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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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1

ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE  

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

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

2

January 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

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

3

March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

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

4

October 2003, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

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

5

October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY  

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

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

6

Nuclear fusion advances  

Science Conference Proceedings (OSTI)

The last decade has seen advances in the shaping and confinement of plasmas, and in approaches to noninductive current drive. Here, the author presents an overview of nuclear fusion advances between 1983-93 examining: fusion milestones; plasma shaping; ...

W. Sweet

1994-02-01T23:59:59.000Z

7

UNEDF: Advanced Scienti?c Computing Collaboration Transforms the Low-Energy Nuclear Many-Body Problem  

Science Conference Proceedings (OSTI)

With diverse scienti?c backgrounds, the UNEDF SciDAC collaboration of nuclear theorists, applied mathematicians, and computer scientists is developing a comprehensive description of nuclei and their reactions that delivers maximum predictive power with quanti?ed uncertainties. This paper describes the UNEDF collaboration and identi?es attributes that classify UNEDF as a successful computational collaboration. We illustrate signi?cant milestones accomplished by UNEDF through integrative solutions using the most reliable theoretical approaches, the most advanced algorithms, and leadership class computational resources.

Nam, Hai A.; Stoitsov, M.; Nazarewicz, Witold; Bulgac, Aurel; Hagen, Gaute; Kortelainene, Markus; Maris, P.; Pei, Junchen; Roche, Kenneth J.; Schunck, Nicolas; Thompson, Ian; Vary, James; Wild, Stefan

2012-11-03T23:59:59.000Z

8

Malaysia: economic transformation advances oil palm industry  

Science Conference Proceedings (OSTI)

Malaysia is currently the world’s largest exporter of palm oil although it is the second-largest producer of the oil after neighboring Indonesia. Malaysia: economic transformation advances oil palm industry Inform Magazine Biofuels and Bioproducts and Bi

9

ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE  

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

Reactor (SFR) * Gas-Cooled Fast Reactor (GFR) * Lead-Bismuth-Cooled Fast Reactor (LFR) * Molten Salt Reactor (MSR). While the international community will study all six concepts,...

10

Advanced Reactor Development and Technology - Nuclear Engineering...  

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

Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Nuclear Data Program Advanced Reactor Development Overview Advanced Fast Reactor...

11

Advancements in nuclear waste assay.  

E-Print Network (OSTI)

??The research described in this thesis is directed at advancing the state of the practice of the non-destructive gamma-ray assay of nuclear waste containers. A… (more)

Curtis, Deborah Claire

2008-01-01T23:59:59.000Z

12

Advanced Nuclear Fuels  

Science Conference Proceedings (OSTI)

Oct 19, 2010 ... The United States Department of Energy has defined an approach to energy security that includes sustainable nuclear energy. To achieve ...

13

University Program in Advanced Technology | National Nuclear...  

National Nuclear Security Administration (NNSA)

University Program in Advanced Technology | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

14

Advanced nuclear plant control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

15

Structural Materials in Advanced Nuclear Energy Systems  

Science Conference Proceedings (OSTI)

Apr 28, 2008 ... Structural Materials in Advanced Nuclear Energy Systems: The Need for ... of functionalized interfaces for optimization of materials properties.

16

Advanced Nuclear Reactors | Department of Energy  

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

Advanced Nuclear Advanced Nuclear Reactors Advanced Nuclear Reactors Turbulent Flow of Coolant in an Advanced Nuclear Reactor Visualizing Coolant Flow in Sodium Reactor Subassemblies Sodium-cooled Fast Reactor (SFR) Coolant Flow At the heart of a nuclear power plant is the reactor. The fuel assembly is placed inside a reactor vessel where all the nuclear reactions occur to produce the heat and steam used for power generation. Nonetheless, an entire power plant consists of many other support components and key structures like coolant pipes; pumps and tanks including their surrounding steel framing; and concrete containment and support structures. The Reactors Product Line within NEAMS is concerned with modeling the reactor vessel as well as those components of a complete power plant that

17

Advanced Nuclear Medicine Initiative Owen Lowe  

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

Isotopes for Life Isotopes for Life Isotopes for Life Advanced Nuclear Medicine Initiative Owen Lowe Office of Isotopes for Medicine and Science Office of Nuclear Energy, Science and Technology October 1, 2002 Isotopes for Life Isotopes for Life Isotopes for Life Office of Nuclear Energy, Science and Technology Lowe/Oct01_02 ANMI to NERAC.ppt (2) Advanced Nuclear Medicine Initiative Advanced Nuclear Medicine Initiative 6 Sponsor nuclear medical science research using a peer-review selection process * 9 three-year research grants awarded 6 Sponsor the training of individuals in nuclear medical science * 5 three-year education grants awarded 6 Continue research and education programs to completion; however, no additional funds for new grants is in the FY 2003 budget Isotopes for Life Isotopes for Life

18

Presented by Collaboration for Advanced Nuclear  

E-Print Network (OSTI)

Presented by Collaboration for Advanced Nuclear Simulation: Predictive Reactor Simulation for GNEP Kevin Clarno Reactor Analysis, NST Nuclear Science and Technology Division #12;2 Clarno_GNEP_SC07 Many operating nuclear reactors worldwide 2 Clarno_GNEP_SC07 Immediate response to global warming Designs static

19

Transform, Protect and Advance - DOE's IT Modernization Strategy |  

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

Transform, Protect and Advance - DOE's IT Modernization Transform, Protect and Advance - DOE's IT Modernization Strategy Transform, Protect and Advance - DOE's IT Modernization Strategy September 5, 2012 - 12:57pm Addthis The Obama Administration's Digital Government Strategy provides a vision for a 21st century government that lays a strong foundation for modernizing technology services across the Federal Government. At Energy, we're implementing a three-pillar approach -- Transform, Protect and Advance - as part of this broader strategy, driving more secure, cost-effective, and efficient IT infrastructure and services. Transforming IT architecture to drive cost savings and streamlined operations The Department is leveraging new tools and services that will further reduce costs and streamline operations - making our IT infrastructure

20

Transform, Protect and Advance - DOE's IT Modernization Strategy |  

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

Transform, Protect and Advance - DOE's IT Modernization Transform, Protect and Advance - DOE's IT Modernization Strategy Transform, Protect and Advance - DOE's IT Modernization Strategy September 5, 2012 - 12:57pm Addthis The Obama Administration's Digital Government Strategy provides a vision for a 21st century government that lays a strong foundation for modernizing technology services across the Federal Government. At Energy, we're implementing a three-pillar approach -- Transform, Protect and Advance - as part of this broader strategy, driving more secure, cost-effective, and efficient IT infrastructure and services. Transforming IT architecture to drive cost savings and streamlined operations The Department is leveraging new tools and services that will further reduce costs and streamline operations - making our IT infrastructure

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Advances in metallic nuclear fuel  

Science Conference Proceedings (OSTI)

Metallic nuclear fuels have generated renewed interest for advanced liquid metal reactors (LMRs) due to their physical properties, ease of fabrication, irradiation behavior, and simple reprocessing. Irradiation performance for both steady-state and transient operations is excellent. Ongoing irradiation tests in Argonne-West's Idaho-based Experimental Breeder Reactor II (EBR-II) have surpassed 100,000 MWd/T burnup and are on their way to a lifetime burnup of 150,000 MWd/T or greater. Metallic fuel also has a unique neutronic characteristic that enables benign reactor responses to loss-of-flow without scram and loss-of-heat-sink without scram accident conditions. This inherent safety potential of metallic fuel was demonstrated in EBR-II just one year ago. Safety tests performed in the reactor have also demonstrated that there is ample margin to fuel element cladding failure under transient overpower conditions. These metallic fuel attributes are key ingredients of the integral fast reactor (IFR) concept being developed at Argonne National Laboratory.

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

1987-04-01T23:59:59.000Z

22

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

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

Global Nuclear Energy Partnership Fact Sheet - Develop Advanced Burner Reactors Global Nuclear Energy Partnership Fact Sheet - Develop Advanced Burner Reactors GNEP will develop...

23

Energy Department Announces New Investments in Advanced Nuclear...  

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

Agencies You are here Home Energy Department Announces New Investments in Advanced Nuclear Power Reactors Energy Department Announces New Investments in Advanced Nuclear...

24

Advanced research workshop: nuclear materials safety  

SciTech Connect

The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of nuclear experience on a common objectiveÑthe safe and secure storage and disposition of excess fissile nuclear materials.

Jardine, L J; Moshkov, M M

1999-01-28T23:59:59.000Z

25

Advanced Nuclear Fuel | Y-12 National Security Complex  

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

Lithium-based Technologies Advanced Nuclear Fuel Advanced Nuclear Fuel Y-12 developers co-roll zirconium clad LEU-Mo. The Y-12 National Security Complex has over 60 years of...

26

Global Nuclear Energy Partnership Fact Sheet - Develop Advanced Burner  

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

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

27

Advanced Nuclear Fuel Development for the Future in the United ...  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, Materials Science & Technology 2010. Symposium, Materials Solutions for the Nuclear Renaissance. Presentation Title, Advanced ...

28

Advanced Computation & Visualization - Nuclear Engineering Division...  

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

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

29

Advanced nuclear reactor public opinion project  

SciTech Connect

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

Benson, B.

1991-07-25T23:59:59.000Z

30

NEAMS: The Nuclear Energy Advanced Modeling and Simulation Program  

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

NEAMS: The Nuclear Energy Advanced NEAMS: The Nuclear Energy Advanced Modeling and Simulation Program The Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program is developing a simulation tool kit using leading-edge computational methods that will accelerate the development and deployment of nuclear power technologies that employ enhanced safety and security features, produce power more cost-effectively, and utilize natural resources more efficiently. The NEAMS ToolKit

31

Advanced nuclear plant control room complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

32

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

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

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

33

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software...  

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

and Simulation (NEAMS) Software Verification and Validation (V&V) Plan Requirements Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software Verification and...

34

University Program in Advanced Technology | National Nuclear Security  

National Nuclear Security Administration (NNSA)

University Program in Advanced Technology | National Nuclear Security University Program in Advanced Technology | 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 University Program in Advanced Technology Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing and

35

Development of Ceramic Waste Forms for an Advanced Nuclear ...  

Science Conference Proceedings (OSTI)

Presentation Title, Development of Ceramic Waste Forms for an Advanced Nuclear Fuel Cycle. Author(s), James C. Marra, Amanda Billings, Kyle Brinkman,  ...

36

Advanced Nuclear Fuel Concepts for Minor Actinide Burning  

Science Conference Proceedings (OSTI)

Abstract Scope, New fuel cycle strategies entail advanced nuclear fuel concepts. This especially applies for the burning of minor actinides in a fast reactor cycle ...

37

Basic Research Needs for Advanced Nuclear Energy Systems - TMS  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... Report of the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems. Summarizes current status ...

38

University Program in Advanced Technology | National Nuclear...  

National Nuclear Security Administration (NNSA)

& Technology Programs > Office of Advanced Simulation and Computing and Institutional R&D Programs > Institutional Research & Development > University Program in Advanced...

39

Decision Framework for Evaluating Advanced Nuclear Fuel Cycle Options  

Science Conference Proceedings (OSTI)

EPRI is working to develop tools to support long-term strategic planning for research, development, and demonstration (RD&D) of advanced nuclear fuel cycle technologies for electricity generation. The development of a decision framework to help guide the eventual deployment of advanced nuclear technologies represents a key component of this effort. This interim report describes the structure of a prototypical EPRI decision framework and illustrates how that framework can be applied to assess nuclear fuel...

2011-12-13T23:59:59.000Z

40

Energy Department Announces New Investments in Advanced Nuclear Power  

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

Energy Department Announces New Investments in Advanced Nuclear Energy Department Announces New Investments in Advanced Nuclear Power Reactors Energy Department Announces New Investments in Advanced Nuclear Power Reactors June 27, 2013 - 2:20pm Addthis News Media Contact (202) 586-4940 WASHINGTON - As part of the Obama Administration's all-of-the-above strategy to accelerate clean energy leadership and to enable a low-carbon economy, the Energy Department today announced $3.5 million for four advanced nuclear reactor projects that go beyond traditional light water designs. These projects -- led by General Atomics, GE Hitachi, Gen4 Energy and Westinghouse -- will address key technical challenges to designing, building and operating the next generation of nuclear reactors. These steps support the President's plan to cut carbon pollution and spark innovation

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Energy Department Announces New Investments in Advanced Nuclear Power  

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

Investments in Advanced Nuclear Investments in Advanced Nuclear Power Reactors Energy Department Announces New Investments in Advanced Nuclear Power Reactors June 27, 2013 - 2:20pm Addthis News Media Contact (202) 586-4940 WASHINGTON - As part of the Obama Administration's all-of-the-above strategy to accelerate clean energy leadership and to enable a low-carbon economy, the Energy Department today announced $3.5 million for four advanced nuclear reactor projects that go beyond traditional light water designs. These projects -- led by General Atomics, GE Hitachi, Gen4 Energy and Westinghouse -- will address key technical challenges to designing, building and operating the next generation of nuclear reactors. These steps support the President's plan to cut carbon pollution and spark innovation

42

Advanced safeguards for the nuclear renaissance  

SciTech Connect

The global expansion of nuclear energy provides not only the benefit of carbon-neutral electricity, but also the potential for proliferation concern as well. Nuclear safeguards implemented at the state level (domestic) and at the international level by the International Atomic Energy Agency (IAEA) are essential for ensuring that nuclear materials are not misused and are thereby a critical component of the increased usage of nuclear energy. In the same way that the 1950's Atoms for Peace initiative provided the foundation for a robust research and development program in nuclear safeguards, the expansion of nuclear energy that is underway today provides the impetus to enter a new era of technical development in the safeguards community. In this paper, we will review the history of nuclear safeguards research and development as well future directions.

Miller, Michael C [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

43

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software  

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

Advanced Modeling and Simulation (NEAMS) Software Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan Requirements Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan Requirements The purpose of the NEAMS Software V&V Plan is to define what the NEAMS program expects in terms of V&V for the computational models that are developed under NEAMS. NEAMS Software Verification and Validation Plan Requirements Version 0.pdf More Documents & Publications NEAMS Quarterly Report for January-March 2013 Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program Plan CRAD, Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities

44

Advanced Nuclear Reactors | Department of Energy  

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

in Sodium Reactor Subassemblies Sodium-cooled Fast Reactor (SFR) Coolant Flow At the heart of a nuclear power plant is the reactor. The fuel assembly is placed inside a reactor...

45

Advanced Nuclear Technology: Embedded Sensors in Concrete  

Science Conference Proceedings (OSTI)

One of the greatest hindrances to concrete inspection in nuclear power plants is the lack of accessibility to many concrete structures. This report aims to address the use of embedded sensors in future power plants to allow for inspection of inaccessible structures and to facilitate continuous monitoring of the critical concrete structures of the power plants. Monitoring these structures using embedded sensors is especially important because many large concrete structures in nuclear power plants are not ...

2011-11-30T23:59:59.000Z

46

Environmental Degradation Nuclear IX-Advance Mailer  

Science Conference Proceedings (OSTI)

Aug 5, 1999 ... dation of Materials in Nuclear Power Systems - Water Reac- tors will be held August ..... SIMS Examination of Steam Generator Tubing for Evidence of. Internal Oxidation: ..... Neutron Irradiation-Induced Changes in Percent IGSCC of Ther- .... Recent Data on Void Formation in US & Russian Stainless Steels.

47

Advanced control methodology for intelligent universal transformers based on fuzzy logic controllers  

Science Conference Proceedings (OSTI)

Intelligent Universal Transformer (IUT) is a power electronic base transformer introducing for Advanced Distribution Automation (ADA) in future. ADA is the state of art employing the new architecture based on both the flexible electrical network and ... Keywords: ADA, FLC, IED, IUT, membership function, power electronic

Maryam Sadeghi; Magid Gholami

2011-03-01T23:59:59.000Z

48

Development of Advanced Concepts for Nuclear Processes in Deuterated Metals  

Science Conference Proceedings (OSTI)

The excess heat generated in electrochemical cells with palladium cathodes and heavy water electrolyte appears to be far too large to result from chemical or metallurgical transformation. The evidence implies that the heat source is a nuclear reaction of some as yet undetermined nature.

1994-09-23T23:59:59.000Z

49

Current Comparison of Advanced Nuclear Fuel Cycles  

SciTech Connect

This paper compares potential nuclear fuel cycle strategies – once-through, recycling in thermal reactors, sustained recycle with a mix of thermal and fast reactors, and sustained recycle with fast reactors. Initiation of recycle starts the draw-down of weapons-usable material and starts accruing improvements for geologic repositories and energy sustainability. It reduces the motivation to search for potential second geologic repository sites. Recycle in thermal-spectru

Steven Piet; Trond Bjornard; Brent Dixon; Robert Hill; Gretchen Matthern; David Shropshire

2007-04-01T23:59:59.000Z

50

Human factors aspects of advanced instrumentation in the nuclear industry  

SciTech Connect

An important consideration in regards to the use of advanced instrumentation in the nuclear industry is the interface between the instrumentation system and the human. A survey, oriented towards identifying the human factors aspects of digital instrumentation, was conducted at a number of United States (US) and Canadian nuclear vendors and utilities. Human factors issues, subsumed under the categories of computer-generated displays, controls, organizational support, training, and related topics were identified. 20 refs., 2 tabs.

Carter, R.J.

1989-01-01T23:59:59.000Z

51

Nuclear Maintenance Application Center: Dry Type Transformer and Reactor Application and Maintenance Guide  

Science Conference Proceedings (OSTI)

This report is focused on dry-type transformers used in unit secondary substations of nuclear power plants for power delivery purposes. This report does not cover instrument transformers, nor is it specifically for transformers used in grounding circuits, although these usages are addressed in Section 3.The primary purpose of this report is to inform the engineer or technician who has been assigned responsibility for secondary unit substation transformers in a nuclear station’s ...

2012-11-28T23:59:59.000Z

52

MIT - Center for Advanced Nuclear Energy Systems | Open Energy Information  

Open Energy Info (EERE)

MIT - Center for Advanced Nuclear Energy Systems MIT - Center for Advanced Nuclear Energy Systems Jump to: navigation, search Logo: MIT - Center for Advanced Nuclear Energy Systems Name MIT - Center for Advanced Nuclear Energy Systems Address 77 Massachusetts Avenue, 24-215 Place Cambridge, Massachusetts Zip 02139-4307 Phone number (617) 452-2660 Coordinates 42.3613041°, -71.0967653° 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":42.3613041,"lon":-71.0967653,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

53

Cost estimate guidelines for advanced nuclear power technologies  

SciTech Connect

To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies. 10 refs., 8 figs., 32 tabs.

Delene, J.G.; Hudson, C.R. II.

1990-03-01T23:59:59.000Z

54

Advanced Nuclear Fuel Cycles -- Main Challenges and Strategic Choices  

Science Conference Proceedings (OSTI)

This report presents the results of a critical review of the technological challenges to the growth of nuclear energy, emerging advanced technologies that would have to be deployed, and fuel cycle strategies that could conceivably involve interim storage, plutonium recycling in thermal and fast reactors, reprocessed uranium recycling, and transmutation of minor actinide elements and fission products before eventual disposal of residual wastes.

2010-09-02T23:59:59.000Z

55

Advanced Nuclear Technology Advanced Light Water Reactor Utility Requirements Document, Revision 12  

Science Conference Proceedings (OSTI)

The utility requirement document (URD) is an industry-developed technical foundation for the design of advanced light water reactors (ALWRs). It was created with the objective of providing a comprehensive set of plant functional requirements that are considered important to utilities considering the construction of a nuclear plant and in ensuring successful deployment and operation of the plant. The scope of the URD is broad, addressing the entire plant (including the nuclear steam supply system, ...

2013-12-16T23:59:59.000Z

56

Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants  

SciTech Connect

OAK-B135 Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants

O' Connell, J. Michael

2002-01-01T23:59:59.000Z

57

Basic Research Needs for Advanced Nuclear Systems. Report of the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems, July 31-August 3, 2006  

Science Conference Proceedings (OSTI)

The global utilization of nuclear energy has come a long way from its humble beginnings in the first sustained nuclear reaction at the University of Chicago in 1942. Today, there are over 440 nuclear reactors in 31 countries producing approximately 16% of the electrical energy used worldwide. In the United States, 104 nuclear reactors currently provide 19% of electrical energy used nationally. The International Atomic Energy Agency projects significant growth in the utilization of nuclear power over the next several decades due to increasing demand for energy and environmental concerns related to emissions from fossil plants. There are 28 new nuclear plants currently under construction including 10 in China, 8 in India, and 4 in Russia. In the United States, there have been notifications to the Nuclear Regulatory Commission of intentions to apply for combined construction and operating licenses for 27 new units over the next decade. The projected growth in nuclear power has focused increasing attention on issues related to the permanent disposal of nuclear waste, the proliferation of nuclear weapons technologies and materials, and the sustainability of a once-through nuclear fuel cycle. In addition, the effective utilization of nuclear power will require continued improvements in nuclear technology, particularly related to safety and efficiency. In all of these areas, the performance of materials and chemical processes under extreme conditions is a limiting factor. The related basic research challenges represent some of the most demanding tests of our fundamental understanding of materials science and chemistry, and they provide significant opportunities for advancing basic science with broad impacts for nuclear reactor materials, fuels, waste forms, and separations techniques. Of particular importance is the role that new nanoscale characterization and computational tools can play in addressing these challenges. These tools, which include DOE synchrotron X-ray sources, neutron sources, nanoscale science research centers, and supercomputers, offer the opportunity to transform and accelerate the fundamental materials and chemical sciences that underpin technology development for advanced nuclear energy systems. The fundamental challenge is to understand and control chemical and physical phenomena in multi-component systems from femto-seconds to millennia, at temperatures to 1000?C, and for radiation doses to hundreds of displacements per atom (dpa). This is a scientific challenge of enormous proportions, with broad implications in the materials science and chemistry of complex systems. New understanding is required for microstructural evolution and phase stability under relevant chemical and physical conditions, chemistry and structural evolution at interfaces, chemical behavior of actinide and fission-product solutions, and nuclear and thermomechanical phenomena in fuels and waste forms. First-principles approaches are needed to describe f-electron systems, design molecules for separations, and explain materials failure mechanisms. Nanoscale synthesis and characterization methods are needed to understand and design materials and interfaces with radiation, temperature, and corrosion resistance. Dynamical measurements are required to understand fundamental physical and chemical phenomena. New multiscale approaches are needed to integrate this knowledge into accurate models of relevant phenomena and complex systems across multiple length and time scales.

Roberto, J.; Diaz de la Rubia, T.; Gibala, R.; Zinkle, S.; Miller, J.R.; Pimblott, S.; Burns, C.; Raymond, K.; Grimes, R.; Pasamehmetoglu, K.; Clark, S.; Ewing, R.; Wagner, A.; Yip, S.; Buchanan, M.; Crabtree, G.; Hemminger, J.; Poate, J.; Miller, J.C.; Edelstein, N.; Fitzsimmons, T.; Gruzalski, G.; Michaels, G.; Morss, L.; Peters, M.; Talamini, K.

2006-10-01T23:59:59.000Z

58

ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS  

SciTech Connect

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

Marra, J.

2010-09-29T23:59:59.000Z

59

Foundational development of an advanced nuclear reactor integrated safety code.  

SciTech Connect

This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

2010-02-01T23:59:59.000Z

60

Shielding considerations for advanced space nuclear reactor systems  

SciTech Connect

To meet the anticipated future space power needs, the Los Alamos National Laboratory is developing components for a compact, 100 kW/sub e/-class heat pipe nuclear reactor. The reactor uses uranium dioxide (UO/sub 2/) as its fuel, and is designed to operate around 1500 k. Heat pipes are used to remove thermal energy from the core without the use of pumps or compressors. The reactor heat pipes transfer mal energy to thermoelectric conversion elements that are advanced versions of the converters used on the enormously successful Voyager missions to the outer planets. Advanced versions of this heat pipe reactor could also be used to provide megawatt-level power plants. The paper reviews the status of this advanced heat pipe reactor and explores the radiation environments and shielding requirements for representative manned and unmanned applications.

Angelo, J.P. Jr.; Buden, D.

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

The AMP (Advanced MultiPhysics) Nuclear Fuel Performance Code  

Science Conference Proceedings (OSTI)

The AMP (Advanced MultiPhysics) Nuclear Fuel Performance code is a new, three-dimensional, multi-physics tool that uses state-of-the-art solution methods and validated nuclear fuel models to simulate the nominal operation and anticipated operational transients of nuclear fuel. The AMP Nuclear Fuel Performance code leverages existing validated material models from traditional fuel performance codes and the Scale/ORIGEN-S spent-fuel characterization code to provide an initial capability that is shown to be sufficiently accurate for a single benchmark problem and anticipated to be accurate for a broad range of problems. The thermomechanics-chemical foundation can be solved in a time-dependent or quasi-static approach with any variation of operator-split or fully-coupled solutions at each time step. The AMP Nuclear Fuel Performance code provides interoperable interfaces to leading computational mathematics tools, which will simplify the integration of the code into existing parallel code suites for reactor simulation or lower-length-scale coupling. A baseline validation of the AMP Nuclear Fuel Performance code has been performed through the modeling of an experiment in the Halden Reactor Project (IFA-432), which is the first validation problem incorporated in the FRAPCON Integral Assessment report.

Clarno, Kevin T [ORNL; Philip, Bobby [ORNL; Cochran, Bill [ORNL; Sampath, Rahul S [ORNL; Allu, Srikanth [ORNL; Barai, Pallab [ORNL; Simunovic, Srdjan [ORNL; Ott, Larry J [ORNL; Pannala, Sreekanth [ORNL; Dilts, Gary A [ORNL; Mihaila, Bogdan [ORNL; Yesilyurt, Gokhan [ORNL; Lee, Jung Ho [Argonne National Laboratory (ANL); Banfield, James E [ORNL; Berrill, Mark A [ORNL

2012-01-01T23:59:59.000Z

62

Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.  

SciTech Connect

This report presents requirements for advanced simulation of nuclear reactor and chemical processing plants that are of interest to the Global Nuclear Energy Partnership (GNEP) initiative. Justification for advanced simulation and some examples of grand challenges that will benefit from it are provided. An integrated software tool that has its main components, whenever possible based on first principles, is proposed as possible future approach for dealing with the complex problems linked to the simulation of nuclear reactor and chemical processing plants. The main benefits that are associated with a better integrated simulation have been identified as: a reduction of design margins, a decrease of the number of experiments in support of the design process, a shortening of the developmental design cycle, and a better understanding of the physical phenomena and the related underlying fundamental processes. For each component of the proposed integrated software tool, background information, functional requirements, current tools and approach, and proposed future approaches have been provided. Whenever possible, current uncertainties have been quoted and existing limitations have been presented. Desired target accuracies with associated benefits to the different aspects of the nuclear reactor and chemical processing plants were also given. In many cases the possible gains associated with a better simulation have been identified, quantified, and translated into economical benefits.

Palmiotti, G.; Cahalan, J.; Pfeiffer, P.; Sofu, T.; Taiwo, T.; Wei,T.; Yacout, A.; Yang, W.; Siegel, A.; Insepov, Z.; Anitescu, M.; Hovland,P.; Pereira, C.; Regalbuto, M.; Copple, J.; Willamson, M.

2006-12-11T23:59:59.000Z

63

Advanced nuclear reactor public opinion project. Interim report  

SciTech Connect

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

Benson, B.

1991-07-25T23:59:59.000Z

64

Directions for advanced use of nuclear power in century XXI  

SciTech Connect

Nuclear power can provide a significant contribution to electricity generation and meet other needs of the world and the US during the next century provided that certain directions are taken to achieve its public acceptance. These directions include formulation of projections of population, energy consumption, and energy resources over a responsible period of time. These projections will allow assessment of cumulative effects on the environment and on fixed resources. Use of fossil energy resources in a century of growing demand for energy must be considered in the context of long-term environmental damage and resource depletion. Although some question the validity of these consequences, they can be mitigated by use of advanced fast reactor technology. It must be demonstrated that nuclear power technology is safe, resistant to material diversion for weapon use, and economical. An unbiased examination of all the issues related to energy use, especially of electricity, is an essential direction to take.

Walter, C E

1999-05-01T23:59:59.000Z

65

Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants  

E-Print Network (OSTI)

Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants ANL-AFCI-168 of Nuclear Reactor and Chemical Separation Plants ANL-AFCI-168 by G. Palmiotti, J. Cahalan, P. Pfeiffer, T;2 ANL-AFCI-168 Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants G

Anitescu, Mihai

66

Indicator system for advanced nuclear plant control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

67

NUCLEAR DATA RESOURCES FOR ADVANCED ANALYSIS AND SIMULATION.  

SciTech Connect

The mission of the National Nuclear Data Center (NNDC) includes collection, evaluation, and dissemination of nuclear physics data for basic nuclear research and applied nuclear technologies. In 2004, to answer the needs of nuclear data users, NNDC completed a project to modernize storage and management of its databases and began offering new nuclear data Web services. Examples of nuclear reaction, nuclear structure and decay database applications along with a number of nuclear science codes are also presented.

PRITYCHENKO, B.

2006-06-05T23:59:59.000Z

68

ENTERPRISE SRS: LEVERAGING ONGOING OPERATIONS TO ADVANCE NUCLEAR FUEL CYCLES RESEARCH AND DEVELOPMENT PROGRAMS  

SciTech Connect

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

Murray, A.; Marra, J.; Wilmarth, B.; Mcguire, P.; Wheeler, V.

2013-07-03T23:59:59.000Z

69

DOE Issues Landmark Rule for Risk Insurance for Advanced Nuclear Facilities  

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

Landmark Rule for Risk Insurance for Advanced Nuclear Landmark Rule for Risk Insurance for Advanced Nuclear Facilities DOE Issues Landmark Rule for Risk Insurance for Advanced Nuclear Facilities May 8, 2006 - 10:36am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) issued on Saturday, the interim final rule required by the Energy Policy Act of 2005 (EPACT) for risk insurance to facilitate construction of new advanced nuclear power facilities. The rule establishes the requirements for risk insurance to cover costs associated with certain regulatory or litigation-related delays in the start-up of new nuclear power plants. The resurgence of nuclear power is a key component of President Bush's Advanced Energy Initiative. The Standby Support provisions of EPACT (section 638), also referred to as federal risk insurance, authorize the Secretary of Energy to enter into

70

Conference on Advances in Materials Science | National Nuclear...  

National Nuclear Security Administration (NNSA)

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

71

United States and Italy Sign Agreements to Advance Developments in Nuclear  

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

Italy Sign Agreements to Advance Developments in Italy Sign Agreements to Advance Developments in Nuclear Energy United States and Italy Sign Agreements to Advance Developments in Nuclear Energy September 30, 2009 - 12:00am Addthis Washington, D.C. - U.S. Secretary of Energy Steven Chu and Italian Minister for Economic Development Claudio Scajola today signed two important nuclear energy agreements that may lead to construction of new nuclear power plants and improved cooperation on advanced nuclear energy systems and fuel cycle technologies in both countries. The U.S.-Italy Joint Declaration Concerning Industrial and Commercial Cooperation in the Nuclear Energy Sector, which was signed on behalf of the United States by Secretary Chu and Deputy Secretary of Commerce Dennis F. Hightower, affirms the strong interest of the United States and Italy to

72

The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology  

Science Conference Proceedings (OSTI)

To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team projects and faculty/staff exchanges. In June of 2008, the first week-long ATR NSUF Summer Session was attended by 68 students, university faculty and industry representatives. The Summer Session featured presentations by 19 technical experts from across the country and covered topics including irradiation damage mechanisms, degradation of reactor materials, LWR and gas reactor fuels, and non-destructive evaluation. High impact research results from leveraging the entire research infrastructure, including universities, industry, small business, and the national laboratories. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. Current partner facilities include the MIT Reactor, the University of Michigan Irradiated Materials Testing Laboratory, the University of Wisconsin Characterization Laboratory, and the University of Nevada, Las Vegas transmission Electron Microscope User Facility. Needs for irradiation of material specimens at tightly controlled temperatures are being met by dedication of a large in-pile pressurized water loop facility for use by ATR NSUF users. Several environmental mechanical testing systems are under construction to determine crack growth rates and fracture toughness on irradiated test systems.

