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

Wisconsin nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

218

Ohio Nuclear Profile - Power Plants  

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

Ohio nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

219

Alabama Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

220

Virginia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

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

Michigan Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

222

Iowa Nuclear Profile - Power Plants  

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

Iowa nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

223

Arkansas Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

224

Maryland Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

225

Vermont Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

226

Investing in the next generation: The Office of Nuclear Energy Issues Requests for Scholarship and Fellowship Applications.  

Broader source: Energy.gov [DOE]

Today, the Department of Energy's (DOE) Office of Nuclear Energy (NE) announced two new Requests for Applications (RFAs) for the Integrated University Program (IUP).

227

Solid radioactive waste management facility design for managing CANDU{sup R} 600 MW nuclear generating station re-tube/refurbishment Waste Streams  

SciTech Connect (OSTI)

The main design features of the re-tube canisters, waste handling equipment and waste containers designed by Atomic Energy of Canada Limited (AECL{sup R}) and implemented in support of the re-tube/refurbishment activities for Candu 600 MW nuclear generating stations are described in this paper. The re-tube/refurbishment waste characterization and the waste management principles, which form the basis of the design activities, are also briefly outlined. (authors)

Pontikakis, N.; Hopkins, J.; Scott, D.; Bajaj, V.; Nosella, L. [AECL, 2251 Speakman Drive, Mississauga, Ontario, L5K 1B2 (Canada)

2007-07-01T23:59:59.000Z

228

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]

EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSINGEmergency Planning for Nuclear Power Plants Determination ofproposed nuclear power plants . . . . . . . . . . . . .

Yen, W.W.S.

2010-01-01T23:59:59.000Z

229

* ^ -^. «*'*: IV: .<:.**  

Gasoline and Diesel Fuel Update (EIA)

* ^ -^. «*'*: IV: .<:.**,.,? '* -^^V; , *"'^"T-'^T * .^'^ **'*--'"-* *'*V-; "'^ v ^V ^^-^^;-'jl^'-^^i5^^v>^Ll-';.i»S-'^^^ * . '"* L"".'"-'?_,. -*'-_*:'?'. v>;': |: ,^% ;'. >' 4-.**;- *"-.''' * Lite -^ t.-^»!, m ". *Bfc' Table 8. Foreign Crude Oil and Natural Gas Liquids Reserve Interest for FRS Companies, 1983 and Percent Change from 1982 Crude Oil and Reserves Total OECD Foreign___Canada___Europe Africa___Mtdeast Other Eastern Hemisphere Other Western Hemisphere 1983 (million barrels) Total Crude and |GL

230

Reactor Physics Parametric and Depletion Studies in Support of TRISO Particle Fuel Specification for the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

Reactor physics calculations were initiated to answer several major questions related to the proposed TRISO-coated particle fuel that is to be used in the prismatic Very High Temperature Reactor (VHTR) or the Next Generation Nuclear Plant (NGNP). These preliminary design evaluation calculations help ensure that the upcoming fuel irradiation tests will test appropriate size and type of fuel particles for a future NGNP reactor design. Conclusions from these calculations are expected to confirm and suggest possible modifications to the current particle fuel parameters specified in the evolving Fuel Specification. Calculated results dispel the need for a binary fuel particle system, which is proposed in the General Atomics GT-MHR concept. The GT-MHR binary system is composed of both a fissile and fertile particle with 350- and 500- micron kernel diameters, respectively. For the NGNP reactor, a single fissile particle system (single UCO kernel size) can meet the reactivity and power cycle length requirements demanded of the NGNP. At the same time, it will provide substantial programmatic cost savings by eliminating the need for dual particle fabrication process lines and dual fuel particle irradiation tests required of a binary system. Use of a larger 425-micron kernel diameter single fissile particle (proposed here), as opposed to the 350-micron GT-MHR fissile particle size, helps alleviate current compact particle packing fractions fabrication limitations (<35%), improves fuel block loading for higher n-batch reload options, and tracks the historical correlation between particle size and enrichment (10 and 14 wt% U-235 particle enrichments are proposed for the NGNP). Overall, the use of the slightly larger kernel significantly broadens the NGNP reactor core design envelope and provides increased design margin to accommodate the (as yet) unknown final NGNP reactor design. Maximum power-peaking factors are calculated for both the initial and equilibrium NGNP cores. Radial power-peaking can be fully controlled with particle packing fraction zoning (no enrichment zoning required) and discrete burnable poison rods. Optimally loaded NGNP cores can expect radial powerpeaking factors as low as 1.14 at beginning of cycle (BOC), increasing slowly to a value of 1.25 by end of cycle (EOC), an axial power-peaking value of 1.30 (BOC), and for individual fuel particles in the maximum compact <1.05 (BOC) and an approximate value of 1.20 (EOC) due to Pu-239 buildup in particles on the compact periphery. The NGNP peak particle powers, using a conservative total power-peaking factor (~2.1 factor), are expected to be <150 mW/particle (well below the 250 mW/particle limit, even with the larger 425-micron kernel size).

James W. Sterbentz; Bren Phillips; Robert L. Sant; Gray S. Chang; Paul D. Bayless

2003-09-01T23:59:59.000Z

231

Effect of Nuclear Motion on Molecular High-Order Harmonics and on Generation of Attosecond Pulses in Intense Laser Pulses  

SciTech Connect (OSTI)

We calculate harmonic spectra and shapes of attosecond-pulse trains using numerical solutions of Non-Born-Oppenheimer time-dependent Shroedinger equation for 1D H{sub 2} molecules in an intense laser pulse. A very strong signature of nuclear motion is seen in the time profiles of high-order harmonics. In general the nuclear motion shortens the part of the attosecond-pulse train originating from the first electron contribution, but it may enhance the second electron contribution for longer pulses. The shape of time profiles of harmonics can thus be used for monitoring the nuclear motion.

Bandrauk, Andre D.; Chelkowski, Szczepan; Kawai, Shinnosuke; Lu, Huizhong [Departement de Chimie, Universite de Sherbrooke, Sherbrooke, Qc, J1K 2R1 (Canada)

2008-10-10T23:59:59.000Z

232

Illinois Nuclear Profile - Power Plants  

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

Illinois nuclear power plants, summer capacity and net generation, 2010" Illinois nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Braidwood Generation Station Unit 1, Unit 2","2,330","19,200",20.0,"Exelon Nuclear" "Byron Generating Station Unit 1, Unit 2","2,300","19,856",20.6,"Exelon Nuclear" "Clinton Power Station Unit 1","1,065","8,612",9.0,"Exelon Nuclear" "Dresden Generating Station Unit 2, Unit 3","1,734","14,593",15.2,"Exelon Nuclear" "LaSalle Generating Station

233

Energy Department Announces New Investments to Train Next Generation...  

Office of Environmental Management (EM)

to Train Next Generation of Nuclear Energy Leaders, Advance University-Led Nuclear Innovation Energy Department Announces New Investments to Train Next Generation of Nuclear Energy...

234

Energy Department Invests $60 Million to Train Next Generation...  

Office of Environmental Management (EM)

60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology Energy Department Invests 60 Million to Train Next Generation Nuclear Energy...

235

Nuclear Concrete Materials Database Phase I Development  

SciTech Connect (OSTI)

The FY 2011 accomplishments in Phase I development of the Nuclear Concrete Materials Database to support the Light Water Reactor Sustainability Program are summarized. The database has been developed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In this Phase I development, the database has been successfully designed and constructed to manage documents in the Portable Document Format generated from the Structural Materials Handbook that contains nuclear concrete materials data and related information. The completion of the Phase I database has established a solid foundation for Phase II development, in which a digital database will be designed and constructed to manage nuclear concrete materials data in various digitized formats to facilitate electronic and mathematical processing for analysis, modeling, and design applications.

Ren, Weiju [ORNL; Naus, Dan J [ORNL

2012-05-01T23:59:59.000Z

236

NUCLEAR SAFETY SPECIALIST QUALIFICATION STANDARD REFERENCE GUIDE  

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

Nuclear Nuclear Safety Specialist Qualification Standard Reference Guide AUGUST 2008 This page is intentionally blank. i Table of Contents LIST OF FIGURES ..................................................................................................................... iv LIST OF TABLES ........................................................................................................................ v ACRONYMS ................................................................................................................................ vi PURPOSE...................................................................................................................................... 1 SCOPE ...........................................................................................................................................

237

Tsiklauri-Durst combined cycle (T-D Cycle{trademark}) application for nuclear and fossil-fueled power generating plants  

SciTech Connect (OSTI)

The Tsiklauri-Durst combined cycle is a combination of the best attributes of both nuclear power and combined cycle gas power plants. A technology patented in 1994 by Battelle Memorial Institute offers a synergistic approach to power generation. A typical combined cycle is defined as the combination of gas turbine Brayton Cycle, topping steam turbine Rankine Cycle. Exhaust from the gas turbine is used in heat recovery steam generators to produce steam for a steam turbine. In a standard combined cycle gas turbine-steam turbine application, the gas turbine generates about 65 to 70 percent of system power. The thermal efficiency for such an installation is typically about 45 to 50 percent. A T-D combined cycle takes a new, creative approach to combined cycle design by directly mixing high enthalpy steam from the heat recovery steam generator, involving the steam generator at more than one pressure. Direct mixing of superheated and saturated steam eliminates the requirement for a large heat exchanger, making plant modification simple and economical.

Tsiklauri, B.; Korolev, V.N.; Durst, B.M.; Shen, P.K.

1998-07-01T23:59:59.000Z

238

Civilian Nuclear Programs  

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

Civilian Nuclear Programs Civilian Nuclear Programs Civilian Nuclear Programs Los Alamos is committed to using its advanced nuclear expertise and unique facilities to meet the civilian nuclear national security demands of the future. CONTACT US Program Director Bruce Robinson (505) 667-1910 Email Los Alamos partners extensively with other laboratories, universities, industry, and the international nuclear community to address real-world technical challenges The Civilian Nuclear Programs Office is the focal point for nuclear energy research and development and next-generation repository science at Los Alamos National Laboratory. The Civilian Nuclear Programs Office manages projects funded by the Department of Energy's offices of Nuclear Energy Environmental Management Nuclear Regulatory Commission

239

Activation cross sections of $\\alpha$-particle induced nuclear reactions on hafnium and deuteron induced nuclear reaction on tantalum: production of $^{178}$W/$^{178m}$Ta generator  

E-Print Network [OSTI]

In the frame of a systematic study of charged particle production routes of medically relevant radionuclei, the excitation function for indirect production of $^{178m}$Ta through $^{nat}$Hf($\\alpha$,xn)$^{178}$W-$^{178m}$Ta nuclear reaction was measured for the first time up to 40 MeV. In parallel, the side reactions $^{nat}$Hf($\\alpha$,x)$^{179,177,176,175}$W, $^{183,182,178g,177,176,175}$Ta, $^{179m,177m,175}$Hf were also assessed. Stacked foil irradiation technique and $\\gamma$-ray spectrometry were used. New experimental cross section data for the $^{nat}$Ta(d,xn)$^{178}$W reaction are also reported up to 40 MeV. The measured excitation functions are compared with the results of the ALICE-IPPE, and EMPIRE nuclear reaction model codes and with the TALYS 1.4 based data in the TENDL-2013 library. The thick target yields were deduced and compared with yields of other charged particle ((p,4n), (d,5n) and ($^3$He,x)) production routes for $^{178}$W.

Trk'anyi, F; Ditri, F; Hermanne, A; Ignatyuk, A V; Uddin, M S

2014-01-01T23:59:59.000Z

240

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]

Response Planning for Nuclear Power Plants in California",and Related Standards for Nuclear Power Plants", Lawrencejected lifetime for a nuclear power plant is 40 years, a

Nero, jA.V.

2010-01-01T23:59:59.000Z

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

Gen IV public comments-G Vine.PDF  

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

Generation IV Goals and Roadmap Generation IV Goals and Roadmap Public meeting, Thursday, Nov. 16, 2000 JW Marriott, Washington DC Gary Vine, EPRI I'd like to cite two regulatory landmarks established during the U.S. DOE/Industry ALWR Program, 1983-98, the intent of which should be incorporated into the goal setting for all future reactors. These are followed by four specific comments on the Generation IV goals. A. ALWR goals are Industry goals, and must be kept distinct from regulatory requirements. The ALWR Program was very careful to maintain and preserve clear separation between regulatory requirements and industry goals, as expressed in the EPRI ALWR Utility Requirements Document. The industry needed to decide how to comply with regulations in the most cost-effective way, and needed to strategically design-in the extra margins needed for investment protection, operational

242

Heavy Liquid Metal Reactor Development - Nuclear Engineering Division  

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

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

243

New Reactor Concepts and New Nuclear Data Needed to Develop Them  

Science Journals Connector (OSTI)

Developments of new reactor designs for the utilization of thorium such as the Advanced Heavy Water Reactor especially demand creation of new nuclear data for all the isotopes of the thorium fuel cycle. Improved nuclear data are essential to support new initiatives such as the international project on innovative nuclear reactors and fuel cycles (INPRO) which aims to support the safe sustainable economic and proliferation?resistant use of nuclear technology to meet the global energy needs of the 21st century. The detailed pursuit of development of Generation IV nuclear energy systems that offer advantages in the areas of economics safety reliability and sustainability require significantly improved nuclear data. The development of Accelerator Driven Sub?critical Systems proposed by Carlo Rubbia and others require a significant amount of new nuclear data in extended energy regions and improvement of the presently available nuclear data. The quality assurance in design and safety studies in nuclear energy in the next few decades and centuries require new and improved nuclear data with high accuracy and energy resolution. The paper presents from the perspective of the author an overview of some of the improvements in nuclear data required for a sound scientific basis of advanced nuclear systems. Also from the perspective of benchmarking and integral validation of nuclear data presented briefly is the status of thorium irradiations performed in a Pressurized Heavy Water Reactor (PHWR) in India and new results of post?irradiation analyses available thus far.

S. Ganesan

2005-01-01T23:59:59.000Z

244

INSTRUCTIONS FOR SUBMITTING NUCLEAR  

E-Print Network [OSTI]

waste management proceedings. Keywords Nuclear, nuclear power plant, spent fuel, nuclear waste, dataCALIFORNIA ENERGY COMMISSION INSTRUCTIONS FOR SUBMITTING NUCLEAR POWER PLANT-RELATED DATA of Submitted Data 3 NUCLEAR POWER PLANT DATA REQUESTS 6 A. Environmental Impacts 6 B. Spent Fuel Generation 8 C

245

DD nuclear fusion induced by laser-generated plasma at 1016Wcm?2 intensity  

Science Journals Connector (OSTI)

Deuterated polyethylene targets (CD2-monomer), as thin and thick films, were laser irradiated in a vacuum at 1016Wcm?2 intensity. The produced plasma was monitored in situ using the Thomson parabola spectrometer, ion collectors and SiC semiconductor detectors. For thin targets irradiated under target-normal-sheath-acceleration conditions, laser accelerated deuterons with energies higher than 3.0MeV were measured along the normal to the target surface. Characteristic emissions at 3.0 and 2.5MeV for protons and neutrons, respectively, have been detected confirming the production of nuclear fusion events. The evidence of nuclear fusion effects was evaluated and discussed.

Lorenzo Torrisi; Salvatore Cavallaro; Maria Cutroneo; Josef Krasa; Daniel Klir

2014-01-01T23:59:59.000Z

246

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]

Nuclear Regulatory Commission Standard Review Plan for LightRegulatory Commission. Office of Nuclear Reactor Licens- ing. Standard Review Plan.

Nero, jA.V.

2010-01-01T23:59:59.000Z

247

Radioisotope Power System Delivery, Ground Support and Nuclear Safety Implementation: Use of the Multi-Mission Radioisotope Thermoelectric Generator for the NASA's Mars Science Laboratory  

SciTech Connect (OSTI)

Radioisotope power systems have been used for over 50 years to enable missions in remote or hostile environments. They are a convenient means of supplying a few milliwatts up to a few hundred watts of useable, long-term electrical power. With regard to use of a radioisotope power system, the transportation, ground support and implementation of nuclear safety protocols in the field is a complex process that requires clear identification of needed technical and regulatory requirements. The appropriate care must be taken to provide high quality treatment of the item to be moved so it arrives in a condition to fulfill its missions in space. Similarly it must be transported and managed in a manner compliant with requirements for shipment and handling of special nuclear material. This presentation describes transportation, ground support operations and implementation of nuclear safety and security protocols for a radioisotope power system using recent experience involving the Multi-Mission Radioisotope Thermoelectric Generator for National Aeronautics and Space Administrations Mars Science Laboratory, which launched in November of 2011.