T. R. Allen; J. B. Benson; J. A. Foster; F. M. Marshall; M. K. Meyer; M. C. Thelen

2009-05-01T23:59:59.000Z

73

Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research  

SciTech Connect

The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called User’s Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. User’s week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

John Jackson; Todd Allen; Frances Marshall; Jim Cole

2013-03-01T23:59:59.000Z

74

AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT  

SciTech Connect

An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mills/kwh. In a similar plant with a net electrical output of 530 Mw, the estimated power generating cost is 5.4 mills/ kwh. Most of the components of the plant are within the capability of current technology. The major exception is the fuel material, uranium carbide. Preliminary results of the development work now in progress indicate that uranium carbide would be an excellent fuel for high-temperature reactors, but temperature and burnup limitation have yet to be firmly established. Additional development work is also required on the steam generators. These are the single-barrier type similar to those which will be used in the Enrico Fernri Fast Breeder Reactor plant but produce steam at higher pressure and temperature. Questions also remain regarding the use of nitrogen as a cover gas over sodium at 1200 deg F and compatibility of the materials used in the primary neutron shield. All of these questions are currently under investigation. (auth)

Churchill, J.R.; Renard, J.

1960-03-15T23:59:59.000Z

75

Thermal-Fluid Characterizations of ZnO and SiC Nanofluids for Advanced Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Technical Paper / Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics

In Cheol Bang; Ji Hyun Kim

76

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

Science Conference Proceedings (OSTI)

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

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

77

Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s Transformational Materials Initiative  

DOE Green Energy (OSTI)

As the nation's nuclear weapons age and the demands placed on them change, significant challenges face the nuclear stockpile. Risks include material supply issues, ever-increasing lifecycle costs, and loss of technical expertise across the weapons complex. For example, non-nuclear materials are becoming increasingly difficult to replace because manufacturing methods and formulations have evolved in such a way as to render formerly available materials unprofitable, unsafe, or otherwise obsolete. Subtle formulation changes in available materials that occur without the knowledge of the weapons community for proprietary reasons have frequently affected the long-term performance of materials in the nuclear weapon environment. Significant improvements in performance, lifetime, or production cost can be realized with modern synthesis, modeling, and manufacturing methods. For example, there are currently supply and aging issues associated with the insensitive high explosive formulations LX-17 and PBX 9502 that are based on triaminotrinitrobenzene (TATB) and Kel-F, neither of which are commercially available today. Assuring the reliability of the stockpile through surveillance and regularly scheduled Life Extension Programs is an increasingly expensive endeavor. Transforming our current stockpile surveillance--a system based on destructive testing of increasingly valuable assets--to a system based on embedded sensors has a number of potential advantages that include long-term cost savings, reduced risk associated with asset transportation, state-of-health assessments in the field, and active management of the stockpile.

Maxwell, R; Fried, L; Campbell, G; Saab, A; Kotovsky, J; Carter, C; Chang, J

2009-10-11T23:59:59.000Z

78

Advanced Nuclear Technology: Impact of EPRI Pre-Operational and Operational Configuration Management Report (1022684) on the Nuclear Industry  

Science Conference Proceedings (OSTI)

EPRI Technical Report 1022684, Elements of Pre-Operational and Operational Configuration Management for a New Nuclear Facility, was developed by an EPRI Advanced Nuclear Technology (ANT) technical advisory group whose mission was to develop guidance for establishing a comprehensive configuration management (CM) program for the unique challenges of a new nuclear facility. The program elements developed for the pre-operation phase would then be in place to manage the configuration for the ...

2013-03-20T23:59:59.000Z

79

Containment building : architecture between the city and advanced nuclear reactors  

E-Print Network (OSTI)

Since the inception of nuclear energy research, the element thorium (Th) has been considered the superior fuel for nuclear reactions because of its potency, safety, abundance and reduced waste. Cold War agendas broke from ...

Pauli, Lisa M

2011-01-01T23:59:59.000Z

80

Potential Role of Nanotechnologies in Advanced Nuclear Energy ...  

Science Conference Proceedings (OSTI)

Office of Fuel Cycle Technologies. Office of Nuclear Energy. February 28, 2012. Nanotechnology Workshop. Rice University, Houston, Texas ...

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Program on Technology Innovation: Cladding and Structural Materials for Advanced Nuclear Energy Systems  

Science Conference Proceedings (OSTI)

This EPRI technical update gives an overview of the initial work being done under a 3-year research program on cladding and structural materials for advanced nuclear energy systems. This research is part of EPRI's Program on Technology Innovation.

2008-12-23T23:59:59.000Z

82

Programme A. Nuclear Power Subprogramme A.4 Technology Development for Advanced Reactor Lines  

E-Print Network (OSTI)

and the economic merits of centralized versus distributed production units. #12;Page 2 Programme B. Nuclear Fuel natural polymers. New marketable advanced materials (using, for example, the concept of nanomaterials

De Cindio, Fiorella

83

Development and Analysis of Advanced High-Temperature Technology for Nuclear Heat Transport and Power Conversion  

DOE Green Energy (OSTI)

This project by the Thermal Hydraulics Research Laboratory at U.C. Berkeley Studied advanced high-temperature heat transport and power conversion technology, in support of the Nuclear Hydrogen Initiative and Generation IV.

Per F. Peterson

2010-03-01T23:59:59.000Z

84

Program on Technology Innovation: Advanced Nuclear Technology--Component Margins and Monitoring Database  

Science Conference Proceedings (OSTI)

The Advanced Nuclear Technology Margins and Monitoring Database, available to EPRI members, documents a consensus of experts on issues relating to equipment design margins and monitoring recommendations for large capital, balance-of-plant (BOP) components important to power production.

2008-04-21T23:59:59.000Z

85

Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors  

E-Print Network (OSTI)

H. G. MacPherson The molten salt adventure Nuclear Scienceand P.F. Peterson, Molten-Salt-Cooled Advanced High-Clarno Assessment of candidate molten salt coolants for the

Galvez, Cristhian

2011-01-01T23:59:59.000Z

86

TRANSFORMATION  

SciTech Connect

Transformation, which alters the genetic makeup of an individual, is a concept that intrigues the human imagination. In Streptococcus pneumoniae such transformation was first demonstrated. Perhaps our fascination with genetics derived from our ancestors observing their own progeny, with its retention and assortment of parental traits, but such interest must have been accelerated after the dawn of agriculture. It was in pea plants that Gregor Mendel in the late 1800s examined inherited traits and found them to be determined by physical elements, or genes, passed from parents to progeny. In our day, the material basis of these genetic determinants was revealed to be DNA by the lowly bacteria, in particular, the pneumococcus. For this species, transformation by free DNA is a sexual process that enables cells to sport new combinations of genes and traits. Genetic transformation of the type found in S. pneumoniae occurs naturally in many species of bacteria (70), but, initially only a few other transformable species were found, namely, Haemophilus influenzae, Neisseria meningitides, Neisseria gonorrheae, and Bacillus subtilis (96). Natural transformation, which requires a set of genes evolved for the purpose, contrasts with artificial transformation, which is accomplished by shocking cells either electrically, as in electroporation, or by ionic and temperature shifts. Although such artificial treatments can introduce very small amounts of DNA into virtually any type of cell, the amounts introduced by natural transformation are a million-fold greater, and S. pneumoniae can take up as much as 10% of its cellular DNA content (40).

LACKS,S.A.

2003-10-09T23:59:59.000Z

87

Advancing Small Modular Reactors: How We're Supporting Next-Gen Nuclear  

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

Advancing Small Modular Reactors: How We're Supporting Next-Gen Advancing Small Modular Reactors: How We're Supporting Next-Gen Nuclear Energy Technology Advancing Small Modular Reactors: How We're Supporting Next-Gen Nuclear Energy Technology December 12, 2013 - 4:00pm Addthis The basics of small modular reactor technology explained. | Infographic by Sarah Gerrity, Energy Department. The basics of small modular reactor technology explained. | Infographic by Sarah Gerrity, Energy Department. Assistant Secretary Lyons Assistant Secretary Lyons Assistant Secretary for Nuclear Energy Nuclear energy continues to be an important part of America's diverse energy portfolio, and the Energy Department is committed to supporting a domestic nuclear industry.

88

Conference on Advances in Materials Science | National Nuclear...  

National Nuclear Security Administration (NNSA)

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

89

Advanced LWR Nuclear Fuel Cladding System Development Trade-off...  

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

composite Zr-based alloy hybrids, advanced Zr-based alloys, and engineered stainless steel alloys. Potential benefits and drawbacks have been identified in this study to aid...

90

Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview  

SciTech Connect

Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R & D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

Unal, Cetin [Los Alamos National Laboratory; Pasamehmetoglu, Kemal [IDAHO NATIONAL LAB; Carmack, Jon [IDAHO NATIONAL LAB

2010-01-01T23:59:59.000Z

91

Advanced Nuclear Technology: Potential Modification to Source Term Requirements  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commission’s Regulatory Guide 1.183 (RG 1.183), “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors” describes a method that the staff of the Nuclear Regulatory Commission considers acceptable in complying with alternative source term regulations for design basis accident dose consequence analysis. RG 1.183 establishes the alternative source term based onNUREG-1465, “Accident ...

2013-03-27T23:59:59.000Z

92

Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options  

SciTech Connect

The Nuclear Waste Policy Act requires the Secretary of Energy to inform Congress before 2010 on the need for a second geologic repository for spent nuclear fuel. By that time, the spent fuel discharged from current commercial reactors will exceed the statutory limit of the first repository. There are several approaches to eliminate the need for another repository in this century. This paper presents a high-level analysis of these spent fuel management options in the context of a full range of possible nuclear energy futures. The analysis indicates the best option to implement varies depending on the nuclear energy future selected.

Dixon, B.W.; Piet, S.J.

2004-10-03T23:59:59.000Z

93

Congressional Preferences and the Advancement of American Nuclear Waste Policy.  

E-Print Network (OSTI)

??The problem of nuclear waste disposal has existed since the time of the Manhattan Project in World War II. Although there exist a number of… (more)

Ternate, Rhoel Gonzales

2013-01-01T23:59:59.000Z

94

Discussions@TMS - Materials Issues for Advanced Nuclear Systems ...  

Science Conference Proceedings (OSTI)

Feb 27, 2007... for applications in high temperature nuclear reactor core materials, ... Theory of RIS was introduced and how over-size solute additions can ...

95

TRANSFORMER  

DOE Patents (OSTI)

Transformers of a type adapted for use with extreme high power vacuum tubes where current requirements may be of the order of 2,000 to 200,000 amperes are described. The transformer casing has the form of a re-entrant section being extended through an opening in one end of the cylinder to form a coaxial terminal arrangement. A toroidal multi-turn primary winding is disposed within the casing in coaxial relationship therein. In a second embodiment, means are provided for forming the casing as a multi-turn secondary. The transformer is characterized by minimized resistance heating, minimized external magnetic flux, and an economical construction.

Baker, W.R.

1959-08-25T23:59:59.000Z

96

Plant Support Engineering: Guidance for Planned Replacement of Large Power Transformers at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Utilities continue to pursue license renewal applications and power uprates, and these initiatives are being undertaken on an aging fleet of nuclear plants. Many plants are facing the necessity of replacing large power transformers to support these initiatives. However, industry expertise to support such activities has diminished since the days of plant construction8212there are fewer qualified vendors and equipment manufacturers, materials and standards might have changed, and licensees are typically no...

2007-11-02T23:59:59.000Z

97

Advancing our Nuclear Collaboration with the Czech Republic ...  

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

the data as well. Fourth, the collaboration opens the door for information sharing on fluoride volatility methods and how they can be applied to treat used nuclear fuel. And...

98

Advanced Sensor Diagnostics in Nuclear Power Plant Applications  

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

Sensor Diagnostics in Nuclear Power Plant Applications Sensor Diagnostics in Nuclear Power Plant Applications R.B. Vilim Argonne National Laboratory Sensor degradation occurs routinely during nuclear power plant operation and can contribute to reduced power production and less efficient plant operation. Mechanisms include drift of sensor electronics and mechanical components, fouling and erosion of flow meter orifice plates, and general degradation of thermocouples. One solution to this problem is the use of higher quality instrumentation and of physical redundancy. This, however, increases plant cost and does not address the degradation problem in a fundamental way. An alternative approach is to use signal processing algorithms to detect a degraded sensor and to construct a replacement value using an

99

LOFT advanced densitometer for nuclear loss-of-coolant experiments  

SciTech Connect

A ''nuclear hardened'' gamma densitometer, a device which uses radiation attenuation to measure fluid density in the presence of a background radiation field, is described. Data from the nuclear hardened gamma densitometer are acquired by time sampling the coolant fluid piping and fluid attenuated source energy spectrum. The data are used to calculate transient coolant fluid cross sectional average density to analyze transient mass flow and other thermal-hydraulic characteristics during the Loss-of-Fluid Test (LOFT) loss-of-coolant experiments. The nuclear hardened gamma densitometer uses a pulse height analysis or energy discrimination, pulse counting technique which makes separation of the gamma radiation source signal from the reactor generated gamma radiation background noise signal possible by processing discrete pulses which retain their pulse amplitude information.

Johnson, L.O.; Lassahn, G.D.; Wood, D.B.

1979-01-01T23:59:59.000Z

100

Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study  

SciTech Connect

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

Kristine Barrett; Shannon Bragg-Sitton

2012-09-01T23:59:59.000Z

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


101

Advanced reactors, passive safety, and acceptance of nuclear energy  

SciTech Connect

If nuclear power is to make a serious impact on CO{sub 2} emission, the industry will have to be very large. A 1000-MWe coal-fired power plant releases about 1.4 {times} 10{sup {minus}3} gigatons of carbon per year in the form of CO{sub 2}. The total of 6 GTC/yr of carbon released by human use of 300 quads/yr of energy worldwide then corresponds to the equivalent of about 4000 one-gigawatt power plants. By the middle of the next century, the world's energy demand might grow to about 500 quads/yr. One might halve the implied 10 GTC/yr by deploying 3500 1000-megawatt large reactors. Now the median core melt probability of today's fleet of reactors is according to Rasmussen 5 {times} 10{sup {minus}5} per reactor year which corresponds to a core melt frequency in such a large nuclear system of 0.18/yr - one accident equivalent to that at Three Mile Island Unit 2 every six years. This is almost surely unacceptable. Thus one concludes that a necessary condition for deployment of nuclear reactors on a scale sufficient to contribute significantly to mitigation of the greenhouse effect is reduction of the core melt probability considerably below Rasmussen's fiducial figure. In this paper, the authors summarize developments, both institutional and technical, since 1985 in the development of safer, if not inherently safe, reactors.

Forsberg, C.W. (Chemical Technology Div., Oak Ridge National Lab., Oak Ridge, TN (US)); Weinberg, A.M. (Oak Ridge Associated Univ., Oak Ridge, TN (US))

1990-01-01T23:59:59.000Z

102

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plants: Industry Recommendations for Design  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries. Good initial and continued performance is vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

103

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

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

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

104

A Path Forward to Advanced Nuclear Fuels: Spectroscopic Calorimetry of Nuclear Fuel Materials  

SciTech Connect

The goal is to relieve the shortage of thermodynamic and kinetic information concerning the stability of nuclear fuel alloys. Past studies of the ternary nuclear fuel UPuZr have demonstrated constituent redistribution when irradiated or with thermal treatment. Thermodynamic data is key to predicting the possibilities of effects such as constituent redistribution within the fuel rods and interaction with cladding materials.

Tobin, J G

2009-02-10T23:59:59.000Z

105

SiCf/SiC Composites for Advanced Nuclear Applications  

SciTech Connect

Composite materials have the potential for their properties to be tailored to specific applications by engineering the combination of fibers and matrices. Ceramic matrix composites are attractive because of their excellent high-temperature properties and corrosion resistance. In particular, ceramic composites made from silicon carbide fibers and silicon carbide matrices (SiCf/SiC) are promising for nuclear applications because of the radiation resistance of the ??phase of SiC, their excellent high-temperature fracture, creep, corrosion and thermal shock resistance. The ??phase of SiC has been shown by numerous studies to have a saturation swelling value of about 0.1 to 0.2% at 800 to 1000°C. This suggests that composites of SiC/SiC have the potential for excellent radiation stability. The continuous fiber architecture, coupled with engineered interfaces between the fiber and matrix, provide excellent fracture properties and fracture toughness values on the order of 25 MPa m1/2. The strength and fracture toughness are independent of temperature up to the limit of the fiber stability. Also, these fiber/matrix microstructures impart excellent thermal shock and thermal fatigue resistance so start-up and shut-down cycles and coolant loss scenarios should not induce significant structural damage.

Jones, Russell H.

2003-06-16T23:59:59.000Z

106

Reactor Physics and Criticality Benchmark Evaluations for Advanced Nuclear Fuel - Final Technical Report  

SciTech Connect

The nuclear industry interest in advanced fuel and reactor design often drives towards fuel with uranium enrichments greater than 5 wt% 235U. Unfortunately, little data exists, in the form of reactor physics and criticality benchmarks, for uranium enrichments ranging between 5 and 10 wt% 235U. The primary purpose of this project is to provide benchmarks for fuel similar to what may be required for advanced light water reactors (LWRs). These experiments will ultimately provide additional information for application to the criticality-safety bases for commercial fuel facilities handling greater than 5 wt% 235U fuel.

William Anderson; James Tulenko; Bradley Rearden; Gary Harms

2008-09-11T23:59:59.000Z

107

Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)  

SciTech Connect

The Nuclear Energy Computational Fluid Dynamics Advanced Modeling and Simulation (NE-CAMS) system is being developed at the Idaho National Laboratory (INL) in collaboration with Bettis Laboratory, Sandia National Laboratory (SNL), Argonne National Laboratory (ANL), Utah State University (USU), and other interested parties with the objective of developing and implementing a comprehensive and readily accessible data and information management system for computational fluid dynamics (CFD) verification and validation (V&V) in support of nuclear energy systems design and safety analysis. The two key objectives of the NE-CAMS effort are to identify, collect, assess, store and maintain high resolution and high quality experimental data and related expert knowledge (metadata) for use in CFD V&V assessments specific to the nuclear energy field and to establish a working relationship with the U.S. Nuclear Regulatory Commission (NRC) to develop a CFD V&V database, including benchmark cases, that addresses and supports the associated NRC regulations and policies on the use of CFD analysis. In particular, the NE-CAMS system will support the Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program, which aims to develop and deploy advanced modeling and simulation methods and computational tools for reliable numerical simulation of nuclear reactor systems for design and safety analysis. Primary NE-CAMS Elements There are four primary elements of the NE-CAMS knowledge base designed to support computer modeling and simulation in the nuclear energy arena as listed below. Element 1. The database will contain experimental data that can be used for CFD validation that is relevant to nuclear reactor and plant processes, particularly those important to the nuclear industry and the NRC. Element 2. Qualification standards for data evaluation and classification will be incorporated and applied such that validation data sets will result in well-defined, well-characterized data. Element 3. Standards will be established for the design and operation of experiments for the generation of new validation data sets that are to be submitted to NE-CAMS that addresses the completeness and characterization of the dataset. Element 4. Standards will be developed for performing verification and validation (V&V) to establish confidence levels in CFD analyses of nuclear reactor processes; such processes will be acceptable and recognized by both CFD experts and the NRC.

Kimberlyn C. Mousseau

2011-10-01T23:59:59.000Z

108

Data mining for oil-insulated power transformers: an advanced literature survey  

Science Conference Proceedings (OSTI)

Knowledge discovery in database and data mining (DM) have emerged as high profile, rapidly evolving, urgently needed, and highly practical approaches to use dissolved gas analysis (DGA) data to monitor conditions and faults in oil-immersed power transformers. ... Keywords: Industry Specific Applications

Yann-Chang Huang; Chao-Ming Huang; Huo-Ching Sun

2012-03-01T23:59:59.000Z

109

Improving Text and Document-Based Operations For Advanced Nuclear Plants  

Science Conference Proceedings (OSTI)

An important industry goal for Advanced Nuclear Plants (ANPs) is to ensure they are equipped with a modern, full scope, integrated Information Management System (IMS). As part of this overall goal, there is a need to identify ANP activities that could readily and greatly benefit from the application of existing and emerging IMS technologies. The objective of this project is to identify and prioritize work in such areas for ANPs based on current plant operations and maintenance (O&M) activities. Activitie...

2000-05-22T23:59:59.000Z

110

Technical Guidance for Achieving Higher Levels of Electromagnetic Compatibility for Advanced Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report presents guidance for enhancing electromagnetic compatibility (EMC) for advanced nuclear power plants (NPPs). Included is a summary of EMC challenges facing these plants and the threats that utilities, equipment designers, and plant designers must be aware of. The following requested areas are covered: 1) programmatically addressing EMC through the development of an EMC protection system, 2) minimizing the use of exclusion zones through the demonstration of electromagnetic energy (EM) calcula...

2010-12-22T23:59:59.000Z

111

Management of the Licensed Bases of Advanced Nuclear Plants: Proof of Approach  

Science Conference Proceedings (OSTI)

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its lifecycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This project adopted and demonstrated a "twin-engine" approach that integrates a program from the emerging class of concept searching tools with a mod...

2000-08-28T23:59:59.000Z

112

Program on Technology Innovation: Comparative Radiological Risk Assessment of Advanced Nuclear Fuel Cycles  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) is working to develop tools to support long-term strategic planning for research, development, and demonstration (RDD) of advanced nuclear fuel cycle technologies for electricity generation. The research described in this EPRI progress report supports the larger decision framework endeavor and intends to provide a standalone usable tool. Two strategic issues are addressed: radioactive and chemical waste management and safety (both radiological and chemical). U...

2012-05-21T23:59:59.000Z

113

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

SciTech Connect

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

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

2007-05-01T23:59:59.000Z

114

Khalil named co-director of the Center for Advanced Nuclear Fuel...  

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

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

115

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

E-Print Network (OSTI)

Framework   for   Nuclear   Fuel   Cycle   Concepts,”  Of   Used   Nuclear   Fuel”,   Nuclear  Engineering  and  Radiotoxicity  of  Spent  Nuclear   Fuel,”   Integrated  

Djokic, Denia

2013-01-01T23:59:59.000Z

116

Advanced Nuclear Technology: Supplier Quality Management for New Nuclear Plant Construction Projects  

Science Conference Proceedings (OSTI)

This report provides guidance for new nuclear power plant construction projects on supplier quality-related risks associated with the procurement of materials, equipment, and services intended for use in a safety-related plant application. This guidance takes an in-depth look into the procurement-related challenges that new construction projects face and at measures for overcoming these challenges. A methodology is provided for identifying, managing, evaluating, and mitigating quality-related risks ...

2013-06-26T23:59:59.000Z

117

Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06  

SciTech Connect

Following the highly successful ICAPP'05 meeting held in Seoul Korea, the 2006 International Congress on Advances in Nuclear Power Plants brought together international experts of the nuclear industry involved in the operation, development, building, regulation and research related to Nuclear Power Plants. The program covers the full spectrum of Nuclear Power Plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program covers lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design and reliability. The program by technical track deals with: - 1. Water-Cooled Reactor Programs and Issues Evolutionary designs, innovative, passive, light and heavy water cooled reactors; issues related to meeting medium term utility needs; design and regulatory issues; business, political and economic challenges; infrastructure limitations and improved construction techniques including modularization. - 2. High Temperature Gas Cooled Reactors Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, hydrogen production and other industrial uses; advanced thermal and fast reactors. - 3. Long Term Reactor Programs and Strategies Reactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Potential reactor designs with longer development times such as, super critical water reactors, liquid metal reactors, gaseous and liquid fuel reactors, Gen IV, INPRO, EUR and other programs. - 4. Operation, Performance and Reliability Management Training, O and M costs, life cycle management, risk based maintenance, operational experiences, performance and reliability improvements, outage optimization, human factors, plant staffing, outage reduction features, major component reliability, repair and replacement, in-service inspection, and codes and standards. - 5. Plant Safety Assessment and Regulatory Issues Transient and accident performance including LOCA and non-LOCA, severe accident analysis, impact of risk informed changes, accident management, assessment and management of aging, degradation and damage, life extension lessons from plant operations, probabilistic safety assessment, plant safety analysis, reliability engineering, operating and future plants. - 6. Thermal Hydraulic Analysis and Testing Phenomena identification and ranking, computer code scaling applicability and uncertainty, containment thermal hydraulics, component and integral system tests, improved code development and qualification, single and two phase flow; advanced computational thermal hydraulic methods. - 7. Core and Fuel Cycle Concepts and Experiments Core physics, advances in computational reactor analysis, in-core fuel management, mixed-oxide fuel, thorium fuel cycle, low moderation cores, high conversion reactor designs, particle and pebble bed fuel design, testing and reliability; fuel cycle waste minimization, recycle, storage and disposal. - 8. Materials and Structural Issues Fuel, core, RPV and internals structures, advanced materials issues and fracture mechanics, concrete and steel containments, space structures, analysis, design and monitoring for seismic, dynamic and extreme accidents; irradiation issues and materials for new plants. - 9. Nuclear Energy and Sustainability including Hydrogen, Desalination and Other Applications Environmental impact of nuclear and alternative systems, spent fuel dispositions and transmutation systems, fully integrated fuel cycle and symbiotic nuclear power systems, application of advanced designs to non-power applications such as the production of hydrogen, sea water desalination, heating and other co-generation applications. - 10. Near Term Issues (New) Applies to plants that have a significa

NONE

2006-07-01T23:59:59.000Z

118

Advanced international training course on state systems of accounting for and control of nuclear materials  

Science Conference Proceedings (OSTI)

This report incorporates all lectures and presentations at the Advanced International Training Course on State Systems of Accounting for and Control of Nuclear Material held April 27 through May 12, 1981 at Santa Fe and Los Alamos, New Mexico, and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards. Major emphasis for the 1981 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory, the Battelle Pacific Northwest Laboratory, and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at both the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, Richland, Washington.

Not Available

1981-10-01T23:59:59.000Z

119

Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)  

SciTech Connect

NE-KAMS knowledge base will assist computational analysts, physics model developers, experimentalists, nuclear reactor designers, and federal regulators by: (1) Establishing accepted standards, requirements and best practices for V&V and UQ of computational models and simulations, (2) Establishing accepted standards and procedures for qualifying and classifying experimental and numerical benchmark data, (3) Providing readily accessible databases for nuclear energy related experimental and numerical benchmark data that can be used in V&V assessments and computational methods development, (4) Providing a searchable knowledge base of information, documents and data on V&V and UQ, and (5) Providing web-enabled applications, tools and utilities for V&V and UQ activities, data assessment and processing, and information and data searches. From its inception, NE-KAMS will directly support nuclear energy research, development and demonstration programs within the U.S. Department of Energy (DOE), including the Consortium for Advanced Simulation of Light Water Reactors (CASL), the Nuclear Energy Advanced Modeling and Simulation (NEAMS), the Light Water Reactor Sustainability (LWRS), the Small Modular Reactors (SMR), and the Next Generation Nuclear Power Plant (NGNP) programs. These programs all involve computational modeling and simulation (M&S) of nuclear reactor systems, components and processes, and it is envisioned that NE-KAMS will help to coordinate and facilitate collaboration and sharing of resources and expertise for V&V and UQ across these programs. In addition, from the outset, NE-KAMS will support the use of computational M&S in the nuclear industry by developing guidelines and recommended practices aimed at quantifying the uncertainty and assessing the applicability of existing analysis models and methods. The NE-KAMS effort will initially focus on supporting the use of computational fluid dynamics (CFD) and thermal hydraulics (T/H) analysis for M&S of nuclear reactor systems, components and processes, and will later expand to include materials, fuel system performance and other areas of M&S as time and funding allow.

Rich Johnson; Kimberlyn C. Mousseau; Hyung Lee

2011-09-01T23:59:59.000Z

120

The Nuclear Energy Advanced Modeling and Simulation Enabling Computational Technologies FY09 Report  

SciTech Connect

In this document we report on the status of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Enabling Computational Technologies (ECT) effort. In particular, we provide the context for ECT In the broader NEAMS program and describe the three pillars of the ECT effort, namely, (1) tools and libraries, (2) software quality assurance, and (3) computational facility (computers, storage, etc) needs. We report on our FY09 deliverables to determine the needs of the integrated performance and safety codes (IPSCs) in these three areas and lay out the general plan for software quality assurance to meet the requirements of DOE and the DOE Advanced Fuel Cycle Initiative (AFCI). We conclude with a brief description of our interactions with the Idaho National Laboratory computer center to determine what is needed to expand their role as a NEAMS user facility.

Diachin, L F; Garaizar, F X; Henson, V E; Pope, G

2009-10-12T23:59:59.000Z

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

An Advanced Reverse Osmosis Technology For Application in Nuclear Desalination Facilities  

SciTech Connect

The lack of adequate supplies of clean, safe water is a growing global problem that has reached crisis proportions in many parts of the world. It is estimated that 1.5 billion people do not have access to adequate supplies of safe water, and that as a result nearly 10,000 people die every day and thousands more suffer from a range of debilitating illnesses due to water related diseases. Included in this total is an estimated 2.2 million child deaths annually. As the world's need for additional sources of fresh water continues to grow, seawater and brackish water desalination are providing an increasingly important contribution to the solution of this problem. Because desalination is an energy intensive process, nuclear desalination provides an economically attractive and environmentally sound alternative to the burning of fossil fuels for desalination. Nevertheless, the enormity of the problem dictates that additional steps must be taken to improve the efficiency of energy utilization and reduce the cost of water production in order to reduce the financial and environmental burden to communities in need. An advanced reverse osmosis (RO) desalination technology has been developed that emphasizes a nontraditional approach to system design and operation, and makes use of a sophisticated design optimization process that can lead to highly optimized design configurations and operating regimes. The technology can be coupled with a nuclear generating station (NGS) to provide an integrated facility for the co-generation of both water and electricity. Waste heat from the NGS allows the use of 'preheated' feedwater into the RO system, improving the efficiency of the RO process and reducing the cost of water production. Because waste heat, rather than process heat, is used the desalination system can be readily coupled to any existing or advanced reactor technology with little or no impact on reactor design and operation and without introducing additional reactor safety considerations. Analyses of nuclear desalination systems employing this advanced RO technology under a variety of seawater feed conditions have consistently shown that the cost of potable water production can be reduced by as much as 15-20% relative to systems designed in a more traditional manner. Demonstration testing has been carried out using a trailer mounted system producing up to 150 m{sup 3}/d of potable water. Experimental results from the demonstration testing are behaving as expected based on the analytical performance models, validating the advanced design concept and confirming that the performance improvements indicated by the analyses can be achieved in operating systems. Further demonstration testing is planned using a 1000 m{sup 3}/d containerized system, currently under design, coupled to an existing nuclear power reactor. (authors)

Humphries, J.R.; Davies, K.; Ackert, J.A. [CANDESAL Technologies Limited, Ottawa (Canada)

2002-07-01T23:59:59.000Z

122

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

E-Print Network (OSTI)

DOE  FCRD   Office  of  Nuclear  Energy,  Department  of  for   Sustainable   Nuclear   Energy   (PATEROS),   Annex  Training   on   Nuclear   Energy   /   Management  of  

Djokic, Denia

2013-01-01T23:59:59.000Z

123

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

E-Print Network (OSTI)

a   Geologic   Repository”,   Nuclear  Technology,   154,  in  decommissioned  U.S.  nuclear   facilities,  German  Framework   for   Nuclear   Fuel   Cycle   Concepts,”  

Djokic, Denia

2013-01-01T23:59:59.000Z

124

Attainable entanglement of unitary transformed thermal states in liquid-state nuclear magnetic resonance with the chemical shift  

E-Print Network (OSTI)

Recently, Yu, Brown, and Chuang [Phys. Rev. A {\\bf 71}, 032341 (2005)] investigated the entanglement attainable from unitary transformed thermal states in liquid-state nuclear magnetic resonance (NMR). Their research gave an insight into the role of the entanglement in a liquid-state NMR quantum computer. Moreover, they attempted to reveal the role of mixed-state entanglement in quantum computing. However, they assumed that the Zeeman energy of each nuclear spin which corresponds to a qubit takes a common value for all; there is no chemical shift. In this paper, we research a model with the chemical shifts and analytically derive the physical parameter region where unitary transformed thermal states are entangled, by the positive partial transposition (PPT) criterion with respect to any bipartition. We examine the effect of the chemical shifts on the boundary between the separability and the nonseparability, and find it is negligible.

Yukihiro Ota; Shuji Mikami; Motoyuki Yoshida; Ichiro Ohba

2006-12-19T23:59:59.000Z

125

Assessment of modular construction for safety-related structures at advanced nuclear power plants  

SciTech Connect

Modular construction techniques have been successfully used in a number of industries, both domestically and internationally. Recently, the use of structural modules has been proposed for advanced nuclear power plants. The objective in utilizing modular construction is to reduce the construction schedule, reduce construction costs, and improve the quality of construction. This report documents the results of a program which evaluated the proposed use of modular construction for safety-related structures in advanced nuclear power plant designs. The program included review of current modular construction technology, development of licensing review criteria for modular construction, and initial validation of currently available analytical techniques applied to concrete-filled steel structural modules. The program was conducted in three phases. The objective of the first phase was to identify the technical issues and the need for further study in order to support NRC licensing review activities. The two key findings were the need for supplementary review criteria to augment the Standard Review Plan and the need for verified design/analysis methodology for unique types of modules, such as the concrete-filled steel module. In the second phase of this program, Modular Construction Review Criteria were developed to provide guidance for licensing reviews. In the third phase, an analysis effort was conducted to determine if currently available finite element analysis techniques can be used to predict the response of concrete-filled steel modules.

Braverman, J.; Morante, R.; Hofmayer, C.

1997-03-01T23:59:59.000Z

126

The Next Generation Nuclear Plant/Advanced Gas Reactor Fuel Irradiation Experiments in the Advanced Test Reactor  

SciTech Connect

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating eight separate low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of at least six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006, and the second experiment (AGR-2) is currently in the design phase. The design of test trains, as well as the support systems and fission product monitoring system that will monitor and control the experiment during irradiation will be discussed. In addition, the purpose and differences between the two experiments will be compared and the irradiation results to date on the first experiment will be presented.

S. Blaine Grover

2009-09-01T23:59:59.000Z

127

Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who  

SciTech Connect

The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs.

Forsberg, C.W.; Reich, W.J.

1991-09-01T23:59:59.000Z

128

Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who  

SciTech Connect

The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs.

Forsberg, C.W.; Reich, W.J.

1991-09-01T23:59:59.000Z

129

High Level Requirements for the Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)  

Science Conference Proceedings (OSTI)

The US Department of Energy, Office of Nuclear Energy (DOE-NE), has been tasked with the important mission of ensuring that nuclear energy remains a compelling and viable energy source in the U.S. The motivations behind this mission include cost-effectively meeting the expected increases in the power needs of the country, reducing carbon emissions and reducing dependence on foreign energy sources. In the near term, to ensure that nuclear power remains a key element of U.S. energy strategy and portfolio, the DOE-NE will be working with the nuclear industry to support safe and efficient operations of existing nuclear power plants. In the long term, to meet the increasing energy needs of the U.S., the DOE-NE will be investing in research and development (R&D) and working in concert with the nuclear industry to build and deploy new, safer and more efficient nuclear power plants. The safe and efficient operations of existing nuclear power plants and designing, licensing and deploying new reactor designs, however, will require focused R&D programs as well as the extensive use and leveraging of advanced modeling and simulation (M&S). M&S will play a key role in ensuring safe and efficient operations of existing and new nuclear reactors. The DOE-NE has been actively developing and promoting the use of advanced M&S in reactor design and analysis through its R&D programs, e.g., the Nuclear Energy Advanced Modeling and Simulation (NEAMS) and Consortium for Advanced Simulation of Light Water Reactors (CASL) programs. Also, nuclear reactor vendors are already using CFD and CSM, for design, analysis, and licensing. However, these M&S tools cannot be used with confidence for nuclear reactor applications unless accompanied and supported by verification and validation (V&V) and uncertainty quantification (UQ) processes and procedures which provide quantitative measures of uncertainty for specific applications. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation (NE-KAMS) is being developed at the Idaho National Laboratory in conjunction with Bettis Laboratory, Sandia National Laboratories, Argonne National Laboratory, Utah State University and others with the objective of establishing a comprehensive and web-accessible knowledge base that will provide technical services and resources for V&V and UQ of M&S in nuclear energy sciences and engineering. The knowledge base will serve as an important resource for technical exchange and collaboration that will enable credible and reliable computational models and simulations for application to nuclear reactor design, analysis and licensing. NE-KAMS will serve as a valuable resource for the nuclear industry, academia, the national laboratories, the U.S. Nuclear Regulatory Commission (NRC) and the public and will help ensure the safe, economical and reliable operation of existing and future nuclear reactors. From its inception, NE-KAMS will directly support nuclear energy research, development and demonstration programs within the U.S. Department of Energy (DOE), including the CASL, NEAMS, Light Water Reactor Sustainability (LWRS), Small Modular Reactors (SMR), and Next Generation Nuclear Power Plant (NGNP) programs. These programs all involve M&S of nuclear reactor systems, components and processes, and it is envisioned that NE-KAMS will help to coordinate and facilitate collaboration and sharing of resources and expertise for V&V and UQ across these programs.

Rich Johnson; Hyung Lee; Kimberlyn C. Mousseau

2011-09-01T23:59:59.000Z

130

February 2004, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE  

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

The ANTT Subcommittee of NERAC met February 26th and 27th (S. Pillon absent) to begin a review of the potential role of transmutation technologies in increasing the capacity of the geological...

131

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

E-Print Network (OSTI)

Anthony   V.   Guide  Nuclear  Reactors.   University   of  of   fuel   for   nuclear   reactors—create   wastes  Level  Waste   nuclear reactors, and subsequent utilization

Djokic, Denia

2013-01-01T23:59:59.000Z

132

Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors  

E-Print Network (OSTI)

L. J. Hamilton Nuclear Reactor Analysis John Wiley and Sons,R. J. Neuhold, Introductury Nuclear Reactor Dynamics. ANSL. J. Hamilton Nuclear Reactor Analysis John Wiley and Sons,

Galvez, Cristhian

2011-01-01T23:59:59.000Z

133

Recent advances in nuclear fission theory: pre- and post-scission physics  

Science Conference Proceedings (OSTI)

Recent advances in the modeling of the nuclear fission process for data evaluation purposes are reviewed. In particular, it is stressed that a more comprehensive approach to fission data is needed if predictive capability is to be achieved. The link between pre- and post-scission data is clarified, and a path forward to evaluate those data in a consistent and comprehensive manner is presented. Two examples are given: (i) the modeling of fission cross-sections in the R-matrix formalism, for which results for Pu isotopes from 239 to 242 are presented; (ii) the modeling of prompt fission neutrons in the Monte Carlo Hauser-Feshbach framework. Results for neutron-induced fission on {sup 235}U are discussed.

Talou, Patrick [Los Alamos National Laboratory; Kawano, Toshihiko [Los Alamos National Laboratory; Bouland, Olivier [Los Alamos National Laboratory; Moller, Peter [Los Alamos National Laboratory; Chadwick, Mark B [Los Alamos National Laboratory; Lynn, J E [CEA DEN FRANCE

2010-01-01T23:59:59.000Z

134

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

SciTech Connect

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

E. R. Johnson; R. E. Best

2009-12-28T23:59:59.000Z

135

Advanced Nuclear Technology: EPRI Materials Management Matrix Project—Toshiba Advanced Boiling Water Reactor Materials Managem ent Table Report, Revision 0  

Science Conference Proceedings (OSTI)

Experience gained through years of operating nuclear plants has shown that materials performance issues can be a significant concern related to economic and safe long-term plant operations. Although concerns remain, industry efforts to address materials performance issues at operating plants have led to several important advances in both the underlying scientific understanding of materials degradation and the implementation of practical mitigation and management technologies. The Electric Power Research...

2010-02-09T23:59:59.000Z

136

Advanced design nuclear power plants: Competitive, economical electricity. An analysis of the cost of electricity from coal, gas and nuclear power plants  

SciTech Connect

This report presents an updated analysis of the projected cost of electricity from new baseload power plants beginning operation around the year 2000. Included in the study are: (1) advanced-design, standardized nuclear power plants; (2) low emissions coal-fired power plants; (3) gasified coal-fired power plants; and (4) natural gas-fired power plants. This analysis shows that electricity from advanced-design, standardized nuclear power plants will be economically competitive with all other baseload electric generating system alternatives. This does not mean that any one source of electric power is always preferable to another. Rather, what this analysis indicates is that, as utilities and others begin planning for future baseload power plants, advanced-design nuclear plants should be considered an economically viable option to be included in their detailed studies of alternatives. Even with aggressive and successful conservation, efficiency and demand-side management programs, some new baseload electric supply will be needed during the 1990s and into the future. The baseload generating plants required in the 1990s are currently being designed and constructed. For those required shortly after 2000, the planning and alternatives assessment process must start now. It takes up to ten years to plan, design, license and construct a new coal-fired or nuclear fueled baseload electric generating plant and about six years for a natural gas-fired plant. This study indicates that for 600-megawatt blocks of capacity, advanced-design nuclear plants could supply electricity at an average of 4.5 cents per kilowatt-hour versus 4.8 cents per kilowatt-hour for an advanced pulverized-coal plant, 5.0 cents per kilowatt-hour for a gasified-coal combined cycle plant, and 4.3 cents per kilowatt-hour for a gas-fired combined cycle combustion turbine plant.

1992-06-01T23:59:59.000Z

137

Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development  

SciTech Connect

The Oak Ridge National Laboratory (ORNL) and the Korean Atomic Energy Research Institute (KAERI) are performing collaborative research as part of a three-year United States (U.S.) / Republic of Korea (ROK) International Nuclear Energy Research Initiative (I-NERI) project to provide improved neutron cross-section data with uncertainty or covariance data important for advanced fuel cycle and nuclear safeguards applications. ORNL and KAERI have initiated efforts to prepare new cross-section evaluations for 240Pu, 237Np, and the stable Cm isotopes. At the current stage of the I-NERI project, ORNL has recently completed a preliminary resonance-region cross-section evaluation with covariance data for 240Pu and initiated resonance evaluation efforts for 237Np and 244Cm. Likewise, KAERI is performing corresponding high-energy cross-section analyses (i.e., above the resonance region) for the noted isotopes. The paper provides results pertaining to the new resonance region evaluation efforts with emphasis on the new 240Pu evaluation.

Dunn, Michael E [ORNL; Derrien, Herve [ORNL; Leal, Luiz C [ORNL; Gil, Choong-Sup [Korea Atomic Energy Research Institute; Kim, D. [Korea Atomic Energy Research Institute

2011-01-01T23:59:59.000Z

138

THERMODYNAMIC AND KINETIC MODELING OF ADVANCED NUCLEAR FUELS - FINAL LDRD-ER REPORT  

SciTech Connect

This project enhanced our theoretical capabilities geared towards establishing the basic science of a high-throughput protocol for the development of advanced nuclear fuel that should couple modern computational materials modeling and simulation tools, fabrication and characterization capabilities, and targeted high throughput performance testing experiments. The successful conclusion of this ER project allowed us to upgrade state-of-the-art modeling codes, and apply these modeling tools to ab initio energetics and thermodynamic assessments of phase diagrams of various mixtures of actinide alloys, propose a tool for optimizing composition of complex alloys for specific properties, predict diffusion behavior in diffusion couples made of actinide and transition metals, include one new equation in the LLNL phase-field AMPE code, and predict microstructure evolution during alloy coring. In FY11, despite limited funding, the team also initiated an experimental activity, with collaboration from Texas A&M University by preparing samples of nuclear fuels in bulk forms and for diffusion couple studies and metallic matrices, and performing preliminary characterization.

Turchi, P

2011-11-28T23:59:59.000Z

139

Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing  

Science Conference Proceedings (OSTI)

New materials are being considered for fuel, cladding, and structures in next generation and existing nuclear reactors. These materials can undergo significant dimensional and physical changes during high temperature irradiations. Currently, such changes are determined by repeatedly irradiating a specimen for a specified period of time in the Advanced Test Reactor (ATR) and then removing it from the reactor for evaluation. The labor and time to remove, examine, and return irradiated samples for each measurement makes this approach very expensive. In addition, such techniques provide limited data and may disturb the phenomena of interest. To resolve these issues, an instrumented creep testing capability is being developed for specimens irradiated in pressurized water reactor (PWR) coolant conditions in the ATR at the Idaho National Laboratory (INL). This paper reports the status of INL efforts to develop this testing capability. In addition to providing an overview of in-pile creep test capabilities available at other test reactors, this paper focuses on efforts to design and evaluate a prototype test rig in an autoclave at INL's High Temperature Test Laboratory (HTTL).

D. L. Knudson; J. L. Rempe

2012-02-01T23:59:59.000Z

140

Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing  

Science Conference Proceedings (OSTI)

New materials are being considered for fuel, cladding and structures in next generation and existing nuclear reactors. These materials can undergo significant dimensional and physical changes during high temperature irradiations. Currently, such changes are determined by repeatedly irradiating a specimen for a specified period of time in the Advanced Test Reactor (ATR) and then removing it from the reactor for evaluation. The labor and time to remove, examine and return irradiated samples for each measurement make this approach very expensive. In addition, such techniques provide limited data and may disturb the phenomena of interest. To resolve these issues, an instrumented creep testing capability is being developed for specimens irradiated under pressurized water reactor coolant conditions in the ATR at the Idaho National Laboratory (INL). This paper reports the status of INL efforts to develop this testing capability. In addition to providing an overview of in-pile creep test capabilities available at other test reactors, this paper focuses on efforts to design and evaluate a prototype test rig in an autoclave at INL’s High Temperature Test Laboratory.

D. L. Knudson; J. L. Rempe

2012-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plant Projects: Industry Recommendations for Storage, Construction, and Testing  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries and vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

142

Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).  

Science Conference Proceedings (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

Schultz, Peter Andrew

2011-12-01T23:59:59.000Z

143

Securing special nuclear material: Recent advances in neutron detection and their role in nonproliferation  

Science Conference Proceedings (OSTI)

Neutrondetection is an integral part of the global effort to prevent the proliferation of special nuclear material (SNM). Applications relying on neutron-detection technology range from traditional nuclear nonproliferation objectives

R. C. Runkle; A. Bernstein; P. E. Vanier

2010-01-01T23:59:59.000Z

144

Analyzing the proliferation resistance of advanced nuclear fuel cycles : in search of an assessment methodology for use in fuel cycle simulations  

E-Print Network (OSTI)

A methodology to assess proliferation resistance of advanced nuclear energy systems is investigated. The framework, based on Multi-Attribute Utility Theory (MAUT), is envisioned for use within early-stage fuel cycle ...

Pierpoint, Lara Marie

2008-01-01T23:59:59.000Z

145

Science based integrated approach to advanced nuclear fuel development - integrated multi-scale multi-physics hierarchical modeling and simulation framework Part III: cladding  

Science Conference Proceedings (OSTI)

Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Reactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems to develop predictive tools is critical. Not only are fabrication and performance models needed to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. In this paper we review the current status of the advanced modeling and simulation of nuclear reactor cladding, with emphasis on what is available and what is to be developed in each scale of the project, how we propose to pass information from one scale to the next, and what experimental information is required for benchmarking and advancing the modeling at each scale level.

Tome, Carlos N [Los Alamos National Laboratory; Caro, J A [Los Alamos National Laboratory; Lebensohn, R A [Los Alamos National Laboratory; Unal, Cetin [Los Alamos National Laboratory; Arsenlis, A [LLNL; Marian, J [LLNL; Pasamehmetoglu, K [INL

2010-01-01T23:59:59.000Z

146

Advanced X-ray Systems for the Detection of Special Nuclear ...  

Science Conference Proceedings (OSTI)

... The Dosimetry Group provides support to the Domestic Nuclear Detection Office ... radiation dosimetry in and around these high-energy systems. ...

2013-03-13T23:59:59.000Z

147

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

E-Print Network (OSTI)

LLW-­?GTCC   GTCC  in  NRC  criteria.   Vitrified  glass;  Matheson,   Jim.   Letter   to   NRC   Chairman   Dale   E  California   Press,   NRC  2008   Nuclear   Regulatory  

Djokic, Denia

2013-01-01T23:59:59.000Z

148

Does US Foreign Policy Achieve Meaningful Results to Stop Nuclear Advancement?.  

E-Print Network (OSTI)

??Despite the vast research by academics and their attempt to explain why states aspire nuclear power, why states transfer conventional arms, and the effect of… (more)

Garcia Juarez, Gabriela

2013-01-01T23:59:59.000Z

149

Materials and Fuels for the Current and Advanced Nuclear Reactors II  

Science Conference Proceedings (OSTI)

Lifetime extension of reactors - nuclear materials aging, degradation and others ... A Rate-Theory Approach to Irradiation Damage Modeling with Random ...

150

Materials and Fuels for the Current and Advanced Nuclear Reactors III  

Science Conference Proceedings (OSTI)

Jul 15, 2013 ... Lifetime extension of reactors - nuclear materials aging, degradation and ... A Theoretical Model of Corrosion Rate Distribution in Liquid LBE ...

151

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980  

Science Conference Proceedings (OSTI)

Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

Not Available

1980-06-25T23:59:59.000Z

152

Steam Reforming Solidification of Cesium and Strontium Separations Product from Advanced Aqueous Processing of Spent Nuclear Fuel  

SciTech Connect

The Advanced Fuel Cycle Initiative program is conducting research on aqueous separations processes for the nuclear fuel cycle. This research includes development of solvent extraction processes for the separation of cesium and strontium from dissolved spent nuclear fuel solutions to reduce the short-term decay heat load. The cesium/strontium strip solution from candidate separation processes will require treatment and solidification for managed storage. Steam reforming is currently being investigated for stabilization of these streams because it can potentially destroy the nitrates and organics present in these aqueous, nitrate-bearing solutions, while converting the cesium and strontium into leach-resistant aluminosilicate minerals, such as pollucite. These ongoing experimental studies are being conducted to evaluate the effectiveness of steam reforming for this application.

Julia L. Tripp; T. G. Garn; R. D. Boardman; J. D. Law

2006-02-01T23:59:59.000Z

153

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

E-Print Network (OSTI)

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

Yancey, Kristina D.

2010-05-01T23:59:59.000Z

154

Nuclear Materials  

Science Conference Proceedings (OSTI)

Materials and Fuels for the Current and Advanced Nuclear Reactors III ... response of oxide ceramics for nuclear applications through experiment, theory, and ...

155

Advanced Techniques for In-Situ Monitoring of Phase Transformations During Welding Using Synchrotron-Based X-Ray Diffraction  

SciTech Connect

Understanding the evolution of microstructure in welds is an important goal of welding research because of the strong correlation between weld microstructure and weld properties. To achieve this goal it is important to develop a quantitative measure of phase transformations encountered during welding in order to ultimately develop methods for predicting weld microstructures from the characteristics of the welding process. To aid in this effort, synchrotron radiation methods have been developed at Lawrence Livermore National Laboratory (LLNL) for direct observation of microstructure evolution during welding. Using intense, highly collimated synchrotron radiation, the atomic structure of the weld heat affected and fusion zones can be probed in real time. Two synchrotron-based techniques, known as spatially resolved (SRXRD) and time resolved (TRXRD) x-ray diffraction, have been developed for these investigations. These techniques have now been used to investigate welding induced phase transformations in titanium alloys, low alloy steels, and stainless steel alloys. This paper will provide a brief overview of these methods and will discuss microstructural evolution during the welding of low carbon (AISI 1005) and medium carbon (AISI 1045) steels where the different levels of carbon influence the evolution of microstructures during welding.

Elmer, J W; Palmer, T A; Zhang, W; DebRoy, T

2005-06-05T23:59:59.000Z

156

Advanced Nuclear Technology: EPRI Utility Requirements Document (URD) Fukushima Lessons-Learned Treatment  

Science Conference Proceedings (OSTI)

The Fukushima accident of March 2011 resulted in critical lessons learned for both current and future nuclear plants. As part of an ongoing review and update of the EPRI Utility Requirements Document (URD) for New Nuclear Plants, a specific review of Fukushima lessons learned was undertaken.This report provides background information on the process for accomplishing the Fukushima review. It also provides the unique changes that were made to the EPRI URD along with specific linkage back ...

2013-12-13T23:59:59.000Z

157

Plant Engineering: Advanced Nuclear Plant Cable System Design and Installation Concepts to Assure Longevity  

Science Conference Proceedings (OSTI)

Although the electrical cable systems for existing nuclear power plants have functioned well for up to 40 years, the desired service life for new plants is 60 or more years. Experience with existing plants indicates that relatively small changes during the design and construction of nuclear plants will lead to longer cable system lives and greater ease of testing and assessment of cables to verify their remaining service life. This report describes those changes and provides recommendations for their imp...

2012-04-16T23:59:59.000Z

158

THE ATTRACTIVENESS OF MATERIALS IN ADVANCED NUCLEAR FUEL CYCLES FOR VARIOUS PROLIFERATION AND THEFT SCENARIOS  

Science Conference Proceedings (OSTI)

We must anticipate that the day is approaching when details of nuclear weapons design and fabrication will become common knowledge. On that day we must be particularly certain that all special nuclear materials (SNM) are adequately accounted for and protected and that we have a clear understanding of the utility of nuclear materials to potential adversaries. To this end, this paper examines the attractiveness of materials mixtures containing SNM and alternate nuclear materials associated with the plutonium-uranium reduction extraction (Purex), uranium extraction (UREX), coextraction (COEX), thorium extraction (THOREX), and PYROX (an electrochemical refining method) reprocessing schemes. This paper provides a set of figures of merit for evaluating material attractiveness that covers a broad range of proliferant state and subnational group capabilities. The primary conclusion of this paper is that all fissile material must be rigorously safeguarded to detect diversion by a state and must be provided the highest levels of physical protection to prevent theft by subnational groups; no 'silver bullet' fuel cycle has been found that will permit the relaxation of current international safeguards or national physical security protection levels. The work reported herein has been performed at the request of the U.S. Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for, the nuclear materials in DOE nuclear facilities. The methodology and findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security is discussed.

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

2012-08-29T23:59:59.000Z

159

The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios  

Science Conference Proceedings (OSTI)

This paper is an extension to earlier studies1,2 that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, COEX, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant state and sub-national group capabilities. The primary conclusion of this study is that all fissile material needs to be rigorously safeguarded to detect diversion by a state and provided the highest levels of physical protection to prevent theft by sub-national groups; no “silver bullet” has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of "attractiveness levels" that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities.3 The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.

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

2010-09-01T23:59:59.000Z

160

Development of Advanced Technologies to Reduce Design, Fabrication and Construction Costs for Future Nuclear Power Plants  

SciTech Connect

OAK-B135 This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies.

Camillo A. DiNunzio Framatome ANP DE& S; Dr. Abhinav Gupta Assistant Professor NCSU; Dr. Michael Golay Professor MIT Dr. Vincent Luk Sandia National Laboratories; Rich Turk Westinghouse Electric Company Nuclear Systems; Charles Morrow, Sandia National Laboratories; Geum-Taek Jin, Korea Power Engineering Company Inc.

2002-11-30T23:59:59.000Z

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Advanced Intermediate Heat Transport Loop Design Configurations for Hydrogen Production Using High Temperature Nuclear Reactors  

DOE Green Energy (OSTI)

The US Department of Energy is investigating the use of high-temperature nuclear reactors to produce hydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogen production processes are in an early stage of development, coupling either of these processes to the high-temperature reactor requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear power plant. An intermediate heat transport loop will be required to separate the operations and safety functions of the nuclear and hydrogen plants. A next generation high-temperature reactor could be envisioned as a single-purpose facility that produces hydrogen or a dual-purpose facility that produces hydrogen and electricity. Early plants, such as the proposed Next Generation Nuclear Plant (NGNP), may be dual-purpose facilities that demonstrate both hydrogen and efficient electrical generation. Later plants could be single-purpose facilities. At this stage of development, both single- and dual-purpose facilities need to be understood. A number of possible configurations for a system that transfers heat between the nuclear reactor and the hydrogen and/or electrical generation plants were identified. These configurations included both direct and indirect cycles for the production of electricity. Both helium and liquid salts were considered as the working fluid in the intermediate heat transport loop. Methods were developed to perform thermal-hydraulic evaluations and cycle-efficiency evaluations of the different configurations and coolants. The thermal-hydraulic evaluations estimated the sizes of various components in the intermediate heat transport loop for the different configurations. The relative sizes of components provide a relative indication of the capital cost associated with the various configurations. Estimates of the overall cycle efficiency of the various configurations were also determined. The evaluations determined which configurations and coolants are the most promising from thermal-hydraulic and efficiency points of view.

Chang Oh; Cliff Davis; Rober Barner; Paul Pickard

2005-11-01T23:59:59.000Z

162

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

Science Conference Proceedings (OSTI)

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

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

2011-06-01T23:59:59.000Z

163

Evaluation of an Advanced Radiation Shielding Material for Permanent Installation at an Operating Commercial Nuclear Reactor  

Science Conference Proceedings (OSTI)

The industry continues to investigate, validate, and implement new radiation field reduction measures in response to increased emphasis on reducing dose to workers. Many nuclear plants are interested in permanent shielding applications to further reduce personnel exposure and to reduce the recurring effort associated with temporary installations. In 2008, a flexible, impregnated, layered matrix material was identified as a possible material for incorporating a shielding substance. This report provides an...

2010-09-30T23:59:59.000Z

164

Advanced Nuclear Technology: Quality Control of Concrete During Construction - Voids Detection  

Science Conference Proceedings (OSTI)

The main type of degradation of concrete structures during the construction of nuclear power plants has been the existence of honeycombs and voids due to inadequate concrete design and placement. The detection of these honeycombs and voids in concrete structures has been attempted with nondestructive evaluation technologies with limited success. The addition of steel-concrete construction techniques further complicates the ability of these technologies to ...

2012-12-22T23:59:59.000Z

165

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

SciTech Connect

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

Knapp, F.F. Jr.

1998-03-01T23:59:59.000Z

166

Advanced Nuclear Technology: Final Test Results on 80% Service Test and Implementation Plans  

Science Conference Proceedings (OSTI)

Current practice within the nuclear power industry is to use performance discharge tests for condition monitoring to determine when a battery has reached 80% of its rated capacity, which is considered the end of its service life. A service test is now used every refueling outage to verify that a battery can satisfy its design basis function as defined by the battery duty cycle. A modified performance test is used at ...

2013-04-03T23:59:59.000Z

167

Advanced Nuclear Technology: Regulatory Performance Requirements for Safety-Related Instrumentation, Revision 1  

Science Conference Proceedings (OSTI)

This report proposes an acceptable methodology to apply to safety-related instrumentation to demonstrate 95% probability and 95% confidence (95/95) uncertainties in support of the requirements of Nuclear Regulatory Commission Regulatory Guide (RG) 1.105 Revision 3. This methodology should serve as a means to specify testing and analysis requirements to instrumentation manufacturers and suppliers for their use in meeting the RG 1.105 Revision 3 95% probability and 95% confidence requirements. A ...

2013-08-07T23:59:59.000Z

168

Advanced Technologies for Groundwater Monitoring and Remediation at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

As part of the industry Groundwater Protection Initiative, EPRI has been investigating groundwater monitoring and remediation technologies that have potential for implementation at nuclear power plant sites. This report explores groundwater monitoring and remediation technologies under development or implemented at other industrial and U.S. Department of Energy sites, for both radionuclide and non-radionuclide contaminants. The report documents the potential for development of these technologies for impl...

2008-12-03T23:59:59.000Z

169

Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors  

Science Conference Proceedings (OSTI)

Issues of obsolescence and lack of infrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I&C) systems with digital and microprocessor-based systems. While these technologies have several advantages, their application to safety-related systems in nuclear power plants raises key issues relating to the systems` environmental qualification and functional reliability. To bound the problem of new I&C system functionality and qualification, the authors focused this study on protection systems proposed for use in ALWRs. Specifically, both functional and environmental qualification issues for ALWR protection system I&C were addressed by developing an environmental, functional, and aging data template for a protection division of each proposed ALWR design. By using information provided by manufacturers, environmental conditions and stressors to which I&C equipment in reactor protection divisions may be subjected were identified. The resulting data were then compared to a similar template for an instrument string typically found in an analog protection division of a present-day nuclear power plant. The authors also identified fiber-optic transmission systems as technologies that are relatively new to the nuclear power plant environment and examined the failure modes and age-related degradation mechanisms of fiber-optic components and systems. One reason for the exercise of caution in the introduction of software into safety-critical systems is the potential for common-cause failure due to the software. This study, however, approaches the functionality problem from a systems point of view. System malfunction scenarios are postulated to illustrate the fact that, when dealing with the performance of the overall integrated system, the real issues are functionality and fault tolerance, not hardware vs. software.

Korsah, K.; Clark, R.L.; Wood, R.T. [Oak Ridge National Lab., TN (United States)

1994-04-01T23:59:59.000Z

170

Structural Integrity of Advanced Claddings During Spent Nuclear Fuel Transportation and Storage  

Science Conference Proceedings (OSTI)

Thermal creep is the dominant deformation mechanism of fuel cladding during transportation and dry storage of spent nuclear fuel. Thermal creep data and creep models of Westinghouse ZIRLO and LK3 cladding tubes were generated for use in spent-fuel storage and transportation applications. The final report consists of two volumes. This document (Volume 1) provides the project results obtained on non-irradiated and irradiated standard ZIRLO and non-irradiated optimized ZIRLO claddings.

2011-06-28T23:59:59.000Z

171

Advancing Methods for Determining the Source of HEU Used in Terrorist Nuclear Weapon  

E-Print Network (OSTI)

An algorithm was developed that uses measured isotopic ratios from fission product residue following the detonation of a high-enriched uranium nuclear weapon to compute the original attributes of the material used in the device. The specific attributes assessed are the uranium isotopics (considering 234U, 235U, 236U, and 238U) and the enrichment process used to create the material (e.g., gaseous diffusion, gas centrifuge, etc.). Using the original attributes of the weapon significantly increases the probability of identifying the perpetrator of the attack. In this study, research was conducted to perform sensitivity analysis of the calculated values, analyze alternate enrichment methods, determine the source (uranium mine) from which the feed material was taken and assess potential “spoofing” techniques. The purpose of this research was to verify that the analytical method developed would remain valid for a multitude of variations that could be used to disguise the origin of the nuclear material in the device. It is envisioned that this methodology could serve as a preprocessing step to a more computationally intensive and more accurate system in the event of a nuclear terrorist attack.

LaFleur, Adrienne; Charlton, William

2007-09-17T23:59:59.000Z

172

Securing Special Nuclear Material: Recent Advances in Neutron Detection and Their Role in Nonproliferation  

Science Conference Proceedings (OSTI)

Neutron detection is an integral part of the global effort to prevent the proliferation of special nuclear material (SNM). Applications relying on neutron-detection technology range from traditional nuclear non-proliferation objectives, such as safeguarding nuclear material and verifying stockpile reductions, to the interdiction of SNM—a goal that has recently risen in priority to a level on par with traditional applications. Large multi-national programs targeting detection and safeguards have deployed radiation-detection assets across the globe. Alongside these deployments of commercially available technology, significant research and development efforts have been directed towards the creation of next-generation assets. While much of this development has focused on gamma-ray spectrometers, neutron-detection technology remains an important component of the global strategy because of the capability of neutrons to penetrate materials that readily absorb gamma rays and the unique multiplicity signatures offered by neutrons. One particularly acute technology-development challenge results from dwindling supplies of 3He, partially triggered by widespread deployment of high-efficiency systems for portal monitoring. Other emerging missions, such as the desire to detect SNM at greater standoff distances, have also stimulated neutron-detection technology development. In light of these needs for novel neutron-detection technologies, this manuscript reviews the signatures of neutrons emitted by SNM, the principles of neutron detection, and various strategies under investigation for detection in the context of nonproliferation.

Runkle, Robert C.; Bernstein, A.; Vanier, Peter

2010-12-01T23:59:59.000Z

173

Advanced Ceramics  

Science Conference Proceedings (OSTI)

Table 2   Classification of advanced ceramics...solid electrolytes, piezoelectrics, dielectrics, superconductors Optical Low absorption coefficient Lamps, windows, fiber optics, infrared optics Nuclear Irradiation resistance, high absorption coefficient,

174

Use of Friction Stir Welding and Friction Stir Processing for Advanced Nuclear Fuels and Materials Joining Applications  

SciTech Connect

Application of the latest developments in materials technology may greatly aid in the successful pursuit of next generation reactor and transmutation technologies. One such area where significant progress is needed is joining of advanced fuels and materials. Rotary friction welding, also referred to as friction stir welding (FSW), has shown great promise as a method for joining traditionally difficult to join materials such as aluminum alloys. This relatively new technology, first developed in 1991, has more recently been applied to higher melting temperature alloys such as steels, nickel-based and titanium alloys. An overview of the FSW technology is provided and two specific nuclear fuels and materials applications where the technique may be used to overcome limitations of conventional joining technologies are highlighted.