S.G. Johnson; K.L. Lively; C.C. Dwight

2014-07-01T23:59:59.000Z

248

PARTNERSHIP FOR THE DEVELOPMENT OF NEXT GENERATION SIMULATION TOOLS TO EVALUATE CEMENTITIOUS BARRIERS AND MATERIALS USED IN NUCLEAR APPLICATION - 8388  

SciTech Connect (OSTI)

The US DOE has initiated a multidisciplinary cross cutting project to develop a reasonable and credible set of tools to predict the structural, hydraulic and chemical performance of cement barriers used in nuclear applications over extended time frames (e.g., > 100 years for operating facilities and > 1000 years for waste management). A partnership that combines DOE, NRC, academia, private sector, and international expertise has been formed to accomplish the project objectives by integrating existing information and realizing advancements where necessary. The set of simulation tools and data developed under this project will be used to evaluate and predict the behavior of cementitious barriers used in near surface engineered waste disposal systems, e.g., waste forms, containment structures, entombments and environmental remediation, including decontamination and decommissioning (D&D) activities. The simulation tools will also support analysis of structural concrete components of nuclear facilities (spent fuel pools, dry spent fuel storage units, and recycling facilities, e.g., fuel fabrication, separations processes). Simulation parameters will be obtained from prior literature and will be experimentally measured under this project, as necessary, to demonstrate application of the simulation tools for three prototype applications (waste form in concrete vault, high level waste tank grouting, and spent fuel pool). Test methods and data needs to support use of the simulation tools for future applications will be defined. This is a national issue that affects all waste disposal sites that use cementitious waste forms and structures, decontamination and decommissioning activities, service life determination of existing structures, and design of future public and private nuclear facilities. The problem is difficult because it requires projecting conditions and responses over extremely long times. Current performance assessment analyses show that engineered barriers are typically the primary control to prevent the release of radionuclides from nuclear facilities into the environment. In the absence of an adequate predictive tool, assessments cannot fully incorporate the effectiveness of the concrete barriers, and the inventory of radionuclides (especially the long-lived radionuclides) that may be safely disposed of in shallow land disposal and the predicted service life of operating nuclear facilities. This project is 5 year effort focused on reducing uncertainties associated with current methodologies for assessing cementitious barrier performance and increasing the consistency and transparency of the assessment process. The results of this project will enable improved risk-informed, performance-based decision making, and supports several of the strategic initiatives in the DOE-EM Engineering & Technology Roadmap.

Langton, C; Richard Dimenna, R

2008-01-29T23:59:59.000Z

249

North Carolina Nuclear Profile - Power Plants  

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

Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

250

New Jersey Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

251

New Hampshire Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (nw)","Net generation (thousand mwh)","Share of State nuclear net...

252

EIS-0402: Santa Susana Field Laboratory Area IV, California | Department of  

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

2: Santa Susana Field Laboratory Area IV, California 2: Santa Susana Field Laboratory Area IV, California EIS-0402: Santa Susana Field Laboratory Area IV, California Summary This EIS evaluates the environmental impacts of remediation of Area IV of the Santa Susana Field Laboratory (SSFL Area IV). SSFL Area IV, occupying approximately 290 acres of the total 2,852-acre SSFL site is located in the hills between Chatsworth and Simi Valley, CA, and was developed as a remote site to test rocket engines and conduct nuclear research. This EIS will evaluate alternatives for disposition of radiological facilities and support buildings, remediation of the affected environment, and disposal of all resulting waste at existing, approved sites. Public Comment Opportunities No public comment opportunities available at this time.

253

Role of Nuclear Grade Graphite in Oxidation in Modular HTGRs  

SciTech Connect (OSTI)

The passively safe High Temperature Gas-cooled Reactor (HTGR) design is one of the primary concepts considered for Generation IV and Small Modular Reactor (SMR) programs. The helium cooled, nuclear grade graphite moderated core achieves extremely high operating temperatures allowing either industrial process heat or electricity generation at high efficiencies. In addition to their neutron moderating properties, nuclear grade graphite core components provide excellent high temperature stability, thermal conductivity, and chemical compatibility with the high temperature nuclear fuel form. Graphite has been continuously used in nuclear reactors since the 1940s and has performed remarkably well over a wide range of core environments and operating conditions. Graphite moderated, gas-cooled reactor designs have been safely used for research and power production purposes in multiple countries since the inception of nuclear energy development. However, graphite is a carbonaceous material, and this has generated a persistent concern that the graphite components could actually burn during either normal or accident conditions [ , ]. The common assumption is that graphite, since it is ostensibly similar to charcoal and coal, will burn in a similar manner. While charcoal and coal may have the appearance of graphite, the internal microstructure and impurities within these carbonaceous materials are very different. Volatile species and trapped moisture provide a source of oxygen within coal and charcoal allowing them to burn. The fabrication process used to produce nuclear grade graphite eliminates these oxidation enhancing impurities, creating a dense, highly ordered form of carbon possessing high thermal diffusivity and strongly (covalently) bonded atoms.

Willaim Windes; G. Strydom; J. Kane; R. Smith

2014-11-01T23:59:59.000Z

254

Nuclear Power Technology for the Future  

SciTech Connect (OSTI)

Ensuring sufficient energy for electricity, fresh water and transportation represents a major challenge for this century. Energy demand will increase dramatically as developing countries improve their standards of living. Nuclear power will become an increasingly important source of energy for production of electricity, fresh water and hydrogen as transportation fuel. Hydrocarbon sources of energy are not acceptable in the long term because of global warming and uneven supply. To ensure that nuclear power can meet this challenge, improved technologies are required to address the problems of nuclear waste, management of nuclear materials and safety as many more nuclear plants are built. These technologies are being developed at Argonne National Laboratory as part of the DOE international program of Generation IV reactors. Essential to meeting these challenges is the development of fast-spectrum nuclear reactors for which fuel and fission products are recycled to the reactor to be 'burned'. I will discuss work on fast-spectrum reactor and fuel-cycle design. The technologies discussed will be 'passively safe' reactor design and 'pyroprocessing' for fuel reprocessing.

Sackett, John I. (ANL) [ANL

2003-07-23T23:59:59.000Z

255

Category IV Dixon Recreation Center  

E-Print Network [OSTI]

Category IV Dixon Recreation Center BB or VB court $60 RB/Squash court $45 Multipurpose Room $60 for any rental that is cancelled with less than seven days notice Department of Recreational Sports

Escher, Christine

256

Alta IV | Open Energy Information  

Open Energy Info (EERE)

IV IV Jump to: navigation, search Name Alta IV Facility Alta IV Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Terra-Gen Power Developer Terra-Gen Power Energy Purchaser Southern California Edison Co Location Tehachapi Pass CA Coordinates 35.01917213°, -118.3031845° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":35.01917213,"lon":-118.3031845,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

257

Preparing Non-nuclear Engineers for the Nuclear Field  

E-Print Network [OSTI]

Preparing Non-nuclear Engineers for the Nuclear Field Elizabeth K. Ervin The University. An understanding of power generation is important for all modern-day engineers, and nuclear energy serves as a good-four universities have nuclear- related programs, including Nuclear or Radiological Engineering, Nuclear Science

Ervin, Elizabeth K.

258

DOE Hydrogen Program FY 2005 Progress Report IV.F Photoelectrochemical  

E-Print Network [OSTI]

barriers from the Hydrogen Production section of the Hydrogen, Fuel Cells and Infrastructure TechnologiesDOE Hydrogen Program FY 2005 Progress Report 13 IV.F Photoelectrochemical IV.F.1 High-Efficiency Generation of Hydrogen Using Solar Thermochemical Splitting of Water - UNLV: Photoelectrochemical Hydrogen

259

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]

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel

Nero, jA.V.

2010-01-01T23:59:59.000Z

260

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]

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

Yen, W.W.S.

2010-01-01T23:59:59.000Z

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

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

262

Tennessee Nuclear Profile - Watts Bar Nuclear Plant  

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

Watts Bar Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

263

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

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

Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

264

Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station  

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

Pilgrim Nuclear Power Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer cpacity factor (percent)","Type","Commercial operation date","License...

265

Arkansas Nuclear Profile - Arkansas Nuclear One  

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

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

266

REGULATORY STRATEGIES TO MINIMIZE GENERATION OF REGULATED WASTES FROM CLEANUP, CONTINUED USE OR DECOMMISSIONING OF NUCLEAR FACILITIES CONTAMINATED WITH POLYCHLORINATED BIPHENYLS (PCBS) - 11198  

SciTech Connect (OSTI)

Disposal costs for liquid PCB radioactive waste are among the highest of any category of regulated waste. The high cost is driven by the fact that disposal options are extremely limited. Toxic Substances Control Act (TSCA) regulations require most liquids with PCBs at concentration of {ge} 50 parts-per-million to be disposed by incineration or equivalent destructive treatment. Disposal fees can be as high as $200 per gallon. This figure does not include packaging and the cost to transport the waste to the disposal facility, or the waste generator's labor costs for managing the waste prior to shipment. Minimizing the generation of liquid radioactive PCB waste is therefore a significant waste management challenge. PCB spill cleanups often generate large volumes of waste. That is because the removal of PCBs typically requires the liberal use of industrial solvents followed by a thorough rinsing process. In a nuclear facility, the cleanup process may be complicated by the presence of radiation and other occupational hazards. Building design and construction features, e.g., the presence of open grating or trenches, may also complicate cleanup. In addition to the technical challenges associated with spill cleanup, selection of the appropriate regulatory requirements and approach may be challenging. The TSCA regulations include three different sections relating to the cleanup of PCB contamination or spills. EPA has also promulgated a separate guidance policy for fresh PCB spills that is published as Subpart G of 40 CFR 761 although it is not an actual regulation. Applicability is based on the circumstances of each contamination event or situation. Other laws or regulations may also apply. Identification of the allowable regulatory options is important. Effective communication with stakeholders, particularly regulators, is just as important. Depending on the regulatory path that is taken, cleanup may necessitate the generation of large quantities of regulated waste. Allowable options must be evaluated carefully in order to reduce compliance risks, protect personnel, limit potential negative impacts on facility operations, and minimize the generation of wastes subject to TSCA. This paper will identify critical factors in selecting the appropriate TSCA regulatory path in order to minimize the generation of radioactive PCB waste and reduce negative impacts to facilities. The importance of communicating pertinent technical issues with facility staff, regulatory personnel, and subsequently, the public, will be discussed. Key points will be illustrated by examples from five former production reactors at the DOE Savannah River Site. In these reactors a polyurethane sealant was used to seal piping penetrations in the biological shield walls. During the intense neutron bombardment that occurred during reactor operation, the sealant broke down into a thick, viscous material that seeped out of the piping penetrations over adjacent equipment and walls. Some of the walls were painted with a PCB product. PCBs from the paint migrated into the degraded sealant, creating PCB 'spill areas' in some of these facilities. The regulatory cleanup approach selected for each facility was based on its operational status, e.g., active, inactive or undergoing decommissioning. The selected strategies served to greatly minimize the generation of radioactive liquid PCB waste. It is expected that this information would be useful to other DOE sites, DOD facilities, and commercial nuclear facilities constructed prior to the 1979 TSCA ban on most manufacturing and uses of PCBs.

Lowry, N.

2010-11-05T23:59:59.000Z

267

Nuclear Eclectic Power  

Science Journals Connector (OSTI)

...much higher future costs for oil and natural gas. However, the...ELECTRICITY GENERATION FROM COAL, OIL, AND NUCLEAR FUEL, NUCLEAR...electricity generation from coal, oil, and nuclear fuel, cite about...possibility that stimu-lated a marathon debate between the Union of...

David J. Rose

1974-04-19T23:59:59.000Z

268

Hydrogen Gas Production from Nuclear Power Plant in Relation to Hydrogen Fuel Cell Technologies Nowadays  

Science Journals Connector (OSTI)

Recently world has been confused by issues of energy resourcing including fossil fuel use global warming and sustainable energy generation. Hydrogen may become the choice for future fuel of combustion engine. Hydrogen is an environmentally clean source of energy to end?users particularly in transportation applications because without release of pollutants at the point of end use. Hydrogen may be produced from water using the process of electrolysis. One of the GEN?IV reactors nuclear projects (HTGRs HTR VHTR) is also can produce hydrogen from the process. In the present study hydrogen gas production from nuclear power plant is reviewed in relation to commercialization of hydrogen fuel cell technologies nowadays.

2010-01-01T23:59:59.000Z

269

A preliminary user-friendly, digital console for the control room parameters supervision in old-generation Nuclear Plants  

SciTech Connect (OSTI)

Improvements in the awareness of a system status is an essential requirement to achieve safety in every kind of plant. In particular, in the case of Nuclear Power Plants (NPPs), a progress is crucial to enhance the Human Machine Interface (HMI) in order to optimize monitoring and analyzing processes of NPP operational states. Firstly, as old-fashioned plants are concerned, an upgrading of the whole console instrumentation is desirable in order to replace an analog visualization with a full-digital system. In this work, we present a novel instrument able to interface the control console of a nuclear reactor, developed by using CompactRio, a National Instruments embedded architecture and its dedicated programming language. This real-time industrial controller composed by a real-time processor and FPGA modules has been programmed to visualize the parameters coming from the reactor, and to storage and reproduce significant conditions anytime. This choice has been made on the basis of the FPGA properties: high reliability, determinism, true parallelism and re-configurability, achieved by a simple programming method, based on LabVIEW real-time environment. The system architecture exploits the FPGA capabilities of implementing custom timing and triggering, hardware-based analysis and co-processing, and highest performance control algorithms. Data stored during the supervisory phase can be reproduced by loading data from a measurement file, re-enacting worthwhile operations or conditions. The system has been thought to be used in three different modes, namely Log File Mode, Supervisory Mode and Simulation Mode. The proposed system can be considered as a first step to develop a more complete Decision Support System (DSS): indeed this work is part of a wider project that includes the elaboration of intelligent agents and meta-theory approaches. A synoptic has been created to monitor every kind of action on the plant through an intuitive sight. Furthermore, another important aim of this work is the possibility to have a front panel available on a web interface: CompactRio acts as a remote server and it is accessible on a dedicated LAN. This supervisory system has been tested and validated on the basis of the real control console for the 1-MW TRIGA reactor RC-1 at the ENEA, Casaccia Research Center. In this paper we show some results obtained by recording each variable as the reactor reaches its maximum level of power. The choice of a research reactor for testing the developed system relies on its training and didactic importance for the education of plant operators: in this context a digital instrument can offer a better user-friendly tool for learning and training. It is worthwhile to remark that such a system does not interfere with the console instrumentation, the latter continuing to preserve the total control. (authors)

Memmi, F.; Falconi, L.; Cappelli, M.; Palomba, M.; Santoro, E.; Bove, R.; Sepielli, M. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy)

2012-07-01T23:59:59.000Z

270

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

271

TVA chooses nuclear power  

Science Journals Connector (OSTI)

TVA chooses nuclear power ... In giving the nod to a nuclear (over a coal) power generating station 10 days ago, TVA probably gave nuclear power its biggest boost to date. ... The $247 million nuclear power planta dual boiling-water reactor unit with a total capacity of 2.2 million kw(e).will ...

1966-06-27T23:59:59.000Z

272

On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers  

SciTech Connect (OSTI)

Integrity monitoring and flaw diagnostics of flat beams and tubular structures was investigated in this research task using guided acoustic signals. A piezo-sensor suite was deployed to activate and collect Lamb wave signals that propagate along metallic specimens. The dispersion curves of Lamb waves along plate and tubular structures are generated through numerical analysis. Several advanced techniques were explored to extract representative features from acoustic time series. Among them, the Hilbert-Huang transform (HHT) is a recently developed technique for the analysis of non-linear and transient signals. A moving window method was introduced to generate the local peak characters from acoustic time series, and a zooming window technique was developed to localize the structural flaws. The time-frequency analysis and pattern recognition techniques were combined for classifying structural defects in brass tubes. Several types of flaws in brass tubes were tested, both in the air and in water. The techniques also proved to be effective under background/process noise. A detailed theoretical analysis of Lamb wave propagation was performed and simulations were carried out using the finite element software system ABAQUS. This analytical study confirmed the behavior of the acoustic signals acquired from the experimental studies. The report presents the background the analysis of acoustic signals acquired from piezo-electric transducers for structural defect monitoring. A comparison of the use of time-frequency techniques, including the Hilbert-Huang transform, is presented. The report presents the theoretical study of Lamb wave propagation in flat beams and tubular structures, and the need for mode separation in order to effectively perform defect diagnosis. The results of an extensive experimental study of detection, location, and isolation of structural defects in flat aluminum beams and brass tubes are presented. The results of this research show the feasibility of on-line monitoring of small structural flaws by the use of transient and nonlinear acoustic signal analysis, and its implementation by the proper design of a piezo-electric transducer suite.

Belle R. Upadhyaya; J. Wesley Hines

2004-09-27T23:59:59.000Z

273

Materials Challenges in Nuclear Energy  

SciTech Connect (OSTI)

Nuclear power currently provides about 13% of the worldwide electrical power, and has emerged as a reliable baseload source of electricity. A number of materials challenges must be successfully resolved for nuclear energy to continue to make further improvements in reliability, safety and economics. The operating environment for materials in current and proposed future nuclear energy systems is summarized, along with a description of materials used for the main operating components. Materials challenges associated with power uprates and extensions of the operating lifetimes of reactors are described. The three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues. The major corrosion and stress corrosion cracking degradation mechanisms for light water reactors are reviewed. The materials degradation issues for the Zr alloy clad UO2 fuel system currently utilized in the majority of commercial nuclear power plants is discussed for normal and off-normal operating conditions. Looking to proposed future (Generation IV) fission and fusion energy systems, there are 5 key bulk radiation degradation effects (low temperature radiation hardening and embrittlement, radiation-induced and modified solute segregation and phase stability, irradiation creep, void swelling, and high temperature helium embrittlement) and a multitude of corrosion and stress corrosion cracking effects (including irradiation-assisted phenomena) that can have a major impact on the performance of structural materials.

Zinkle, Steven J [ORNL] [ORNL; Was, Gary [University of Michigan] [University of Michigan

2013-01-01T23:59:59.000Z

274

A Perspective on Nuclear Waste  

Science Journals Connector (OSTI)

The management of spent nuclear fuel and high-level nuclear waste has the deserved reputation as one of ... facing the United States and other nations using nuclear reactors for electric power generation. This pa...

D. Warner North

1999-08-01T23:59:59.000Z

275

Nuclear Waste Disposal Plan Drafted  

Science Journals Connector (OSTI)

Nuclear Waste Disposal Plan Drafted ... Of all the issues haunting nuclear power plants, that of disposing of the radioactive wastes and spent nuclear fuel they generate has been the most vexing. ...