J. I. Cole; J. F. Jue

2006-06-01T23:59:59.000Z

175

Radioactive waste shipments to Hanford retrievable storage from Westinghouse Advanced Reactors and Nuclear Fuels Divisions, Cheswick, Pennsylvania  

Science Conference Proceedings (OSTI)

During the next two decades the transuranic (TRU) waste now stored in the burial trenches and storage facilities at the Hanford Sits in southeastern Washington State is to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico for final disposal. Approximately 5.7 percent of the TRU waste to be retrieved for shipment to WIPP was generated by the decontamination and decommissioning (D&D) of the Westinghouse Advanced Reactors Division (WARD) and the Westinghouse Nuclear Fuels Division (WNFD) in Cheswick, Pennsylvania and shipped to the Hanford Sits for storage. This report characterizes these radioactive solid wastes using process knowledge, existing records, and oral history interviews.

Duncan, D. [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J.A.; Weyns, M.I.; Dicenso, K.D.; DeLorenzo, D.S. [Los Alamos Technical Associates, Inc., NM (United States)

1994-04-01T23:59:59.000Z

176

Advanced Fuels Campaign Execution Plan  

SciTech Connect

The purpose of the Advanced Fuels Campaign (AFC) Execution Plan is to communicate the structure and management of research, development, and demonstration (RD&D) activities within the Fuel Cycle Research and Development (FCRD) program. Included in this document is an overview of the FCRD program, a description of the difference between revolutionary and evolutionary approaches to nuclear fuel development, the meaning of science-based development of nuclear fuels, and the “Grand Challenge” for the AFC that would, if achieved, provide a transformational technology to the nuclear industry in the form of a high performance, high reliability nuclear fuel system. The activities that will be conducted by the AFC to achieve success towards this grand challenge are described and the goals and milestones over the next 20 to 40 year period of research and development are established.

Kemal Pasamehmetoglu

2010-10-01T23:59:59.000Z

177

Advanced Fuels Campaign Execution Plan  

SciTech Connect

The purpose of the Advanced Fuels Campaign (AFC) Execution Plan is to communicate the structure and management of research, development, and demonstration (RD&D) activities within the Fuel Cycle Research and Development (FCRD) program. Included in this document is an overview of the FCRD program, a description of the difference between revolutionary and evolutionary approaches to nuclear fuel development, the meaning of science-based development of nuclear fuels, and the 'Grand Challenge' for the AFC that would, if achieved, provide a transformational technology to the nuclear industry in the form of a high performance, high reliability nuclear fuel system. The activities that will be conducted by the AFC to achieve success towards this grand challenge are described and the goals and milestones over the next 20 to 40 year period of research and development are established.

Kemal Pasamehmetoglu

2011-09-01T23:59:59.000Z

178

Advanced Fuels Campaign Execution Plan  

SciTech Connect

The purpose of the Advanced Fuels Campaign (AFC) Execution Plan is to communicate the structure and management of research, development, and demonstration (RD&D) activities within the Fuel Cycle Research and Development (FCRD) program. Included in this document is an overview of the FCRD program, a description of the difference between revolutionary and evolutionary approaches to nuclear fuel development, the meaning of science-based development of nuclear fuels, and the 'Grand Challenge' for the AFC that would, if achieved, provide a transformational technology to the nuclear industry in the form of a high performance, high reliability nuclear fuel system. The activities that will be conducted by the AFC to achieve success towards this grand challenge are described and the goals and milestones over the next 20 to 40 year period of research and development are established.

Kemal Pasamehmetoglu

2011-09-01T23:59:59.000Z

179

I have worked in nuclear science for most of my life and have seen tremendous advances since my early  

E-Print Network (OSTI)

by controlled optical or infrared pulses and understanding the atomic and electronic transformation by means

Liu, Taosheng

180

Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities  

Science Conference Proceedings (OSTI)

The research effort is a part of the Light Water Reactor Sustainability (LWRS) Program. LWRS is a research and development program sponsored by the Department of Energy, performed in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The Outage Control Center (OCC) Pilot Project was directed at carrying out the applied research for development and pilot of technology designed to enhance safe outage and maintenance operations, improve human performance and reliability, increase overall operational efficiency, and improve plant status control. Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Unfortunately, many of the underlying technologies supporting outage control are the same as those used in the 1980’s. They depend heavily upon large teams of staff, multiple work and coordination locations, and manual administrative actions that require large amounts of paper. Previous work in human reliability analysis suggests that many repetitive tasks, including paper work tasks, may have a failure rate of 1.0E-3 or higher (Gertman, 1996). With between 10,000 and 45,000 subtasks being performed during an outage (Gomes, 1996), the opportunity for human error of some consequence is a realistic concern. Although a number of factors exist that can make these errors recoverable, reducing and effectively coordinating the sheer number of tasks to be performed, particularly those that are error prone, has the potential to enhance outage efficiency and safety. Additionally, outage management requires precise coordination of work groups that do not always share similar objectives. Outage managers are concerned with schedule and cost, union workers are concerned with performing work that is commensurate with their trade, and support functions (safety, quality assurance, and radiological controls, etc.) are concerned with performing the work within the plants controls and procedures. Approaches to outage management should be designed to increase the active participation of work groups and managers in making decisions that closed the gap between competing objectives and the potential for error and process inefficiency.

Gregory Weatherby

2012-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Global Nuclear Security Technology Division (GNSTD)  

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

Systems Nonproliferation Technology Nuclear Material Detection & Characterization Nuclear Security Advanced Technologies Safeguards & Security Technology Threat Reduction...

182

Irradiation Performance of Advanced and Model Alloys  

Science Conference Proceedings (OSTI)

Mar 14, 2012 ... Mechanical Performance of Materials for Current and Advanced Nuclear Reactors: Irradiation Performance of Advanced and Model Alloys

183

Design of the Next Generation Nuclear Plant Graphite Creep Experiments for Irradiation in the Advanced Test Reactor  

SciTech Connect

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating six gas reactor graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These graphite irradiations are being accomplished to support development of the next generation reactors in the United States. The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain seven separate stacks of graphite specimens. Six of the specimen stacks will have half of their graphite specimens under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six stacks will be organized into pairs with a different compressive load being applied to the top half of each pair of specimen stacks. The seventh stack will not have a compressive load on the graphite specimens during irradiation. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be the capability of sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during initial start-up of the experiment. The final design phase for the first experiment was completed in September 2008, and the fabrication and assembly of the experiment test train as well as installation and testing of the control and support systems that will monitor and control the experiment during irradiation are being completed in early calendar 2009. The first experiment is scheduled to be ready for insertion in the ATR by April 30, 2009. This paper will discuss the design of the experiment including the test train and the temperature and compressive load monitoring, control, and data collection systems.

S. Blaine Grover

2009-05-01T23:59:59.000Z

184

DEVELOPMENT OF CERAMIC WASTE FORMS FOR AN ADVANCED NUCLEAR FUEL CYCLE  

SciTech Connect

A series of ceramic waste forms were developed and characterized for the immobilization of a Cesium/Lanthanide (CS/LN) waste stream anticipated to result from nuclear fuel reprocessing. Simple raw materials, including Al{sub 2}O{sub 3} and TiO{sub 2} were combined with simulated waste components to produce multiphase ceramics containing hollandite-type phases, perovskites (particularly BaTiO{sub 3}), pyrochlores and other minor metal titanate phases. Three fabrication methodologies were used, including melting and crystallizing, pressing and sintering, and Spark Plasma Sintering (SPS), with the intent of studying phase evolution under various sintering conditions. X-Ray Diffraction (XRD) and Scanning Electron Microscopy coupled with Energy Dispersive Spectroscopy (SEM/EDS) results showed that the partitioning of the waste elements in the sintered materials was very similar, despite varying stoichiometry of the phases formed. Identification of excess Al{sub 2}O{sub 3} via XRD and SEM/EDS in the first series of compositions led to a Phase II study, with significantly reduced Al{sub 2}O{sub 3} concentrations and increased waste loadings. The Phase II compositions generally contained a reduced amount of unreacted Al{sub 2}O{sub 3} as identified by XRD. Chemical composition measurements showed no significant issues with meeting the target compositions. However, volatilization of Cs and Mo was identified, particularly during melting, since sintering of the pressed pellets and SPS were performed at lower temperatures. Partitioning of some of the waste components was difficult to determine via XRD. SEM/EDS mapping showed that those elements, which were generally present in small concentrations, were well distributed throughout the waste forms.

Marra, J.; Billings, A.; Brinkman, K.; Fox, K.

2010-11-30T23:59:59.000Z

185

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

Science Conference Proceedings (OSTI)

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

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

2012-06-11T23:59:59.000Z

186

Advanced neutron irradiation system using Texas A&M University Nuclear Science Center Reactor  

E-Print Network (OSTI)

A heavily filtered fast neutron irradiation system (FNIS) was developed for a variety of applications, including the study of long-term health effects of fast neutrons by evaluating the biological mechanisms of damage in cultured cells and living animals such as rats or mice. This irradiation system includes an exposure cave made with a lead-bismuth alloy, a cave positioning system, a gamma and neutron monitoring system, a sample transfer system, and interchangeable filters. This system was installed in the irradiation cell of the Texas A&M University Nuclear Science Center Reactor (NSCR). By increasing the thickness of the lead-bismuth alloy, the neutron spectra were shifted into lower energies by the scattering interactions of fast neutrons with the alloy. It is possible, therefore, by changing the alloy thickness, to produce distinctly different dose weighted neutron spectra inside the exposure cave of the FNIS. The calculated neutron spectra showed close agreement with the results of activation foil measurements, unfolded by SAND-II close to the cell window. However, there was a considerable less agreement for locations far away from the cell window. Even though the magnitude of values such as neutron flux and tissue kerma rates in air differed, the weighted average neutron energies showed close agreement between the MCNP and SAND-II since the normalized neutron spectra were in a good agreement each other. A paired ion chamber system was constructed, one with a tissue equivalent plastic (A-150) and propane gas for total dose monitoring, and another with graphite and argon for photon dose monitoring. Using the pair of detectors, the neutron to gamma ratio can be inferred. With the 20 cm-thick FNIS, the absorbed dose rates of neutrons measured with the paired ion chamber method and calculated with the SAND-II results were 13.7 ?? 0.02 Gy/min and 15.5 Gy/min, respectively. The absorbed dose rate of photons and the gamma contribution to total dose were 6.7??10-1 ?? 1.3??10-1 Gy/min and 4.7%, respectively. However, the estimated gamma contribution to total dose varied between 3.6 % to 6.6 % as the assumed neutron sensitivity to the graphite detector was changed from 0.01 to 0.03.

Jang, Si Young

2004-08-01T23:59:59.000Z

187

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.  

SciTech Connect

This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologic-chemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.

Criscenti, Louise Jacqueline; Sassani, David Carl; Arguello, Jose Guadalupe, Jr.; Dewers, Thomas A.; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Wang, Yifeng; Schultz, Peter Andrew

2011-02-01T23:59:59.000Z

188

Advances in Development of the Fission Product Extraction Process for the Separation of Cesium and Strontium from Spent Nuclear Fuel  

Science Conference Proceedings (OSTI)

The Fission Product Extraction (FPEX) Process is being developed as part of the United States Department of Energy Advanced Fuel Cycle Initiative for the simultaneous separation of cesium (Cs) and strontium (Sr) from spent light water reactor (LWR) fuel. Separation of the Cs and Sr will reduce the short-term heat load in a geological repository, and when combined with the separation of americium (Am) and curium (Cm), could increase the capacity of the geological repository by a factor of approximately 100. The FPEX process is based on two highly specific extractants: 4,4',(5')-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) and Calix[4]arene-bis-(tert-octylbenzo-crown-6) (BOBCalixC6). The DtBuCH18C6 extractant is selective for strontium and the BOBCalixC6 extractant is selective for cesium. Results of flowsheet testing of the FPEX process with a simulated feed solution in 3.3-cm centrifugal contactors are detailed. Removal efficiencies, distribution coefficient data, coextraction of metals, and process hydrodynamic performance are discussed along with recommendations for future flowsheet testing with actual spent nuclear fuel.

JAck D. Law

2007-09-01T23:59:59.000Z

189

Deployment & Market Transformation (Brochure)  

SciTech Connect

NREL's deployment and market transformation (D and MT) activities encompass the laboratory's full range of technologies, which span the energy efficiency and renewable energy spectrum. NREL staff educates partners on how they can advance sustainable energy applications and also provides clients with best practices for reducing barriers to innovation and market transformation.

Not Available

2012-04-01T23:59:59.000Z

190

Deployment & Market Transformation (Brochure)  

SciTech Connect

NREL's deployment and market transformation (D and MT) activities encompass the laboratory's full range of technologies, which span the energy efficiency and renewable energy spectrum. NREL staff educates partners on how they can advance sustainable energy applications and also provides clients with best practices for reducing barriers to innovation and market transformation.

2012-04-01T23:59:59.000Z

191

Nuclear Maintenance Application Center: Development and Analysis of an Open Phase Detection Scheme for Various Configurations of Auxiliary Transformers  

Science Conference Proceedings (OSTI)

Two recent failures have highlighted the need to detect open-phase conditions that can occur in the power delivery system. The analysis described in this report was performed to determine the response of system auxiliary transformers during open-phase conditions to aid in the development of system protection schemes to detect such conditions.BackgroundIn January 2012, an auxiliary component tripped due to a bus under-voltage. The cause of the event was the ...

2013-05-10T23:59:59.000Z

192

Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).  

Science Conference Proceedings (OSTI)

This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

2010-09-01T23:59:59.000Z

193

NUCLEAR ENERGY  

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

could improve the economic and safety performance of these advanced reactors. Nuclear power can reduce GHG emissions from electricity production and possibly in co-generation...

194

Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants  

SciTech Connect

The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs). This research project is aimed at providing methodologies, information, and insights that inform the process for determining and optimizing candidate areas for new advanced nuclear power generation plants and consolidated ISFSIs to meet projected US electric power demands for the future.

Mays, Gary T [ORNL; Belles, Randy [ORNL; Cetiner, Mustafa Sacit [ORNL; Howard, Rob L [ORNL; Liu, Cheng [ORNL; Mueller, Don [ORNL; Omitaomu, Olufemi A [ORNL; Peterson, Steven K [ORNL; Scaglione, John M [ORNL

2012-06-01T23:59:59.000Z

195

AdvAnced  

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

AdvAnced test reActor At the InL advanced Unlike large, commercial power reactors, ATR is a low- temperature, low-pressure reactor. A nuclear reactor is basically an elaborate tool...

196

Materials Characterization | Advanced Materials | ORNL  

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

Characterization Nuclear Forensics Scanning Probes Related Research Materials Theory and Simulation Energy Frontier Research Centers Advanced Materials Home | Science &...

197

Advanced Modeling and Evaluation of the Response of Base-Isolated Nuclear Facility Structures to Vertical Earthquake Excitation  

E-Print Network (OSTI)

Deeply Embedded Nuclear Power Plant Structures. ” NUREG/CR–6896, BNL–NUREG–75410–2006, Brookhaven National Laboratory,

Keldrauk, Eric Scott

2012-01-01T23:59:59.000Z

198

Advanced Nuclear Research Reactor  

SciTech Connect

This report describes technical modifications implemented by INVAP to improve the safety of the Research Reactors the company designs and builds.

Lolich, J.V.

2004-10-06T23:59:59.000Z

199

Civilian Nuclear Programs, SPO-CNP: LANL  

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

Civilian Nuclear Programs, SPO-CNP Science Program Office Applied Energy Civilian Nuclear Office of Science Civilian Nuclear Programs Home Advanced Nuclear Energy Programs Yucca...

200

nuclear energy legislation on track  

Science Conference Proceedings (OSTI)

07/8 - NUCLEAR ENERGY LEGISLATION ON TRACK ... the safety and economic viability of nuclear power, the management of nuclear waste, the advancement ...

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


201

Nuclear Energy Systems  

NLE Websites -- All DOE Office Websites (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...

202

Evaluation of the applicability of existing nuclear power plant regulatory requirements in the U.S. to advanced small modular reactors.  

SciTech Connect

The current wave of small modular reactor (SMR) designs all have the goal of reducing the cost of management and operations. By optimizing the system, the goal is to make these power plants safer, cheaper to operate and maintain, and more secure. In particular, the reduction in plant staffing can result in significant cost savings. The introduction of advanced reactor designs and increased use of advanced automation technologies in existing nuclear power plants will likely change the roles, responsibilities, composition, and size of the crews required to control plant operations. Similarly, certain security staffing requirements for traditional operational nuclear power plants may not be appropriate or necessary for SMRs due to the simpler, safer and more automated design characteristics of SMRs. As a first step in a process to identify where regulatory requirements may be met with reduced staffing and therefore lower cost, this report identifies the regulatory requirements and associated guidance utilized in the licensing of existing reactors. The potential applicability of these regulations to advanced SMR designs is identified taking into account the unique features of these types of reactors.

LaChance, Jeffrey L.; Wheeler, Timothy A.; Farnum, Cathy Ottinger; Middleton, Bobby D.; Jordan, Sabina Erteza; Duran, Felicia Angelica; Baum, Gregory A.

2013-05-01T23:59:59.000Z

203

ARPA-E Announces $43 Million for Transformational Energy Storage...  

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

43 Million for Transformational Energy Storage Projects to Advance Electric Vehicle and Grid Technologies ARPA-E Announces 43 Million for Transformational Energy Storage Projects...

204

ARPA-E Announces $43 Million for Transformational Energy Storage...  

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

ARPA-E Announces 43 Million for Transformational Energy Storage Projects to Advance Electric Vehicle and Grid Technologies ARPA-E Announces 43 Million for Transformational Energy...

205

Report on the workshop "Decay spectroscopy at CARIBU: advanced fuel cycle applications, nuclear structure and astrophysics". 14-16 April 2011, Argonne National Laboratory, USA.  

SciTech Connect

A workshop on 'Decay Spectroscopy at CARIBU: Advanced Fuel Cycle Applications, Nuclear Structure and Astrophysics' will be held at Argonne National Laboratory on April 14-16, 2011. The aim of the workshop is to discuss opportunities for decay studies at the Californium Rare Isotope Breeder Upgrade (CARIBU) of the ATLAS facility with emphasis on advanced fuel cycle (AFC) applications, nuclear structure and astrophysics research. The workshop will consist of review and contributed talks. Presentations by members of the local groups, outlining the status of relevant in-house projects and availabile equipment, will also be organized. time will also be set aside to discuss and develop working collaborations for future decay studies at CARIBU. Topics of interest include: (1) Decay data of relevance to AFC applications with emphasis on reactor decay heat; (2) Discrete high-resolution gamma-ray spectroscopy following radioactive decya and related topics; (3) Calorimetric studies of neutron-rich fission framgents using Total ABsorption Gamma-Ray Spectrometry (TAGS) technique; (4) Beta-delayed neutron emissions and related topics; and (5) Decay data needs for nuclear astrophysics.

Kondev, F.; Carpenter, M.P.; Chowdhury, P.; Clark, J.A.; Lister, C.J.; Nichols, A.L.; Swewryniak, D. (Nuclear Engineering Division); (Univ. of Massachusetts); (Univ. of Surrey)

2011-10-06T23:59:59.000Z

206

Advanced Reactor Technologies | Department of Energy  

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

Advanced Reactor Advanced Reactor Technologies Advanced Reactor Technologies Advanced Reactor Technologies Advanced Reactor Technologies The Office of Advanced Reactor Technologies (ART) sponsors research, development and deployment (RD&D) activities through its Next Generation Nuclear Plant (NGNP), Advanced Reactor Concepts (ARC), and Advanced Small Modular Reactor (aSMR) programs to promote safety, technical, economical, and environmental advancements of innovative Generation IV nuclear energy technologies. The Office of Nuclear Energy (NE) will pursue these advancements through RD&D activities at the Department of Energy (DOE) national laboratories and U.S. universities, as well as through collaboration with industry and international partners. These activities will focus on advancing scientific

207

Nuclear Waste Management  

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

Waste Management's Yucca Mountain Project and the Office of Nuclear Energy's Advanced Fuel Cycle Initiative (AFCI) and Global Nuclear Energy Partnership (GNEP) programs. Efforts...

208

Nuclear Fuels - Modeling  

Science Conference Proceedings (OSTI)

Mar 12, 2012... for the Current and Advanced Nuclear Reactors: Nuclear Fuels - Modeling .... Using density functional theory (DFT), we have predicted that ...

209

TITAN : an advanced three dimensional coupled neutronicthermal-hydraulics code for light water nuclear reactor core analysis  

E-Print Network (OSTI)

The accurate analysis of nuclear reactor transients frequently requires that neutronics, thermal-hydraulics and feedback be included. A number of coupled neutronics/thermal-hydraulics codes have been developed for this ...

Griggs, D. P.

1984-01-01T23:59:59.000Z

210

Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS) Code Verification and Validation Data Standards and Requirements: Fluid Dynamics Version 1.0  

SciTech Connect

V&V and UQ are the primary means to assess the accuracy and reliability of M&S and, hence, to establish confidence in M&S. Though other industries are establishing standards and requirements for the performance of V&V and UQ, at present, the nuclear industry has not established such standards or requirements. However, the nuclear industry is beginning to recognize that such standards are needed and that the resources needed to support V&V and UQ will be very significant. In fact, no single organization has sufficient resources or expertise required to organize, conduct and maintain a comprehensive V&V and UQ program. What is needed is a systematic and standardized approach to establish and provide V&V and UQ resources at a national or even international level, with a consortium of partners from government, academia and industry. Specifically, what is needed is a structured and cost-effective knowledge base that collects, evaluates and stores verification and validation data, and shows how it can be used to perform V&V and UQ, leveraging collaboration and sharing of resources to support existing engineering and licensing procedures as well as science-based V&V and UQ processes. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation (NE-KAMS) is being developed at the Idaho National Laboratory in conjunction with Bettis Laboratory, Sandia National Laboratories, Argonne National Laboratory, Utah State University and others with the objective of establishing a comprehensive and web-accessible knowledge base to provide V&V and UQ resources for M&S for nuclear reactor design, analysis and licensing. The knowledge base will serve as an important resource for technical exchange and collaboration that will enable credible and reliable computational models and simulations for application to nuclear power. NE-KAMS will serve as a valuable resource for the nuclear industry, academia, the national laboratories, the U.S. Nuclear Regulatory Commission (NRC) and the public and will help ensure the safe, economical and reliable operation of existing and future nuclear reactors.

Greg Weirs; Hyung Lee

2011-09-01T23:59:59.000Z

211

Appell Transformation and Canonical Transforms  

E-Print Network (OSTI)

The interpretation of the optical Appell transformation, as previously elaborated in relation to the free-space paraxial propagation under both a rectangular and a circular cylindrical symmetry, is reviewed. Then, the caloric Appell transformation, well known in the theory of heat equation, is shown to be amenable for a similar interpretation involving the Laplace transform rather than the Fourier transform, when dealing with the 1D heat equation. Accordingly, when considering the radial heat equation, suitably defined Hankel-type transforms come to be involved in the inherent Appell transformation. The analysis is aimed at outlining the link between the Appell transformation and the canonical transforms.

Torre, Amalia

2011-01-01T23:59:59.000Z

212

Riesz transforms for Dunkl transform  

E-Print Network (OSTI)

In this paper we obtain the $L^p$-boundedness of Riesz transforms for Dunkl transform for all $1

Amri, Béchir

2011-01-01T23:59:59.000Z

213

Nuclear Hydrogen Initiative  

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

Advanced Nuclear Research Advanced Nuclear Research Office of Nuclear Energy, Science and Technology FY 2003 Programmatic Overview Nuclear Hydrogen Initiative Nuclear Hydrogen Initiative Office of Nuclear Energy, Science and Technology Henderson/2003 Hydrogen Initiative.ppt 2 Nuclear Hydrogen Initiative Nuclear Hydrogen Initiative Program Goal * Demonstrate the economic commercial-scale production of hydrogen using nuclear energy by 2015 Need for Nuclear Hydrogen * Hydrogen offers significant promise for reduced environmental impact of energy use, specifically in the transportation sector * The use of domestic energy sources to produce hydrogen reduces U.S. dependence on foreign oil and enhances national security * Existing hydrogen production methods are either inefficient or produce

214

Phase Transformations  

Science Conference Proceedings (OSTI)

Aug 9, 2013 ... O. Advanced Neutron and Synchrotron Studies of Materials: Phase .... We will describe recent advances at the Advanced Photon Source in ... Finally, we will describe upgrade plans for microdiffraction capabilities at the APS.

215

Integral transformation and Darboux transformation  

E-Print Network (OSTI)

We review Darboux-Crum transformation of Heun's differential equation. By rewriting an integral transformation of Heun's differential equation into a form of elliptic functions, we see that the integral representation is a generalization of Darboux-Crum transformation. We also consider conservation of monodromy with respect to the transformations.

Takemura, Kouichi

2009-01-01T23:59:59.000Z

216

Nondestructive Spent Fuel Assay Using Nuclear Resonance Fluorescence  

E-Print Network (OSTI)

09-01188, ANS Advances in Nuclear Fuel Management IV, Hiltonanalysis of spent nuclear fuel via nuclear resonanceNondestructive Spent Fuel Assay Using Nuclear Resonance

Quiter, Brian

2010-01-01T23:59:59.000Z

217

Grid Transformation Workshop Results Grid Transformation Workshop Results 2 April 2012  

E-Print Network (OSTI)

Grid Transformation Workshop Results April 2012 #12;Grid Transformation Workshop Results 2 April 2012 Grid Transformation Workshop Results plications. We will explore the basics of data modeling Transformation Workshop: Advanced Reading Material Product ID 1024659. The material in this report builds upon

218

Testability Transformation  

E-Print Network (OSTI)

A testability transformation is a source-to-source transformation that aims to improve the ability of a given test generation method to generate test data for the original program. This paper

Mark Harman; Lin Hu; Robert Hierons; Joachim Wegener; Harmen Sthamer; Andre Baresel; Marc Roper

2004-01-01T23:59:59.000Z

219

Transformational Manufacturing | Argonne National Laboratory  

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

Transformational Manufacturing Transformational Manufacturing Argonne's new Advanced Battery Materials Synthesis and Manufacturing R&D Program focuses on scalable process R&D to produce advanced battery materials in sufficient quantity for industrial testing. The U.S. manufacturing industry consumes more than 30 quadrillion Btu of energy per year, directly employs about 12 million people and generates another 7 million jobs in related businesses. Argonne is working with industry to develop innovative and transformational technology to improve the efficiency and competitiveness of domestic manufacturing while reducing its carbon footprint. The lab's efforts concentrate on sustainable manufacturing, applied nanotechnology and distributed energy, with an emphasis on transitioning science discoveries to the market.

220

Market Transformation  

DOE Green Energy (OSTI)

Summarizes the goals and activities of the DOE Solar Energy Technologies Program efforts within its market transformation subprogram.

Not Available

2008-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Advanced Pipe Replacement Procedure for a Defective CRDM Housing Nozzle Enables Continued Normal Operation of a Nuclear Power Plant  

SciTech Connect

During the 2003 outage at the Ringhals Nuclear Plant in Sweden, a leak was found in the vicinity of a Control Rod Drive Mechanism (CRDM) housing nozzle at Unit 1. Based on the ALARA principle for radioactive contamination, a unique repair process was developed. The repair system includes utilization of custom, remotely controlled GTAW-robots, a CNC cutting and finishing machine, snake-arm robots and NDE equipment. The success of the repair solution was based on performing the machining and welding operations from the inside of the SCRAM pipe through the CRDM housing since accessibility from the outside was extremely limited. Before the actual pipe replacement procedure was performed, comprehensive training programs were conducted. Training was followed by certification of equipment, staff and procedures during qualification tests in a full scale mock-up of the housing nozzle. Due to the ingenuity of the overall repair solution and training programs, the actual pipe replacement procedure was completed in less than half the anticipated time. As a result of the successful pipe replacement, the nuclear power plant was returned to normal operation. (authors)

Gilmore, Geoff; Becker, Andrew [Climax Portable Machine Tools, Inc., 2712 East Second Street, Newberg, OR 97132 (United States)

2006-07-01T23:59:59.000Z

222

Final LDRD report : nanoscale mechanisms in advanced aging of materials during storage of spent %22high burnup%22 nuclear fuel.  

Science Conference Proceedings (OSTI)

We present the results of a three-year LDRD project focused on understanding microstructural evolution and related property changes in Zr-based nuclear cladding materials towards the development of high fidelity predictive simulations for long term dry storage. Experiments and modeling efforts have focused on the effects of hydride formation and accumulation of irradiation defects. Key results include: determination of the influence of composition and defect structures on hydride formation; measurement of the electrochemical property differences between hydride and parent material for understanding and predicting corrosion resistance; in situ environmental transmission electron microscope observation of hydride formation; development of a predictive simulation for mechanical property changes as a function of irradiation dose; novel test method development for microtensile testing of ionirradiated material to simulate the effect of neutron irradiation on mechanical properties; and successful demonstration of an Idaho National Labs-based sample preparation and shipping method for subsequent Sandia-based analysis of post-reactor cladding.

Clark, Blythe G.; Rajasekhara, Shreyas; Enos, David George; Dingreville, Remi Philippe Michel; Doyle, Barney Lee; Hattar, Khalid Mikhiel; Weiner, Ruth F.

2013-09-01T23:59:59.000Z

223

Civilian Nuclear Programs  

NLE Websites -- All DOE Office Websites (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

224

Determination of Basic Structure-Property Relations for Processing and Modeling in Advanced Nuclear Fuel: Microstructure Evolution and Mechanical Properties  

SciTech Connect

The project objective is to study structure-property relations in solid solutions of nitrides and oxides with surrogate elements to simulate the behavior of fuels of inert matrix fuels of interest to the Advanced Fuel Cycle Initiative (AFCI), with emphasis in zirconium-based materials. Work with actual fuels will be carried out in parallel in collaboration with Los Alamos National Laboratory (LANL). Three key aspects will be explored: microstructure characterization through measurement of global texture evolution and local crystallographic variations using Electron Backscattering Diffraction (EBSD); determination of mechanical properties, including fracture toughness, quasi-static compression strength, and hardness, as functions of load and temperature, and, finally, development of structure-property relations to describe mechanical behavior of the fuels based on experimental data. Materials tested will be characterized to identify the mechanisms of deformation and fracture and their relationship to microstructure and its evolution. New aspects of this research are the inclusion of crystallographic information into the evaluation of fuel performance and the incorporation of statistical variations of microstructural variables into simplified models of mechanical behavior of fuels that account explicitly for these variations. The work is expected to provide insight into processing conditions leading to better fuel performance and structural reliability during manufacturing and service, as well as providing a simplified testing model for future fuel production.

Kirk Wheeler; Manuel Parra; Pedro Peralta

2009-03-01T23:59:59.000Z

225

6 Nuclear Fuel Designs  

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

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

226

Deputy Secretary Poneman to Attend International Framework for Nuclear  

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

to Attend International Framework for to Attend International Framework for Nuclear Energy Cooperation Meeting in Jordan Deputy Secretary Poneman to Attend International Framework for Nuclear Energy Cooperation Meeting in Jordan November 3, 2010 - 12:00am Addthis Washington, D.C. - U.S. Deputy Secretary of Energy Daniel Poneman will represent the United States at the International Framework for Nuclear Energy Cooperation (IFNEC) Executive Committee Meeting in Jordan on Thursday, November 4, 2010. The conference aims to advance cooperation among participating states to promote the peaceful use of nuclear energy in a manner that meets high standards of safety, security and nonproliferation. IFNEC developed out of the Global Nuclear Energy Partnership. Last June, the Global Nuclear Energy Partnership Steering Group agreed to transform to

227

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

SciTech Connect

Framatome ANP, Sandia National Laboratories (SNL), Oak Ridge National Laboratory (ORNL), and the University of Florida are cooperating on the U.S. Department of Energy Nuclear Energy Research Initiative (NERI) project 2001-0124 to design, assemble, execute, analyze, and document a series of critical experiments to validate reactor physics and criticality safety codes for the analysis of commercial power reactor fuels consisting of UO{sub 2} with {sup 235}U enrichments {>=}5 wt%. The experiments will be conducted at the SNL Pulsed Reactor Facility.Framatome ANP and SNL produced two series of conceptual experiment designs based on typical parameters, such as fuel-to-moderator ratios, that meet the programmatic requirements of this project within the given restraints on available materials and facilities. ORNL used the Tools for Sensitivity and Uncertainty Analysis Methodology Implementation (TSUNAMI) to assess, from a detailed physics-based perspective, the similarity of the experiment designs to the commercial systems they are intended to validate. Based on the results of the TSUNAMI analysis, one series of experiments was found to be preferable to the other and will provide significant new data for the validation of reactor physics and criticality safety codes.