1984-01-09T23:59:59.000Z

276

Shiloh IV | Open Energy Information  

Open Energy Info (EERE)

Shiloh IV Shiloh IV Facility Shiloh IV Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner EDF Renewable Energy Developer EDF Renewable Energy Energy Purchaser Pacific Gas & Electric Location Birds Landing CA Coordinates 38.13891092°, -121.8480349° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":38.13891092,"lon":-121.8480349,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

277

Louisiana Nuclear Profile - Power Plants  

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

Louisiana nuclear power plants, summer capacity and net generation, 2010" "Plant NameTotal Reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

278

California Nuclear Profile - Power Plants  

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

California nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

279

Connecticut Nuclear Profile - Power Plants  

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

Connecticut nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

280

Mississippi Nuclear Profile - Power Plants  

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

Mississippi nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

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

Washington Nuclear Profile - Power Plants  

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

Washington nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

282

Theories of Low Energy Nuclear Transmutations  

E-Print Network [OSTI]

Employing concrete examples from nuclear physics it is shown that low energy nuclear reactions can and have been induced by all of the four fundamental interactions (i) (stellar) gravitational, (ii) strong, (iii) electromagnetic and (iv) weak. Differences are highlighted through the great diversity in the rates and similarity through the nature of the nuclear reactions initiated by each.

Y. N. Srivastava; A. Widom; J. Swain

2012-10-27T23:59:59.000Z

283

Nuclear Data Measurements for 21st Century Reactor Physics Applications  

SciTech Connect (OSTI)

The United States Department of Energy (DOE), Office of Nuclear Energy (NE) has embarked on a long-term program to significantly advance the science and technology of nuclear energy. This is in response to the overall national plan for accelerated development of domestic energy resources on several fronts, punctuated by recent dramatic events that have emphasized the need for the US to reduce its dependence on foreign petroleum supplies. Key aspects of the DOE-NE agenda are embodied in the Generation-IV (Gen-IV) advanced nuclear energy systems development program and in the Advanced Fuel Cycle (AFC) program. The planned efforts involve near-term and intermediate-term improvements in fuel utilization and recycling in current nuclear power reactor systems as well as the longer-term development of new nuclear energy systems that offer much improved fuel utilization and proliferation resistance, along with continued advances in operational safety. The success of the overall NE effort will depend not only on sophisticated system development and engineering, but also on the advances in the supporting sciences and technologies. Of these, one of the most important is the improvement of the relevant fundamental nuclear science data bases, especially the evaluated neutron interaction cross section files that serve as the foundation of all reactor system designs, operating strategies, and fuel cycle engineering activities. The new concepts for reactors and fuel cycles involve the use of transuranic nuclides that were previously of little interest, and where experimentally measured information is lacking. The current state of the cross section database for some of these nuclides is such that design computations for advanced fast-spectrum reactor systems and fuel cycles that incorporate such materials in significant quantities are meaningful only for approximate conceptual applications. No actual system could reliably be designed according to currently accepted standards, nor could such a system be safely and efficiently operated, with the limited nuclear data and related information now available.

Rahmat Aryaeinejad; Jerald D. Cole; Mark W. Drigert; James K. Jewell; Christopher A. McGrath; David W. Nigg; Edward L. Reber

2003-03-01T23:59:59.000Z

284

Bush Administration Moves Forward to Develop Next Generation...  

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

Forum Signs Agreement to Collaborate on Sodium Cooled Fast Reactors China and Russia to Join the Generation IV International Forum Renewed energy and enhanced coordination...

285

The Role of Nuclear Power in Reducing Risk of the Fossil Fuel Prices and Diversity of Electricity Generation in Tunisia: A Portfolio Approach  

Science Journals Connector (OSTI)

Given the global energy trend to substitute fossil fuel, the nuclear power has known an important ... degrees of uncertainties related to nuclear and fossil fuel. The higher uncertainty of fossil fuel prices make...

Mohamed Ben Abdelhamid; Chaker Aloui; Corinne Chaton

2010-04-01T23:59:59.000Z

286

Nuclear Energy Systems  

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

Role of Synchrotron Radiation in Solving Scientific Challenges in Advanced Nuclear Energy Systems 27 to 28 January 2010 at Argonne's Advanced Photon Source Scope Third-generation...

287

EIA - State Nuclear Profiles  

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

Massachusetts Nuclear Profile 2010 Massachusetts profile Massachusetts total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy...

288

EIA - State Nuclear Profiles  

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

Iowa Nuclear Profile 2010 Iowa profile Iowa total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw)...

289

EIA - State Nuclear Profiles  

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

Illinois Nuclear Profile 2010 Illinois profile Illinois total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer...

290

EIA - State Nuclear Profiles  

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

Louisiana Nuclear Profile 2010 Louisiana profile Louisiana total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer...

291

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

292

The Next Generation Nuclear The Next Generation Nuclear  

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

Use VHTR technology to: Use VHTR technology to: Produce electricity, and Produce electricity, and Process heat for hydrogen production and other Process heat for...

293

Plutonium(IV) precipitates formed in alkaline media in the presence of various anions  

SciTech Connect (OSTI)

The tendency of Pu(IV) to hydrolyze and form true solutions, colloid solutions, or insoluble precipitates has been known since the Manhattan Project. Since then, specific studies have been performed to examine in detail the equilibria of Pu(IV) hydrolytic reactions in various media. Great attention also has been paid to the preparation, structure, and properties of Pu(IV) polymers or colloids. These compounds found an important application in sol-gel technology for the preparation of nuclear fuel materials. A most important result of these works was the conclusion that Pu(IV) hydroxide, after some aging, consists of very small PuO{sub 2} crystallites and should therefore be considered to be Pu(IV) hydrous oxide. However, studies of the properties and behavior of solid Pu(IV) hydroxide in complex heterogeneous systems are rare. The primary goal of this investigation was to obtain data on the composition and properties of Pu(IV) hydrous oxide or other compounds formed in alkaline media under different conditions. Such information is important to understand Pu(IV) behavior and the forms of its existence in the Hanford Site alkaline tank waste sludge. This knowledge then may be applied in assessing plutonium criticality hazards in the storage, retrieval, and treatment of Hanford Site tank wastes as well as in understanding its contribution to the transuranic waste inventory (threshold at 100 nCi/g or about 5 {times} 10{sup {minus}6} M) of the separate solution and solid phases.

Krot, N.N.; Shilov, V.P.; Yusov, A.B.; Tananaev, I.G.; Grigoriev, M.S.; Garnov, A.Yu.; Perminov, V.P.; Astafurova, L.N.

1998-09-01T23:59:59.000Z

294

Type IV Pilin Proteins: Versatile Molecular Modules  

Science Journals Connector (OSTI)

...2012 review-article Reviews Type IV Pilin Proteins...adaptable functional plan. The type IV pilin is...substrates. In this review, we consider recent...adaptable functional plan. The type IV pilin is...substrates. In this review, we consider recent...

Carmen L. Giltner; Ylan Nguyen; Lori L. Burrows

2012-12-01T23:59:59.000Z

295

Pressemitteilung Graduiertenkolleg Automatismen Media Transatlantic IV Traffic.  

E-Print Network [OSTI]

Pressemitteilung Graduiertenkolleg Automatismen Media Transatlantic IV ­ Traffic. Internationale untersuchen anlässlich der Tagung Media Transatlantic IV ­ Traffic an der Universität Paderborn die verselbstständigende und somit zunehmend unkontrollierbare Strukturen entstehen. Media Transatlantic IV ­ Traffic ist

Paderborn, Universität

296

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

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

For Records Disposition Authority-Nuclear Weapons This document identifies the nuclear weapon records generated by the Department of Energy's (DOE) Nuclear Weapons Complex Request...

297

Next Generation Nuclear Plant Phenomena  

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

High- importance phenomena related to the RPV include crack initiation and subcritical crack growth; field fabrication process control; property control in heavy...

298

Next Generation Nuclear Plant Phenomena  

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

of enhanced heat transfer in the primary heat exchanger. After blowdown, there will be a loss of the heat sink. < Leak into reactor primary system. The total gas inventory in the...

299

Nuclear reactor characteristics and operational history  

Gasoline and Diesel Fuel Update (EIA)

1. Capacity and Generation, Table 3. Characteristics and Operational History 1. Capacity and Generation, Table 3. Characteristics and Operational History Table 2. U.S. Nuclear Reactor Ownership Data PDF XLS Plant/Reactor Name Generator ID Utility Name - Operator Owner Name % Owned Arkansas Nuclear One 1 Entergy Arkansas Inc Entergy Arkansas Inc 100 Arkansas Nuclear One 2 Entergy Arkansas Inc Entergy Arkansas Inc 100 Beaver Valley 1 FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Generation Corp 100 Beaver Valley 2 FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Generation Corp 100 Braidwood Generation Station 1 Exelon Nuclear Exelon Nuclear 100 Braidwood Generation Station 2 Exelon Nuclear Exelon Nuclear 100 Browns Ferry 1 Tennessee Valley Authority Tennessee Valley Authority 100

300

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

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

Technology Technology Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Bookmark and Share The NE system engineering activities involve the conceptual design, through the manufacturing and qualification testing of the Mk-IV and Mk-V electrorefiner and the cathode processor. These first-of-a-kind large scale

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

Nuclear Energy  

Science Journals Connector (OSTI)

Nuclear Energy ... A brief summary of the history and key concepts of nuclear energy. ... Nuclear / Radiochemistry ...

Charles D. Mickey

1980-01-01T23:59:59.000Z

302

Nuclear batteries  

Science Journals Connector (OSTI)

Nuclear batteries ... Describes the structure, operation, and application of nuclear batteries. ... Nuclear / Radiochemistry ...

Alfred B. Garrett

1956-01-01T23:59:59.000Z

303

IV  

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

of 99 of 99 Fiscal Year (FY) 2010 Energy Efficient Building Systems Regional Innovation Cluster Initiative A joint FOA published by: The Department of Energy The Department of Commerce-Economic Development Administration The Department of Commerce-National Institute of Standards and Technology The Small Business Administration The Department of Labor The Department of Education

304

IV  

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

Supplement to the Draft Solar PEIS iii October 2011 CONTENTS 1 2 3 NOTATION ........................................................................................................................ ix 4 5 ENGLISH/METRIC AND METRIC/ENGLISH EQUIVALENTS .................................. xiii 6 7 1 INTRODUCTION ..................................................................................................... 1-1 8

305

Measurements of photon ionizing radiation fields in the reactor room of the 4th power-generating unit of the chernobyl nuclear power plant  

Science Journals Connector (OSTI)

A radiation examination of the reactor room of the damaged fourth unit of the Chernobyl nuclear power plant was performed. The most strongly radiating surfaces...

A. G. Volkovich; V. N. Potapov; S. V. Smirnov; L. I. Urutskoev

2000-03-01T23:59:59.000Z

306

ORNL/TM-2008/129 Generation IV Reactors Integrated  

E-Print Network [OSTI]

. L. Snead, ORNL W. E. Windes, INL T. E. McGreevy, Caterpillar R. Soto, INL J. K. Wright, INL D. Morgan, University of Wisconsin K. Sridharan, University of Wisconsin R. N. Wright, INL R. K. Nanstad. Ghoniem, UCLA T. L. Sham D. F. Wilson, ORNL Yutai Katoh, ORNL L. L. Snead, ORNL W. E. Windes, INL T. E. Mc

Pennycook, Steve

307

Nuclear Forensics  

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

nuclear forensics Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear...

308

Plutonium Oxidation and Subsequent Reduction by Mn (IV) Minerals  

SciTech Connect (OSTI)

Plutonium sorbed to rock tuff was preferentially associated with manganese oxides. On tuff and synthetic pyrolusite (Mn{sup IV}O{sub 2}), Pu(IV) or Pu(V) was initially oxidized, but over time Pu(IV) became the predominant oxidation state of sorbed Pu. Reduction of Pu(V/VI), even on non-oxidizing surfaces, is proposed to result from a lower Gibbs free energy of the hydrolyzed Pu(IV) surface species versus that of the Pu(V) or Pu(VI) surface species. This work suggests that despite initial oxidation of sorbed Pu by oxidizing surfaces to more soluble forms, the less mobile form of Pu, Pu(IV), will dominate Pu solid phase speciation during long term geologic storage. The safe design of a radioactive waste or spent nuclear fuel geologic repository requires a risk assessment of radionuclides that may potentially be released into the surrounding environment. Geochemical knowledge of the radionuclide and the surrounding environment is required for predicting subsurface fate and transport. Although difficult even in simple systems, this task grows increasingly complicated for constituents, like Pu, that exhibit complex environmental chemistries. The environmental behavior of Pu can be influenced by complexation, precipitation, adsorption, colloid formation, and oxidation/reduction (redox) reactions (1-3). To predict the environmental mobility of Pu, the most important of these factors is Pu oxidation state. This is because Pu(IV) is generally 2 to 3 orders of magnitude less mobile than Pu(V) in most environments (4). Further complicating matters, Pu commonly exists simultaneously in several oxidation states (5, 6). Choppin (7) reported Pu may exist as Pu(IV), Pu(V), or Pu(VI) oxic natural groundwaters. It is generally accepted that plutonium associated with suspended particulate matter is predominantly Pu(IV) (8-10), whereas Pu in the aqueous phase is predominantly Pu(V) (2, 11-13). The influence of the character of Mn-containing minerals expected to be found in subsurface repository environments on Pu oxidation state distributions has been the subject of much recent research. Kenney-Kennicutt and Morse (14), Duff et al. (15), and Morgenstern and Choppin (16) observed oxidation of Pu facilitated by Mn(IV)-bearing minerals. Conversely, Shaughnessy et al. (17) used X-ray Absorption near-edge spectroscopy (XANES) to show reduction of Pu(VI) by hausmannite (Mn{sup II}Mn{sub 2}{sup III}O{sub 4}) and manganite ({gamma}-Mn{sup III}OOH) and Kersting et al., (18) observed reduction of Pu(VI) by pyrolusite (Mn{sup IV}O{sub 2}). In this paper, we attempt to reconcile the apparently conflicting datasets by showing that Mn-bearing minerals can indeed oxidize Pu, however, if the oxidized species remains on the solid phase, the oxidation step competes with the formation of Pu(IV) that becomes the predominant solid phase Pu species with time. The experimental approach we took was to conduct longer term (approximately two years later) oxidation state analyses on the Pu sorbed to Yucca Mountain tuff (initial analysis reported by Duff et al., (15)) and measure the time-dependant changes in the oxidation state distribution of Pu in the presence of the Mn mineral pyrolusite.

KAPLAN, DANIEL

2005-09-13T23:59:59.000Z

309

Quadrennial Technology Review's Alternative Generation Workshop...  

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

Workshop Slides Preliminary Slides for Alternative Generation Workshop including Carbon Capture and Sequestration, Nuclear Power, Wind Power, Water Power, Geothermal...

310

A Roadmap to Deploy New Nuclear Power Plants  

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

I I Summary Report Prepared for the United States Department of Energy Office of Nuclear Energy, Science and Technology and its Nuclear Energy Research Advisory Committee Subcommittee on Generation IV Technology Planning October 31, 2001 Disclaimer This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any of its employees make any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe upon privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not

311

The Prospects for Closed Cycle M.P.D. Power Generation  

Science Journals Connector (OSTI)

...P.D. Power Generation B. C. Lindley...cycles (direct nuclear, indirect nuclear...on combustion or nuclear energy, to the...restrictions. Nuclear reactors to provide temperatures...p.d. power generation is mainly in progress...

1967-01-01T23:59:59.000Z

312

Nuclear Energy Research Brookhaven National  

E-Print Network [OSTI]

Nuclear Energy Research Brookhaven National Laboratory William C. Horak, Chair Nuclear Science and Technology Department #12;BNL Nuclear Energy Research Brookhaven Graphite Research Reactor - 1948 National&T Department #12;Nuclear Energy Today 435 Operable Power Reactors, 12% electrical generation (100 in US, 19

Ohta, Shigemi

313

SECTION IV: ATOMIC AND MOLECULAR SCIENCE  

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

Projectile ionization in collisions of U 28+ with gases ... IV-1 R. E. Olson, R. L. Watson, V. Horvat, K. E....

314

Inhibition of Oxidation in Nuclear Graphite  

SciTech Connect (OSTI)

Graphite is a fundamental material of high temperature gas cooled nuclear reactors, providing both structure and neutron moderation. Its high thermal conductivity, chemical inertness, thermal heat capacity, and high thermal structural stability under normal and off normal conditions contribute to the inherent safety of these reactor designs. One of the primary safety issues for a high temperature graphite reactor core is the possibility of rapid oxidation of the carbon structure during an off normal design basis event where an oxidizing atmosphere (air ingress) can be introduced to the hot core. Although the current Generation IV high temperature reactor designs attempt to mitigate any damage caused by a postualed air ingress event, the use of graphite components that inhibit oxidation is a logical step to increase the safety of these reactors. Recent experimental studies of graphite containing between 5.5 and 7 wt% boron carbide (B4C) indicate that oxidation is dramatically reduced even at prolonged exposures at temperatures up to 900C. The proposed addition of B4C to graphite components in the nuclear core would necessarily be enriched in B-11 isotope in order to minimize B-10 neutron absorption and graphite swelling. The enriched boron can be added to the graphite during billet fabrication. Experimental oxidation rate results and potential applications for borated graphite in nuclear reactor components will be discussed.