Rearden, B.T. [Oak Ridge National Laboratory (United States); Anderson, W.J. [Framatome ANP, Inc. (France); Harms, G.A. [Sandia National Laboratories (United States)

2005-08-15T23:59:59.000Z

228

Nuclear Data Program - Nuclear Engineering Division (Argonne)  

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

Data Program Data Program Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program We contribute to the development of comprehensive nuclear reactions and nuclear structure databases, including nuclear data measurement, analysis, modeling and evaluation methodologies, that are implemented in basic science research and advanced nuclear technologies. Bookmark and Share Recent Events Nuclear Structure 2012 Conference Argonne National Laboratory hosted the

229

Downloads - Nuclear Engineering Division (Argonne)  

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

Assessment Team (VAT) Argonne's National Security Information Systems Argonne's Facility Decommissioning Training Course Reactor Safety Experimentation Nuclear Energy Advanced...

230

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

Science Conference Proceedings (OSTI)

May 7, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear Power ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science, Nuclear ... This 'thermodynamic database for advanced nuclear fuels' was ...

231

Market Transformation  

Fuel Cell Technologies Publication and Product Library (EERE)

This Fuel Cell Technologies Program fact sheet outlines current status and challenges in the market transformation of hydrogen and fuel cell technologies.

232

The Global Nuclear Energy Partnership | Department of Energy  

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

The Global Nuclear Energy Partnership (GNEP) GNEP Element:Develop Advanced Burner Reactors Global Nuclear Energy Partnership Fact Sheet - Develop Advanced Burner Reactors...

233

Materials for Nuclear Power: Digital Resource Center Text Topic - TMS  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Office of Nuclear Energy and Office of Advanced Scientific Computing Research. Simulation and Modeling for Advanced Nuclear Energy ...

234

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

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Office of Nuclear Energy and Office of Advanced Scientific Computing Research. Simulation and Modeling for Advanced Nuclear Energy ...

235

Chemical Sciences Division | Advanced Materials |ORNL  

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

at the fluid-solid interface that will enable transformative advances in electrical energy storage and catalysis. The division also provides analytical support and leadership...

236

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

SciTech Connect

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.

Denia Djokic; Steven J. Piet; Layne F. Pincock; Nick R. Soelberg

2013-02-01T23:59:59.000Z

237

ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS - EBS INPUT  

Science Conference Proceedings (OSTI)

The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geologic environment and the waste forms being emplaced. The UFD Campaign is considering a range of fuel cycles that in turn produce a range of waste forms. The UFD Campaign is also considering a range of geologic media. These ranges could be thought of as adding uncertainty to what the disposal facility design will ultimately be; however, it may be preferable to thinking about the ranges as adding flexibility to design of a disposal facility. For example, as the overall DOE-NE program and industrial actions result in the fuel cycles that will produce waste to be disposed, and the characteristics of those wastes become clear, the disposal program retains flexibility in both the choice of geologic environment and the specific repository design. Of course, other factors also play a major role, including local and State-level acceptance of the specific site that provides the geologic environment. In contrast, the Yucca Mountain Project (YMP) repository license application (LA) is based on waste forms from an open fuel cycle (PWR and BWR assemblies from an open fuel cycle). These waste forms were about 90% of the total waste, and they were the determining waste form in developing the engineered barrier system (EBS) design for the Yucca Mountain Repository design. About 10% of the repository capacity was reserved for waste from a full recycle fuel cycle in which some actinides were extracted for weapons use, and the remaining fission products and some minor actinides were encapsulated in borosilicate glass. Because the heat load of the glass was much less than the PWR and BWR assemblies, the glass waste form was able to be co-disposed with the open cycle waste, by interspersing glass waste packages among the spent fuel assembly waste packages. In addition, the Yucca Mountain repository was designed to include some research reactor spent fuel and naval reactor spent fuel, within the envelope that was set using the commercial reactor assemblies as the design basis waste form. This milestone report supports Sandia National Laboratory milestone M2FT-12SN0814052, and is intended to be a chapter in that milestone report. The independent technical review of this LLNL milestone was performed at LLNL and is documented in the electronic Information Management (IM) system at LLNL. The objective of this work is to investigate what aspects of quantifying, characterizing, and representing the uncertainty associated with the engineered barrier are affected by implementing different advanced nuclear fuel cycles (e.g., partitioning and transmutation scenarios) together with corresponding designs and thermal constraints.

Sutton, M; Blink, J A; Greenberg, H R; Sharma, M

2012-04-25T23:59:59.000Z

238

Comparison of the High-Temperature Steam Oxidation Kinetics of Advanced Cladding Materials  

Science Conference Proceedings (OSTI)

Technical Paper / Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Materials for Nuclear Systems

M. Grosse

239

Recapitalizing Our Infrastructure | National Nuclear Security...  

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

Recapitalizing Our Infrastructure The FY2011 Budget Request increase represents the investment needed to transform a Cold War nuclear weapons complex into a 21st century Nuclear...

240

Lightweight transformer  

DOE Green Energy (OSTI)

The technical effort described in this report relates to the program that was performed to design, fabricate, and test a lightweight transformer for Strategic Defense Initiative Organization (SDIO) mission requirements. The objectives of this program were two-fold: (1) design and fabricate a lightweight transformer using liquid hydrogen as the coolant; and (2) test the completed transformer assembly with a low voltage, dc power source. Although the full power testing with liquid helium was not completed, the program demonstrated the viability of the design approach. The lightweight transformer was designed and fabricated, and low and moderate power testing was completed. The transformer is a liquid hydrogen cooled air core transformer that uses thin copper for its primary and secondary windings. The winding mass was approximately 12 kg, or 0.03 kg/kW. Further refinements of the design to a partial air core transformer could potentially reduce the winding mass to as low as 4 or 5 kg, or 0.0125 kg/kW. No attempt was made on this program to reduce the mass of the related structural components or cryogenic container. 8 refs., 39 figs., 2 tabs.

Swallom, D.W.; Enos, G.

1990-05-01T23:59:59.000Z

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


241

Nuclear Imaging instrumentation  

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

Nuclear Imaging instrumentation Advances in gamma-ray detection and imaging have increased the pace of discovery in a broad cross-section of the sciences ranging from nuclear...

242

Enabling the Nuclear Renaissance  

Science Conference Proceedings (OSTI)

Symposium, Materials Solutions for the Nuclear Renaissance ... Glass Development for the Combined Cs + LN + TM Fission Products from the Advanced Fuel ...

243

ADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING  

E-Print Network (OSTI)

The components of a modern Advanced Boiling Water Reactor (ABWR) nuclear power plant are modeled in this thesis) is a single-cycle, forced circulation, light-water nuclear reactor designed by the General Electric Company better control of the nuclear reaction in the fuel core. 2.1 Modifications to the BWR [1] · The reactor

Mitchell, John E.

244

Studying the Atomic Nucleus - A New Era in Nuclear Structure Studies  

SciTech Connect

The study of atomic nuclei is part of the fascinating quest to understand the fundamental nature and origins of matter. This field, nuclear structure, is undergoing a revolutionary transformation that is breaking cherished paradigms, opening new vistas of nuclear matter for study, and which has the promise of leading to a new comprehensive understanding. The advent of new facilities for the production and study of exotic nuclei provides access to an entirely new territory of nuclei, and advances in extreme computing are enabling similar advances in the theory of atomic nuclei.

Casten, R. F. [Wright Nuclear Structure Laboratory, Yale University, New Haven, CT 06520 (United States)

2011-05-06T23:59:59.000Z

245

Transformative copy  

E-Print Network (OSTI)

The ability to create an unlimited number of identical copies is a privilege of digital documents. What if that would not be the case, if each copy of a digital file would go along with some sort of transformation? This ...

Offenhuber, Dietmar

2008-01-01T23:59:59.000Z

246

Advanced Materials  

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

Advanced Materials Advanced Materials Availability Technology Express Licensing Active Terahertz Metamaterial Devices Express Licensing Anion-Conducting Polymer, Composition, And...

247

Department of Energy and Nuclear Regulatory Commission Increase...  

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

Nuclear Regulatory Commission Increase Cooperation to Advance Global Nuclear Energy Partnership Department of Energy and Nuclear Regulatory Commission Increase Cooperation to...

248

NUCLEI: Nuclear Computational Low-Energy Initiative | Argonne...  

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

NUCLEI: Nuclear Computational Low-Energy Initiative NUCLEI: Nuclear Computational Low-Energy Initiative This project seeks to advance large-scale nuclear physics compoutations in...

249

Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) verification and validation plan. version 1.  

SciTech Connect

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. To meet this objective, NEAMS Waste IPSC M&S capabilities will be applied to challenging spatial domains, temporal domains, multiphysics couplings, and multiscale couplings. A strategic verification and validation (V&V) goal is to establish evidence-based metrics for the level of confidence in M&S codes and capabilities. Because it is economically impractical to apply the maximum V&V rigor to each and every M&S capability, M&S capabilities will be ranked for their impact on the performance assessments of various components of the repository systems. Those M&S capabilities with greater impact will require a greater level of confidence and a correspondingly greater investment in V&V. This report includes five major components: (1) a background summary of the NEAMS Waste IPSC to emphasize M&S challenges; (2) the conceptual foundation for verification, validation, and confidence assessment of NEAMS Waste IPSC M&S capabilities; (3) specifications for the planned verification, validation, and confidence-assessment practices; (4) specifications for the planned evidence information management system; and (5) a path forward for the incremental implementation of this V&V plan.

Bartlett, Roscoe Ainsworth; Arguello, Jose Guadalupe, Jr.; Urbina, Angel; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Knupp, Patrick Michael; Wang, Yifeng; Schultz, Peter Andrew; Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); McCornack, Marjorie Turner

2011-01-01T23:59:59.000Z

250

United States and Italy Sign Agreements to Advance Developments...  

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

nuclear power plants and improved cooperation on advanced nuclear energy systems and fuel cycle technologies in both countries. The U.S.-Italy Joint Declaration Concerning...

251

A survey of Existing V&V, UQ and M&S Data and Knowledge Bases in Support of the Nuclear Energy - Knowledge base for Advanced Modeling and Simulation (NE-KAMS)  

SciTech Connect

The Nuclear Energy - Knowledge base for Advanced Modeling and Simulation (NE-KAMS) is being developed at the Idaho National Laboratory in conjunction with Bettis Laboratory, Sandia National Laboratories, Argonne National Laboratory, Oak Ridge National Laboratory, Utah State University and others. The objective of this consortium is to establish a comprehensive knowledge base to provide Verification and Validation (V&V) and Uncertainty Quantification (UQ) and other resources for advanced modeling and simulation (M&S) in nuclear reactor design and analysis. NE-KAMS will become a valuable resource for the nuclear industry, the national laboratories, the U.S. NRC and the public to help ensure the safe operation of existing and future nuclear reactors. A survey and evaluation of the state-of-the-art of existing V&V and M&S databases, including the Department of Energy and commercial databases, has been performed to ensure that the NE-KAMS effort will not be duplicating existing resources and capabilities and to assess the scope of the effort required to develop and implement NE-KAMS. The survey and evaluation have indeed highlighted the unique set of value-added functionality and services that NE-KAMS will provide to its users. Additionally, the survey has helped develop a better understanding of the architecture and functionality of these data and knowledge bases that can be used to leverage the development of NE-KAMS.

Hyung Lee; Rich Johnson, Ph.D.; Kimberlyn C. Moussesau

2011-12-01T23:59:59.000Z

252

Advanced Windows Test Facility  

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

Exterior of Advanced Windows Test Facility Exterior of Advanced Windows Test Facility Advanced Windows Test Facility This multi-room laboratory's purpose is to test the performance and properties of advanced windows and window systems such as electrochromic windows, and automatically controlled shutters and blinds. The lab simulates real-world office spaces. Embedded instrumentation throughout the lab records solar gains and losses for specified time periods, weather conditions, energy use, and human comfort indicators. Electrochromic glazings promise to be a major advance in energy-efficient window technology, helping to achieve the goal of transforming windows and skylights from an energy liability in buildings to an energy source. The glazing can be reversibly switched from a clear to a transparent, colored

253

Nuclear Systems Technology | Nuclear Science | ORNL  

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

Advanced Fuel Cycle Systems Criticality Safety Irradiation Experiment Development and Execution Robotics & Remote Systems Engineering and Applications Thermal & Hydraulic Experiments & Analysis Used Nuclear Fuel Storage, Transportation, and Disposal Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research Areas | Nuclear Systems Technology SHARE Nuclear Systems Technology Nuclear Systems Technology Image 2 ORNL has had historic involvement in a broad set of nuclear research areas: irradiated materials and isotopes R&D, fission and fusion reactors development, neutron scattering, fuel enrichment, used fuel recycling and disposal, etc. The skills and knowledge required to succeed in these research areas often cultivated core areas of expertise in which ORNL is

254

Wavelet Transforms and Ocean Current Data Analysis  

Science Conference Proceedings (OSTI)

The recently advanced approach of wavelet transforms is applied to the analysis of ocean currents. The conventional analyses of time series in the frequency domain can be readily generalized to the frequency.and time domain using wavelet ...

Paul C. Liu; Gerald S. Miller

1996-10-01T23:59:59.000Z

255

Substantial Transformation  

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

4 4 Recovery Act/Buy American Information Related to Substantial Transformation GUIDANCE ON MANUFACTURED GOODS AND SUBSTANTIAL TRANSFORMATION FOR FINANCIAL ASSISTANCE AWARDS Section 1605 of the Recovery Act states, "None of the funds appropriated or otherwise made available by this Act may be used for a project for the construction, alteration, maintenance, or repair of a public building or public work unless all of the iron, steel, and manufactured goods used in the project are produced in the United States." The Office of Management and Budget's (OMB) guidance on implementing this section defines "manufactured good" as a "good brought to the construction site for incorporation into

256

SRNL Project Supports Nuclear Energy Research  

will provide necessary data and analyses to further U.S. nuclear fuel cycle technology development, meet the need for advanced nuclear energy

257

Nuclear power high technology colloquium: proceedings  

Science Conference Proceedings (OSTI)

Reports presenting information on technology advancements in the nuclear industry and nuclear power plant functions have been abstracted and are available on the energy data base.

Not Available

1984-12-10T23:59:59.000Z

258

Fourier Transform Near Infrared Microspectroscopy, Infrared Chemical Imaging, High-Resolution Nuclear Magnetic Resonance and Fluorescence Microspectroscopy Detection of Single Cancer Cells and Single Viral Particles  

E-Print Network (OSTI)

Single Cancer Cells from Human tumors are being detected and imaged by Fourier Transform Infrared (FT-IR), Fourier Transform Near Infrared (FT-NIR)Hyperspectral Imaging and Fluorescence Correlation Microspectroscopy. The first FT-NIR chemical, microscopic images of biological systems approaching one micron resolution are here reported. Chemical images obtained by FT-NIR and FT-IR Microspectroscopy are also presented for oil in soybean seeds and somatic embryos under physiological conditions. FT-NIR spectra of oil and proteins were obtained for volumes as small as two cubic microns. Related, HR-NMR analyses of oil contents in somatic embryos as well as 99% accurate calibrations are also presented here with nanoliter precision. Such high-resolution, 400 MHz H-1 NMR analyses allowed the selection of mutagenized embryos with higher oil content (e.g. >~20%) compared to the average levels in non-mutagenized control embryos. Moreover, developmental changes in single soybean seeds and/or somatic embryos may be monito...

Baianu,I C; Hofmann, N E; Korban, S S; Lozano, P; You, T

2004-01-01T23:59:59.000Z

259

The DOE Advanced Gas Reactor Fuel Development and Qualification  

Science Conference Proceedings (OSTI)

Materials for Nuclear Power Overview. The DOE Advanced ... electricity- generation applications, such as ... United States by reducing dependence on foreign ...

260

Transformative role of computation and 'big data' | Department...  

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

role of computation and 'big data' Transformative role of computation and 'big data' SEAB - Foster presentation.pdf More Documents & Publications Slide 1 Nuclear Science and...

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

RF transformer  

DOE Patents (OSTI)

There is provided an improved RF transformer having a single-turn secondary of cylindrical shape and a coiled encapsulated primary contained within the secondary. The coil is tapered so that the narrowest separation between the primary and the secondary is at one end of the coil. The encapsulated primary is removable from the secondary so that a variety of different capacity primaries can be utilized with one secondary.

Smith, James L. (Naperville, IL); Helenberg, Harold W. (Calumet City, IL); Kilsdonk, Dennis J. (Joliet, IL)

1979-01-01T23:59:59.000Z

262

Contact Us | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

National Laboratories Press Release 62912). Institutional Research & Development National Nuclear Security Administration Office of Advanced Simulation and Computing and...

263

Capabilities listed by Department: Nuclear Engineering Division...  

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

Executive Bio Research & Test Reactor Advanced Reactor Development Decontamination and Decommissioning Heat Transfer and fluid Mechanics International Nuclear Safety Reactor...

264

Evaluation of the Use of Synroc to Solidify the Cesium and Strontium Separations Product from Advanced Aqueous Reprocessing of Spent Nuclear Fuel  

SciTech Connect

This report is a literature evaluation on the Synroc process for determining the potential for application to solidification of the Cs/Sr strip product from advanced aqueous fuel separations activities.

Julia Tripp; Vince Maio

2006-03-01T23:59:59.000Z

265

Lorentz Transformations  

E-Print Network (OSTI)

This paper describes a particularly didactic and transparent derivation of basic properties of the Lorentz group. The generators for rotations and boosts along an arbitrary direction, as well as their commutation relations, are written as functions of the unit vectors that define the axis of rotation or the direction of the boost (an approach that can be compared with the one that in electrodynamics, works with the electric and magnetic fields instead of the Maxwell stress tensor). For finite values of the angle of rotation or the boost's velocity, collectively denoted by V, the existence of an exponential expansion for the coordinate transformation's matrix, M (in terms of GV where G is the generator) requires that the matrix's derivative with respect to V, be equal to GM. This condition can only be satisfied if the transformation is additive as it is indeed the case for rotations, but not for velocities. If it is assumed, however, that for boosts such an expansion exists, with V = V(v), v being the velocity, and if the above condition is imposed on the boost's matrix then its expression in terms of hyperbolic cosh(V) and sinh(V} is recovered, and the expression for V(= arc tanh(v)) is determined. A general Lorentz transformation can be written as an exponential containing the sum of a rotation and a boost, which to first order is equal to the product of a boost with a rotation. The calculations of the second and third order terms show that the equations for the generators used in this paper, allow to reliably infer the expressions for the higher order generators, without having recourse to the commutation relations. The transformationmatrices for Weyl spinors are derived for finite values of the rotation and velocity, and field representations, leading to the expression for the angular momentum operator, are studied.

Bernard R. Durney

2011-03-01T23:59:59.000Z

266

Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC) : gap analysis for high fidelity and performance assessment code development.  

SciTech Connect

This report describes a gap analysis performed in the process of developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with rigorous verification, validation, and software quality requirements. The gap analyses documented in this report were are performed during an initial gap analysis to identify candidate codes and tools to support the development and integration of the Waste IPSC, and during follow-on activities that delved into more detailed assessments of the various codes that were acquired, studied, and tested. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. The gap analysis indicates that significant capabilities may already exist in the existing THC codes although there is no single code able to fully account for all physical and chemical processes involved in a waste disposal system. Large gaps exist in modeling chemical processes and their couplings with other processes. The coupling of chemical processes with flow transport and mechanical deformation remains challenging. The data for extreme environments (e.g., for elevated temperature and high ionic strength media) that are needed for repository modeling are severely lacking. In addition, most of existing reactive transport codes were developed for non-radioactive contaminants, and they need to be adapted to account for radionuclide decay and in-growth. The accessibility to the source codes is generally limited. Because the problems of interest for the Waste IPSC are likely to result in relatively large computational models, a compact memory-usage footprint and a fast/robust solution procedure will be needed. A robust massively parallel processing (MPP) capability will also be required to provide reasonable turnaround times on the analyses that will be performed with the code. A performance assessment (PA) calculation for a waste disposal system generally requires a large number (hundreds to thousands) of model simulations to quantify the effect of model parameter uncertainties on the predicted repository performance. A set of codes for a PA calculation must be sufficiently robust and fast in terms of code execution. A PA system as a whole must be able to provide multiple alternative models for a specific set of physical/chemical processes, so that the users can choose various levels of modeling complexity based on their modeling needs. This requires PA codes, preferably, to be highly modularized. Most of the existing codes have difficulties meeting these requirements. Based on the gap analysis results, we have made the following recommendations for the code selection and code development for the NEAMS waste IPSC: (1) build fully coupled high-fidelity THCMBR codes using the existing SIERRA codes (e.g., ARIA and ADAGIO) and platform, (2) use DAKOTA to build an enhanced performance assessment system (EPAS), and build a modular code architecture and key code modules for performance assessments. The key chemical calculation modules will be built by expanding the existing CANTERA capabilities as well as by extracting useful components from other existing codes.

Lee, Joon H.; Siegel, Malcolm Dean; Arguello, Jose Guadalupe, Jr.; Webb, Stephen Walter; Dewers, Thomas A.; Mariner, Paul E.; Edwards, Harold Carter; Fuller, Timothy J.; Freeze, Geoffrey A.; Jove-Colon, Carlos F.; Wang, Yifeng

2011-03-01T23:59:59.000Z

267

TRANSFORMER APPARATUS  

DOE Patents (OSTI)

Transformer apparatus is designed for measuring the amount of a paramagnetic substance dissolved or suspended in a diamagnetic liquid. The apparatus consists of a cluster of tubes, some of which are closed and have sealed within the diamagnetic substance without any of the paramagnetic material. The remaining tubes are open to flow of the mix- ture. Primary and secondary conductors are wrapped around the tubes in such a way as to cancel noise components and also to produce a differential signal on the secondaries based upon variations of the content of the paramagnetic material. (AEC)

Wolfgang, F.; Nicol, J.

1962-11-01T23:59:59.000Z

268

Nuclear Science at NERSC  

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

Accelerator Science Accelerator Science Astrophysics Biological Sciences Chemistry & Materials Science Climate & Earth Science Energy Science Engineering Science Environmental Science Fusion Science Math & Computer Science Nuclear Science Science Highlights NERSC Citations HPC Requirements Reviews Home » Science at NERSC » Nuclear Science Nuclear Science Experimental and theoretical nuclear research carried out at NERSC is driven by the quest for improving our understanding of the building blocks of matter. This includes discovering the origins of nuclei and identifying the forces that transform matter. Specific topics include: Nuclear astrophysics and the synthesis of nuclei in stars and elsewhere in the cosmos; Nuclear forces and quantum chromodynamics (QCD), the quantum field

269

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

Science Conference Proceedings (OSTI)

REPORT: Technology and Applied R&D Needs for Advanced Nuclear Energy Systems A resource document for the Workshop on Basic Research Needs for ...

270

NUCLEAR PROPULSION--AN EMERGING TECHNOLOGY  

SciTech Connect

The use of nuclear energy in the space programs is discussed. Nuclear rocket development is reviewed, and the Nevada rocket development station, nuclear electric propulsion and power generation, and advanced research projects are discussed. (J.R.D.)

Finger, H.B.

1963-01-01T23:59:59.000Z

271

Evaluating Transformer Losses  

E-Print Network (OSTI)

This paper outlines how to determine what transformer losses cost and how to evaluate transformer bids to optimize the investment.

Grun, R. L. Jr.

1989-09-01T23:59:59.000Z

272

New Research Center to Increase Safety and Power Output of U.S. Nuclear Reactors  

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

The Department of Energy dedicated the Consortium for Advanced Simulation of Light Water Reactors (CASL), an advanced research facility that will accelerate the advancement of nuclear reactor technology.

273

Energy Department Announces Awards to Projects Advancing Innovative...  

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

the selection of eight projects to advance the development of transformational oxy-combustion technologies capable of high-efficiency, low-cost carbon dioxide capture from...

274

Nuclear Astrophysics  

E-Print Network (OSTI)

Nuclear physics has a long and productive history of application to astrophysics which continues today. Advances in the accuracy and breadth of astrophysical data and theory drive the need for better experimental and theoretical understanding of the underlying nuclear physics. This paper will review some of the scenarios where nuclear physics plays an important role, including Big Bang Nucleosynthesis, neutrino production by our sun, nucleosynthesis in novae, the creation of elements heavier than iron, and neutron stars. Big-bang nucleosynthesis is concerned with the formation of elements with A nuclear physics inputs required are few-nucleon reaction cross sections. The nucleosynthesis of heavier elements involves a variety of proton-, alpha-, neutron-, and photon-induced reactions, coupled with radioactive decay. The advent of radioactive ion beam facilities has opened an important new avenue for studying these processes, as many involve radioactive species. Nuclear physics also plays an important role in neutron stars: both the nuclear equation of state and cooling processes involving neutrino emission play a very important role. Recent developments and also the interplay between nuclear physics and astrophysics will be highlighted.

Carl R. Brune

2005-02-28T23:59:59.000Z

275

Advanced Modeling & Simulation | Department of Energy  

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

Advanced Modeling & Simulation Advanced Modeling & Simulation Advanced Modeling & Simulation Advanced Modeling & Simulation ADVANCING THE STATE OF THE ART Innovation advances science. Historically, innovation resulted almost exclusively from fundamental theories combined with observation and experimentation over time. With advancements in engineering, computing power and visualization tools, scientists from all disciplines are gaining insights into physical systems in ways not possible with traditional approaches alone. Modeling and simulation has a long history with researchers and scientists exploring nuclear energy technologies. In fact, the existing fleet of currently operating reactors was licensed with computational tools that were produced or initiated in the 1970s. Researchers and scientists in

276

NUCLEAR REGULATORY COMMISSION  

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

December 21, 1999 (Volume 64, Number 244)] December 21, 1999 (Volume 64, Number 244)] [Proposed Rules] [Page 71331-71333] From the Federal Register Online via GPO Access [wais.access.gpo.gov] [DOCID:fr21de99-21] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION 10 CFR Parts 71 and 73 RIN 3150-AG41 Advance Notification to Native American Tribes of Transportation of Certain Types of Nuclear Waste AGENCY: Nuclear Regulatory Commission. ACTION: Advance notice of proposed rulemaking. ----------------------------------------------------------------------- SUMMARY: The Nuclear Regulatory Commission (NRC) is considering an amendment to its regulations that would require NRC licensees to notify

277

The DOE Advanced Gas Reactor Fuel Development and Qualification Program  

Science Conference Proceedings (OSTI)

The high outlet temperatures and high thermal-energy conversion efficiency of modular High Temperature Gas-cooled Reactors (HTGRs) enable an efficient and cost effective integration of the reactor system with non-electricity generation applications, such as process heat and/or hydrogen production, for the many petrochemical and other industrial processes that require temperatures between 300°C and 900°C. The Department of Energy (DOE) has selected the HTGR concept for the Next Generation Nuclear Plant (NGNP) Project as a transformative application of nuclear energy that will demonstrate emissions-free nuclear-assisted electricity, process heat, and hydrogen production, thereby reducing greenhouse-gas emissions and enhancing energy security. The objective of the DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification program is to qualify tristructural isotropic (TRISO)-coated particle fuel for use in HTGRs. The Advanced Gas Reactor Fuel Development and Qualification Program consists of five elements: fuel manufacture, fuel and materials irradiations, post-irradiation examination (PIE) and safety testing, fuel performance modeling, and fission-product transport and source term evaluation. An underlying theme for the fuel development work is the need to develop a more complete, fundamental understanding of the relationship between the fuel fabrication process and key fuel properties, the irradiation and accident safety performance of the fuel, and the release and transport of fission products in the NGNP primary coolant system. An overview of the program and recent progress is presented.

David Petti

2010-09-01T23:59:59.000Z

278

Advanced Simulation and Computing  

National Nuclear Security Administration (NNSA)

NA-ASC-117R-09-Vol.1-Rev.0 NA-ASC-117R-09-Vol.1-Rev.0 Advanced Simulation and Computing PROGRAM PLAN FY09 October 2008 ASC Focal Point Robert Meisner, Director DOE/NNSA NA-121.2 202-586-0908 Program Plan Focal Point for NA-121.2 Njema Frazier DOE/NNSA NA-121.2 202-586-5789 A Publication of the Office of Advanced Simulation & Computing, NNSA Defense Programs i Contents Executive Summary ----------------------------------------------------------------------------------------------- 1 I. Introduction -------------------------------------------------------------------------------------------------------- 2 Realizing the Vision ------------------------------------------------------------------------------------------------- 2 The Future of the Nuclear Weapons Complex ---------------------------------------------------------------- 2

279

Advanced characterization of physical properties of coals with different coal structures by nuclear magnetic resonance and X-ray computed tomography  

Science Conference Proceedings (OSTI)

In order to understand the correlation between coal structure and physical property of coal, samples with different coal structures were collected from the Late Permian period coal seams in the Laochang area, Yunnan Province, China. A set of experiments ... Keywords: Adsorption capacities, Coal structure, Nuclear magnetic resonance (NMR), Seepage capacities, X-ray computed tomography (X-CT)

Song Li; Dazhen Tang; Hao Xu; Zi Yang

2012-11-01T23:59:59.000Z

280

Nuclear | Department of Energy  

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

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

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Nano-particles for Spent Nuclear Fuel Separation  

Science Conference Proceedings (OSTI)

Symposium, Materials and Fuels for the Current and Advanced Nuclear Reactors III ... Development and Testing Advanced Ferritic Steels for Fast Reactor ...

282

Advance Mailer  

Science Conference Proceedings (OSTI)

Oct 9, 2002 ... Opportunities and Issues in Homeland Security........... 5 ..... CORROSION IN REACTORS AND NUCLEAR POWER SYSTEMS. Sponsored by: ...

283

Nuclear Resonance Fluorescence to Measure Plutonium Mass in Spent Nuclear Fuel  

E-Print Network (OSTI)

09-01188, ANS Advances in Nuclear Fuel Management IV, HiltonParameter Library Spent Nuclear Fuel Transmission detector (Pu) mass in spent nuclear fuel (SNF) assemblies and to

Ludewigt, Bernhard A

2011-01-01T23:59:59.000Z

284

Perfect NOT transformation and conjugate transformation  

E-Print Network (OSTI)

The perfect NOT transformation, probabilistic perfect NOT transformation and conjugate transformation are studied. Perfect NOT transformation criteria on a quantum state set $S$ of a qubit are obtained. Two necessary and sufficient conditions for realizing a perfect NOT transformation on $S$ are derived. When these conditions are not satisfied we discuss a probabilistic perfect NOT transformation (gate). We construct a probabilistic perfect NOT machine (gate) by a general unitary-reduction operation. With a postselection of the measurement outcomes, the probabilistic NOT gate yields perfectly complements of the input states. We prove that one can realize probabilistically the NOT gate of the input states secretly chosen from a certain set $S=\\{|\\Psi_1>, |\\Psi_2>,..., |\\Psi_n>\\}$ if and only if $|\\Psi_1>, |\\Psi_2>,...,$ and $|\\Psi_n>$ are linearly independent. We also generalize the probabilistic NOT transformation to the conjugate transformation in the multi-level quantum system. The lower bound of the best p...

Yan, Fengli; Yan, Zhichao

2012-01-01T23:59:59.000Z

285

Inelastic X-ray and Nuclear Resonant Scattering  

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

Beamlines Divisions Argonne Home > Advanced Photon Source > Inelastic X-ray and Nuclear Resonant Scattering The Inelastic X-ray and Nuclear Resonant Scattering group...

286

Atomistic Simulations of Radiation Effects in Ceramics for Nuclear ...  

Science Conference Proceedings (OSTI)

This work is supported by the DOE Nuclear Energy Advanced Modeling and ... Simulations of Radiation Effects in Ceramics for Nuclear Waste Disposal.

287

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

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... A resource document for the Workshop on Basic Research Needs for Advanced Nuclear Energy Systems. Includes an overview of nuclear ...