Phil Winston; James W. Sterbentz; William E. Windes

2013-10-01T23:59:59.000Z

315

Safety evaluation of RTG launches aboard Titan IV launch vehicles  

SciTech Connect (OSTI)

The analytical tool used to evaluate accidents aboard a Titan IV launch vehicle involving a Radioisotope Thermoelectric Generator (RTG) is discussed. The Launch Accident Scenario Evaluation Program-Titan IV version (LASEP-T) uses a Monte Carlo approach to determine the response of an RTG to various threatening environments. The threatening environments arise from a complex interplay of probabilistic and deterministic processes, and are therefore parameterized by a set of random variables with probability distributions. The assessment of the RTG response to a given environment is based on both empirical data and theoretical modeling. Imbedding detailed, complex response models into the LASEP-T calculation was not practical. Simpler response models have been constructed to capture both the inherent variability due to the phenomenology of the accident scenario along with the uncertainty of predicting response behavior. The treatment of variability and uncertainty as it pertains to the launch accident evaluation of RTG response will be discussed.

Rosko, Robert J.; Loughin, Stephen [Lockheed Martin Missiles and Space P.O. Box 8555 Philadelphia, Pennsylvania 19101 (United States)

1997-01-10T23:59:59.000Z

316

Nano-Continuum Modeling of a Nuclear Glass Specimen Altered for 25 Years  

E-Print Network [OSTI]

Contract No. DE-AC02-05CH11231. Nano-Continuum Modeling of aNano-Continuum Modeling of a Nuclear Glass Specimen AlteredSignature on File) iv Nano-Continuum Modeling of a Nuclear

Steefel, Carl

2014-01-01T23:59:59.000Z

317

Materials Research Needs for Near-Term Nuclear Reactors  

Science Journals Connector (OSTI)

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

John R. Weeks

318

Nuclear | Department of Energy  

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

Nuclear Nuclear Nuclear Radioisotope Power Systems, a strong partnership between the Energy Department's Office of Nuclear Energy and NASA, has been providing the energy for deep space exploration. Nuclear power is the use of sustained nuclear fission to generate heat and electricity. Nuclear power plants provide about 6 percent of the world's energy and 13-14 percent of the world's electricity. Featured Five Years of Building the Next Generation of Reactors Simulated three-dimensional fission power distribution of a single 17x17 rod PWR fuel assembly. | Photo courtesy of the Consortium for Advanced Simulation of Light Water Reactors (CASL). A two-year update on the Consortium for Advanced Simulation of Light Water Reactors and the progress being made in overcoming barriers to national

319

Nuclear Decommissioning Financing Act (Maine)  

Broader source: Energy.gov [DOE]

The Nuclear Decommissioning Financing Act calls for the establishment of a tax-exempt, tax-deductible decommissioning fund by the licensee of any nuclear power generating facility to pay for the...

320

Electricity investments and development of power generation capacities : An approach of the drivers for investment choices in Europe regarding nuclear energy.  

E-Print Network [OSTI]

??In a context of growing energy prices and climate change mitigation, the thesis addresses the issues of investments in power generation capacities and in particular (more)

Shoai Tehrani, Bianka

2014-01-01T23:59:59.000Z

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

Simulation of thermal stress influence on the Boom Clay kerogen (Oligocene, Belgium) in relation to long-term storage of high activity nuclear waste: I. Study of generated soluble compounds  

Science Journals Connector (OSTI)

Closed pyrolyses were performed on the Boom Clay kerogen to simulate the weak thermal stress applied during the in situ CERBERUS heating experiment (80 C for 5 a). Two stronger thermal stresses, encompassing the range generally considered for the long-term disposal of high-activity nuclear waste (80 C for 1 ka and 120 C for 3 ka), were also simulated. Quantitative and qualitative studies were carried out on the products thus generated with a focus on the C12+ fraction, especially on its polar components. It thus appeared that the soluble C12+ fractions generated during these simulation experiments comprise a wide variety of polar O- and/or N-containing compounds, including carboxylic acids and phenols. The nature and/or the relative abundance of these polar compounds exhibit strong variations, with the extent of the thermal stress, reflecting the primary cracking of different types of structures with different thermal stability and the occurrence of secondary degradation reactions. These observations support the idea that the compounds, generated upon exposure of the Boom Clay kerogen to a low to moderate thermal stress, may affect the effectiveness of the geological barrier upon long-term storage of high-activity nuclear waste.

I. Deniau; S. Derenne; C. Beaucaire; H. Pitsch; C. Largeau

2005-01-01T23:59:59.000Z

322

Nuclear Power Technology: A Mandate for Change  

Science Journals Connector (OSTI)

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

Kunmo Chung; George A. Hazelrigg

323

Nuclear Facility Safety Basis Fundamentals Self-Study Guide - November 2002  

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

Oak Ridge Operations Office Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)] November 2002 Nuclear Facility Safety Basis Fundamentals Self-Study Guide TABLE OF CONTENTS Acronyms and Abbreviations ......................................................................................... iii List of Figures ....................................................................................................................iv List of Tables......................................................................................................................iv INTRODUCTION..............................................................................................................1

324

Covariance and sensitivity data generation at ORNL  

Science Journals Connector (OSTI)

......parameter covariance generation. In this paper...retroactive covariance generation approach for the gadolinium...COVARIANCE DATA GENERATION IN SAMMY Over the...quality of the basic nuclear data. Thermal reactor designs and applications......

L. C. Leal; H. Derrien; N. M. Larson; A. Alpan

2005-12-20T23:59:59.000Z

325

Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant  

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

Calvert Cliffs Nuclear Power Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

326

New York Nuclear Profile - Nine Mile Point Nuclear Station  

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

Nine Mile Point Nuclear Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

327

New York Nuclear Profile - R E Ginna Nuclear Power Plant  

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

R E Ginna Nuclear Power Plant" "Unit","Summer Capacity (MW)","Net Generation (Thousand MWh)","Summer Capacity Factor (Percent)","Type","Commercial Operation Date","License...

328

Surprising Coordination Geometry Differences in Ce(IV)- and Pu(IV)-Maltol Complexes  

SciTech Connect (OSTI)

As part of a study to characterize the detailed coordination behavior of Pu(IV), single crystal X-ray diffraction structures have been determined for Pu(IV) and Ce(IV) complexes with the naturally-occurring ligand maltol (3-hydroxy-2-methyl-pyran-4-one) and its derivative bromomaltol (5-bromo-3-hydroxy-2-methyl-pyran-4-one). Although Ce(IV) is generally accepted as a structural analog for Pu(IV), and the maltol complexes of these two metals are isostructural, the corresponding bromomaltol complexes are strikingly different with respect to ligand orientation about the metal ion: All complexes exhibit trigonal dodecahedral coordination geometry but the Ce(IV)-bromomaltol complex displays an uncommon ligand arrangement not mirrored in the Pu(IV) complex, although the two metal species are generally accepted to be structural analogs.

Lawrence Berkeley National Laboratory; Raymond, Kenneth; Szigethy, Geza; Xu, Jide; Gorden, Anne E.V.; Teat, Simon J.; Shuh, David K.; Raymond, Kenneth N.

2008-02-12T23:59:59.000Z

329

Comparison between steady-state and dynamic I-V measurements from a single-cell thermionic fuel element  

SciTech Connect (OSTI)

A comparison between steady-state and dynamic I-V measurements from a single-cell thermionic fuel element (TFE) is made. The single-cell TFE used in this study is the prototype for the 40 kW{sub e} space nuclear power system that is similar to the 6 kW{sub e} TOPAZ-II. The steady-state I-V measurements influence the emitter temperature due to electron cooling. Therefore, to eliminate the steady-state I-V measurement influence on the TFE and provide a better understanding of the behavior of the thermionic energy converter and TFE characteristics, dynamic I-V measurements are made. The dynamic I-V measurements are made at various input power levels, cesium pressures, collector temperatures, and steady-state current levels. From these measurements, it is shown that the dynamic I-V's do not change the TFE characteristics at a given operating point. Also, the evaluation of the collector work function from the dynamic I-V measurements shows that the collector optimization is not due to a minimum in the collector work function but due to an emission optimization. Since the dynamic I-V measurements do not influence the TFE characteristics, it is believed that these measurements can be done at a system level to understand the influence of TFE placement in the reactor as a function of the core thermal distribution.

Wernsman, Bernard [New Mexico Engineering Research Institute Thermionics Evaluation Facility 901 University SE Albuquerque, New Mexico 87106 (United States)

1997-01-10T23:59:59.000Z

330

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]

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

Nero, A.V.

2010-01-01T23:59:59.000Z

331

World nuclear outlook 1995  

SciTech Connect (OSTI)

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

NONE

1995-09-29T23:59:59.000Z

332

Office of Advanced Nuclear Research Office of Nuclear Energy, Science and Technology  

E-Print Network [OSTI]

Integrate applicable work conducted in programs in the Offices of Nuclear Energy (Gen IV, NERI, I · FY 2010: Complete the design of a commercial-scale nuclear hydrogen production system · FY 2015 to budget uncertainties (risk/benefit) · Guide the development of technology to support decisions Develop

333

Pennsylvania Nuclear Profile - Power Plants  

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

Pennsylvania nuclear power plants, summer capacity and net generation, 2010" Pennsylvania nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Beaver Valley Unit 1, Unit 2","1,777","14,994",19.3,"FirstEnergy Nuclear Operating Company" "Limerick Unit 1, Unit 2","2,264","18,926",24.3,"Exelon Nuclear" "PPL Susquehanna Unit 1, Unit 2","2,450","18,516",23.8,"PPL Susquehanna LLC" "Peach Bottom Unit 2, Unit 3","2,244","18,759",24.1,"Exelon Nuclear" "Three Mile Island Unit 1",805,"6,634",8.5,"Exelon Nuclear"

334

Nuclear Reactions in Stars  

Science Journals Connector (OSTI)

21 February 1961 research-article Nuclear Reactions in Stars T. G. Cowling Thermonuclear reactions important for the generation of stellar energy during different phases of stellar evolution are discussed. The Royal...

1961-01-01T23:59:59.000Z

335

State Nuclear Profiles 2010  

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

electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 620 55.0 4,782 72.2 Hydro and Pumped Storage 324 28.7 1,347 20.3 Natural Gas - - 4...

336

Absolute nuclear material assay  

DOE Patents [OSTI]

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-05-15T23:59:59.000Z

337

Energy from nuclear power  

SciTech Connect (OSTI)

Nuclear power should play a pivotal and expanded role in supplying world energy, the authors says. Risks must be minimized by designing a new generation of safe reactors. Atomic energy's vast potential can be harnessed only if issues of safety, waste and nuclear-weapon proliferation are addressed by a globally administered institution. The current situation in nuclear power is described before addressing its future.

Haefele, W.

1990-09-01T23:59:59.000Z

338

Lithium and nuclear fusion  

Science Journals Connector (OSTI)

... the EEC of a decision on the siting of the Joint European Torus (JET) nuclear fusion project, worrying setbacks though these are for European fusion research, should not be allowed ... gain is the highest (about 1,800 per fusion reaction). The first generation of nuclear fusion reactors will therefore need a continuous supply of both deuterium and tritium fuel.

Nick Walton, Ed Spooner

1976-06-17T23:59:59.000Z

339

Developing the DSM-IV-DSM-IV Criteria to Identify Adolescent Problem Gambling in Non-Clinical Populations  

Science Journals Connector (OSTI)

This paper presents a revised version of DSM-IV-J criteria for youth, the DSM-IV-MR-J, together with psychometric data...gold standard measure.

Sue Fisher

2000-09-01T23:59:59.000Z

340

The MAX IV storage ring project  

Science Journals Connector (OSTI)

The design of the MAX IV 3 GeV ultralow-emittance storage ring is presented and the implementation of solutions to the technological challenges imposed by the compact multi-bend achromat lattice are described.

Tavares, P.F.

2014-08-27T23:59:59.000Z

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

SECTION IV: ATOMIC, MOLECULAR AND MATERIALS SCIENCE  

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

ATOMIC, MOLECULAR AND MATERIALS SCIENCE A semiempirical scaling law for target K x-ray production in heavy ion collisions... IV-1 R. L. Watson, Y. Peng, V. Horvat, and A....

342

International Energy Outlook 1999 - Nuclear Power  

Gasoline and Diesel Fuel Update (EIA)

nuclear.jpg (5137 bytes) nuclear.jpg (5137 bytes) Nuclear electricity generation remains flat in the IEO99 reference case, representing a declining share of the world’s total electricity consumption. Net reductions in nuclear capacity are projected for most industrialized nations. In 1997, a total of 2,276 billion kilowatthours of electricity was generated from nuclear power worldwide, providing 17 percent of the world’s electricity generation. Among the countries with operating nuclear power plants, national dependence on nuclear power for electricity varies greatly (Figure 53). Ten countries met at least 40 percent of their total electricity demand with generation from nuclear reactors. The prospects for nuclear power to maintain a significant share of worldwide electricity generation are uncertain, despite projected growth of

343

Specific activity of243Am and243Cm in the fuel of the 4th power-generating unit of the Chernobyl nuclear power plant  

Science Journals Connector (OSTI)

The activity ratios241Am/241Am.243Cm/244Cm, and242Cm/244Cm in core samples taken at the industrial site of the object Cover were measured. The content of243Am and243Cm in the fuel in the 4th power-generating un...

V. A. Ageev; S. L. Vyrichek; A. P. Lashko; T. N. Lashko; A. A. Odintsov

1999-11-01T23:59:59.000Z

344

Snap-Together Nuclear Power  

Science Journals Connector (OSTI)

Snap-Together Nuclear Power ... The U.S. moved further along last month on an experiment to build a new generation of nuclear power plant reactors. ... Supporters hope these physically smaller reactors will have more flexible applications and incur less financial risk and construction cost than the nations current fleet of 104 large and aging nuclear power plants. ...

JEFF JOHNSON

2012-12-09T23:59:59.000Z

345

Comparison between steady-state and dynamic I-V measurements from a single-cell thermionic fuel element  

SciTech Connect (OSTI)

A comparison between steady-state and dynamic I-V measurements from a single-cell thermionic fuel element (TFE) is made. The single-cell TFE used in this study is the prototype for the 40kW{sub e} space nuclear power system that is similar to the 6kW{sub e} TOPAZ-II. The steady-state I-V measurements influence the emitter temperature due to electron cooling. Therefore, to eliminate the steady-state I-V measurement influence on the TFE and provide a better understanding of the behavior of the thermionic energy converter and TFE characteristics, dynamic I-V measurements are made. The dynamic I-V measurements are made at various input power levels, cesium pressures, collector temperatures, and steady-state current levels. From these measurements, it is shown that the dynamic I-V{close_quote}s do not change the TFE characteristics at a given operating point. Also, the evaluation of the collector work function from the dynamic I-V measurements shows that the collector optimization is not due to a minimum in the collector work function but due to an emission optimization. Since the dynamic I-V measurements do not influence the TFE characteristics, it is believed that these measurements can be done at a system level to understand the influence of TFE placement in the reactor as a function of the core thermal distribution. {copyright} {ital 1997 American Institute of Physics.}

Wernsman, B. [New Mexico Engineering Research Institute Thermionics Evaluation Facility 901 University SE Albuquerque, New Mexico87106 (United States)

1997-01-01T23:59:59.000Z

346

Nuclear Energy  

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

Research Programs >> Nuclear Energy Error Error Nuclear Energy Home - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Energy Home - RCC * Increasing...

347

National Nuclear Data Center Nuclear Data Portal www.nndc.bnl.gov  

E-Print Network [OSTI]

National Nuclear Data Center #12;Nuclear Data Portal www.nndc.bnl.gov Nuclear Data Portal New generation of nuclear data services, using modern and powerful DELL servers, Sybase relational database software, Linux operating system, and Java programming language. The Portal includes nuclear structure

Ohta, Shigemi

348

THE NUCLEAR ENERGY REVOLUTION1966  

Science Journals Connector (OSTI)

...of the coming generation. It is this...cheap nuclear power, about which...water nuclear power plant. At its...for a coal-fired power plant of the...Utilities Rochester Gas & Electric Consolidated...available for generation 76 per cent of...

Alvin M. Weinberg; Gale Young

1967-01-01T23:59:59.000Z

349

Honoring Our Past, Securing Our Future | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

nuclear weapons into LEU fuel for U.S. power plants, generating 10 percent of U.S. electricity. Preventing nuclear smuggling and strengthening the nonproliferation regime -...

350

Nondestructive Spent Fuel Assay Using Nuclear Resonance Fluorescence  

E-Print Network [OSTI]

Techniques for Nuclear Safeguards," LA-UR 09-01188, ANSessential for many nuclear safeguards applications, such asof the Next Generation Safeguards Initiative, NA-241 has

Quiter, Brian

2010-01-01T23:59:59.000Z

351

ENSURING A SKILLED WORKFORCE FOR THE NUCLEAR RENAISSANCE The...  

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

Carolina. Georgia's four nuclear units account for more than one-fourth of the State's electricity generation. South Carolina's five nuclear units supply about half of the...

352

Definition: Distributed generation | Open Energy Information  

Open Energy Info (EERE)

generation generation Jump to: navigation, search Dictionary.png Distributed generation A term used by the power industry to describe localized or on-site power generation[1] View on Wikipedia Wikipedia Definition Distributed generation, also called on-site generation, dispersed generation, embedded generation, decentralized generation, decentralized energy or distributed energy, generates electricity from many small energy sources. Most countries generate electricity in large centralized facilities, such as fossil fuel, nuclear, large solar power plants or hydropower plants. These plants have excellent economies of scale, but usually transmit electricity long distances and can negatively affect the environment. Distributed generation allows collection of energy from many

353

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]

emergencies, Le. , accidents at nuclear facilities, there isas a result of nuclear accidents; these are the Protectiveassociated with a nuclear accident is of greater importance

Nero, A.V.