288

MIT Nuclear Space Research Andrew C. Kadak  

E-Print Network (OSTI)

SELENE MIT Nuclear Space Research Andrew C. Kadak Professor of the Practice Nuclear Science with Nuclear Energy ­ Selene - Sodium-Cooled Epithermal Long-term Exploration Nuclear Engine (MS thesis) ­ The Martian Surface Reactor: An Advanced Nuclear Power Station for Manned Extraterrestrial Exploration

289

Motivations and challenges for M-business transformation: a multiple-case study  

Science Conference Proceedings (OSTI)

With the advance of wireless technology in recent years, issues of mobile (m-) business transformation become more important for researchers and practitioners. Subsequent to e-business transformation, mobile technology creates another opportunity of ... Keywords: business transformation, m-business, m-commerce, m-transformation, mobile business

Heng-Sheng Tsai; Raj Gururajan

2007-08-01T23:59:59.000Z

290

Advanced Gasification  

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

Advanced Gasification Carbon feedstock gasification is a promising pathway for high-efficiency, low-pollutant power generation and chemical production. The inability, however, to...

291

Advanced Ceramics  

Science Conference Proceedings (OSTI)

Table 3   Raw materials for advanced structural and magnetic (ferrite) ceramics...conductivity Wear resistance Oxygen sensors, fuel cells (potential), high-temperature

292

Advanced Manufacturing  

Science Conference Proceedings (OSTI)

... new metrologically-based methods for industry as well ... for Advanced Catalyst Development and Durability ... Electron-Beam Irradiation of Solar Cells. ...

2013-07-29T23:59:59.000Z

293

Transformations | Open Energy Information  

Open Energy Info (EERE)

Transformations Transformations Jump to: navigation, search Name Transformations Place Townsend, MA Website http://transformations-inc.com References Transformations[1] Information About Partnership with NREL Partnership with NREL Yes Partnership Type Test & Evaluation Partner Partnering Center within NREL Electricity Resources & Building Systems Integration LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! Transformations is a company located in Townsend, MA. References ↑ "Transformations" Retrieved from "http://en.openei.org/w/index.php?title=Transformations&oldid=381743" Categories: Clean Energy Organizations Companies Organizations What links here Related changes Special pages Printable version Permanent link Browse properties

294

Spacetime transformation acoustics  

E-Print Network (OSTI)

A recently proposed analogue transformation method has allowed the extension of transformation acoustics to general spacetime transformations. We analyze here in detail the differences between this new analogue transformation acoustics (ATA) method and the standard one (STA). We show explicitly that STA is not suitable for transformations that mix space and time. ATA takes as starting point the acoustic equation for the velocity potential, instead of that for the pressure as in STA. This velocity-potential equation by itself already allows for some transformations mixing space and time, but not all of them. We explicitly obtain the entire set of transformations that do not leave its form invariant. It is in these cases that ATA shows its true potential, allowing for building a transformation acoustics method that enables the full range of spacetime transformations. We provide an example of an important transformation which cannot be achieved with STA. Using this transformation, we design and simulate an acous...

García-Meca, C; Barceló, C; Jannes, G; Sánchez-Dehesa, J; Martínez, A

2013-01-01T23:59:59.000Z

295

Advanced Mailer  

Science Conference Proceedings (OSTI)

Feb 14, 2005 ... (biomass, hydro, wind, solar, geothermal) and non-re- newable (nuclear, coal, natural gas) energy sources can be employed to produce ...

296

Multiscale Modeling of Defect Mechanics in Nuclear Materials  

Science Conference Proceedings (OSTI)

Abstract Scope, The key to developing advanced materials for nuclear applications is ... Physics-Based Homogenization of Random Continuum Microstructures.

297

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

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... It has been written primarily for advanced undergraduate and beginning graduate students in Nuclear Engineering, Radiation Physics, ...

298

Tag: transformation | Y-12 National Security Complex  

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

transformation transformation Tag: transformation Displaying 1 - 10 of 11... Category: News Y-12 Knows Uranium Y-12 produces many forms of uranium. More... Category: News Energy Secretary Moniz visits Y-12 Secretary of Energy Ernest Moniz (at right) tours the Highly Enriched Uranium Materials Facility during his visit Monday to Y-12. More... Category: About Site improvements of $490 million result from FIRP The Facilities and Infrastructure Recapitalization Program has been a key component of modernization and transformation efforts at Y-12. More... Category: Nuclear Deterrence Processing Y-12's core manufacturing and processing operations are housed in decades-old buildings near or past the end of their expected life spans. More... Category: About Uranium Processing Facility An integral part of Y-12's transformation efforts and a key component

299

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network (OSTI)

for magnetic fusion reactors and IFMIF. Journal of NuclearFusion reactors blanket nucleonics. In Progress in NuclearFusion-Fission hybrid reactors. In Advances in Nuclear

Kramer, Kevin James

2010-01-01T23:59:59.000Z

300

Learning Transformations From Video  

E-Print Network (OSTI)

on Natural Video . . . . . . . . . . . . . . . . .3 Learning Continuous Transformation from VideoProposed Video Coder

Wang, Ching Ming

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Generative model transformer  

Science Conference Proceedings (OSTI)

The Generative Model Transformer (GMT) project is an Open Source initiative to build a Model Driven Architecure™ tool that allows fully customisable Platform Independent Models, Platform Description Models, Texture Mappings, and Refinement Transformations. ... Keywords: QVT, domain-specific languages, generative model transformer (GMT), model driven architecture (MDA), model transformation, open source

Jorn Bettin; Ghica van Emde Boas

2003-10-01T23:59:59.000Z

302

Advanced Reactor Technology Documents | Department of Energy  

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

Nuclear Reactor Technologies » Advanced Reactor Nuclear Reactor Technologies » Advanced Reactor Technologies » Advanced Reactor Technology Documents Advanced Reactor Technology Documents January 30, 2013 Advanced Reactor Concepts Technical Review Panel Report This report documents the establishment of a technical review process and the findings of the Advanced Reactor Concepts (ARC) Technical Review Panel (TRP).1 The intent of the process is to identify R&D needs for viable advanced reactor concepts in order to inform DOE-NE R&D investment decisions. A goal of the process is to facilitate greater engagement between DOE and industry. The process involved establishing evaluation criteria, conducting a pilot review, soliciting concept inputs from industry entities, reviewing the concepts by TRP members and compiling the

303

A green transformer  

Science Conference Proceedings (OSTI)

The use of a new transformer and transformer fluid by a rural electric cooperative is described in the article. Edisol TR Transformers, which require about half as much fluid, are being used to replace existing transformers from 10- to 50 kVA. The dielectric fluid used in the transformers biodegrades more rapidly and completely, and is non-bioaccumulating in aquatic species. Standardized tests show that five to six weeks is required for biodegradation. The thermal design increases the efficiency of heat removal and reduces thermal gradients in the winding; the transformer is 20% smaller and 25% lighter than conventional transformers.

Wagner, A.

1997-03-01T23:59:59.000Z

304

Advanced Materials  

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

Advanced Materials Advanced Materials Advanced Materials Express Licensing Active Terahertz Metamaterial Devices Express Licensing Anion-Conducting Polymer, Composition, And Membrane Express Licensing Analysis Of Macromolecule, Liggands And Macromolecule-Lingand Complexes Express Licensing Carbon Microtubes Express Licensing Chemical Synthesis Of Chiral Conducting Polymers Express Licensing Forming Adherent Coatings Using Plasma Processing Express Licensing Hydrogen Scavengers Express Licensing Laser Welding Of Fused Quartz Express Licensing Multiple Feed Powder Splitter Negotiable Licensing Boron-10 Neutron Detectors for Helium-3 Replacement Negotiable Licensing Insensitive Extrudable Explosive Negotiable Licensing Durable Fuel Cell Membrane Electrode Assembly (MEA) Express Licensing Method of Synthesis of Proton Conducting Materials

305

Nuclear Sciences | More Science | ORNL  

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

Chemistry Chemistry Advanced Materials Nuclear Forensics Climate & Environment Biology and Soft Matter Chemical and Engineering Materials Quantum Condensed Matter Computational Chemistry Nuclear Sciences More Science Home | Science & Discovery | More Science | Chemistry | Nuclear Sciences SHARE Nuclear Sciences In World War II's Manhattan Project, ORNL helped usher in the nuclear age. Today, laboratory scientists are leaders in using nuclear technologies and systems to improve human health; explore safer, more environmentally friendly power; and better understand the structure of matter. Thanks to its nuclear heritage, ORNL is a world leader in the production of isotopes for medical purposes and research. The lab's High Flux Isotope Reactor (HFIR) and Radiochemical Engineering Development Center (REDC)

306

Friction Stir Welding and Processing of Advanced Materials for Coal ...  

Science Conference Proceedings (OSTI)

Presentation Title, Friction Stir Welding and Processing of Advanced Materials for Coal and Nuclear Power Applications. Author(s), Glenn J. Grant, Scott Weil, ...

307

Advanced Vehicle Testing Activity - Plug-in Electric Vehicle...  

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

and reduce the nation's dependence on foreign oil Multi-program DOE laboratory * N l Nuclear E Energy * Fossil, Biomass, Wind, Geothermal and Hydropower Energy * Advanced...

308

Melt Processed Crystalline Ceramic Wasteforms for an Advanced ...  

Science Conference Proceedings (OSTI)

Presentation Title, Melt Processed Crystalline Ceramic Wasteforms for an Advanced Nuclear Fuel Cycle. Author(s), Kyle S Brinkman, Jake Amoroso, Kevin Fox, ...

309

Superalloys: Their Use and Requirements in Advanced Energy ...  

Science Conference Proceedings (OSTI)

this paper discusses advanced methods of conversion of fossil and nuclear re- sources ... the fuels and fluids of prime importance which superalloys will face. It's

310

The Advanced Test Reactor National Scientific User Facility  

Science Conference Proceedings (OSTI)

Symposium, Materials Solutions for the Nuclear Renaissance ... U.S. Department of Energy designated the Advanced Test Reactor (ATR) as a National Scientific ...

311

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

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

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

312

Advanced Manufacturing Office: Solicitations  

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

Solicitations on Twitter Bookmark Advanced Manufacturing Office: Solicitations on Google Bookmark Advanced Manufacturing Office: Solicitations on Delicious Rank Advanced...

313

Advanced Manufacturing Office: Webcasts  

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

Office: Webcasts on Twitter Bookmark Advanced Manufacturing Office: Webcasts on Google Bookmark Advanced Manufacturing Office: Webcasts on Delicious Rank Advanced...

314

Advanced Manufacturing Office: Subscribe  

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

Office: Subscribe on Twitter Bookmark Advanced Manufacturing Office: Subscribe on Google Bookmark Advanced Manufacturing Office: Subscribe on Delicious Rank Advanced...

315

Advanced Manufacturing Office: Workshops  

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

Office: Workshops on Twitter Bookmark Advanced Manufacturing Office: Workshops on Google Bookmark Advanced Manufacturing Office: Workshops on Delicious Rank Advanced...

316

Reactor Physics and Criticality Benchmark Evaluations for Advanced Nuclear Fuel, Progress Report for Work through August 31, 2002, First Annual/4th Quarterly Report  

SciTech Connect

OAK B204 The objective of this Nuclear Energy Research Initiative (NERI) project is to design, perform, and analyze critical benchmark experiments for validating reactor physics methods and models for fuel enrichments greater than 5-wt% 235U. These experiments will also provide additional information for application to the criticality-safety bases for commercial fuel facilities handling greater than 5-wt% 235U fuel. These experiments are designed as reactor physics benchmarks, to include measurements of critical boron concentration, burnable absorber worth, relative pin powers, and relative average powers.The first year focused primarily on designing the experiments using available fuel, preparing the necessary plans, procedures and authorization basis for performing the experiments, and preparing for the transportation, receipt and storage of the Pathfinder fuel currently stored at Pennsylvania State University.Framatome ANP, Inc. leads the project with the collaboration of Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and the University of Florida (UF). The project is organized into 5 tasks:Task 1: Framatome ANP, Inc., ORNL, and SNL will design the specific experiments, establish the safety authorization, and obtain approvals to perform these experiments at the SNL facility. ORNL will apply their sensitivity/uncertainty methodology to verify the need for particular experiments and the parameters that these experiments need to explore.Task 2: Framatome ANP, Inc., ORNL, and UF will analyze the proposed experiments using a variety of reactor-physics methods employed in the nuclear industry. These analyses will support the operation of the experiments by predicting the expected experimental values for the criticality and physics parameters.Task 3: This task encompasses the experiments to be performed. The Pathfinder fuel will be transported from Penn State to SNL for use in the experiments. The experiments will be performed and the hardware will be decontaminated and decommissioned.Task 4: Framatome ANP, Inc., ORNL, and UF will analyze the experiments and compare calculated values of physics parameters for the experiments with the measured values. Potential sources of differences will be sought between calculated physics parameter values and the experimental values. The results of all analyses will be documented.Task 5: UF and Framatome ANP, Inc. will evaluate typical fuel-processing operations to establish the limits and restrictions required for fabricating higher-enriched fuel.Work in Year 1 included completion of Task 1 and the licensing of a transportation cask under Task 5. This work entailed a number of milestones accomplished in Year 1. These include:?h Issuance of the Preliminary Design Report in February 2002?h Completion of the Sensitivity and Uncertainty Analysis in May 2002?h Completion of the Final Design Report in June 2002?h Submittal of the NRC license application for the transportation package in May 2002.This first year was a year of successes as all deliverables were met on time and the project completed the year within the budget.In Year 2, the project moves into a manufacturing and application phase. Year 2 includes successful completion of the licensing process for the transportation package and transportation of the fuel from Pennsylvania State University to Sandia National Laboratories in Albuquerque, New Mexico. Also, Year 2 includes the fabrication of the fuel into smaller aluminum cladding. Once the fuel is ready and the necessary approvals are in place, the experiments will end; begin following the design presented in the Final Design Report. Although Year 2 will be primarily ''hand's on'' fabrication and handling work, the analytical work will continue on the experiments and the generic fuel processing facility.

Anderson, William J.; Ake, Timothy N.; Punatar, Mahendra; Pitts, Michelle L.; Harms, Gary A.; Rearden, Bradley T.; Parks, Cecil V.; Tulenko, James S.; Dugan, Edward; Smith, Robert M.

2002-09-23T23:59:59.000Z

317

On discrete cosine transform  

E-Print Network (OSTI)

The discrete cosine transform (DCT), introduced by Ahmed, Natarajan and Rao, has been used in many applications of digital signal processing, data compression and information hiding. There are four types of the discrete cosine transform. In simulating the discrete cosine transform, we propose a generalized discrete cosine transform with three parameters, and prove its orthogonality for some new cases. A new type of discrete cosine transform is proposed and its orthogonality is proved. Finally, we propose a generalized discrete W transform with three parameters, and prove its orthogonality for some new cases.

Zhou, Jianqin

2011-01-01T23:59:59.000Z

318

Advanced Fuels Campaign 2012 Accomplishments  

Science Conference Proceedings (OSTI)

The Advanced Fuels Campaign (AFC) under the Fuel Cycle Research and Development (FCRD) program is responsible for developing fuels technologies to support the various fuel cycle options defined in the DOE Nuclear Energy Research and Development Roadmap, Report to Congress, April 2010. The fiscal year 2012 (FY 2012) accomplishments are highlighted below. Kemal Pasamehmetoglu is the National Technical Director for AFC.

Not Listed

2012-11-01T23:59:59.000Z

319

Office of Nuclear Energy | Department of Energy  

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

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

320

Nuclear Deterrence | Y-12 National Security Complex  

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

the nation's Uranium Center of Excellence. We employ only the most advanced and failsafe technologies to protect the stockpile. Nuclear Deterrence Stockpile Weapons production...

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Argonne Chemical Sciences & Engineering - Nuclear & Environmental...  

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

Energy's Advanced Fuel Cycle Research and Development Program. More Closing the nuclear fuel cycle Recycling long-lived fissile materials as fuel Developing chemical process models...

322

WEB RESOURCE: Nuclear Physics and Related Computational ...  

Science Conference Proceedings (OSTI)

Feb 6, 2007 ... This site provides presentations from the Nuclear Physics and Related Computational Science R&D for Advanced Fuel Cycles Workshop:

323

Nuclear Systems Modeling, Simulation & Validation | ORNL  

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

from single processors to the world's largest supercomputers. The DOE Nuclear Energy Hub (CASL, the Consortium for Advanced Simulation of Light Water Reactors) is a prominent...

324

Nuclear Systems Modeling & Simulation | More Science | ORNL  

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

from single processors to the world's largest supercomputers. The DOE Nuclear Energy Hub (CASL, the Consortium for Advanced Simulation of Light Water Reactors) is a prominent...

325

Advanced Simulation Capability for  

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

Simulation Capability for Simulation Capability for Environmental Management (ASCEM) ASCEM is being developed to provide a tool and approach to facilitate robust and standardized development of perfor- mance and risk assessments for cleanup and closure activi- ties throughout the EM complex. The ASCEM team is composed of scientists from eight National Laboratories. This team is leveraging Department of Energy (DOE) investments in basic science and applied research including high performance computing codes developed through the Advanced Scientific Computing Research and Advanced Simulation & Computing pro- grams as well as collaborating with the Offices of Science, Fossil Energy, and Nuclear Energy. Challenge Current groundwater and soil remediation challenges that will continue to be addressed in the next decade include

326

Advanced Safeguards Approaches for New Reprocessing Facilities  

Science Conference Proceedings (OSTI)

U.S. efforts to promote the international expansion of nuclear energy through the Global Nuclear Energy Partnership (GNEP) will result in a dramatic expansion of nuclear fuel cycle facilities in the United States. New demonstration facilities, such as the Advanced Fuel Cycle Facility (AFCF), the Advanced Burner Reactor (ABR), and the Consolidated Fuel Treatment Center (CFTC) will use advanced nuclear and chemical process technologies that must incorporate increased proliferation resistance to enhance nuclear safeguards. The ASA-100 Project, “Advanced Safeguards Approaches for New Nuclear Fuel Cycle Facilities,” commissioned by the NA-243 Office of NNSA, has been tasked with reviewing and developing advanced safeguards approaches for these demonstration facilities. Because one goal of GNEP is developing and sharing proliferation-resistant nuclear technology and services with partner nations, the safeguards approaches considered are consistent with international safeguards as currently implemented by the International Atomic Energy Agency (IAEA). This first report reviews possible safeguards approaches for the new fuel reprocessing processes to be deployed at the AFCF and CFTC facilities. Similar analyses addressing the ABR and transuranic (TRU) fuel fabrication lines at AFCF and CFTC will be presented in subsequent reports.

Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Richard; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

2007-06-24T23:59:59.000Z

327

Metrics for enterprise transformation  

E-Print Network (OSTI)

The objective of this thesis is to depict the role of metrics in the evolving journey of enterprise transformation. To this end, three propositions are explored: (i) metrics and measurement systems drive transformation, ...

Blackburn, Craig D. (Craig David), S. M. Massachusetts Institute of Technology

2009-01-01T23:59:59.000Z

328

Advanced Systems  

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

Advanced Systems: Advanced Systems: high Performance fenestration systems Research areas: Research activities to improve the performance of windows and other fenestration products must address window systems issues as well as Glazing Materials research. LBNL activities in the area of Advanced Systems include research at both the product level and the building envelope and building systems levels. Highly insulating windows - using non structural center layers Lower cost solutions to more insulating three layer glazing systems, with the potential to turn windows in U.S. heating dominated residential applications into net-energy gainers. Highly Insulating Window Frames In collaboration with the Norwegian University of Science and Technology, we are researching the potentials for highly insulating window frames. Our initial work examines European frames with reported U-factors under 0.15 Btu/hr-ft2-F. Future research aims to analyze these designs, verify these performance levels and ensure that procedures used to calculate frame performance are accurate.

329

Uncertainty Analyses of Advanced Fuel Cycles  

SciTech Connect

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

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

2008-12-12T23:59:59.000Z

330

Nuclear Energy Enabling Technologies | Department of Energy  

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

Enabling Technologies Enabling Technologies Nuclear Energy Enabling Technologies Nuclear Energy Enabling Technologies The Nuclear Energy Enabling Technologies (NEET) Program will develop crosscutting technologies that directly support and complement the Department of Energy, Office of Nuclear Energy's (DOE-NE) advanced reactor and fuel cycle concepts, focusing on innovative research that offers the promise of dramatically improved performance. NEET will coordinate research efforts on common issues and challenges that confront the DOE-NE R&D programs (Light Water Reactor Sustainability [LWRS], Next Generation Nuclear Plant [NGNP], Advanced Reactor Technologies [ART], and Small Modular Reactors [SMR]) to advance technology development and deployment. The activities undertaken in the NEET program will

331

Typechecking for XML transformers  

Science Conference Proceedings (OSTI)

We study the typechecking problem for XML transformers: given an XML transformation program and a DTD for the input XML documents, check whether every result of the program conforms to a specified output DTD. We model XML transformers using a novel device ...

Tova Milo; Dan Suciu; Victor Vianu

2000-05-01T23:59:59.000Z

332

A dc transformer  

Science Conference Proceedings (OSTI)

Although conventional transformers are ac, a device that may be termed a dc transformer has been constructed by using superconductors. To provide an understanding of how such a transformer would operate, some of the properties of type I and type II superconductors ...

I. Giaever

1966-09-01T23:59:59.000Z

333

Advanced Modeling and Simulation Documents | Department of Energy  

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

Advanced Modeling & Simulation » Advanced Modeling Advanced Modeling & Simulation » Advanced Modeling and Simulation Documents Advanced Modeling and Simulation Documents October 30, 2013 NEAMS Quarterly Report April-June 2013 The Nuclear Energy Advanced Modeling and Simulation (NEAMS) quarterly report includes highlights, fuel and reactor product line accomplishments, recent and upcoming milestones, news on BISON fuel benchmarks, the latest MeshKit release features, and information on numerical simulations of pebble-bed reactor cores performed by the thermal hydraulics team. September 9, 2013 Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan Requirements The purpose of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan is to define what the NEAMS

334

Nuclear Forensics | More Science | ORNL  

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

Materials Science and Engineering Materials Science and Engineering Advanced Materials Clean Energy Materials Theory and Simulation Neutron Science Nuclear Forensics Nuclear Science Supercomputing Theory, Modeling and Simulation More Science Home | Science & Discovery | More Science | Materials Science and Engineering | Nuclear Forensics SHARE Nuclear Forensics image Tools, techniques, and expertise in nuclear fuel cycle research gained over seven decades help ORNL scientists control and track nuclear bomb-grade materials to be sure they don't fall into the wrong hands. Among the leading-edge technologies used by researchers are high-resolution techniques that allow analysis of radiation detector data in stunning detail. Researchers are also developing aerosol sampling systems to collect

335

SC e-journals, Nuclear  

Office of Scientific and Technical Information (OSTI)

Nuclear Nuclear Annals of Nuclear Energy Annual Review of Nuclear and Particle Science Atomic Data & Nuclear Data Tables Atomic Energy BMC Medical Physics - OAJ Cancer Prevention Journals Portal Cancer Prevention Research Cancer Reviews Online Dose Response Energy & Environmental Science Energy Policy EURASIP Journal on Advances in Signal Processing - OAJ EURASIP Journal on Bioinformatics and Systems Biology - OAJ EURASIP Journal on Embedded Systems (2006 forward) - OAJ Fuel Fusion Engineering and Design Fusion Nuclear Society Health Physics IETE Journal of Research - OAJ International Journal of Cancer International Journal of Low Radiation International Journal of Microwave Science and Technology - OAJ International Journal of Radiation Biology Journal of Cancer Eqidemiology - OAJ

336

A Technical Review of Non-Destructive Assay Research for the Characterization of Spent Nuclear Fuel Assemblies Being Conducted Under the US DOE NGSI - 11544  

E-Print Network (OSTI)

the Characterization of Spent Nuclear Fuel Assemblies BeingSociety’s Advances in Nuclear Fuel Management IV, HiltonPlutonium Mass in Spent Nuclear Fuel,” 2010 ANS Annual

Croft, S.

2012-01-01T23:59:59.000Z

337

Transforming a Transformative School | Department of Energy  

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

You are here You are here Home » Transforming a Transformative School Transforming a Transformative School October 11, 2012 - 10:14am Addthis During a yearlong renovation, Harding Charter Preparatory school upgraded lighting fixtures, installed a new heating and cooling system, and replaced the entry doors. The new doors allow daylight into the school and restore the historical building envelope. | Photo courtesy of John Winkel, Energy Department. During a yearlong renovation, Harding Charter Preparatory school upgraded lighting fixtures, installed a new heating and cooling system, and replaced the entry doors. The new doors allow daylight into the school and restore the historical building envelope. | Photo courtesy of John Winkel, Energy Department. Julie McAlpin

338

Advanced Sensors and Instrumentation | Department of Energy  

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

Sensors and Instrumentation Sensors and Instrumentation Advanced Sensors and Instrumentation The ASI subprogram plans to develop the scientific basis for sensors and supporting infrastructure technology that will address crosscutting technology gaps relating to measurements at existing and advanced nuclear power plants as well as within their fuel cycles. The focus of the program is on the following technical challenges and objectives: Identify needed physical measurement accuracy of nuclear system process parameters and minimize uncertainty. Identify and conduct research into monitoring and control technologies, including human factors, to achieve control of new nuclear energy processes, and new methodologies for monitoring to achieve high reliability and availability. Integrate control of multiple processes, potential reductions in

339

Advanced converter reactors  

SciTech Connect

Advanced converter reactors (ACRs) of primary US interest are those which can be commercialized within about 20 years, and are: Advanced Light-Water Reactors, Spectral-Shift-Control Reactors, Heavy-Water Reactors (CANDU type), and High-Temperature Gas-Cooled Reactors. These reactors can operate on uranium, thorium, or uranium-thorium fuel cycles, but have the greatest fuel utilization on thorium type cycles. The water reactors tend to operate more economically on uranium cycles, while the HTGR is more economical on thorium cycles. Thus, the HTGR had the greatest practical potential for improving fuel utilization. If the US has 3.4 to 4 million tons U/sub 3/O/sub 8/ at reasonable costs, ACRs can make important contributions to maintaining a high nuclear power level for many decades; further, they work well with fast breeder reactors in the long term under symbiotic fueling conditions. Primary nuclear data needs of ACRs are integral measurements of reactivity coefficients and resonance absorption integrals.

Kasten, P.R.

1979-01-01T23:59:59.000Z

340

Advanced Model and Methodology Development [Heat Transfer and Fluid  

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

Advanced Model and Advanced Model and Methodology Development Capabilities Engineering Computation and Design Engineering and Structural Mechanics Systems/Component Design, Engineering and Drafting Heat Transfer and Fluid Mechanics Overview Thermal Hydraulic Optimization of Nuclear Systems Underhood Thermal Management Combustion Simulations Advanced Model and Methodology Development Multi-physics Reactor Performance and Safety Simulations Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Heat Transfer and Fluid Mechanics Bookmark and Share Advanced Model and Methodology Development Electrorefiner Model for Treatment of Spent Nuclear Fuel Electrorefiner Model for Treatment of Spent Nuclear Fuel. Click on image to

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


341

Advanced Combustion  

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

Systems Systems Advanced Combustion Background Conventional coal-fired power plants utilize steam turbines to generate electricity, which operate at efficiencies of 35-37 percent. Operation at higher temperatures and pressures can lead to higher efficiencies, resulting in reduced fuel consumption and lower greenhouse gas emissions. Higher efficiency also reduces CO2 production for the same amount of energy produced, thereby facilitating a reduction in greenhouse gas emissions. When combined, oxy-combustion comes with an efficiency hit, so it will actually increase the amount of CO2 to be captured. But without so much N2 in the flue gas, it will be easier and perhaps more efficient to capture, utilize and sequester. NETL's Advanced Combustion Project and members of the NETL-Regional University

342

Advanced Search  

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

Publications Publications Advanced Search Most publications by Environmental Energy Technologies Division authors are searchable from this page, including peer-reviewed publications, book chapters, conference proceedings and LBNL reports. Filter Advanced Search Publications list This publications database is an ongoing project, and not all Division publications are represented here yet. For additional help see the bottom of this page. Documents Found: 4418 Title Keyword LBNL Number Author - Any - Abadie, Marc O Abbey, Chad Abdolrazaghi, Mohamad Aberg, Annika Abhyankar, Nikit Abraham, Marvin M Abshire, James B Abushakra, Bass Acevedo-Ruiz, Manuel Aceves, Salvador Ache, Hans J Ackerly, David D Ackerman, Andrew S Adamkiewicz, Gary Adams, J W Adams, Carl Adamson, Bo Addy, Nathan Addy, Susan E Aden, Nathaniel T Adesola, Bunmi Adhikari,

343

Advanced Radiation-Resistant Ceramic Composites  

SciTech Connect

Ceramic matrix composites (CMC), particularly silicon carbide (SiC) fiber-reinforced SiC-matrix (SiC/SiC) composites, have been studied for advanced nuclear energy applications for more than a decade. The perceived potentials for advanced SiC/SiC composites include the ability to operate at temperature regimes much higher than heat-resistant alloys, the inherent low induced-activation nuclear properties, and the tolerance against neutron irradiation at high temperatures. This paper reviews the recent research and development of the advanced radiation-resistant SiC/SiC composites for nuclear applications. Additionally, remaining general and specific technical issues for SiC/SiC composites for nuclear applications are discussed.

Katoh, Yutai [ORNL; Snead, Lance Lewis [ORNL; Nozawa, Takashi [ORNL; Windes, Will [Idaho National Laboratory (INL); Morley, N.B. [University of California, Los Angeles

2006-01-01T23:59:59.000Z

344

Advanced Combustion  

Science Conference Proceedings (OSTI)

The activity reported in this presentation is to provide the mechanical and physical property information needed to allow rational design, development and/or choice of alloys, manufacturing approaches, and environmental exposure and component life models to enable oxy-fuel combustion boilers to operate at Ultra-Supercritical (up to 650{degrees}C & between 22-30 MPa) and/or Advanced Ultra-Supercritical conditions (760{degrees}C & 35 MPa).

Holcomb, Gordon R. [NETL

2013-03-11T23:59:59.000Z

345

Nuclear data for nuclear transmutation  

Science Conference Proceedings (OSTI)

Current status on nuclear data for the study of nuclear transmutation of radioactive wastes is reviewed

Hideo Harada

2009-01-01T23:59:59.000Z

346

The interlaced chirp Z transform  

Science Conference Proceedings (OSTI)

In this paper we introduce the interlaced chirp Z transform (Interlaced CZT), It is based on the computation of several carefully staggered CZT that are progressively interlaced to result in a spectrum that has denser frequency samples where needed. ... Keywords: chirp Z transform, discrete fourier transform, interlaced chirp Z transform, warped discrete fourier transform, zoom chirp Z transform

Indranil Sarkar; Adly T. Fam

2006-09-01T23:59:59.000Z

347

Advanced (AI-Based) Nonlinear Controllers for Industrial Processes -  

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

Advanced (AI-Based) Nonlinear Controllers for Industrial Processes Advanced (AI-Based) Nonlinear Controllers for Industrial Processes Capabilities Nuclear Systems Technologies Nuclear Criticality Safety Research Reactor Analysis Decontamination and Decommissioning Systems/Process Monitoring, Diagnostics and Control Overview Process Monitoring & Signal Validation Diagnostic & Advisory Systems Advanced (AI-based) Nonlinear Controllers for Industrial Processes Artificial intelligence Other Capabilities Work with Argonne Contact us For Employees Site Map Help Systems/Process Monitoring, Diagnostics and Control Advanced (AI-Based) Nonlinear Controllers for Industrial Processes Bookmark and Share Advanced (AI-Based) Nonlinear Controllers for Industrial Processes The overall objective of this research is to explore and demonstrate the

348

Transforming Commercial Building Operations  

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

Transforming Commercial Building Operations Transforming Commercial Building Operations Transforming Commercial Building Operations Ron Underhill Pacific Northwest National Laboratory ronald.underhill@pnnl.gov (509)375-9765 April 4, 2013 2 | Building Technologies Office eere.energy.gov * Most buildings are not commissioned (Cx) before occupancy, including HVAC and lighting systems * Buildings often are poorly operated and maintained leading to significant energy waste of 5 to 20%, even when they have building automation systems (BASs)

349

Transforming Commercial Building Operations  

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

Transforming Commercial Building Operations Transforming Commercial Building Operations Transforming Commercial Building Operations Ron Underhill Pacific Northwest National Laboratory ronald.underhill@pnnl.gov (509)375-9765 April 4, 2013 2 | Building Technologies Office eere.energy.gov * Most buildings are not commissioned (Cx) before occupancy, including HVAC and lighting systems * Buildings often are poorly operated and maintained leading to significant energy waste of 5 to 20%, even when they have building automation systems (BASs)

350

Adaptive Discrete Cosine Transform  

Science Conference Proceedings (OSTI)

The theory and performance of the adaptive discrete cosine transform filter is examined. The discrete cosine transform filter is a realization of an FIR filter as the cascade of an all-zero FIR filter with a bank of IIR digital resonators. Each bank ... Keywords: FIR filter, IIR digital resonators, LMS algorithm, adaptive discrete cosine transform filter, adaptive filters, all-zero FIR filter, filter coefficient, frequency, magnitude, phase, transfer function, update method

S. J. Bukowinski; L. Gerhardt; M. Fargues; G. Coutu

1995-10-01T23:59:59.000Z

351

EPRI Transformer Guidebook Development  

Science Conference Proceedings (OSTI)

Utilities are losing many of their subject matter experts through retirement and downsizing. This is particularly true in the case of power transformers, so that there is now a critical need for a comprehensive transformer reference book geared toward utility engineers. In 2007, the Electric Power Research Institute EPRI published the technical update report Transformer Guidebook Design 1013799. That report described the results of the initial project to develop the Copper Book, a comprehensive reference...