2010-01-01T23:59:59.000Z

354

The preparation for and survival of an EPA Title IV and Title V facility audit  

SciTech Connect (OSTI)

As part of the 1990 Clean Air Act Amendments, major facilities are required to obtain federally enforceable operating permits (Title V). In a separate permitting action, the electric utilities with units generating more then 25 megawatts are required to obtain permits for NO{sub x} and SO{sub x}, the emissions which contribute to acid rain (Title IV). The Title IV permit is included as part of the Title V permit. This paper will use an actual audit experience at a coal fired generation facility as a case study for the preparation for and outcome of an EPA Title IV Level 3 audit. The paper will document the procedures for preparation, the audit process, and the outcome. The audit is part of the EPA's process for review of the record keeping and instrument calibration methods outlined in Title IV. Both types of permits have many different record keeping and monitoring requirements as well as separate reporting requirements which are submitted to both federal; state and local regulatory agencies for review and evaluation. Title IV units include very specific instrument calibration/audit requirements, and Title V has compliance testing and monitoring requirements. Alliant Power was notified in August 1998 of the intent of EPA Region VII to conduct a Level 3 audit at the Lansing Generation Station. The US EPA and the State of Iowa intended to review all Title IV record keeping (Level 1), continuous emission monitoring calibrations and linearity testing (Level 2) and observe the annual Relative Accuracy Testing Audit performed by an outside contractor. In addition, during this facility site visit, the compliance with Title V permit requirements was also audited.

Facca, G.L.; Faler, M.

1999-07-01T23:59:59.000Z

355

Nuclear Regulatory Commission issuances  

SciTech Connect (OSTI)

This thirty-second volume of issuances (1--496) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Appeal Boards, Atomic Safety and Licensing Boards, and Administrative Law Judges it covers the period from July 1, 1990 to December 31, 1990. The hardbound edition of the Nuclear Regulatory commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. Issuances are referred to as follows: Commission--CLI, Atomic Safety and Licensing Appeal Boards--ALAB, Atomic Safety and Licensing Boards--LBP, Administrative Law Judges--ALJ, Directors'Decisions--DD, and Denial of Petitions for Rulemaking--DPRM. Specific facilities discussed are: Carroll County Nuclear Station; Palo Verde Nuclear Generating Station; Perry Nuclear Power Plant; Quad Cities Nuclear Power Stations; Seabrook Station; Shoreham Nuclear Generating Plant; Vermont Yankee Nuclear Power Station; and Vogtle Electric Generating Plant.

Not Available

1990-01-01T23:59:59.000Z

356

Problems and challenges of teaching nuclear energy physics in a small university  

Science Journals Connector (OSTI)

Internationally, new (classical) power plants are again being built, and a strong increase in the construction of new plants is expected in the future. In addition, there will soon be a demand for construction of more efficient ones, any of the six so-called Generation IV units, in an increasing number. On the contrary, the education of nuclear energy physics and techniques has stagnated, since little construction has been done over the last decades, and thus there has been little need of this kind of education. The paper presents the situation in Finland, especially the development that has been done over the last 5 years at Abo Akademi University in Turku, south-western Finland. It shows that it is possible to set up a strong educational programme in nuclear energy and provides some guidelines as how to do it.

Tom Lonnroth

2011-01-01T23:59:59.000Z

357

Nuclear Debate  

Science Journals Connector (OSTI)

Nuclear Debate ... This month, the Senate will consider the nominations of two women to serve on the Nuclear Regulatory Commission. ... Svinicki is a nuclear engineer with experience in the Department of Energys nuclear energy programs. ...

JEFF JOHNSON

2012-06-11T23:59:59.000Z

358

Nuclear power and the environment  

Science Journals Connector (OSTI)

Although nuclear power is not, in itself, the full answer to the problems of global warming and acid rain, it is true that nuclear power generation produces no carbon or nitrogen emissions. The wastes that nuclear power does produce are small in volume, and can be adequately isolated from the environment. The aim of this paper is to show that an expansion of the nuclear power industry should be one among several measures taken to reduce the world's use of fossil fuels.

Hans Blix

1990-01-01T23:59:59.000Z

359

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]

Health and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel3 of HEALTH AND SAFETY IMPACTS OF FOSSIL-FUEL NUCLEAR,HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL

Nero, A.V.

2010-01-01T23:59:59.000Z

360

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]

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

Nero, A.V.

2010-01-01T23:59:59.000Z

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


361

A REVIEW OF AIR QUALITY MODELING TECHNIQUES. VOLUME 8 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel

Rosen, L.C.

2010-01-01T23:59:59.000Z

362

Pomeroy IV Wind Farm | Open Energy Information  

Open Energy Info (EERE)

IV Wind Farm IV Wind Farm Facility Pomeroy IV Wind Farm Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner MidAmerican Energy Developer MidAmerican Energy Energy Purchaser MidAmerican Energy Location Pomeroy IA Coordinates 42.570484°, -94.702506° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":42.570484,"lon":-94.702506,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

363

Meadow Lake IV | Open Energy Information  

Open Energy Info (EERE)

Meadow Lake IV Meadow Lake IV Facility Meadow Lake IV Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Horizon Wind Energy Developer EDP Renewables Location Brookston IN Coordinates 40.601111°, -86.864167° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.601111,"lon":-86.864167,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

364

Annex IV Environmental Webinar | Department of Energy  

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

Annex IV Environmental Webinar Annex IV Environmental Webinar Annex IV Environmental Webinar January 23, 2014 12:00PM to 1:30PM EST Online The Energy Department will present a live webcast on Instrumentation for Monitoring Around Marine Renewable Energy Devices, highlighting themes that arose during a related workshop. Webinar presentations will include discussion on monitoring of near-field interactions between marine mammals and marine renewable energy converters, determining the distribution and habitat use of marine animals in the vicinity of marine renewable energy converters, and characterizing sound produced by marine renewable energy converters. 12:00 to 1:30 p.m. Eastern Standard Time 9:00 to 10:30 a.m. Pacific Standard Time Join Lync Meeting Join by phone866-528-1882 or 509-375-4555

365

Diophantine Generation,  

E-Print Network [OSTI]

Diophantine Generation, Horizontal and Vertical Problems, and the Weak Vertical Method Alexandra Shlapentokh Diophantine Sets, Definitions and Generation Diophantine Sets Diophantine Generation Properties of Diophantine Generation Diophantine Family of Z Diophantine Family of a Polynomial Ring Going Down Horizontal

Shlapentokh, Alexandra

366

Steam generator support system  

DOE Patents [OSTI]

A support system for connection to an outer surface of a J-shaped steam generator for use with a nuclear reactor or other liquid metal cooled power source. The J-shaped steam generator is mounted with the bent portion at the bottom. An arrangement of elongated rod members provides both horizontal and vertical support for the steam generator. The rod members are interconnected to the steam generator assembly and a support structure in a manner which provides for thermal distortion of the steam generator without the transfer of bending moments to the support structure and in a like manner substantially minimizes forces being transferred between the support structure and the steam generator as a result of seismic disturbances.

Moldenhauer, James E. (Simi Valley, CA)

1987-01-01T23:59:59.000Z

367

Steam generator support system  

DOE Patents [OSTI]

A support system for connection to an outer surface of a J-shaped steam generator for use with a nuclear reactor or other liquid metal cooled power source is disclosed. The J-shaped steam generator is mounted with the bent portion at the bottom. An arrangement of elongated rod members provides both horizontal and vertical support for the steam generator. The rod members are interconnected to the steam generator assembly and a support structure in a manner which provides for thermal distortion of the steam generator without the transfer of bending moments to the support structure and in a like manner substantially minimizes forces being transferred between the support structure and the steam generator as a result of seismic disturbances. 4 figs.

Moldenhauer, J.E.

1987-08-25T23:59:59.000Z

368

Tetrahydrothiophene complexes of technetium(IV)  

Science Journals Connector (OSTI)

A technetium(IV) complex of the composition trans-[TcCl4(tht)2] (tht=tetrahydrothiophene) is formed during heating of \\{K2TcCl6\\} in a mixture of tht and aqueous HCl. The thioether ligands are only weakly bonded and the red crystals slowly decompose under release of tht. The weak technetiumsulphur bonds are confirmed by TcS distances of 2.494(1) . The anionic thioether technetium(IV) complex [TcBr5(tht)]? is formed by the reaction of (NBu4)2[TcBr6] with neat tht. The tetrabutylammonium salt of the complex is indefinitely stable in air.

Adelheid Hagenbach; Ulrich Abram

2004-01-01T23:59:59.000Z

369

The Road to Controlled Nuclear Fusion  

Science Journals Connector (OSTI)

... is one atom of deuterium for every 7,000 atoms of ordinary hydrogen. Second, nuclear fusion does not generate as much radioactive waste as nuclear fission, so storage-a serious ... plants-does not constitute such a serious problem. By contrast with nuclear fission, however, nuclear fusion reactions cannot be sustained by themselves in matter which is in its normal state. ...

L. ARTSIMOVICH

1972-09-01T23:59:59.000Z

370

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect (OSTI)

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

371

Operational Experience in Nuclear Power Stations [and Discussion  

Science Journals Connector (OSTI)

...Operational Experience in Nuclear Power Stations...self-sustaining nuclear reaction to the present...time large-scale generation of electrical power from nuclear energy has become...the C.E.G.B. reactors have been in service...

1974-01-01T23:59:59.000Z

372

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network [OSTI]

Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

373

Carbon-free generation  

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

Carbon-free generation Carbon-free generation Carbon-free central generation of electricity, either through fossil fuel combustion with carbon dioxide capture and storage or development of renewable sources such as solar, wind, and/or nuclear power, is key to our future energy portfolio. Brookhaven also provides tools and techniques for studying geological carbon dioxide sequestration and analyzing safety issues for nuclear systems. Our nation faces grand challenges: finding alternative and cleaner energy sources and improving efficiency to meet our exponentially growing energy needs. Researchers at Brookhaven National Laboratory are poised to meet these challenges with basic and applied research programs aimed at advancing the effective use of renewable energy through improved conversion,

374

New York Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Indian Point Unit 2, Unit 3","2,063","16,321",39.0,"Entergy Nuclear Indian Point" "James A Fitzpatrick Unit 1",855,"6,361",15.2,"Entergy Nuc Fitzpatrick LLC" "Nine Mile Point Nuclear Station Unit 1, Unit 2","1,773","14,239",34.0,"Nine Mile Point Nuclear Sta LLC" "R E Ginna Nuclear Power Plant Unit 1",581,"4,948",11.8,"R.E. Ginna Nuclear Power Plant, LLC" "4 Plants

375

Characterization of the oxide formed in the presence of poly acrylic acid over the steam generator structural materials of nuclear power plants  

Science Journals Connector (OSTI)

On-line addition of polymeric dispersants, such as poly acrylic acid (PAA), to the steam generator (SG) results in the formation of a better protective inner oxide layer that reduces subsequent corrosion of structural materials. Its dispersive action inhibits the growth of a secondary oxide layer thereby facilitating their easy removal. This paper discusses the effect of PAA on the nature of oxides formed over the surfaces of SG. In the case of carbon steel, the inner oxide layer (magnetite) formed in the presence of PAA was protective. Electrochemical studies showed a minimum concentration of 350ppb of PAA was found to be optimum. On the monel surface, in the absence of PAA, nickel ferrite was formed while in the presence of PAA, the oxide formed was a mixture of oxides of copper and nickel. A concentration of 700ppb of PAA was found to be optimum for monel. In the case of incoloy, the effect of PAA was not discernible except for the size and morphology of the crystallites formed.

Akhilesh C. Joshi; Appadurai L. Rufus; Sumathi Suresh; Palogi Chandramohan; Srinivasan Rangarajan; Sankaralingam Velmurugan

2013-01-01T23:59:59.000Z

376

Nuclear Returns  

Science Journals Connector (OSTI)

Nuclear Returns ... For the first time since 1978, the Nuclear Regulatory Commission has given the green light for a new U.S. nuclear power plant. ... NRC granted a license to Southern Co. to build and operate twin 1,100-MW reactors adjacent to two operating nuclear power plants at its Vogtle nuclear facility, near Waynesboro, Ga. ...

JEFF JOHNSON

2012-02-19T23:59:59.000Z

377

PROGRESS TOWARDS NEXT GENERATION, WAVEFORM BASED THREE-DIMENSIONAL MODELS AND METRICS TO IMPROVE NUCLEAR EXPLOSION MONITORING IN THE MIDDLE EAST  

SciTech Connect (OSTI)

Efforts to update current wave speed models of the Middle East require a thoroughly tested database of sources and recordings. Recordings of seismic waves traversing the region from Tibet to the Red Sea will be the principal metric in guiding improvements to the current wave speed model. Precise characterizations of the earthquakes, specifically depths and faulting mechanisms, are essential to avoid mapping source errors into the refined wave speed model. Errors associated with the source are manifested in amplitude and phase changes. Source depths and paths near nodal planes are particularly error prone as small changes may severely affect the resulting wavefield. Once sources are quantified, regions requiring refinement will be highlighted using adjoint tomography methods based on spectral element simulations [Komatitsch and Tromp (1999)]. An initial database of 250 regional Middle Eastern events from 1990-2007, was inverted for depth and focal mechanism using teleseismic arrivals [Kikuchi and Kanamori (1982)] and regional surface and body waves [Zhao and Helmberger (1994)]. From this initial database, we reinterpreted a large, well recorded subset of 201 events through a direct comparison between data and synthetics based upon a centroid moment tensor inversion [Liu et al. (2004)]. Evaluation was done using both a 1D reference model [Dziewonski and Anderson (1981)] at periods greater than 80 seconds and a 3D model [Kustowski et al. (2008)] at periods of 25 seconds and longer. The final source reinterpretations will be within the 3D model, as this is the initial starting point for the adjoint tomography. Transitioning from a 1D to 3D wave speed model shows dramatic improvements when comparisons are done at shorter periods, (25 s). Synthetics from the 1D model were created through mode summations while those from the 3D simulations were created using the spectral element method. To further assess errors in source depth and focal mechanism, comparisons between the three methods were made. These comparisons help to identify problematic stations and sources which may bias the final solution. Estimates of standard errors were generated for each event's source depth and focal mechanism to identify poorly constrained events. A final, well characterized set of sources and stations will be then used to iteratively improve the wave speed model of the Middle East. After a few iterations during the adjoint inversion process, the sources will be reexamined and relocated to further reduce mapping of source errors into structural features. Finally, efforts continue in developing the infrastructure required to 'quickly' generate event kernels at the n-th iteration and invert for a new, (n+1)-th, wave speed model of the Middle East. While development of the infrastructure proceeds, initial tests using a limited number of events shows the 3D model, while showing vast improvement compared to the 1D model, still requires substantial modifications. Employing our new, full source set and iterating the adjoint inversions at successively shorter periods will lead to significant changes and refined wave speed structures of the Middle East.

Savage, B; Peter, D; Covellone, B; Rodgers, A; Tromp, J

2009-07-02T23:59:59.000Z

378

Fears About Nuclear Proliferation  

Science Journals Connector (OSTI)

Recovery and reuse of plutonium in nuclear power programs poses serious threats regarding diversion and terrorism ... A nuclear power plant typically generates about 1000 MW of electric power and, as a worrisome by-product, makes several kilograms a week of plutonium-239. ... Many tons of plutonium- 239 are produced in U.S. power plants; most of it remains in spent fuel elements now being held in interim storage. ...

WINSTON M MANNING

1985-08-12T23:59:59.000Z

379

Nuclear fuel cycle assessment of India: a technical study for U.S.-India cooperation  

E-Print Network [OSTI]

the existing uranium reserves in India, a complete historical assessment of ore production, conversion, and processing capabilities was performed using open source information and compared to independent reports. Nuclear energy and plutonium production... ANALYSIS TO PRESENT DAY ..........................................33 IV.A. Assessment of Plutonium Production and Use: Beginning till 1974 ...............34 IV.B. Assessment of Plutonium Production and Use: Beginning till 1998 ...............38 IV...

Woddi, Taraknath Venkat Krishna

2008-10-10T23:59:59.000Z

380

Under the Saturn IV Rocket | Department of Energy  

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

Rocket October 10, 2013 - 12:05pm Addthis Under the Saturn IV Rocket Photo credit: Kelly Visconti Under the Saturn IV Rocket Photo credit: Kelly Visconti On the Road with...

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

Nuclear | Open Energy Information  

Open Energy Info (EERE)

Nuclear Nuclear Jump to: navigation, search Click to return to AEO2011 page AEO2011 Data From AEO2011 report Full figure data for Figure 82. Reference Case Tables Table 1. Total Energy Supply, Disposition, and Price Summary Table 9. Electricy Generating Capacity Table 96. Electricity Generation by Electricity Market Module Region and Source Table 97. Electricity Generation Capacity by Electricity Market Module Region and Source Market Trends In the AEO2011 Reference case, nuclear power capacity increases from 101.0 gigawatts in 2009 to 110.5 gigawatts in 2035 (Figure 82), including 3.8 gigawatts of expansion at existing plants and 6.3 gigawatts of new capacity. The new capacity includes completion of a second unit at the Watts Bar site, where construction on a partially completed plant has

382

Enhanced-oil-recovery thermal processes, annex IV. Venezuela-MEM/USA-DOE fossil-energy report IV-1  

SciTech Connect (OSTI)

The Agreement between the United States and Venezuela was designed to further energy research and development in six areas. This report focuses on Annex IV - Enhanced-Oil-Recovery Thermal Processes which was divided into seven tasks. This report will discuss the information developed within Task I related to the Department of Energy providing data on the performance of insulated oil-well tubulars. Surface generated steam has been traditionally used in thermal enhanced oil recovery processes. In past years the tubing through which the steam is injected into the reservoir has been bare with relatively high heat losses. In recent years however various materials and designs for insulating the tubing to reduce heat losses have been developed. Evaluation of several of these designs in an instrumented test tower and in an oil field test environment was undertaken. These tests and the resulting data are presented.

Peterson, G.; Schwartz, E.

1983-04-01T23:59:59.000Z

383

Part of the National Nuclear User Facility Culham Materials  

E-Print Network [OSTI]

of Generation IV and fusion entering the market later this century, it is vital for the UK to develop a first-class users a greater range of apparatus. Current users � University of Bristol � University of Manchester

384

Nuclear tanker producing liquid fuels from air and water  

E-Print Network [OSTI]

Emerging technologies in CO? air capture, high temperature electrolysis, microchannel catalytic conversion, and Generation IV reactor plant systems have the potential to create a shipboard liquid fuel production system ...

Galle-Bishop, John Michael

2011-01-01T23:59:59.000Z

385

Nuclear Fusion  

Science Journals Connector (OSTI)

Although not yet developed at the commercial stage, nuclear fusion technology is still being considered as a ... used in nuclear warfare. Since research in nuclear fusion for the production of energy started abou...

Ricardo Guerrero-Lemus; Jos Manuel Martnez-Duart

2013-01-01T23:59:59.000Z

386

Nuclear Nonproliferation  

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

Nuclear Nonproliferation As more countries embrace nuclear power as a cost-effective and clean alternative to fossil fuels, the need exists to ensure that the nuclear fuel cycle is...

387

Nuclear Engineering Nuclear Criticality Safety  

E-Print Network [OSTI]

Nuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear, and neutron spectra. The NE nuclear criticality safety (NCS) capabilities are based on a staff with decades

Kemner, Ken

388

Media Transatlantic IV Traffic March 29 31, 2012  

E-Print Network [OSTI]

Conference Media Transatlantic IV ­ Traffic March 29 ­ 31, 2012 University of Paderborn, Germany . d e / r t g - a u t o m a t i s m s Media Transatlantic IV ­ Traffic Graduiertenkolleg Automatismen;Conference Media Transatlantic IV ­ Traffic March 29 ­ 31, 2012 University of Paderborn, Germany Room B 3

Paderborn, Universität

389

International Energy Outlook 2001 - Nuclear  

Gasoline and Diesel Fuel Update (EIA)

Nuclear Power Nuclear Power picture of a printer Printer Friendly Version (PDF) Nuclear power is projected to represent a growing share of the developing world’s electricity consumption from 1999 through 2020. New plant construction and license extensions for existing plants are expected to produce a net increase in world nuclear capacity. Nuclear power plants generated electricity in 29 countries in 1999. A total of 433 nuclear power reactors were in operation (Figure 61), including 104 in the United States, 59 in France, and 53 in Japan. The largest national share of electricity from nuclear power was in France, at 75 percent (Figure 62). Belgium, Bulgaria, France, Lithuania, Slovenia, Slovakia, Sweden, Ukraine, and South Korea depended on nuclear power for at least 40

390

Nuclear & Uranium - Data - U.S. Energy Information Administration (EIA)  

Gasoline and Diesel Fuel Update (EIA)

Find statistics on nuclear operable units, nuclear electricity net Find statistics on nuclear operable units, nuclear electricity net generation, nuclear share of electricity net generation, and capacity factor. + EXPAND ALL Summary Additional Formats Nuclear Overview: PDF CSV XLS Monthly statistics on nuclear operable units, nuclear electricity net generation, nuclear share of electricity net generation, and capacity factor. PDFXLS Annual statistics on nuclear generating units, power plants operations, and uranium. › Nuclear Generating Units, 1955-2010 › PDF XLS Nuclear Power Plant Operations, 1957-2010 › PDF XLS Uranium Overview, 1949-2010 › PDF XLS Uranium & Nuclear Fuel Additional Formats U.S. Uranium Reserves Estimates › Release Date: July 2010 The U.S. Energy Information Administration (EIA) has updated its estimates of uranium reserves for year-end 2008. This represents the first revision of the estimates since 2004. PDF

391

NUCLEAR REACTORS.  

E-Print Network [OSTI]

??Nuclear reactors are devices containing fissionable material in sufficient quantity and so arranged as to be capable of maintaining a controlled, self-sustaining NUCLEAR FISSION chain (more)

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

392

nuclear reactor  

Science Journals Connector (OSTI)

...a complex atomic apparatus used to obtain energy from nuclear fission chain reaction. Used to produce nuclear energy, radioactive isotopes, and artificial elements.... atomic pile ...

2009-01-01T23:59:59.000Z

393

Nuclear Energy  

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

Nuclear Energy Idaho National Laboratory is the Department of Energy's lead nuclear energy research and development facility. Building upon its legacy responsibilities,...

394

Nuclear Hydrogen  

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

Error Error Nuclear Hydrogen - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Hydrogen - RCC * Increasing your portlet timeout setting. *...

395

Nuclear Physics  

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

Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

396

Nuclear Waste and the Distant Future Nuclear Waste and the Distant Future  

E-Print Network [OSTI]

Nuclear Waste and the Distant Future 1 Nuclear Waste and the Distant Future PER F. PETERSON WILLIAM://www.issues.org/22.4/peterson.html Regulation of nuclear hazards must be consistent with rules governing other of the radioactive material generated by nuclear energy decays away over short times ranging from minutes to several

Kammen, Daniel M.

397

Radioactive target needs for nuclear reactor physics and nuclear astrophysics , G. Barreau1  

E-Print Network [OSTI]

Radioactive target needs for nuclear reactor physics and nuclear astrophysics B.Jurado1* , G Gradignan, France 2 IPN, CNRS/IN2P3, Univ. Paris-Sud, 91405 Orsay, France Abstract: Nuclear reaction cross sections of short-lived nuclei are key inputs for new generation nuclear reactor simulations and for models

Boyer, Edmond

398

Office of Nuclear Energy | Department of Energy  

Office of Environmental Management (EM)

Office of Nuclear Energy Small Modular Reactors Small Modular Reactors The Small Modular Reactor program advances the licensing and commercialization of this next-generation...

399

1. Generation 1 1. Generation  

E-Print Network [OSTI]

1. Generation 1 _________________________________________________________________________ 1. Generation Sound and vibrations or, in more general terms, oscillations of matter (solids or fluids) are generated in many different dynamic processes. The basic mechanisms which underlie these oscillations

Berlin,Technische Universität

400

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]

nuclear, geothermal, and fossil-fuel power plants. However,power plants, which are reviewed and licensed by the Nuclear Regulatory Commission (NRC), and relatively few areas of geothermal and

Nero, A.V.

2010-01-01T23:59:59.000Z

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


401

Nuclear Matter and Nuclear Dynamics  

E-Print Network [OSTI]

Highlights on the recent research activity, carried out by the Italian Community involved in the "Nuclear Matter and Nuclear Dynamics" field, will be presented.

M Colonna

2009-02-26T23:59:59.000Z

402

Nuclear Energy | Argonne National Laboratory  

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

Nuclear Energy Nuclear Energy Argonne has contributed to the development of civilian nuclear power for over 50 years. Our scientists and engineers conduct research in advanced nuclear energy systems, nonproliferation and national security, and environmental management. Nuclear energy is the largest generator of carbon-free electricity in use today, and it will play an increasing role in worldwide power generation as advanced reactor designs and improved fuel-cycle technologies are brought into commercial application. Nearly every commercial reactor in operation today was developed from Argonne research. Building on this heritage, we are supporting the reliable, safe and secure use of nuclear power worldwide - and fostering its increased use in the future by incorporating science and engineering

403

Scram signal generator  

DOE Patents [OSTI]

A scram signal generating circuit for nuclear reactor installations monitors a flow signal representing the flow rate of the liquid sodium coolant which is circulated through the reactor, and initiates reactor shutdown for a rapid variation in the flow signal, indicative of fuel motion. The scram signal generating circuit includes a long-term drift compensation circuit which processes the flow signal and generates an output signal representing the flow rate of the coolant. The output signal remains substantially unchanged for small variations in the flow signal, attributable to long term drift in the flow rate, but a rapid change in the flow signal, indicative of a fast flow variation, causes a corresponding change in the output signal. A comparator circuit compares the output signal with a reference signal, representing a given percentage of the steady state flow rate of the coolant, and generates a scram signal to initiate reactor shutdown when the output signal equals the reference signal.

Johanson, Edward W. (New Lenox, IL); Simms, Richard (Westmont, IL)

1981-01-01T23:59:59.000Z

404

Argonne nuclear pioneer: Leonard Koch  

SciTech Connect (OSTI)

Leonard Koch joined Argonne National Laboratory in 1948. He helped design and build Experimental Breeder Reactor-1 (EBR-1), the first reactor to generate useable amounts of electricity from nuclear energy.

Koch, Leonard

2012-01-01T23:59:59.000Z

405

Advances in Metallic Nuclear Fuel  

Science Journals Connector (OSTI)

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

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

1987-04-01T23:59:59.000Z

406

Michigan Nuclear Profile - All Fuels  

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

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

407

Minnesota Nuclear Profile - All Fuels  

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

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

408

Wisconsin Nuclear Profile - All Fuels  

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

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

409

Washington Nuclear Profile - All Fuels  

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

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

410

Virginia Nuclear Profile - All Fuels  

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

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

411

Implementation Plan and Initial Development of Nuclear Concrete Materials  

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

Implementation Plan and Initial Development of Nuclear Concrete Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program The FY10 activities for development of a nuclear concrete materials database to support the Light Water Reactor Sustainability Program are summarized. The database will be designed and constructed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In Phase I, a static database will be developed to manage searchable documents from the Structural Materials Handbook that contains information on nuclear concrete

412

Implementation Plan and Initial Development of Nuclear Concrete Materials  

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

Implementation Plan and Initial Development of Nuclear Concrete Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program The FY10 activities for development of a nuclear concrete materials database to support the Light Water Reactor Sustainability Program are summarized. The database will be designed and constructed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In Phase I, a static database will be developed to manage searchable documents from the Structural Materials Handbook that contains information on nuclear concrete

413

Where Now With Nuclear Power?  

Science Journals Connector (OSTI)

... disputes, the continuing breakdown of plant, increasing oil prices and soaring capital costs of nuclear power stations have all upset the economic balance between the four electricity generating fuels- coal, ... the chief factors in the energy equation is the fact that the capital cost of nuclear power stations is much greater than that of oil-fired stations: for about 200 million ...

1971-03-19T23:59:59.000Z

414

Nuclear choices  

SciTech Connect (OSTI)

This book contains part of the series New Liberal Arts, which is intended to make science and technology more accessible to students of the liberal arts. Volume in hand provides a comprehensive, multifaceted examination of nuclear energy, in nontechnical terms. Wolfson explains the basics of nuclear energy and radiation, nuclear power..., and nuclear weapons..., and he invites readers to make their own judgments on controversial nuclear issues. Illustrated with photos and diagrams. Each chapter contains suggestions for additional reading and a glossary. For policy, science, and general collections in all libraries. (ES) Topics contained include Atoms and nuclei. Effects and uses of radiation. Energy and People. Reactor safety. Nuclear strategy. Defense in the nuclear age. Nuclear power, nuclear weapons, and nuclear futures.

Wolfson, R.

1991-01-01T23:59:59.000Z

415

ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE  

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

Report of Report of ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE 24 October 2003 BURTON RICHTER, CHAIR DARLEANE C. HOFFMAN SEKAZI K. MTINGWA RONALD P. OMBERG SILVIE PILLON JOY L. REMPE I. INTRODUCTION AND SUMMARY The committee met in Washington on September 16 and 17 to review progress in the program with respect to a changed set of mission priorities. Our last meeting took place in December 2002 after the reorganization that had placed the Advanced Fuel Cycle Initiative (AFCI) and the GEN IV program together in the Advanced Nuclear Research Office (AN-20). Since mission priorities have been evolving, the committee felt that it should wait until they have settled down before we met again. We have kept in touch

416

Distributed Generation  

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

Untapped Value of Backup Generation Untapped Value of Backup Generation While new guidelines and regulations such as IEEE (Institute of Electrical and Electronics Engineers) 1547 have come a long way in addressing interconnection standards for distributed generation, utilities have largely overlooked the untapped potential of these resources. Under certain conditions, these units (primarily backup generators) represent a significant source of power that can deliver utility services at lower costs than traditional centralized solutions. These backup generators exist today in large numbers and provide utilities with another option to reduce peak load, relieve transmission congestion, and improve power reliability. Backup generation is widely deployed across the United States. Carnegie Mellon's Electricity

417

Nuclear power after Chernobyl  

Science Journals Connector (OSTI)

...admit in an intemational meeting that there was a weakness...generated from the Vienna meeting, focusing to a large...nuclear industry, and the public. NRC. The effect ofChernobyl...the percentage ofthe public in favor, and the bars...actions with respect to the Hanford graphite-core N-reactor...

JF Ahearne

1987-05-08T23:59:59.000Z

418

EIA - State Nuclear Profiles  

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

of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,966 4.6 41,335 10.0 Coal 22,335 20.6 150,173 36.5 Hydro and Pumped Storage 689 0.6...

419

Gen IV Materials Handbook Functionalities and Operation  

SciTech Connect (OSTI)

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

Ren, Weiju [ORNL

2009-12-01T23:59:59.000Z

420

Chapter 7 - Nuclear Energy  

Science Journals Connector (OSTI)

Abstract Nuclear energy grew rapidly during the 19601975 period in countries such as France, the United States, and Norway. But nuclear energy ran into problems in the 1970s because of public concern over the radioactive waste it generates, and this concern suppressed the further expansion of nuclear power. The public perception had begun to change in recent years, as concern about atmospheric carbon dioxide levels led to a renewed interest in energy sources not reliant on hydrocarbons. But, in 2010, a tsunami in Japan led to an accident at the Fukushima nuclear power plant, and the ensuing release of radioactive materials once again raised concerns about safety. At the same time, limited supplies of uranium have caused the price of that fuel material to go up. The solution to the shortage and resulting price increase is fast breeder reactors that use both uranium and thorium fuels. Unfortunately, this technology has not yet been perfected and commercialized.

Brian F. Towler

2014-01-01T23:59:59.000Z

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

defense nuclear security | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

nuclear security | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

422

Chernobyl Nuclear Accident | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Chernobyl Nuclear Accident | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

423

Countering Nuclear Terrorism and Trafficking | National Nuclear...  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism and Trafficking | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

424

ARIES-IV Nested Shell Blanket Design  

SciTech Connect (OSTI)

The ARIES-IV Nested Shell Blanket (NSB) Design is an alternate blanket concept of the ARIES-IV low activation helium-cooled reactor design. The reference design has the coolant routed in the poloidal direction and the inlet and outlet plena are located at the top and bottom of the torus. The NSB design has the high velocity coolant routed in the toroidal direction and the plena are located behind the blanket. This is of significance since the selected structural material is SiC-composite. The NSB is designed to have key high performance components with characteristic dimensions of no larger than 2 m. These components can be brazed to form the blanket module. For the diverter design, we eliminated the use of W as the divertor coating material by relying on the successful development of the gaseous divertor concept. The neutronics and thermal-hydraulic performance of both blanket concepts are similar. The selected blanket and divertor configurations can also meet all the projected structural, neutronics and thermal-hydraulics design limits and requirements. With the selected blanket and divertor materials, the design has a level of safety assurance rate of I (LSA-1), which indicates an inherently safe design.

Wong, C.P.C.; Redler, K.; Reis, E.E.; Will, R. [General Atomics, San Diego, CA (United States); Cheng, E. [TSI Research, Inc. (United States); Hasan, C.M.; Sharafat, S. [California Univ., Los Angeles, CA (United States)

1993-11-01T23:59:59.000Z

425

Generation Planning (pbl/generation)  

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

Generation Hydro Power Wind Power Monthly GSP BPA White Book Dry Year Tools Firstgov Generation Planning Thumbnail image of BPA White Book BPA White Book (1998 - 2011) Draft Dry...

426

Signature analysis of the primary components of the Koeberg nuclear power station / J.A. Bezuidenhout.  

E-Print Network [OSTI]

??In line with its commitment to safe nuclear power generation, the Koeberg Nuclear Power Station (KNPS) replaced the outdated vibration monitoring system with a modern (more)

Bezuidenhout, Jandr Albert

2010-01-01T23:59:59.000Z

427

A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation .  

E-Print Network [OSTI]

??With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to (more)

Iamsumang, Chonlagarn

2010-01-01T23:59:59.000Z

428

Hsp10 nuclear localization and changes in lung cells response to cigarette smoke suggest novel roles for this chaperonin  

Science Journals Connector (OSTI)

...author and source are credited. Hsp10 nuclear localization and changes in lung cells...isoelectric point shifts; and (iv) Hsp10 nuclear levels increased after CSE stimulation...epithelial cells|lung fibroblasts|nuclear localization| 2. Introduction The 10...