2009-12-23T23:59:59.000Z

352

A New Integral Transform  

E-Print Network (OSTI)

Using Bauer's expansion and properties of spherical Bessel and Legender functions, we deduce a new transform and briefly indicate its use.

B. G. Sidharth

2004-12-04T23:59:59.000Z

353

Transforming the Freight Industry  

E-Print Network (OSTI)

Transforming the Freight Industry From Regulation to Icommon-carrier freight industry was Competition to backwardjourneys. When the freight industry was deregulated, it was

Regan, Amelia

2002-01-01T23:59:59.000Z

354

Transformer Ratio Enhancement Experiment  

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

TRANSFORMER RATIO ENHANCEMENT EXPERIMENT A. Kanareykin, Euclid Concepts LLC, Solon, OH 44139, USA W. Gai, J. G. Power. ANL, Argonne, IL, 60439, USA E. Nenasheva, Ceramics Ltd., St....

355

Market Transformation Programs  

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

Efficiency Improvement Opportunities in TVs Implications for Market Transformation Programs journal Energy Policy volume year month pages keywords appliance energy efficiency...

356

Advanced Energy Storage Publications  

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

Advanced Energy Storage Publications Reports: Advanced Technology Development Program For Lithium-Ion Batteries: Gen 2 Performance Evaluation Final Report Advanced Technology...

357

Advanced Manufacturing Office: News  

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

Manufacturing Office: News on Twitter Bookmark Advanced Manufacturing Office: News on Google Bookmark Advanced Manufacturing Office: News on Delicious Rank Advanced Manufacturing...

358

Fusion Nuclear Science Facility - Advanced Tokamak Option  

Science Conference Proceedings (OSTI)

Power Plant, Demo, and FNSF / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2)

C. P. C. Wong; V. S. Chan; A. M. Garofalo; J. A. Leuer; M. E. Sawan; J. P. Smith; R. D. Stambaugh

359

Advanced Cooling Options for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Alternative power plant cooling systems exist that offer significant opportunity for reducing the amount of water used in power plant cooling. These systems include direct dry cooling using air-cooled condensers, indirect dry cooling using air-cooled heat exchangers paired with water-cooled surface condensers, and a variety of hybrid systems incorporating both dry and wet cooling elements. The water savings afforded by the use of these systems, however, comes at a price in the form of more expensive ...

2013-11-27T23:59:59.000Z

360

Recent Advances in Nuclear Materials Poster Session  

Science Conference Proceedings (OSTI)

Mar 4, 2013 ... More details will be discussed with comparing the results with insitu He implanter experiments (ISHI) in HFIR and model calculations. F-11: On ...

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Mission Advancing  

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

NETL Accomplishments NETL Accomplishments - the lab 2 Mission Advancing energy options to fuel our economy, strengthen our security, and improve our environment. Renewed Prosperity Through Technological Innovation - Letter from the Director NETL: the ENERGY lab 4 6 3 Contents Technology Transfer Patents and Commercialization Sharing Our Expertise Noteworthy Publications 60 62 63 64 66 Environment, Economy, & Supply Carbon Capture and Storage Partnerships Work to Reduce Atmospheric CO 2 Demand-Side Efficiencies New NETL Facility Showcases Green Technologies Environment & Economy Materials Mercury Membranes NETL Education Program Produces Significant Achievement Monitoring Water Economy & Supply NETL's Natural Gas Prediction Tool Aids Hurricane Recovery Energy Infrastructure

362

Advanced Research  

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

Ductility EnhancEmEnt of molybDEnum Ductility EnhancEmEnt of molybDEnum PhasE by nano-sizED oxiDE DisPErsions Description Using computational modeling techniques, this research aims to develop predictive capabilities to facilitate the design and optimization of molybdenum (Mo), chromium (Cr), and other high-temperature structural materials to enable these materials to withstand the harsh environments of advanced power generation systems, such as gasification-based systems. These types of materials are essential to the development of highly efficient, clean energy technologies such as low-emission power systems that use coal or other fossil fuels.

363

Advanced Research  

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

Super HigH-TemperaTure alloyS and Super HigH-TemperaTure alloyS and CompoSiTeS From nb-W-Cr SySTemS Description The U.S. Department of Energy's Office of Fossil Energy (DOE-FE) has awarded a three-year grant to the University of Texas at El Paso (UTEP) and Argonne National Laboratory (ANL) to jointly explore the high-temperature properties of alloys composed of niobium (Nb), tungsten (W), and chromium (Cr). The grant is administered by the Advanced Research (AR) program of the National

364

Nuclear Energy Advisory Committee  

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

December 9, 2010 L'Enfant Plaza Hotel Washington, D.C. Committee Members Participating John Ahearne Raymond Juzaitis Ashok Bhatnagar William Martin, Chair Dana Christensen Carl Paperiello Thomas Cochran Burton Richter Michael Corradini John Sackett Marvin Fertel Allen Sessoms Donald Hintz Neil Todreas Committee Members Absent Brew Barron Susan Ion Other Participants: Richard Black, Director, Office of Advanced Reactor Concepts, Office of Nuclear Energy, USDOE Nancy Carder, Medical University of South Carolina, NEAC Support Staff David Hill, Director, Institute for Nuclear Energy Science and Technology, Idaho National Laboratory Shane Johnson, Chief Operating Officer, Office of Nuclear Energy, USDOE

365

Supercomputers | National Nuclear Security Administration  

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

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

366

Nuclear Energy | Argonne National Laboratory  

NLE Websites -- All DOE Office Websites (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

367

Transformations of Grassman Spaces  

E-Print Network (OSTI)

This is a version of a part of the book ``Transformations of Grassman Spaces'' (in progress). We study transformations of Grassman spaces preserving certain geometrical constructions related to buildings. The next part will be devoted to Grassman spaces associated with polar spaces.

Mark Pankov

2004-04-05T23:59:59.000Z

368

Generalized Lorentz Transformations  

E-Print Network (OSTI)

Generalized Lorentz transformations with modified velocity parameter are considered. Lorentz transformations depending on the mass of the observer are suggested.The modified formula for the addition of velocities remarkably preserves the constancy of the velocity of light for all observers. The Doppler red shift is affected and can provide a test of such generalisations.

Virendra Gupta

2013-05-22T23:59:59.000Z

369

Biochemical transformation of coals  

DOE Patents (OSTI)

A method of biochemically transforming macromolecular compounds found in solid carbonaceous materials, such as coal is provided. The preparation of new microorganisms, metabolically weaned through challenge growth processes to biochemically transform solid carbonaceous materials at extreme temperatures, pressures, pH, salt and toxic metal concentrations is also disclosed. 7 figs.

Lin, M.S.; Premuzic, E.T.

1999-03-23T23:59:59.000Z

370

Office of Nuclear Energy, Science and Technology Executive Summary  

E-Print Network (OSTI)

-effective, advanced nuclear plant designs and develop gas-cooled reactor technologies in order to pave the way projects to usher forth next-generation nuclear reactors and fuel cycles based on the results that enable used nuclear fuels to be recycled back into the reactors as fresh fuel. The Advanced Fuel Cycle

371

Nuclear Science & Engineering Directorate  

E-Print Network (OSTI)

, and allowable fuel burn-up Typical crud loading in a PWR fuel assembly ( NEI, 2012) CASL is advancing power plant with high-fidelity R&D capabilities · Provide analysis capability on a spatial scale never extremely large problems challenging the U.S. nuclear power industry · Software validation against measured

Pennycook, Steve

372

Introduction to Nuclear Fuel Cycle and Advanced Nuclear Fuels: Jon ...  

Science Conference Proceedings (OSTI)

Mar 1, 2012 ... Increased use of fossil fuel will result in. • Resource shortfalls and regional conflicts,. • Serious environmental impact. • Worldwide expansion of ...

373

Advanced Nuclear Technology: Aerosol Decontamination from Nuclear Containments  

Science Conference Proceedings (OSTI)

Under assumed severe accident conditions, fission products are expected to be released to the containment environment. Small particulates, suspended in the containment atmosphere as aerosols, can leave containment through leakage pathways. These leak paths are expected to include imperfections in door or penetration seals, small weld or concrete cracks, or other capillary-type paths.One physical process that will occur during containment leakage is decontamination of the aerosol-laden ...

2013-03-20T23:59:59.000Z

374

Development of an Automated Testing System for Verification and Validation of Nuclear Data and Simulation Code  

Science Conference Proceedings (OSTI)

Technical Paper / Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Radiation Measurements and Instrumentation

Brian S. Triplett; Samim Anghaie; Morgan C. White

375

Advanced Research  

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

05/2007 05/2007 NitrogeN evolutioN aNd CorrosioN MeChaNisMs With oxyCoMbustioN of Coal Description Under a grant from the University Coal Research (UCR) program, Brigham Young University (BYU) is leading a three-year research effort to investigate the physical processes that several common types of coal undergo during oxy-fuel combustion. Specifically, research addresses the mixture of gases emitted from burning, particularly such pollutants as nitrogen oxides (NO X ) and carbon dioxide (CO 2 ), and the potential for corrosion at the various stages of combustion. The UCR program is administered by the Advanced Research Program at the National Energy Technology Laboratory (NETL), under the U.S. Department of Energy's Office of

376

Bold, Transformational Energy Research Projects Win $151 Million in Funding  

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

Bold, Transformational Energy Research Projects Win $151 Million in Bold, Transformational Energy Research Projects Win $151 Million in Funding Bold, Transformational Energy Research Projects Win $151 Million in Funding October 26, 2009 - 12:00am Addthis San Francisco, Calif. - The Department of Energy today announced major funding for 37 ambitious research projects - including some that could allow intermittent energy sources like wind and solar to provide a steady flow of power, or use bacteria to produce automotive fuel from sunlight, water and carbon dioxide. The $151 million in funding is being awarded through the Department's recently-formed Advanced Research Projects Agency-Energy ("ARPA-E"). ARPA-E's mission is to develop nimble, creative and inventive approaches to transform the global energy landscape while advancing America's technology

377

Ohio Advanced Energy Manufacturing Center  

Science Conference Proceedings (OSTI)

The program goal of the Ohio Advanced Energy Manufacturing Center (OAEMC) is to support advanced energy manufacturing and to create responsive manufacturing clusters that will support the production of advanced energy and energy-efficient products to help ensure the nation's energy and environmental security. This goal cuts across a number of existing industry segments critical to the nation's future. Many of the advanced energy businesses are starting to make the transition from technology development to commercial production. Historically, this transition from laboratory prototypes through initial production for early adopters to full production for mass markets has taken several years. Developing and implementing manufacturing technology to enable production at a price point the market will accept is a key step. Since these start-up operations are configured to advance the technology readiness of the core energy technology, they have neither the expertise nor the resources to address manufacturing readiness issues they encounter as the technology advances toward market entry. Given the economic realities of today's business environment, finding ways to accelerate this transition can make the difference between success and failure for a new product or business. The advanced energy industry touches a wide range of industry segments that are not accustomed to working together in complex supply chains to serve large markets such as automotive and construction. During its first three years, the Center has catalyzed the communication between companies and industry groups that serve the wide range of advanced energy markets. The Center has also found areas of common concern, and worked to help companies address these concerns on a segment or industry basis rather than having each company work to solve common problems individually. EWI worked with three industries through public-private partnerships to sew together disparate segments helping to promote overall industry health. To aid the overall advanced energy industry, EWI developed and launched an Ohio chapter of the non-profit Advanced Energy Economy. In this venture, Ohio joins with six other states including Colorado, Connecticut, Illinois, Maine, Massachusetts, New Hampshire, Rhode Island and Vermont to help promote technologies that deliver energy that is affordable, abundant and secure. In a more specific arena, EWI's advanced energy group collaborated with the EWI-run Nuclear Fabrication Consortium to promote the nuclear supply chain. Through this project EWI has helped bring the supply chain up to date for the upcoming period of construction, and assisted them in understanding the demands for the next generation of facilities now being designed. In a more targeted manner, EWI worked with 115 individual advanced energy companies that are attempting to bring new technology to market. First, these interactions helped EWI develop an awareness of issues common to companies in different advanced energy sectors. By identifying and addressing common issues, EWI helps companies bring technology to market sooner and at a lower cost. These visits also helped EWI develop a picture of industry capability. This helped EWI provide companies with contacts that can supply commercial solutions to their new product development challenges. By providing assistance in developing supply chain partnerships, EWI helped companies bring their technology to market faster and at a lower cost than they might have been able to do by themselves. Finally, at the most granular level EWI performed dedicated research and development on new manufacturing processes for advanced energy. During discussions with companies participating in advanced energy markets, several technology issues that cut across market segments were identified. To address some of these issues, three crosscutting technology development projects were initiated and completed with Center support. This included reversible welds for batteries and high temperature heat exchangers. It also included a novel advanced weld trainer that EWI

Kimberly Gibson; Mark Norfolk

2012-07-30T23:59:59.000Z

378

Ohio Advanced Energy Manufacturing Center  

SciTech Connect

The program goal of the Ohio Advanced Energy Manufacturing Center (OAEMC) is to support advanced energy manufacturing and to create responsive manufacturing clusters that will support the production of advanced energy and energy-efficient products to help ensure the nation's energy and environmental security. This goal cuts across a number of existing industry segments critical to the nation's future. Many of the advanced energy businesses are starting to make the transition from technology development to commercial production. Historically, this transition from laboratory prototypes through initial production for early adopters to full production for mass markets has taken several years. Developing and implementing manufacturing technology to enable production at a price point the market will accept is a key step. Since these start-up operations are configured to advance the technology readiness of the core energy technology, they have neither the expertise nor the resources to address manufacturing readiness issues they encounter as the technology advances toward market entry. Given the economic realities of today's business environment, finding ways to accelerate this transition can make the difference between success and failure for a new product or business. The advanced energy industry touches a wide range of industry segments that are not accustomed to working together in complex supply chains to serve large markets such as automotive and construction. During its first three years, the Center has catalyzed the communication between companies and industry groups that serve the wide range of advanced energy markets. The Center has also found areas of common concern, and worked to help companies address these concerns on a segment or industry basis rather than having each company work to solve common problems individually. EWI worked with three industries through public-private partnerships to sew together disparate segments helping to promote overall industry health. To aid the overall advanced energy industry, EWI developed and launched an Ohio chapter of the non-profit Advanced Energy Economy. In this venture, Ohio joins with six other states including Colorado, Connecticut, Illinois, Maine, Massachusetts, New Hampshire, Rhode Island and Vermont to help promote technologies that deliver energy that is affordable, abundant and secure. In a more specific arena, EWI's advanced energy group collaborated with the EWI-run Nuclear Fabrication Consortium to promote the nuclear supply chain. Through this project EWI has helped bring the supply chain up to date for the upcoming period of construction, and assisted them in understanding the demands for the next generation of facilities now being designed. In a more targeted manner, EWI worked with 115 individual advanced energy companies that are attempting to bring new technology to market. First, these interactions helped EWI develop an awareness of issues common to companies in different advanced energy sectors. By identifying and addressing common issues, EWI helps companies bring technology to market sooner and at a lower cost. These visits also helped EWI develop a picture of industry capability. This helped EWI provide companies with contacts that can supply commercial solutions to their new product development challenges. By providing assistance in developing supply chain partnerships, EWI helped companies bring their technology to market faster and at a lower cost than they might have been able to do by themselves. Finally, at the most granular level EWI performed dedicated research and development on new manufacturing processes for advanced energy. During discussions with companies participating in advanced energy markets, several technology issues that cut across market segments were identified. To address some of these issues, three crosscutting technology development projects were initiated and completed with Center support. This included reversible welds for batteries and high temperature heat exchangers. It also included a novel advanced weld trainer that EWI

Kimberly Gibson; Mark Norfolk

2012-07-30T23:59:59.000Z

379

Reactor and Nuclear Systems Division (RNSD)  

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

RNSD Home RNSD Home Research Groups Advanced Reactor Systems & Safety Nuclear Data & Criticality Safety Nuclear Security Modeling Radiation Safety Information Computational Center Radiation Transport Reactor Physics Thermal Hydraulics & Irradiation Engineering Used Fuel Systems Staff Details (CV/Bios) Publications Org Chart Contact Us ORNL Staff Only Research Groups Advanced Reactor Systems & Safety Nuclear Data & Criticality Safety Nuclear Security Modeling Radiation Safety Information Computational Center Radiation Transport Reactor Physics Thermal Hydraulics & Irradiation Engineering Used Fuel Systems Reactor and Nuclear Systems Division News Highlights U.S. Rep. Fleischmann touts ORNL as national energy treasure Martin Peng wins Fusion Power Associates Leadership Award

380

Office of Nuclear Energy | Department of Energy  

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

Office of Nuclear Energy Office of Nuclear Energy Office of Nuclear Energy Small Modular Reactors The Small Modular Reactor program advances the licensing and commercialization of this next-generation technology in the United States. Read more Middle School STEM Curriculum The Harnessed Atom curriculum offers essential principles and fundamental concepts on energy and nuclear science. Read more Educating Future Nuclear Engineers The Nuclear Energy University Program offers fellowships and scholarships for graduate and undergraduate students. Read more Managing Used Fuel and Waste REPORT: Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Read more Consortium for Advanced Simulations of LWRs The Consortium for Advanced Simulation of Light Water Reactors (CASL) is

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

A discrete fractional random transform  

E-Print Network (OSTI)

We propose a discrete fractional random transform based on a generalization of the discrete fractional Fourier transform with an intrinsic randomness. Such discrete fractional random transform inheres excellent mathematical properties of the fractional Fourier transform along with some fantastic features of its own. As a primary application, the discrete fractional random transform has been used for image encryption and decryption.

Zhengjun Liu; Haifa Zhao; Shutian Liu

2006-05-20T23:59:59.000Z

382

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel ... nuclear reactors, generation, spent fuel. Total Energy. Comprehensive data summaries, comparisons, analysis, and projections ...

383

Prospects for the development of advanced reactors  

SciTech Connect

Energy supply is an important prerequisite for further socio-economic development, especially in developing countries where the per capita energy use is only a very small fraction of that in industrialized countries. Nuclear energy is an essentially unlimited energy resource with the potential to provide this energy in the form of electricity, district heat and process heat under environmentally acceptable conditions. However, this potential will be realized only if nuclear power plants can meet the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide a tremendous amount of experience has been accumulated during development, licensing, construction and operation of nuclear power reactors. The experience forms a sound basis for further improvements. Nuclear programmes in many countries are addressing the development of advanced reactors which are intended to have better economics, higher reliability and improved safety in order to overcome the current concerns of nuclear power. Advanced reactors now being developed could help to meet the demand for new plants in developed and developing countries, not only for electricity generation, but also for district heating, desalination and for process heat. The IAEA, as the only global international governmental organization dealing with nuclear power, promotes international information exchange and international co-operation between all countries with their own advanced nuclear power programmes and offers assistance to countries with an interest in exploratory or research programmes.

Semenov, B.A.; Kupitz, J.; Cleveland, J. [International Atomic Energy Agency Vienna (Austria). Dept. of Nuclear Energy and Safety

1992-12-31T23:59:59.000Z

384

Lorentz transformation by mimicking the Lorentz transformation  

E-Print Network (OSTI)

We show that starting with the fact that special relativity theory is concerned with a distortion of the observed length of a moving rod, without mentioning if it is a "contraction" or "dilation", we can derive the Lorentz transformations for the spacetime coordinates of the same event. This derivation is based on expressing the length of the moving rod as a sum of components with all the lengths involved in this summation being measured by the observers of the same inertial reference frame.

Bernhard Rothenstein; Stefan Popescu

2007-07-16T23:59:59.000Z

385

Plant maintenance and advanced reactors, 2005  

SciTech Connect

The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: First U.S. EPRs in 2015, by Ray Ganthner, Framatome ANP; Pursuing several opportunities, by William E. (Ed) Cummins, Westinghouse Electric Company; Vigorous plans to develop advanced reactors, by Yuliang Sun, Tsinghua University, China; Multiple designs, small and large, by Kumiaki Moriya, Hitachi Ltd., Japan; Sealed and embedded for safety and security, by Handa Norihiko, Toshiba Corporation, Japan; Scheduled online in 2010, by Johan Slabber, PMBR (Pty) Ltd., South Africa; Multi-application reactors, by Nikolay G. Kodochigov, OKBM, Russia; Six projects under budget and on schedule, by David F. Togerson, AECL, Canada; Creating a positive image, by Scott Peterson, Nuclear Energy Institute (NEI); Advanced plans for nuclear power's renaissance, by John Cleveland, International Atomic Energy Agency, Austria; and, Plant profile: last five outages in less than 20 days, by Beth Rapczynski, Exelon Nuclear.

Agnihotri, Newal (ed.)

2005-09-15T23:59:59.000Z

386

Modern Imaging Technology: Recent Advances  

SciTech Connect

This 2-day conference is designed to bring scientist working in nuclear medicine, as well as nuclear medicine practitioners together to discuss the advances in four selected areas of imaging: Biochemical Parameters using Small Animal Imaging, Developments in Small Animal PET Imaging, Cell Labeling, and Imaging Angiogenesis Using Multiple Modality. The presentations will be on molecular imaging applications at the forefront of research, up to date on the status of molecular imaging in nuclear medicine as well as in related imaging areas. Experts will discuss the basic science of imaging techniques, and scheduled participants will engage in an exciting program that emphasizes the current status of molecular imaging as well as the role of DOE funded research in this area.

Welch, Michael J.; Eckelman, William C.

2004-06-18T23:59:59.000Z

387

Market Transformation Fact Sheet  

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

Transformation Market Transformation is based on the concept that federal support can catalyze a market to achieve economic and environmental benefits that can reduce costs through economies of scale. Adoption of fuel cells in emerging markets expands the growth of green jobs, with new opportunities in manufacturing, fuel cell maintenance and support systems, and domestic hydrogen fuel production and delivery. By providing reliable field operations data and increasing user confidence, early market deployments help overcome non-technical challenges like developing appropriate safety codes and standards and reducing high insurance costs. Strategies Market Transformation's primary goal is to accelerate the expansion of hydrogen and fuel cell use by lowering the life

388

Nuclear power and nuclear weapons  

SciTech Connect

The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described.

Vaughen, V.C.A.

1983-01-01T23:59:59.000Z

389

Global Nuclear Energy Partnership Steering Group Members Approve  

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

Global Nuclear Energy Partnership Steering Group Members Approve Global Nuclear Energy Partnership Steering Group Members Approve Transformation to the International Framework for Nuclear Energy Cooperation Global Nuclear Energy Partnership Steering Group Members Approve Transformation to the International Framework for Nuclear Energy Cooperation June 21, 2010 - 11:59am Addthis The Global Nuclear Energy Partnership Steering Group met in Accra, Ghana on June 16-17, 2010, and approved unanimously several transformative changes to reflect global developments that have occurred since the Partnership was established in 2007. The transformation includes a new name - the International Framework for Nuclear Energy Cooperation -- and the establishment of a new Statement of Mission. Participants in this new International Framework agreed that this

390

Final Complex Transformation Supplemental Programmatic Environmental Impact Statement October 2008  

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

I I Volume I Chapters 1 - 4 Chapters 1 - 4 DOE/EIS-0236-S4 National Nuclear Security Administration U.S. Department of Energy October 2008 C C CO O OM MP PL LE EXtransfo o or r rm m mat on COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy, National Nuclear Security Administration TITLE: Final Complex Transformation Supplemental Programmatic Environmental Impact Statement (Complex Transformation SPEIS, DOE/EIS-0236-S4) CONTACTS: For further information on this SPEIS, For general information on the DOE write or call: National Environmental Policy Act (NEPA) process, write or call: Theodore A. Wyka Carol Borgstrom, Director Complex Transformation Office of NEPA Policy and Compliance, GC-20 SPEIS Document Manager U.S. Department of Energy Office of Transformation, NA-10.1 1000 Independence Avenue, SW

391

Final Complex Transformation Supplemental Programmatic Environmental Impact Statement October 2008  

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

Summary Summary Summary DOE/EIS-0236-S4 National Nuclear Security Administration U.S. Department of Energy October 2008 C C CO O OM MP PL LE EXtransfo o or r rm m mat on COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy, National Nuclear Security Administration TITLE: Final Complex Transformation Supplemental Programmatic Environmental Impact Statement (Complex Transformation SPEIS, DOE/EIS-0236-S4) CONTACTS: For further information on this SPEIS, For general information on the DOE write or call: National Environmental Policy Act (NEPA) process, write or call: Theodore A. Wyka Carol Borgstrom, Director Complex Transformation Office of NEPA Policy and Compliance, GC-20 SPEIS Document Manager U.S. Department of Energy Office of Transformation, NA-10.1 1000 Independence Avenue, SW

392

Transformation inverse design  

E-Print Network (OSTI)

We present a new technique for the design of transformation-optics devices based on large-scale optimization to achieve the optimal effective isotropic dielectric materials within prescribed index bounds, which is ...

Liu, David

393

The Quantum Mellin transform  

E-Print Network (OSTI)

We uncover a new type of unitary operation for quantum mechanics on the half-line which yields a transformation to ``Hyperbolic phase space''. We show that this new unitary change of basis from the position x on the half line to the Hyperbolic momentum $p_\\eta$, transforms the wavefunction via a Mellin transform on to the critial line $s=1/2-ip_\\eta$. We utilise this new transform to find quantum wavefunctions whose Hyperbolic momentum representation approximate a class of higher transcendental functions, and in particular, approximate the Riemann Zeta function. We finally give possible physical realisations to perform an indirect measurement of the Hyperbolic momentum of a quantum system on the half-line.

J. Twamley; G. J. Milburn

2007-02-12T23:59:59.000Z

394

On Bianchi's Backlund transformation  

E-Print Network (OSTI)

We investigate basic features of Bianchi's B\\"acklund transformation of quadrics to see if it can be obtained under weaker assumptions and if it can be generalized to deformations of other surfaces.

Dinca, Ion

2011-01-01T23:59:59.000Z

395

Imaging Fourier transform spectrometer  

DOE Patents (OSTI)

This invention is comprised of an imaging Fourier transform spectrometer having a Fourier transform infrared spectrometer providing a series of images to a focal plane array camera. The focal plane array camera is clocked to a multiple of zero crossing occurrences as caused by a moving mirror of the Fourier transform infrared spectrometer and as detected by a laser detector such that the frame capture rate of the focal plane array camera corresponds to a multiple of the zero crossing rate of the Fourier transform infrared spectrometer. The images are transmitted to a computer for processing such that representations of the images as viewed in the light of an arbitrary spectral ``fingerprint`` pattern can be displayed on a monitor or otherwise stored and manipulated by the computer.

Bennett, C.L.

1993-09-13T23:59:59.000Z

396

Series Transmission Line Transformer  

DOE Patents (OSTI)

A series transmission line transformer is set forth which includes two or more of impedance matched sets of at least two transmissions lines such as shielded cables, connected in parallel at one end ans series at the other in a cascading fashion. The cables are wound about a magnetic core. The series transmission line transformer (STLT) which can provide for higher impedance ratios and bandwidths, which is scalable, and which is of simpler design and construction.

Buckles, Robert A. (Livermore, CA); Booth, Rex (Livermore, CA); Yen, Boris T. (El Cerrito, CA)

2004-06-29T23:59:59.000Z

397

Department of Energy and Nuclear Regulatory Commission Increase Cooperation  

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

Nuclear Regulatory Commission Increase Nuclear Regulatory Commission Increase Cooperation to Advance Global Nuclear Energy Partnership Department of Energy and Nuclear Regulatory Commission Increase Cooperation to Advance Global Nuclear Energy Partnership July 17, 2007 - 2:55pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) expanded cooperation for President Bush's Global Nuclear Energy Partnership (GNEP) through a Memorandum of Understanding (MOU) that was signed on Friday by DOE's GNEP Deputy Program Manager Paul Lisowski and NRC Executive Director for Operations Luis Reyes. The MOU establishes the foundation for increased cooperation between DOE and NRC on technological research and engineering studies and marks another important milestone

398

Related Resources - Nuclear Data Program, Nuclear Engineering...  

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

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

399

Publications: Other Resources - Nuclear Data Program - Nuclear...  

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

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

400

Publications 2005 - Nuclear Data Program - Nuclear Engineering...  

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

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

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Publications 2003 - Nuclear Data Program - Nuclear Engineering...  

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

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

402

Contacts - Nuclear Data Program, Nuclear Engineering Division...  

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

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

403

Publications 2001 - Nuclear Data Program - Nuclear Engineering...  

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

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

404

Publications 2004 - Nuclear Data Program - Nuclear Engineering...  

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

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

405

Publications 2009 - Nuclear Data Program - Nuclear Engineering...  

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

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

406

Nuclear Criticality Safety: Current Activities - Nuclear Engineering...  

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

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

407

Nuclear Criticality Safety - Nuclear Engineering Division (Argonne...  

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

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

408

Nuclear Systems Analysis - Nuclear Engineering Division (Argonne...  

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

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

409

Publications 2011 - Nuclear Data Program - Nuclear Engineering...  

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

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

410

Institute for Atom-Efficient Chemical Transformations Energy Frontier  

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

Institute for Atom-Efficient Chemical Transformations DOE Logo Institute for Atom-Efficient Chemical Transformations DOE Logo Focus Areas Reaction Mechanisms Controlled Active Metals Materials Synthesis Search Argonne ... Search Argonne Home > Institute for Atom-Efficient Chemical Transformations > IACT Home IACT News IACT Partners IACT Staff IACT Awards Publications & Presentations Jobs at IACT Energy Frontier Research Centers at Argonne Strategic Alliances Research Facilities & Tools Institute for Atom-Efficient Chemical Transformations - an Energy Frontier Research Center The Institute for Atom-Efficient Chemical Transformations (IACT) employs a multidisciplinary approach to address key catalytic conversions that could improve the efficiency of producing fuels from biomass. IACT focuses on advancing the science of catalysis for the efficient conversion of energy resources into usable forms. IACT's goal is to find ways to achieve control and efficiency of chemical conversions comparable to those in nature.

411

Large Scale Computing and Storage Requirements for Nuclear Physics  

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

Office of Science, Office of Advanced Scientific Computing Research (ASCR), Office of Nuclear Physics (NP), and the National Energy Research Scientific Computing Center (NERSC)...

412

Energy Department Announces New Nuclear Energy Innovation Investments  

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

Energy Department Announces New Nuclear Energy Innovation Investments Sixteen Awards to Advance Cross-cutting R&D, Train Next Generation of Industry Leaders WASHINGTON -...

413

Nuclear engineer Li wins Presidential Early Career Award | Argonne...  

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

Photon Source. Click to enlarge. Argonne's Advanced Photon Source. Click to enlarge. Nuclear engineer Li wins Presidential Early Career Award By Jared Sagoff * January 15, 2014...

414

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... CITATION: Technology and Applied R&D Needs for Advanced Nuclear Energy Systems, Office of Science, U. S. Department of Energy, June ...

415

New RFID technology tracks and monitors nuclear materials | Argonne...  

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

New RFID technology tracks and monitors nuclear materials By Jared Sagoff * March 24, 2009 Tweet EmailPrint Advancement has applications in many areas involving remote sensing...

416

Multi-Scale Modeling of Irradiation Effects on Nuclear Fuel ...  

Science Conference Proceedings (OSTI)

Ab Initio-Based Rate Theory Modeling of Radiation Induced Segregation in ... Benchmarking of Structural Materials Pre-Selected for Advanced Nuclear Reactors.

417

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

Science Conference Proceedings (OSTI)

Sep 12, 2007 ... Use the link provided below to access the following articles featured in the April 2007 issue of JOM: "Materials for Advanced Nuclear Systems," ...

418

Ceramic Matrix Composites for Nuclear and Fusion Energy  

Science Conference Proceedings (OSTI)

Abstract Scope, Ceramic matrix composites are considered among the key enabling materials for advanced nuclear reactors and fusion energy systems. Silicon ...

419

DOE Initiates Environmental Impact Statement for Global Nuclear...  

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

advanced technologies to safely recycle spent nuclear fuel using more proliferation-resistant processes. The EIS will evaluate all reasonable alternative technologies as well as...

420

Secretary Chu Announces Nuclear Energy University Program Awards...  

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

teaching and research capabilities University of Nevada, Las Vegas Physical property measurement system and system upgrade for D8 advance x-ray diffraction for nuclear energy fuels...

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

The Management of Aging in Nuclear Power Plant Concrete Structures  

Science Conference Proceedings (OSTI)

An example of application of structural reliability theory to investigate the impact of ... Cladding and Duct Materials for Advanced Nuclear Recycle Reactors

422

Nuclear Energy Research and Development in the Department of...  

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

used nuclear fuel disposition, effective utilization and deployment of advanced reactor concepts, and eventual development of a permanent geologic repository(s). This should...

423

Nuclear Material Management Abstract  

Science Conference Proceedings (OSTI)

Nevada Test Site (NTS) has transitioned from its historical and critical role of weapons testing to another critical role for the nation. This new role focuses on being a integral element in solving the multiple challenges facing the National Nuclear Security Administration (NNSA) with nuclear material management. NTS is positioned to be a solution for other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to consolidate and modernize the production complex . With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through disposition and consolidation. This includes moving material from other sites to NTS. State of the art nuclear material management and control practices at NTS are essential for NTS to ensure that assigned activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS activities and challenges will be addressed.

Jesse C. Schreiber

2007-07-10T23:59:59.000Z

424

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

425

Plant maintenance and advanced reactors issue, 2008  

Science Conference Proceedings (OSTI)

The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Technologies of national importance, by Tsutomu Ohkubo, Japan Atomic Energy Agency, Japan; Modeling and simulation advances brighten future nuclear power, by Hussein Khalil, Argonne National Laboratory, Energy and desalination projects, by Ratan Kumar Sinha, Bhabha Atomic Research Centre, India; A plant with simplified design, by John Higgins, GE Hitachi Nuclear Energy; A forward thinking design, by Ray Ganthner, AREVA; A passively safe design, by Ed Cummins, Westinghouse Electric Company; A market-ready design, by Ken Petrunik, Atomic Energy of Canada Limited, Canada; Generation IV Advanced Nuclear Energy Systems, by Jacques Bouchard, French Commissariat a l'Energie Atomique, France, and Ralph Bennett, Idaho National Laboratory; Innovative reactor designs, a report by IAEA, Vienna, Austria; Guidance for new vendors, by John Nakoski, U.S. Nuclear Regulatory Commission; Road map for future energy, by John Cleveland, International Atomic Energy Agency, Vienna, Austria; and, Vermont's largest source of electricity, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovation article is titled Intelligent monitoring technology, by Chris Demars, Exelon Nuclear.

Agnihotri, Newal (ed.)

2009-09-15T23:59:59.000Z

426

Optical transformation from chirplet to fractional Fourier transformation kernel  

E-Print Network (OSTI)

We find a new integration transformation which can convert a chirplet function to fractional Fourier transformation kernel, this new transformation is invertible and obeys Parseval theorem. Under this transformation a new relationship between a phase space function and its Weyl-Wigner quantum correspondence operator is revealed.

Hong-yi Fan; Li-yun Hu

2009-02-11T23:59:59.000Z

427

Optical transformation from chirplet to fractional Fourier transformation kernel  

E-Print Network (OSTI)

We find a new integration transformation which can convert a chirplet function to fractional Fourier transformation kernel, this new transformation is invertible and obeys Parseval theorem. Under this transformation a new relationship between a phase space function and its Weyl-Wigner quantum correspondence operator is revealed.

Fan, Hong-yi

2009-01-01T23:59:59.000Z

428

Nuclear Energy Program  

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

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

429

ADVANCED SEISMIC BASE ISOLATION METHODS FOR MODULAR REACTORS  

SciTech Connect

Advanced technologies for structural design and construction have the potential for major impact not only on nuclear power plant construction time and cost, but also on the design process and on the safety, security and reliability of next generation of nuclear power plants. In future Generation IV (Gen IV) reactors, structural and seismic design should be much more closely integrated with the design of nuclear and industrial safety systems, physical security systems, and international safeguards systems. Overall reliability will be increased, through the use of replaceable and modular equipment, and through design to facilitate on-line monitoring, in-service inspection, maintenance, replacement, and decommissioning. Economics will also receive high design priority, through integrated engineering efforts to optimize building arrangements to minimize building heights and footprints. Finally, the licensing approach will be transformed by becoming increasingly performance based and technology neutral, using best-estimate simulation methods with uncertainty and margin quantification. In this context, two structural engineering technologies, seismic base isolation and modular steel-plate/concrete composite structural walls, are investigated. These technologies have major potential to (1) enable standardized reactor designs to be deployed across a wider range of sites, (2) reduce the impact of uncertainties related to site-specific seismic conditions, and (3) alleviate reactor equipment qualification requirements. For Gen IV reactors the potential for deliberate crashes of large aircraft must also be considered in design. This report concludes that base-isolated structures should be decoupled from the reactor external event exclusion system. As an example, a scoping analysis is performed for a rectangular, decoupled external event shell designed as a grillage. This report also reviews modular construction technology, particularly steel-plate/concrete construction using factory prefabricated structural modules, for application to external event shell and base isolated structures.

E. Blanford; E. Keldrauk; M. Laufer; M. Mieler; J. Wei; B. Stojadinovic; P.F. Peterson

2010-09-20T23:59:59.000Z

430

Overview | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Overview | National Nuclear Security Administration Overview | 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 Overview Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing and Institutional R&D Programs > About ASC > Overview Overview

431

Accomplishments | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Accomplishments | National Nuclear Security Administration Accomplishments | 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 Accomplishments Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing and Institutional R&D Programs > About ASC > Accomplishments

432

Accomplishments | National Nuclear Security Administration  

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

Accomplishments | National Nuclear Security Administration Accomplishments | 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 Accomplishments Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing and Institutional R&D Programs > About ASC > Accomplishments

433

Report on Advanced Detector Development  

Science Conference Proceedings (OSTI)

Neutron, gamma and charged particle detection improvements are key to supporting many of the foreseen measurements and systems envisioned in the R&D programs and the future fuel cycle requirements, such as basic nuclear physics and data, modeling and simulation, reactor instrumentation, criticality safety, materials management and safeguards. This task will focus on the developmental needs of the FCR&D experimental programs, such as elastic/inelastic scattering, total cross sections and fission neutron spectra measurements, and will leverage a number of existing neutron detector development efforts and programs, such as those at LANL, PNNL, INL, and IAC as well as those at many universities, some of whom are funded under NE grants and contracts. Novel materials and fabrication processes combined with state-of-the-art electronics and computing provide new opportunities for revolutionary detector systems that will be able to meet the high precision needs of the program. This work will be closely coordinated with the Nuclear Data Crosscut. The Advanced Detector Development effort is a broadly-focused activity that supports the development of improved nuclear data measurements and improved detection of nuclear reactions and reactor conditions. This work supports the design and construction of large-scale, multiple component detectors to provide nuclear reaction data of unprecedented quality and precision. Examples include the Time Projection Chamber (TPC) and the DANCE detector at LANL. This work also supports the fabrication and end-user application of novel scintillator materials detection and monitoring.

James K. Jewell

2012-09-01T23:59:59.000Z

434

Thermal Stability of Uranium-Rich U-Mo Alloys for Advanced ...  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, 2014 TMS Annual Meeting & Exhibition. Symposium , Materials and Fuels for the Current and Advanced Nuclear Reactors III.

435

Sandia LDRD-funded project looks at advanced materials for reactors...  

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

LDRD-funded project looks at advanced materials for reactors | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the...

436

Investigation of Freeze-Cast Scaffolds as an Advanced Reactor Fuel ...  

Science Conference Proceedings (OSTI)

Symposium, Materials and Fuels for the Current and Advanced Nuclear Reactors II ... A Rate-Theory Approach to Irradiation Damage Modeling with Random ...

437

Office of Nuclear Energy | Department of Energy  

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

Office of Nuclear Energy Office of Nuclear Energy Small Modular Reactors The Small Modular Reactor program advances the licensing and commercialization of this next-generation technology in the United States. Read more Middle School STEM Curriculum The Harnessed Atom curriculum offers essential principles and fundamental concepts on energy and nuclear science. Read more Educating Future Nuclear Engineers The Nuclear Energy University Program offers fellowships and scholarships for graduate and undergraduate students. Read more Managing Used Fuel and Waste REPORT: Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Read more Consortium for Advanced Simulations of LWRs The Consortium for Advanced Simulation of Light Water Reactors (CASL) is the first DOE Hub for the modeling and simulation (M&S) of commercial

438

II.AdvancedTcl Advanced Tcl  

E-Print Network (OSTI)

119 P A R T II.AdvancedTcl II Advanced Tcl Part II describes advanced programming techniques that support sophisticated applications. The Tcl interfaces remain simple, so you can quickly construct pow- erful applications. Chapter 10 describes eval, which lets you create Tcl programs on the fly

Chen, Yuanzhu Peter

439

Some political issues related to future special nuclear materials production  

Science Conference Proceedings (OSTI)

The Federal Government must take action to assure the future adequate supply of special nuclear materials for nuclear weapons. Existing statutes permit the construction of advanced defense production reactors and the reprocessing of commercial spent fuel for the production of special materials. Such actions would not only benefit the US nuclear reactor manufacturers, but also the US electric utilities that use nuclear reactors.

Peaslee, A.T. Jr.

1981-08-01T23:59:59.000Z

440

ARPA-E Announces $43 Million for Transformational Energy Storage Projects  

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

ARPA-E Announces $43 Million for Transformational Energy Storage ARPA-E Announces $43 Million for Transformational Energy Storage Projects to Advance Electric Vehicle and Grid Technologies ARPA-E Announces $43 Million for Transformational Energy Storage Projects to Advance Electric Vehicle and Grid Technologies August 2, 2012 - 10:34am Addthis News Media Contact (202) 586-4940 WASHINGTON - The Department of Energy today announced that 19 transformative new projects will receive a total of $43 million in funding from the Department's Advanced Research Projects Agency-Energy (ARPA-E) to leverage the nation's brightest scientists, engineers and entrepreneurs to develop breakthrough energy storage technologies and support promising small businesses. These projects are supported through two new ARPA-E programs -- Advanced Management and Protection of Energy

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Contact transformations for difference schemes  

E-Print Network (OSTI)

We define a class of transformations of the dependent and independent variables in an ordinary difference scheme. The transformations leave the solution set of the system invariant and reduces to a group of contact transformations in the continuous limit. We use a simple example to show that the class is not empty and that such "contact transformations for discrete systems" genuinely exist.

Levi, Decio; Winternitz, Pavel

2011-01-01T23:59:59.000Z

442

Plant maintenance and advanced reactors issue, 2004  

SciTech Connect

The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Optimism about the future of nuclear power, by Ruth G. Shaw, Duke Power Company; Licensed in three countries, by GE Energy; Enhancing public acceptance, by Westinghouse Electric Company; Standardized MOV program, by Ted Neckowicz, Exelon; Inservice testing, by Steven Unikewicz, U.S. Nuclear Regulatory Commission; Asian network for education, Fatimah Mohd Amin, Malaysian Institute for Nuclear Technology Research; and, Cooling water intake optimization, by Jeffrey M. Jones and Bert Mayer, P.E., Framatome ANP.

Agnihotri, Newal (ed.)

2004-09-15T23:59:59.000Z

443

Alternative and Advanced Fuels  

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

There are a variety of alternative and advanced fuels available, which are used to fuel alternative and advanced vehicles. Learn more about:

444

Help - Advanced Search  

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

Advanced Search The advanced search form will help you create a more specific search in the Publications database. First, specify your search criteria. You can search by author,...

445

Idaho National Laboratory Advanced Test Reactor Probabilistic Risk  

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

Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment September 19, 2012 Presenter: Bentley Harwood, Advanced Test Reactor Nuclear Safety Engineer Battelle Energy Alliance Idaho National Laboratory Topics covered: PRA studies began in the late 1980s 1989, ATR PRA published as a summary report 1991, ATR PRA full report 1994 and 2004 various model changes 2011, Consolidation, update and improvement of previous PRA work 2012/2013, PRA risk monitor implementation Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment More Documents & Publications DOE's Approach to Nuclear Facility Safety Analysis and Management Nuclear Regulatory Commission Handling of Beyond Design Basis Events for

446

Nuclear Science and Technology Division - Home page  

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

image image image - mural in bldg 5200 image image Fuels, Isotopes, and Nuclear Materials image Fuels, Isotopes, and Nuclear Materials Nuclear System Analysis, Design, and Safety image Nuclear System Analysis, Design, and Safety WELCOME Performing basic and applied R&D for the Department of Energy, the National Nuclear Security Administration, and other government agencies, as well as supporting and leveraging industrial partnerships Mission Statement The Nuclear Science and Technology Division at Oak Ridge National Laboratory will provide leading-edge science, technology, and engineering research that support our Nation's nuclear science and technology enterprise across a broad spectrum of applications including but not limited to advanced nuclear power systems, nuclear medicine,and nuclear

447

Partial core pulse transformer  

DOE Patents (OSTI)

A light-weight partial-core pule transformer is provided for generating high voltage output pulses with low distortion. The transformer includes sets of ferrite bars arranged so as to extend longitudinally along the inside and outside surfaces of a high frequency cylindrical coil winding-pair. The ferrite bars are arranged in pairs with the bars of each pair being located on opposite sides of winding-pair. The bars are preferably disposed in a radially symmetric arrangement around the winding-pair, and each has a length at least equal to the width of the winding-pair.

Lawson, R.N.; Rohwein, G.J.

1991-12-31T23:59:59.000Z

448

Functional Mellin Transforms  

E-Print Network (OSTI)

Functional integrals are defined in terms of locally compact topological groups and their associated Banach-valued Haar integrals. This approach generalizes the functional integral scheme of Cartier and DeWitt-Morette. The definition allows a construction of functional Mellin transforms. In turn, the functional Mellin transforms can be used to define functional traces, logarithms, and determinants. The associated functional integrals are useful tools for probing function spaces in general and $C^\\ast$-algebras in particular. Several interesting aspects are explored. As an application, we construct a functional Mellin representation of the quantum evolution operator.

J. LaChapelle

2013-08-05T23:59:59.000Z

449

Transforming coal for sustainability: a strategy for China  

E-Print Network (OSTI)

Transforming coal for sustainability: a strategy for China Report by the Task Force on Energy to rely on coal combustion for power generation and on petro- leum-derived fuels, cannot meet the same energy, and ``modernized'' coal. By aggressively pursu- ing the advanced technology strategy now

450

Effect of Highly Enriched/Highly Burnt UO2 Fuels on Fuel Cycle Costs, Radiotoxicity, and Nuclear Design Parameters  

Science Conference Proceedings (OSTI)

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

Robert Gregg; Andrew Worrall

451

Model Transformations And Tool Integration  

E-Print Network (OSTI)

Model transformations are increasingly recognised as being of significant importance to many areas of software development and integration. Recent attention on model transformations has particularly focused on the OMG's Queries / Views / Transformations (QVT) Request for Proposals (RFP). In this paper I motivate the need for dedicated approaches to model transformations, particularly for the data involved in tool integration, outline the challenges involved, and then present a number of technologies and techniques which allow the construction of flexible, powerful and practical model transformations.

Laurence Tratt

2004-01-01T23:59:59.000Z

452

Coordinate transformations in quaternion spaces  

E-Print Network (OSTI)

The quaternion spaces can be used to describe the property of electromagnetic field and gravitational field. In the quaternion space, some coordinate transformations can be deduced from the feature of quaternions, including Lorentz transformation and Galilean transformation etc., when the coordinate system is transformed into others. And some coordinate transformations with variable speed of light can be obtained in the electromagnetic field and gravitational field.

Zihua Weng

2008-08-31T23:59:59.000Z

453

A Review of Nuclear Computational Information  

SciTech Connect

The Radiation Safety Information Computational Center (RSICC) and the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency Data Bank (NEADB) work together to acquire sets of computer codes, nuclear data, and integral experiments relevant to shielding and dosimetry applications for fission, fusion, and accelerator applications. To keep up with advances in computing technology, international researchers continue to develop nuclear software. Collection centers like RSICC and NEADB serve the community and play a role in advancing nuclear science and technology research.

Kirk, Bernadette Lugue [ORNL

2010-01-01T23:59:59.000Z

454

INSIGHTS INTO THE ROLE OF THE OPERATOR IN ADVANCED REACTORS.  

SciTech Connect

NUCLEAR POWER PLANT PERSONNEL PLAY A VITAL ROLE IN THE PRODUCTIVE, EFFICIENT, AND SAFE GENERATION OF ELECTRIC POWER, WHETHER FOR CONVENTIONAL LIGHT WATER REACTORS OR NEW ADVANCED REACTORS. IT IS WIDELY RECOGNIZED THAT HUMAN ACTIONS THAT DEPART FROM OR FAIL TO ACHIEVE WHAT SHOULD BE DONE CAN BE IMPORTANT CONTRIBUTORS TO THE RISK ASSOCIATED WITH THE OPERATION OF NUCLEAR POWER PLANTS. ADVANCED REACTORS ARE EXPECTED TO PRESENT A CONCEPT OF OPERATI...

PERSENSKY, J.; LEWIS, P.; O' HARA, J.

2005-11-13T23:59:59.000Z

455

Nuclear Reactions  

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

Reactions Nuclear reactions and nuclear scattering are used to measure the properties of nuclei. Reactions that exchange energy or nucleons can be used to measure the energies of...

456

Nuclear Safety  

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

Nuclear Safety information site that provides assistance and resources to field elements in implementation of requirements and resolving nuclear safety, facility safety, and quality assurance issues.

457

Plant maintenance and advanced reactors, 2007  

Science Conference Proceedings (OSTI)

The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: A new day for energy in America; Committed to success more than ever, by Andy White, GE--Hitachi Nuclear Energy; Competitive technology for decades, by Steve Tritch, Westinghouse Electric Company; Pioneers of positive community relationship, by Exelon Nuclear; A robust design for 60-years, by Ray Ganthner, Areva; Aiming at no evacuation plants, by Kumiaki Moriya, Hitachi-GE Nuclear Energy, Ltd.; and, Desalination and hydrogen economy, by Dr. I. Khamis, International Atomic Energy Agency. Industry innovation articles in this issue are: Reactor vessel closure head project, by Jeff LeClair, Prairie Island Nuclear Generating Plant; and Submersible remote-operated vehicle, by Michael S. Rose, Entergy's Fitzpatrick Nuclear Station.

Agnihotri, Newal (ed.)

2007-09-15T23:59:59.000Z

458

Transformative Battery Technology at the National Labs | Department of  

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

Transformative Battery Technology at the National Labs Transformative Battery Technology at the National Labs Transformative Battery Technology at the National Labs January 17, 2012 - 10:45am Addthis Vince Battaglia leads a behind-the-scenes tour of Berkeley Lab's Batteries for Advanced Transportation Technologies Program where researchers aim to improve batteries upon which the range, efficiency, and power of tomorrow's electric cars will depend. Michael Hess Michael Hess Former Digital Communications Specialist, Office of Public Affairs What are the key facts? Berkeley's Batteries for Advanced Transportation Technologies Program is developing lithium-ion technology to power a vehicle for 300 miles. Lithium-sulfur and lithium-air are "unknown known" technologies for the future of electric vehicle batteries.

459

Energy Department Announces $66 Million for Transformational Energy  

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

66 Million for Transformational Energy 66 Million for Transformational Energy Technologies Energy Department Announces $66 Million for Transformational Energy Technologies September 19, 2013 - 3:30pm Addthis NEWS MEDIA CONTACT (202) 586-4940 WASHINGTON- Deputy Director Cheryl Martin today announced that 33 breakthrough energy projects will receive approximately $66 million from the Advanced Research Projects Agency-Energy (ARPA-E) under two new programs that provide options for a more sustainable and secure American future. One program, Modern Electro/Thermochemical Advancements for Light-metal Systems (METALS), provides $32 million to find cost-effective and energy-efficient manufacturing techniques to process and recycle metals for lightweight vehicles. The other program, Reducing Emissions using

460

Transformative Battery Technology at the National Labs | Department of  

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

Transformative Battery Technology at the National Labs Transformative Battery Technology at the National Labs Transformative Battery Technology at the National Labs January 17, 2012 - 10:45am Addthis Vince Battaglia leads a behind-the-scenes tour of Berkeley Lab's Batteries for Advanced Transportation Technologies Program where researchers aim to improve batteries upon which the range, efficiency, and power of tomorrow's electric cars will depend. Michael Hess Michael Hess Former Digital Communications Specialist, Office of Public Affairs What are the key facts? Berkeley's Batteries for Advanced Transportation Technologies Program is developing lithium-ion technology to power a vehicle for 300 miles. Lithium-sulfur and lithium-air are "unknown known" technologies for the future of electric vehicle batteries.

Note: This page contains sample records for the topic "advanced nuclear transformation" 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

Sandia National Laboratories: Advanced Simulation and Computing  

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

Facebook Facebook Twitter YouTube Flickr RSS Advanced Simulation and Computing Advanced Simulation and Computing Taking on the World's Complex Challenges Advancing Science Frontiers Our research is producing new scientific insights about the world in which we live and assists in certifying the safety and reliability of the nation's nuclear weapons stockpile. Technology Provides the Tools Growth in data and the software and hardware demands needed for physics-based answers and predictive capabilities are driving technology improvements. We could not achieve the breakthroughs we're making without these important tools. Partnerships Accelerate Innovation Partnerships leverage talent and multiply the effectiveness of our research efforts. Impacting Global Issues ASC software and hardware tools solve global issues ranging from nuclear

462

Nuclear structure far from stability  

E-Print Network (OSTI)

Modern nuclear structure theory is rapidly evolving towards regions of exotic short-lived nuclei far from stability, nuclear astrophysics applications, and bridging the gap between low-energy QCD and the phenomenology of finite nuclei. The principal objective is to build a consistent microscopic theoretical framework that will provide a unified description of bulk properties, nuclear excitations and reactions. Stringent constraints on the microscopic approach to nuclear dynamics, effective nuclear interactions, and nuclear energy density functionals, are obtained from studies of the structure and stability of exotic nuclei with extreme isospin values, as well as extended asymmetric nucleonic matter. Recent theoretical advances in the description of structure phenomena in exotic nuclei far from stability are reviewed.

D. Vretenar

2004-09-27T23:59:59.000Z

463

Advanced Materials in MML  

Science Conference Proceedings (OSTI)

... Advanced Materials Characterization. Fusion Wall Development Research by Neutron Depth Profiling. < Previous 1 2 3 Next ». ...

2012-06-12T23:59:59.000Z

464

Functional Materials for Energy | Advanced Materials | ORNL  

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

Energy Storage Fuel Cells Thermoelectrics Separations Materials Catalysis Sensor Materials Polymers and Composites Carbon Fiber Related Research Chemistry and Physics at Interfaces Materials Synthesis from Atoms to Systems Materials Characterization Materials Theory and Simulation Energy Frontier Research Centers Advanced Materials Home | Science & Discovery | Advanced Materials | Research Areas | Functional Materials for Energy SHARE Functional Materials for Energy The concept of functional materials for energy occupies a very prominent position in ORNL's research and more broadly the scientific research sponsored by DOE's Basic Energy Sciences. These materials facilitate the capture and transformation of energy, the storage of energy or the efficient release and utilization of stored energy. A different kind of

465

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

466

Development of Nuclear Energy Systems and Fuels  

Science Conference Proceedings (OSTI)

Mar 2, 2011 ... Session Chair: Meimei Li, Argonne National Lab; Matthew Kerr, US ... The realization of advanced nuclear reactors as a national source of reliable energy .... 2Illinois Institute of Technology; 3Argonne National Laboratory

467

Algorithms for transform selection in multiple-transform video compression  

E-Print Network (OSTI)

Selecting proper transforms for video compression has been based on the rate-distortion criterion. Transforms that appear reasonable are incorporated into a video coding system and their performance is evaluated. This ...

Cai, Xun, S.M. Massachusetts Institute of Technology

2012-01-01T23:59:59.000Z

468

Final Complex Transformation Supplemental Programmatic Environmental Impact Statement October 2008  

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

Volume II Volume II Volume II Chapters 5 - 15 and Chapters 5 - 15 and Appendices A - G Appendices A - G DOE/EIS-0236-S4 National Nuclear Security Administration U.S. Department of Energy October 2008 C C CO O OM MP PL LE EXtransfo o or r rm m mat on COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy, National Nuclear Security Administration TITLE: Final Complex Transformation Supplemental Programmatic Environmental Impact Statement (Complex Transformation SPEIS, DOE/EIS-0236-S4) CONTACTS: For further information on this SPEIS, For general information on the DOE write or call: National Environmental Policy Act (NEPA) process, write or call: Theodore A. Wyka Carol Borgstrom, Director Complex Transformation Office of NEPA Policy and Compliance, GC-20 SPEIS Document Manager U.S. Department of Energy

469

EXHIBIT PROSPECTUS  

Science Conference Proceedings (OSTI)

Materials for Energy and Sustainability. • Nanomaterials. • Nuclear Materials. • Phase Formations, Transformations, and. Stability in Advanced Materials.

470

Advanced Production Planning Models  

SciTech Connect

>This report describes the innovative modeling approach developed as a result of a 3-year Laboratory Directed Research and Development project. The overall goal of this project was to provide an effective suite of solvers for advanced production planning at facilities in the nuclear weapons complex (NWC). We focused our development activities on problems related to operations at the DOE's Pantex Plant. These types of scheduling problems appear in many contexts other than Pantex--both within the NWC (e.g., Neutron Generators) and in other commercial manufacturing settings. We successfully developed an innovative and effective solution strategy for these types of problems. We have tested this approach on actual data from Pantex, and from Org. 14000 (Neutron Generator production). This report focuses on the mathematical representation of the modeling approach and presents three representative studies using Pantex data. Results associated with the Neutron Generator facility will be published in a subsequent SAND report. The approach to task-based scheduling described here represents a significant addition to the literature for large-scale, realistic scheduling problems in a variety of production settings.

JONES,DEAN A.; LAWTON,CRAIG R.; KJELDGAARD,EDWIN A.; WRIGHT,STEPHEN TROY; TURNQUIST,MARK A.; NOZICK,LINDA K.; LIST,GEORGE F.

2000-12-01T23:59:59.000Z

471

ARPA-E Issues Open Call for Transformational Energy Technologies |  

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

Issues Open Call for Transformational Energy Technologies Issues Open Call for Transformational Energy Technologies ARPA-E Issues Open Call for Transformational Energy Technologies March 2, 2012 - 2:31pm Addthis Washington, D.C. - Today, the Advanced Research Projects Agency - Energy (ARPA-E) issued a $150 million funding opportunity open to all transformational energy technologies to support the Obama Administration's all-of-the-above approach to solving our nation's most pressing energy challenges. This Open Funding Opportunity Announcement is a call to our country's brightest scientists, engineers and entrepreneurs to propose early-stage research projects that would not otherwise be able to attract private investment, but could lead to breakthrough energy technologies. This is the second open funding opportunity released under

472

ARPA-E Issues Open Call for Transformational Energy Technologies |  

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

ARPA-E Issues Open Call for Transformational Energy Technologies ARPA-E Issues Open Call for Transformational Energy Technologies ARPA-E Issues Open Call for Transformational Energy Technologies March 2, 2012 - 2:31pm Addthis Washington, D.C. - Today, the Advanced Research Projects Agency - Energy (ARPA-E) issued a $150 million funding opportunity open to all transformational energy technologies to support the Obama Administration's all-of-the-above approach to solving our nation's most pressing energy challenges. This Open Funding Opportunity Announcement is a call to our country's brightest scientists, engineers and entrepreneurs to propose early-stage research projects that would not otherwise be able to attract private investment, but could lead to breakthrough energy technologies. This is the second open funding opportunity released under

473

Optimizing Power Using Transformations  

E-Print Network (OSTI)

: The increasing demand for portable computing has elevated power consumption to be one of the most critical design parameters. A high-level synthesis system, HYPER-LP, is presented for minimizing power consumption in application specific datapath intensive CMOS circuits using a variety of architectural and computational transformations. The synthesis environment consists of high-level estimation of power consumption, a library of transformation primitives, and heuristic/probabilistic optimization search mechanisms for fast and efficient scanning of the design space. Examples with varying degree of computational complexity and structures are optimized and synthesized using the HYPER-LP system. The results indicate that more than an order of magnitude reduction in power can be achieved over current-day design methodologies while maintaining the system throughput; in some cases this can be accomplished while preserving or reducing the implementation area. 1.0 Introduction VLSI research a...

Anantha P. Chandrakasan; Miodrag Potkonjak; Renu Mehra; Jan Rabaey; Robert W. Brodersen

1995-01-01T23:59:59.000Z

474

Fusion Nuclear Science | ORNL  

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

Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research...

475

ENTERPRISE SRS: LEVERAGING ONGOING OPERATIONS TO ADVANCE RADIOACTIVE WASTE MANAGEMENT TECHNOLOGIES  

SciTech Connect

The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, strategic view of SRS as a united endeavor for “all things nuclear” as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with ongoing missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The DOE Savannah River Operations Office, Savannah River Nuclear Solutions, and the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key objective of this initiative is to bridge the gap between promising transformational nuclear materials management advancements and large-scale deployment of the technology by using SRS assets (e.g. facilities, staff, and property) for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the R&D team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform R&D demonstrations at other facilities. Unique to this approach is the fact that these SRS assets will continue to accomplish DOE’s critical nuclear material missions (e.g., processing in H-Canyon and plutonium storage in K-Area). These demonstrations can be accomplished in a more cost-effective manner through the use of existing facilities in conjunction with ongoing missions. Essentially, the R&D program would not need to pay the full operational cost of a facility, just the incremental cost of performing the demonstration. Current Center activities have been focused on integrating advanced safeguards monitoring technology demonstrations into the SRS H-Canyon and advanced location technology demonstrations into K-Area Materials Storage. These demonstrations are providing valuable information to researchers and program owners. In addition these demonstrations are providing the Center with an improved protocol for demonstration management that can be exercised across the entire SRS (and to offsite venues) to ensure that future demonstrations are done efficiently and provide an opportunity to use these unique assets for multiple purposes involving national laboratories, academia, and commercial entities. Key among the envisioned future use of SRS assets is the demonstration of new radioactive waste management technologies critical for advancing the mission needs of the DOE-EM program offices in their efforts to cleanup 107 sites across the United States. Of particular interest is the demonstration of separations technologies in H-Canyon. Given the modular design of H-Canyon, those demonstrations would be accomplished using a process frame. The demonstration equipment would be installed on the process frame and that frame would then be positioned into an H-Canyon cell so that the demonstration is performed in a radiological environment involving prototypic nuclear materials.

Murray, A.; Wilmarth, W.; Marra, J.; Mcguire, P.; Wheeler, V.

2013-05-16T23:59:59.000Z

476

EPRI Intelligent Universal Transformer  

Science Conference Proceedings (OSTI)

The vision of the EPRI ADA Program (Program 124) is to create the technology basis for the distribution system of the future by transforming traditional single-function distribution systems into multifunctional power and information exchange systems with increased reliability, improved performance (lower system losses), better economics, better power quality, and more customer service options. Achieving this vision will require capturing the benefits of new capabilities in power electronics, information ...

2006-12-18T23:59:59.000Z

477

Grid Transformation Workshop Results  

Science Conference Proceedings (OSTI)

In an earlier white paper entitled Needed: A Grid Operating System to Facilitate Grid Transformation; EPRI; Palo Alto, CA: 2011; 1023223, we set the stage for a new grid operating system called Grid 3.0. Since that time we have identified four core research areas that are required to achieve the expected outcome. These research areas are called: seamless geospatial power system model, seamless power system analytics, integrated energy management system and setting-less protection method. While each area ...

2012-05-08T23:59:59.000Z

478