2014-01-01T23:59:59.000Z

429

Nuclear reactor characteristics and operational history  

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

Nuclear > U.S. reactor operation status tables Nuclear > U.S. reactor operation status tables Nuclear Reactor Operational Status Tables Release date: November 22, 2011 Next release date: November 2012 See also: Table 2. Ownership Data, Table 3. Characteristics and Operational History Table 1. Nuclear Reactor, State, Type, Net Capacity, Generation, and Capacity Factor PDF XLS Plant/Reactor Name Generator ID State Type 2009 Summer Capacity Net MW(e)1 2010 Annual Generation Net MWh2 Capacity Factor Percent3 Arkansas Nuclear One 1 AR PWR 842 6,607,090 90 Arkansas Nuclear One 2 AR PWR 993 8,415,588 97 Beaver Valley 1 PA PWR 892 7,119,413 91 Beaver Valley 2 PA PWR 885 7,874,151 102 Braidwood Generation Station 1 IL PWR 1,178 9,196,689 89

430

Nuclear Medicine | More Science | ORNL  

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

Nuclear Medicine Nuclear Medicine SHARE Nuclear Medicine The Medical Isotope Program is focused on the development of: improved reactor production and processing methods to provide medical radioisotopes; new radionuclide generator systems; design and evaluation of new radiopharmaceuticals for applications in nuclear medicine and oncology; and association with Medical Cooperative Programs throughout the world for the further pre-clinical testing and clinical evaluation of agents developed at ORNL. In the United States, only ORNL has the combined resources of a stable isotope inventory, the High Flux Isotope Reactor (HFIR), hot cell processing capabilities, and a wide range of support functions required for such research. These collective resources provide unique capabilities for

431

Nuclear Science  

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

Science Science and Engineering Education Sourcebook 2013 American Nuclear Society US Department of Energy Nuclear Science & Engineering Education Sourcebook 2013 North American Edition American Nuclear Society Education, Training, and Workforce Division US Department of Energy Office of Nuclear Energy Editor and Founder John Gilligan Professor of Nuclear Engineering North Carolina State University Version 5.13 Welcome to the 2013 Edition of the Nuclear Science and Engineering Education (NS&EE) Sourcebook. We have evolved and improved! The core mission of the Sourcebook has not changed, however. Our purpose is to facilitate interaction among faculty, students, industry, and government agencies to accomplish nuclear research, teaching and service activities. Since 1986 we have compiled critical information on nuclear

432

Nuclear reactions  

Science Journals Connector (OSTI)

Much reference has been made in the last chapter to nuclear energy levels and their various properties (e.g ... ways of doing this the use of nuclear reactions, and studies of how excited nuclei...

R. J. Blin-Stoyle FRS

1991-01-01T23:59:59.000Z

433

nuclear security  

National Nuclear Security Administration (NNSA)

3%2A en Shaping the future of nuclear detection http:nnsa.energy.govblogshaping-future-nuclear-detection

434

Nuclear Ukraine  

Science Journals Connector (OSTI)

... SIR - Your article (Nature 365, 599; 1993) on the US-Ukraine stalemate over nuclear weapons prompts the following remarks. The United States made a mistake ... nuclear weapons prompts the following remarks. The United States made a mistake in not recognizing Ukraine as a legitimate successor state to the Soviet nuclear arsenal and is still insisting that ...

Arno Arrak

1994-01-13T23:59:59.000Z

435

Virtual nuclear weapons  

SciTech Connect (OSTI)

The term virtual nuclear weapons proliferation and arsenals, as opposed to actual weapons and arsenals, has entered in recent years the American lexicon of nuclear strategy, arms control, and nonproliferation. While the term seems to have an intuitive appeal, largely due to its cyberspace imagery, its current use is still vague and loose. The author believes, however, that if the term is clearly delineated, it might offer a promising approach to conceptualizing certain current problems of proliferation. The first use is in a reference to an old problem that has resurfaced recently: the problem of growing availability of weapon-usable nuclear materials in civilian nuclear programs along with materials made `excess` to defense needs by current arms reduction and dismantlement. It is argued that the availability of these vast materials, either by declared nuclear-weapon states or by technologically advanced nonweapon states, makes it possible for those states to rapidly assemble and deploy nuclear weapons. The second use has quite a different set of connotations. It is derived conceptually from the imagery of computer-generated reality. In this use, one thinks of virtual proliferation and arsenals not in terms of the physical hardware required to make the bomb but rather in terms of the knowledge/experience required to design, assemble, and deploy the arsenal. Virtual weapons are a physics reality and cannot be ignored in a world where knowledge, experience, materials, and other requirements to make nuclear weapons are widespread, and where dramatic army reductions and, in some cases, disarmament are realities. These concepts are useful in defining a continuum of virtual capabilities, ranging from those at the low end that derive from general technology diffusion and the existence of nuclear energy programs to those at the high end that involve conscious decisions to develop or maintain militarily significant nuclear-weapon capabilities.

Pilat, J.F.

1997-08-01T23:59:59.000Z

436

Nuclear Engineer (Nuclear Safety Specialist)  

Broader source: Energy.gov [DOE]

A successful candidate of this position will serve as a Nuclear Engineer (Nuclear Safety Specialist) responsible for day-to-day technical monitoring, and evaluation of aspects of authorization...

437

IV1. Yoon and E. Crosbie  

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

19 19 IV1. Yoon and E. Crosbie May 1988 The APS Beam Transfer Line from Linac to Booster Synchrotron In this note, we describe the recently designed APS beam transport system to the booster synchrotron. Another transfer system which guides the beam from the booster to the storage ring is described in ref. 1, and therefore it not be treated here. The system of interest consists of two parts; the transfer line LTOA from the injector linac to the positron accumulator ring (PAR) and the transfer line ATOB from the accumulator ring to booster synchrotron. For the design, we assumed that the rms transverse emittance of the Jinac output beam is about 1.1 mm mrad at 450 MeV andthe energy spread is :11%. The plan view of the designed beam transfer line is shown in Fig. 1. In this figure, B1 bends the

438

Nuclear Deterrence  

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

Nuclear Deterrence Nuclear Deterrence Nuclear Deterrence LANL's mission is to develop and apply science and technology to ensure the safety, security, and effectiveness of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. April 12, 2012 A B-2 Spirit bomber refuels from a KC-135 Stratotanker A B-2 Spirit bomber refuels from a KC-135 Stratotanker. Contact Operator Los Alamos National Laboratory (505) 667-5061 Charlie McMillan, Director: "For the last 70 years there has not been a world war, and I have to think that our strong deterrent has something to do with that fact." Mission nuclear weapons Charlie McMillan, Director of Los Alamos National Laboratory 1:06 Director McMillan on nuclear deterrence While the role and prominence of nuclear weapons in U.S. security policy

439

Buildings Energy Data Book: 6.2 Electricity Generation, Transmission...  

Buildings Energy Data Book [EERE]

Summer Net Winter Plant Fuel Type Generators Capacity Capacity Capacity Coal Petroleum Natural Gas Other Gases Nuclear Hydroelectric Conventional Wind Solar Thermal and...

440

All of Hanford's underground waste tanks generate hydrogen gas...  

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

of Hanford's underground waste tanks generate hydrogen gas to some degree since the radioactivity in the waste releases hydrogen from basic nuclear reactions. The routine release...

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

Kraftwerk Union KWU Siemens Power Generation | Open Energy Information  

Open Energy Info (EERE)

Services Product: KWU is a provider of components and services to the commercial nuclear utility industry. References: Kraftwerk Union (KWU) - Siemens Power Generation.1...

442

At What Cost? A comparative evaluation of the social costs of selected electricity generation alternatives in Ontario.  

E-Print Network [OSTI]

??This thesis examines the private and external costs of electricity generated in Ontario by natural gas, wind, refurbished nuclear and new nuclear power. The purpose (more)

Icyk, Bryan

2007-01-01T23:59:59.000Z

443

CALIBRATING C-IV-BASED BLACK HOLE MASS ESTIMATORS  

SciTech Connect (OSTI)

We present the single-epoch black hole mass estimators based on the C IV {lambda}1549 broad emission line, using the updated sample of the reverberation-mapped active galactic nuclei and high-quality UV spectra. By performing multi-component spectral fitting analysis, we measure the C IV line widths (FWHM{sub C{sub IV}} and line dispersion, {sigma}{sub C{sub IV}}) and the continuum luminosity at 1350 A (L{sub 1350}) to calibrate the C-IV-based mass estimators. By comparing with the H{beta} reverberation-based masses, we provide new mass estimators with the best-fit relationships, i.e., M{sub BH}{proportional_to}L{sub 1350}{sup 0.50{+-}0.07}{sigma}{sub C{sub IV}{sup 2}} and M{sub BH}{proportional_to}L{sub 1350}{sup 0.52{+-}0.09} FWHM{sub C{sub IV}{sup 0.56{+-}0.48}}. The new C-IV-based mass estimators show significant mass-dependent systematic difference compared to the estimators commonly used in the literature. Using the published Sloan Digital Sky Survey QSO catalog, we show that the black hole mass of high-redshift QSOs decreases on average by {approx}0.25 dex if our recipe is adopted.

Park, Daeseong; Woo, Jong-Hak; Shin, Jaejin [Astronomy Program, Department of Physics and Astronomy, Seoul National University, Seoul 151-742 (Korea, Republic of); Denney, Kelly D., E-mail: pds2001@astro.snu.ac.kr, E-mail: woo@astro.snu.ac.kr, E-mail: jjshin@astro.snu.ac.kr, E-mail: kelly@dark-cosmology.dk [Dark Cosmology Centre, Niels Bohr Institute, Juliane Maries Vej 30, DK-2100 Copenhagen O (Denmark)

2013-06-20T23:59:59.000Z

444

www.inl.gov A Future of Nuclear Energy  

E-Print Network [OSTI]

www.inl.gov A Future of Nuclear Energy: The Nuclear Renaissance, the Role of INL, and Potential in Nuclear Energy · Electrical Generation Supply/Demand · Global Warming, Greenhouse Gas Emissions/kilowatt-hour) Facts regarding nuclear energy in the US #12;· Standardized designs based on modularization producing

445

Open problems in nuclear density functional theory  

E-Print Network [OSTI]

This note describes five subjects of some interest for the density functional theory in nuclear physics. These are, respectively, i) the need for concave functionals, ii) the nature of the Kohn-Sham potential for the radial density theory, iii) a proper implementation of a density functional for an "intrinsic" rotational density, iv) the possible existence of a potential driving the square root of the density, and v) the existence of many models where a density functional can be explicitly constructed.

B. G. Giraud

2009-11-30T23:59:59.000Z

446

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

447

Salton Sea IV Geothermal Facility | Open Energy Information  

Open Energy Info (EERE)

IV Geothermal Facility IV Geothermal Facility Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Salton Sea IV Geothermal Facility General Information Name Salton Sea IV Geothermal Facility Facility Salton Sea IV Sector Geothermal energy Location Information Address 6922 Crummer Rd. Location Calipatria, California Zip 92233 Coordinates 33.157511158558°, -115.63861370087° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":33.157511158558,"lon":-115.63861370087,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

448

The Role of Ceramics in a Resurgent Nuclear Industry  

SciTech Connect (OSTI)

With fuel oil and natural gas prices near record highs and worldwide energy demands increasing at an alarming rate, there is growing interest in revitalization of the nuclear power industry within the United States and across the globe. Ceramic materials have long played a very important part in the commercial nuclear industry with applications throughout the entire fuel cycle; from fuel fabrication to waste stabilization. As the international community begins to look at advanced fuel cycles that minimize waste and increase proliferation resistance, ceramic materials will play an even larger role. Many of the advanced reactor concepts being evaluated operate at high-temperature requiring the use of durable, heat-resistant materials. Ceramic fuels are being investigated for a variety of Generation IV reactor concepts. These include the traditional TRISO-coated particles as well as advanced inert-matrix fuels. In order to minimize wastes and legacy materials, ceramic processes are also being applied to fuel reprocessing operations. Ceramic materials continue to provide a vital contribution in ''closing the fuel cycle'' by stabilization of associated low-level and high-level wastes in highly durable grout, ceramics, and glass. In the next five years, programs that are currently in the conceptual phase will begin laboratory- and engineering-scale demonstrations. This will require production-scale demonstrations of several ceramic technologies from fuel form development to advanced stabilization methods. Within the next five to ten years, these demonstrations will move to even larger scales and will also include radioactive demonstrations of these advanced technologies. These radioactive demonstrations are critical to program success and will require advances in ceramic materials associated with nuclear energy applications.

Marra, J

2006-02-28T23:59:59.000Z

449

Nuclear Safety Specialist Functional Area Qualification Standard  

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

83-2007 83-2007 November 2007 DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1183-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1183-2007 iv INTENTIONALLY BLANK DOE-STD-1183-2007 v TABLE OF CONTENTS ACKNOWLEDGMENT ................................................................................................................ vii PURPOSE ....................................................................................................................................9

450

Thermoelectric Generators 1. Thermoelectric generator  

E-Print Network [OSTI]

. Cold Hot I - -- - - - - -- Figure 1 Electron concentration in a thermoelectric material. #12;2 A large1 Thermoelectric Generators HoSung Lee 1. Thermoelectric generator 1.1 Basic Equations In 1821 on the direction of current and material [3]. This is called the Thomson effect (or Thomson heat). These three

Lee, Ho Sung

451

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 tors. for of of These studies can examine safety systems or safety research programsnuclear power plants, and at risk. to reduce population The Light-water Reactor Safety Research Program

Nero, A.V.

2010-01-01T23:59:59.000Z

452

Actinide Corroles: Synthesis and Characterization of Thorium(IV) and Uranium(IV) bis(-chloride) Dimers  

SciTech Connect (OSTI)

The first synthesis and structural characterization of actinide corroles is presented. Thorium(IV) and uranium(IV) macrocycles of Mes2(p-OMePh)corrole were synthesised and characterized by single-crystal X-ray diffraction, UV-Visible spectroscopy, variable-temperature 1H NMR, ESI mass spectrometry and cyclic voltammetry.

Ward, Ashleigh L.; Buckley, Heather L.; Gryko, Daniel T.; Lukens, Wayne W.; Arnold, John

2013-12-01T23:59:59.000Z

453

Extending a MOOS-IvP Autonomy System and Users Guide to the IvPBuild Toolbox  

E-Print Network [OSTI]

This document describes how to extend the suite of MOOS applications and IvP Helm behaviors distributed with the MOOS-IvP software bundle from www.moos-ivp.org. It covers (a) a straw-man repository with a place-holder MOOS ...

Benjamin, Michael R.

2009-08-20T23:59:59.000Z

454

International Energy Outlook 2000 - Nuclear Power  

Gasoline and Diesel Fuel Update (EIA)

In the IEO2000 reference case, nuclear power represents a declining share of the world’s total electricity consumption from 1997 through 2020. Plant retirements are expected to produce net reductions in nuclear capacity in most of the industrialized nations. In the IEO2000 reference case, nuclear power represents a declining share of the world’s total electricity consumption from 1997 through 2020. Plant retirements are expected to produce net reductions in nuclear capacity in most of the industrialized nations. In 1998, a total of 2,291 billion kilowatthours of electricity was generated by nuclear power worldwide, providing 16 percent of the world’s total generation[1]. Among the countries with operating nuclear power plants, national dependence on nuclear energy for electricity varies greatly. Nine countries met at least 40 percent of total electricity demand with generation from nuclear reactors. Figure 68. Nuclear Shares of National Electricity Generation, 1998 [Sources] The prospects for nuclear power to maintain a significant share of

455

Small Modular Nuclear Reactors | Department of Energy  

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

Reactor Technologies » Small Modular Reactor Technologies » Small Modular Nuclear Reactors Small Modular Nuclear Reactors Cutaway of 2-Unit Generation mPower SMR Installation. | © 2012 Generation mPower LLC. All Rights Reserved. Reprinted with permission. Cutaway of 2-Unit Generation mPower SMR Installation. | © 2012 Generation mPower LLC. All Rights Reserved. Reprinted with permission. The development of clean, affordable nuclear power options is a key element of the Department of Energy's Office of Nuclear Energy (DOE-NE) Nuclear Energy Research and Development Roadmap. As a part of this strategy, a high priority of the Department has been to help accelerate the timelines for the commercialization and deployment of small modular reactor (SMR) technologies through the SMR Licensing Technical Support program. Begun

456

U.sup.+4 generation in HTER  

DOE Patents [OSTI]

A improved device and process for recycling spent nuclear fuels, in particular uranium metal, that facilitates the refinement and recovery of uranium metal from spent metallic nuclear fuels. The electrorefiner device comprises two anodes in predetermined spatial relation to a cathode. The anodese have separate current and voltage controls. A much higher voltage than normal for the electrorefining process is applied to the second anode, thereby facilitating oxidization of uranium (III), U.sup.+, to uranium (IV), U.sup.+4. The current path from the second anode to the cathode is physically shorter than the similar current path from the second anode to the spent nuclear fuel contained in a first anode shaped as a basket. The resulting U.sup.+4 oxidizes and solubilizes rough uranium deposited on the surface of the cathode. A softer uranium metal surface is left on the cathode and is more readily removed by a scraper.

Miller, William E. (Naperville, IL); Gay, Eddie C. (Park Forest, IL); Tomczuk, Zygmunt (Homer Glen, IL)

2006-03-14T23:59:59.000Z

457

Identification of nuclear weapons  

DOE Patents [OSTI]

A method and apparatus for non-invasively indentifying different types of nuclear weapons is disclosed. A neutron generator is placed against the weapon to generate a stream of neutrons causing fissioning within the weapon. A first detects the generation of the neutrons and produces a signal indicative thereof. A second particle detector located on the opposite side of the weapon detects the fission particles and produces signals indicative thereof. The signals are converted into a detected pattern and a computer compares the detected pattern with known patterns of weapons and indicates which known weapon has a substantially similar pattern. Either a time distribution pattern or noise analysis pattern, or both, is used. Gamma-neutron discrimination and a third particle detector for fission particles adjacent the second particle detector are preferably used. The neutrons are generated by either a decay neutron source or a pulled neutron particle accelerator.

Mihalczo, J.T.; King, W.T.

1987-04-10T23:59:59.000Z

458

Neutron Generator as a Neutron Source for BNCT  

Science Journals Connector (OSTI)

A neutron generator was investigated for a neutron source for BNCT. Neutron generators have some obvious advantages over nuclear reactors for this purpose. The neutron source is the reaction D(d,n)3He. Moderation...

Gad Shani; Lev Tsvang; Semion Rozin; Michael Quastel

1996-01-01T23:59:59.000Z

459

Benchmarking of MCNP for calculating dose rates at an interim storage facility for nuclear waste  

Science Journals Connector (OSTI)

......an interim storage facility for nuclear waste Burkhard Heuel-Fabianek Ralf...Research Centre Julich, Germany, nuclear waste is stored in drums and other vessels...Research Centre Julich (FZJ) nuclear waste is generated, which has to be......

Burkhard Heuel-Fabianek; Ralf Hille

2005-12-20T23:59:59.000Z

460

Prediction of Prostate-Specific Antigen Recurrence in Men with Long-term Follow-up Postprostatectomy Using Quantitative Nuclear Morphometry  

Science Journals Connector (OSTI)

...Using Quantitative Nuclear Morphometry Robert...Patana Fund. The costs of publication of...fact. Background: Nuclear morphometric signatures...predictive probability graphs were generated...patient-specific quantitative nuclear grade (QNG) alone...predictive probability graphs were generated...

Robert W. Veltri; M. Craig Miller; Sumit Isharwal; Cameron Marlow; Danil V. Makarov; and Alan W. Partin

2008-01-01T23:59:59.000Z

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


461

A Safer Nuclear Enterprise  

Science Journals Connector (OSTI)

...2012 at the Nuclear Security...leadership in nuclear enterprise...multinational assessment of emerging risks and consequences...to assess nuclear risks in...or nuclear terrorism. States...and nuclear power. Since 1945...nuclear power plant can mean...

Sidney D. Drell; George P. Shultz; Steven P. Andreasen

2012-06-08T23:59:59.000Z

462

Quasiseparable Generators  

Science Journals Connector (OSTI)

It is clear from the preceding chapter that any matrix has quasiseparable representations. By padding given quasiseparable generators with zero matrices of large sizes one ... large orders. However, one is lookin...

Yuli Eidelman; Israel Gohberg

2014-01-01T23:59:59.000Z

463

Nuclear astrophysics  

SciTech Connect (OSTI)

The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized.

Haxton, W.C.

1992-12-31T23:59:59.000Z

464

Nuclear astrophysics  

SciTech Connect (OSTI)

The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized.

Haxton, W.C.

1992-01-01T23:59:59.000Z

465

Nuclear Counterterrorism  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information.) Appendices A and B are Official Use Only. Point of contact is Adam Boyd (NA-82), 202-586-0010. Cancels DOE O 457.1 and DOE M 457.1-1.

2013-08-26T23:59:59.000Z

466

TABLE 2. U.S. Nuclear Reactor Ownership Data  

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

2. U.S. Nuclear Reactor Ownership Data" "PlantReactor Name","Generator ID","Utility Name - Operator","Owner Name","% Owned" "Arkansas Nuclear One",1,"Entergy Arkansas...

467

Uranium to Electricity: The Chemistry of the Nuclear Fuel Cycle  

Science Journals Connector (OSTI)

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

Frank A. Settle

2009-03-01T23:59:59.000Z

468

Nuclear Power  

Science Journals Connector (OSTI)

Nuclear Power ... THIS WEEKS issue contains six letters on nuclear power, a representative sample of the letters C&EN received in response to the editorial, Resist Hysteria, I wrote shortly after the earthquake and tsunami in Japan devastated the Fukushima Daiichi Nuclear Power Station (C&EN, March 21, page 5). ... Four of the six letters take sharp issue with the primary point I made in the editorial, which was that, despite the severity of the situation in Japan, nuclear power remains an essential component of our overall energy mix for the near to mid-term because it will help us avert the worst impacts of global climate disruption. ...

RUDY M. BAUM

2011-05-09T23:59:59.000Z

469

NUCLEAR STUDIES  

Science Journals Connector (OSTI)

Japanese nuclear power plant crisis sparks examination of U.S. REACTORS ... Calls are particularly zeroing in on reactors similar in location and design to those in Japan. ...

JEFF JOHNSON

2011-04-04T23:59:59.000Z

470

Evaluating the validities of different DSM-IV-based conceptual constructs of tobacco dependence.  

E-Print Network [OSTI]

Interview Schedule for DSM-IV (DIS-IV). St Louis, MO:R. A. Finding order in the DSM-IV nicotine dependence syn-Kilbey M. M. , Andreski P. DSM-III-R nicotine dependence in

Hendricks, Peter S; Prochaska, Judith J; Humfleet, Gary L; Hall, Sharon M

2008-01-01T23:59:59.000Z

471

Chapter 24 - Nuclear energy future  

Science Journals Connector (OSTI)

Abstract This chapter attempts to concisely describe the role that nuclear power may take in the meeting the worlds future energy needs. Historically, economic considerations have triumphed all other considerations when selecting an energy source. Nuclear power growth stagnated in the late twentieth century for a variety of reasons. A revival in nuclear reactor construction is beginning in the United States and elsewhere at the start of the twenty-first century. World energyand especially electricityuse is increasing and sustainable approaches to meeting this need are sought. With rising concern about climate change, nuclear power is found to be the lowest contributor to carbon dioxide emissions, even compared to solar and wind power. Besides electricity generation, power reactors can be utilized for large-scale desalination and hydrogen generation.

Raymond L. Murray; Keith E. Holbert

2015-01-01T23:59:59.000Z

472

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]

quality assurance Standard Review Plan totally dissolvedmore fully in the Standard Review Plan (see Stage 3). Seenuclear power plants: the Standard Review Plan The Nuclear

Nero, A.V.

2010-01-01T23:59:59.000Z

474

"1. Mystic Generating Station","Gas","Boston Generating LLC",1968  

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

Massachusetts" Massachusetts" "1. Mystic Generating Station","Gas","Boston Generating LLC",1968 "2. Brayton Point","Coal","Dominion Energy New England, LLC",1545 "3. Canal","Petroleum","Mirant Canal LLC",1119 "4. Northfield Mountain","Pumped Storage","FirstLight Power Resources Services LLC",1080 "5. Salem Harbor","Coal","Dominion Energy New England, LLC",744 "6. Fore River Generating Station","Gas","Boston Generating LLC",688 "7. Pilgrim Nuclear Power Station","Nuclear","Entergy Nuclear Generation Co",685 "8. Bear Swamp","Pumped Storage","Brookfield Power New England",600

475

EIA - State Nuclear Profiles  

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

Florida Nuclear Profile 2010 Florida profile Florida Nuclear Profile 2010 Florida profile Florida total electric power industry, summer capacity and net generation, by energy source, 2010 Primary Energy Source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,924 6.6 23,936 10.4 Coal 9,975 16.9 59,897 26.1 Hydro and Pumped Storage 55 0.1 177 0.1 Natural Gas 31,563 53.4 128,634 56.1 Other1 544 0.9 2,842 1.2 Other Renewable1 1,053 1.8 4,487 2.0 Petroleum 12,033 20.3 9,122 4.0 Total 59,147 100.0 229,096 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

476

EIA - State Nuclear Profiles  

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

North Carolina Nuclear Profile 2010 North Carolina profile North Carolina Nuclear Profile 2010 North Carolina profile North Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,958 17.9 40,740 31.7 Coal 12,766 46.1 71,951 55.9 Hydro and Pumped Storage 2,042 7.4 4,757 3.7 Natural Gas 6,742 24.4 8,447 6.6 Other 1 50 0.2 407 0.3 Other Renewable1 543 2.0 2,083 1.6 Petroleum 573 2.1 293 0.2 Total 27,674 100.0 128,678 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

477

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

California Nuclear Profile 2010 California profile California Nuclear Profile 2010 California profile California total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,390 6.5 32,201 15.8 Coal 374 0.6 2,100 1.0 Hydro and Pumped Storage 13,954 20.7 33,260 16.3 Natural Gas 41,370 61.4 107,522 52.7 Other 1 220 0.3 2,534 1.2 Other Renewable1 6,319 9.4 25,450 12.5 Petroleum 701 1.0 1,059 0.5 Total 63,328 100.0 204,126 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

478

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Georgia Nuclear Profile 2010 Georgia profile Georgia Nuclear Profile 2010 Georgia profile Georgia total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,061 11.1 33,512 24.6 Coal 13,230 36.1 73,298 54.0 Hydro and Pumped Storage 3,851 10.5 3,044 2.7 Natural Gas 12,668 34.6 23,884 15.9 Other 1 - - 18 * Other Renewable1 637 1.7 3,181 2.2 Petroleum 2,189 6.0 641 0.5 Total 36,636 100.0 128,698 100 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable. * = Absolute percentage less than 0.05.

479

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Mississippi Nuclear Profile 2010 Mississippi profile Mississippi Nuclear Profile 2010 Mississippi profile Mississippi total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,251 8.0 9,643 17.7 Coal 2,526 16.1 13,629 25.0 Natural Gas 11,640 74.2 29,619 54.4 Other 1 4 * 10 * Other Renewable1 235 1.5 1,504 2.8 Petroleum 35 0.2 18 0.1 Total 15,691 100.0 54,487 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable. * = Absolute percentage less than 0.05. Notes: Totals may not equal sum of components due to independent rounding.

480

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

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

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


481

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Massachusetts Nuclear Profile 2010 Massachusetts profile Massachusetts Nuclear Profile 2010 Massachusetts profile Massachusetts total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 685 5.0 5,918 13.8 Coal 1,669 12.2 8,306 19.4 Hydro and Pumped Storage 1,942 14.2 659 1.5 Natural Gas 6,063 44.3 25,582 59.8 Other 1 3 * 771 1.8 Other Renewable1 304 2.2 1,274 3.0 Petroleum 3,031 22.1 296 0.7 Total 13,697 100.0 42,805 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

482

Nuclear Power Overview  

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

Onofre Nuclear Generating Station Onofre Nuclear Generating Station San Onofre Nuclear Generating Station Bob Ashe-Everest Southern California Edison 10 Incoming New Fuel Inspecting New Fuel SONGS Unit 1 Fuel Storage SONGS Unit 1 Fuel Storage History History u Shipped 270 Fuel Assemblies (F/A) from Unit 1 to Morris, Illinois. u Transshipped 70 U1 F/As to U2 spent fuel pool (SFP). u Transshipped 118 U1 F/As to U3 SFP. SONGS ISFSI Loading SONGS ISFSI Loading u Moved 5 dry shielded canisters (DSC) from U3 SFP to the Independent Spent Fuel Storage Installation (ISFSI). Each DSC contains up to 24 F/As. u Moved 9 DSCs from U1 SFP to the ISFSI. u At total of 325 U1 F/As have been moved into dry storage to date. u Scheduled to move 3 DSCs from U2 SFP to the ISFSI May 2005. Canister into Cask FA being loaded into canister

483

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Michigan Nuclear Profile 2010 Michigan profile Michigan Nuclear Profile 2010 Michigan profile Michigan total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,947 13.2 29,625 26.6 Coal 11,531 38.7 65,604 58.8 Hydro and Pumped Storage 2,109 7.1 228 0.2 Natural Gas 11,033 37.0 12,249 11.0 Other 1 - - 631 0.6 Other Renewable1 571 1.9 2,832 2.5 Petroleum 640 2.1 382 0.3 Total 29,831 100.0 111,551 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

484

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Florida Nuclear Profile 2010 Florida profile Florida Nuclear Profile 2010 Florida profile Florida total electric power industry, summer capacity and net generation, by energy source, 2010 Primary Energy Source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,924 6.6 23,936 10.4 Coal 9,975 16.9 59,897 26.1 Hydro and Pumped Storage 55 0.1 177 0.1 Natural Gas 31,563 53.4 128,634 56.1 Other1 544 0.9 2,842 1.2 Other Renewable1 1,053 1.8 4,487 2.0 Petroleum 12,033 20.3 9,122 4.0 Total 59,147 100.0 229,096 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

485

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Missouri Nuclear Profile 2010 Missouri profile Missouri Nuclear Profile 2010 Missouri profile Missouri total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,190 5.5 8,996 9.7 Coal 12,070 55.5 75,047 81.3 Hydro and Pumped Storage 1,221 5.6 2,427 2.6 Natural Gas 5,579 25.7 4,690 5.1 Other 1 - - 39 * Other Renewable1 466 2.1 988 1.1 Petroleum 1,212 5.6 126 0.1 Total 21,739 100.0 92,313 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable. * = Absolute percentage less than 0.05.

486

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Alabama Nuclear Profile 2010 Alabama profile Alabama Nuclear Profile 2010 Alabama profile Alabama total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 5,043 15.6 37,941 24.9 Coal 11,441 35.3 63,050 41.4 Hydro and Pumped Storage 3,272 10.1 8,704 5.7 Natural Gas 11,936 36.8 39,235 25.8 Other1 100 0.3 643 0.4 Other Renewable1 583 1.8 2,377 1.6 Petroleum 43 0.1 200 0.1 Total 32,417 100.0 152,151 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

487

EIA - State Nuclear Profiles  

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

Arizona Nuclear Profile 2010 Arizona profile Arizona Nuclear Profile 2010 Arizona profile Arizona total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,937 14.9 31,200 27.9 Coal 6,233 23.6 43,644 39.1 Hydro and Pumped Storage 2,937 11.1 6,831 6.1 Natural Gas 13,012 49.3 29,676 26.6 Other 1 - - 15 * Other Renewable1 181 0.7 319 0.3 Petroleum 93 0.4 66 0.1 Total 26,392 100.0 111,751 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable. * = Absolute percentage less than 0.05.

488

EIA - State Nuclear Profiles  

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

Minnesota Nuclear Profile 2010 Minnesota profile Minnesota Nuclear Profile 2010 Minnesota profile Minnesota total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,549 10.8 13,478 25.1 Coal 4,789 32.5 28,083 52.3 Hydro and Pumped Storage 193 1.3 840 1.6 Natural Gas 4,936 33.5 4,341 8.1 Other 1 13 0.1 258 0.5 Other Renewable1 2,395 16.3 6,640 12.4 Petroleum 795 5.4 31 0.1 Total 14,715 100.0 53,670 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

489

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Pennsylvania Nuclear Profile 2010 Pennsylvania profile Pennsylvania Nuclear Profile 2010 Pennsylvania profile Pennsylvania total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 9,540 20.9 77,828 33.9 Coal 18,481 40.6 110,369 48.0 Hydro and Pumped Storage 2,268 5.0 1,624 0.7 Natural Gas 9,415 20.7 33,718 14.7 Other 1 100 0.2 1,396 0.6 Other Renewable1 1,237 2.7 4,245 1.8 Petroleum 4,534 9.9 571 0.2 Total 45,575 100.0 229,752 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

490

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

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

491

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

North Carolina Nuclear Profile 2010 North Carolina profile North Carolina Nuclear Profile 2010 North Carolina profile North Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,958 17.9 40,740 31.7 Coal 12,766 46.1 71,951 55.9 Hydro and Pumped Storage 2,042 7.4 4,757 3.7 Natural Gas 6,742 24.4 8,447 6.6 Other 1 50 0.2 407 0.3 Other Renewable1 543 2.0 2,083 1.6 Petroleum 573 2.1 293 0.2 Total 27,674 100.0 128,678 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

492

EIA - State Nuclear Profiles  

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

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

493

EIA - State Nuclear Profiles  

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

Georgia Nuclear Profile 2010 Georgia profile Georgia Nuclear Profile 2010 Georgia profile Georgia total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,061 11.1 33,512 24.6 Coal 13,230 36.1 73,298 54.0 Hydro and Pumped Storage 3,851 10.5 3,044 2.7 Natural Gas 12,668 34.6 23,884 15.9 Other 1 - - 18 * Other Renewable1 637 1.7 3,181 2.2 Petroleum 2,189 6.0 641 0.5 Total 36,636 100.0 128,698 100 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable. * = Absolute percentage less than 0.05.

494

EIA - State Nuclear Profiles  

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

Michigan Nuclear Profile 2010 Michigan profile Michigan Nuclear Profile 2010 Michigan profile Michigan total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,947 13.2 29,625 26.6 Coal 11,531 38.7 65,604 58.8 Hydro and Pumped Storage 2,109 7.1 228 0.2 Natural Gas 11,033 37.0 12,249 11.0 Other 1 - - 631 0.6 Other Renewable1 571 1.9 2,832 2.5 Petroleum 640 2.1 382 0.3 Total 29,831 100.0 111,551 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

495

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Louisiana Nuclear Profile 2010 Louisiana profile Louisiana Nuclear Profile 2010 Louisiana profile Louisiana total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (nw) Share of State total (percent) Net generation (thousand nwh) Share of State total (percent) Nuclear 2,142 8.0 18,639 18.1 Coal 3,417 12.8 23,924 23.3 Hydro and Pumped Storage 192 0.7 1,109 1.1 Natural Gas 19,574 73.2 51,344 49.9 Other 1 213 0.8 2,120 2.1 Other Renewable1 325 1.2 2,468 2.4 Petroleum 881 3.3 3,281 3.2 Total 26,744 100.0 102,885 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.

496

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Illinois Nuclear Profile 2010 Illinois profile Illinois Nuclear Profile 2010 Illinois profile Illinois total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 11,441 25.9 96,190 47.8 Coal 15,551 35.2 93,611 46.5 Hydro and Pumped Storage 34 0.1 119 0.1 Natural Gas 13,771 31.2 5,724 2.8 Other 1 145 0.3 461 0.2 Other Renewable1 2,078 4.7 5,138 2.6 Petroleum 1,106 2.5 110 0.1 Total 44,127 100.0 201,352 100 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable.