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Note: This page contains sample records for the topic "university research reactor" from the National Library of EnergyBeta (NLEBeta).
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1

University Research Reactor Task Force to the Nuclear Energy Research  

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

University Research Reactor Task Force to the Nuclear Energy University Research Reactor Task Force to the Nuclear Energy Research Advisory Committee University Research Reactor Task Force to the Nuclear Energy Research Advisory Committee In mid-February, 2001 The University Research Reactor (URR) Task Force (TF), a sub-group of the Department of Energy (DOE) Nuclear Energy Research Advisory Committee (NERAC), was asked to: * Analyze information collected by DOE, the NERAC "Blue Ribbon Panel," universities, and other sources pertaining to university reactors including their research and training capabilities, costs to operate, and operating data, and * Provide DOE with clear, near-term recommendations as to actions that should be taken by the Federal Government and a long-term strategy to assure the continued operation of vital university reactor facilities in

2

Two U.S. University Research Reactors to be Converted From Highly...  

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

are here Home Two U.S. University Research Reactors to be Converted From Highly Enriched Uranium to Low-Enriched Uranium Two U.S. University Research Reactors to be Converted...

3

Research reactor usage at the Idaho National Engineering Laboratory in support of university research and education  

SciTech Connect

The Idaho National Engineering Laboratory is a US Department of Energy laboratory which has a substantial history of research and development in nuclear reactor technologies. There are a number of available nuclear reactor facilities which have been incorporated into the research and training needs of university nuclear engineering programs. This paper addresses the utilization of the Advanced Reactivity Measurement Facility (ARMF) and the Coupled Fast Reactivity Measurement Facility (CFRMF) for thesis and dissertation research in the PhD program in Nuclear Science and Engineering by the University of Idaho and Idaho State University. Other reactors at the INEL are also being used by various members of the academic community for thesis and dissertation research, as well as for research to advance the state of knowledge in innovative nuclear technologies, with the EBR-II facility playing an essential role in liquid metal breeder reactor research. 3 refs.

Woodall, D.M.; Dolan, T.J.; Stephens, A.G. (Idaho National Engineering Lab., Idaho Falls, ID (USA))

1990-01-01T23:59:59.000Z

4

Final Site-Specific Decommissioning Inspection Report for the University of Washington Research and Test Reactor  

SciTech Connect

Report of site-specific decommissioning in-process inspection activities at the University of Washington Research and Test Reactor Facility.

Sarah Roberts

2006-10-18T23:59:59.000Z

5

Two U.S. University Research Reactors to be Converted From Highly Enriched  

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

U.S. University Research Reactors to be Converted From Highly U.S. University Research Reactors to be Converted From Highly Enriched Uranium to Low-Enriched Uranium Two U.S. University Research Reactors to be Converted From Highly Enriched Uranium to Low-Enriched Uranium April 11, 2005 - 11:34am Addthis WASHINGTON, D.C. - As part of the Bush administration's aggressive effort to reduce the amount of weapons-grade nuclear material worldwide, Secretary of Energy Samuel W. Bodman announced today that the Department of Energy (DOE) has begun to convert research reactors from using highly-enriched uranium (HEU) to low-enriched uranium fuel (LEU) at the University of Florida and Texas A&M University. This effort, by DOE's National Nuclear Security Administration (NNSA) and the Office of Nuclear Energy, Science and Technology, are the latest steps

6

Modular Pebble Bed Reactor Project, University Research Consortium Annual Report  

Science Conference Proceedings (OSTI)

This project is developing a fundamental conceptual design for a gas-cooled, modular, pebble bed reactor. Key technology areas associated with this design are being investigated which intend to address issues concerning fuel performance, safety, core neutronics and proliferation resistance, economics and waste disposal. Research has been initiated in the following areas: · Improved fuel particle performance · Reactor physics · Economics · Proliferation resistance · Power conversion system modeling · Safety analysis · Regulatory and licensing strategy Recent accomplishments include: · Developed four conceptual models for fuel particle failures that are currently being evaluated by a series of ABAQUS analyses. Analytical fits to the results are being performed over a range of important parameters using statistical/factorial tools. The fits will be used in a Monte Carlo fuel performance code, which is under development. · A fracture mechanics approach has been used to develop a failure probability model for the fuel particle, which has resulted in significant improvement over earlier models. · Investigation of fuel particle physio-chemical behavior has been initiated which includes the development of a fission gas release model, particle temperature distributions, internal particle pressure, migration of fission products, and chemical attack of fuel particle layers. · A balance of plant, steady-state thermal hydraulics model has been developed to represent all major components of a MPBR. Component models are being refined to accurately reflect transient performance. · A comparison between air and helium for use in the energy-conversion cycle of the MPBR has been completed and formed the basis of a master’s degree thesis. · Safety issues associated with air ingress are being evaluated. · Post shutdown, reactor heat removal characteristics are being evaluated by the Heating-7 code. · PEBBED, a fast deterministic neutronic code package suitable for numerous repetitive calculations has been developed. Use of the code has focused on scoping studies for MPBR design features and proliferation issues. Publication of an archival journal article covering this work is being prepared. · Detailed gas reactor physics calculations have also been performed with the MCNP and VSOP codes. Furthermore, studies on the proliferation resistance of the MPBR fuel cycle has been initiated using these code · Issues identified during the MPBR research has resulted in a NERI proposal dealing with turbo-machinery design being approved for funding beginning in FY01. Two other NERI proposals, dealing with the development of a burnup “meter” and modularization techniques, were also funded in which the MIT team will be a participant. · A South African MPBR fuel testing proposal is pending ($7.0M over nine years).

Petti, David Andrew

2000-07-01T23:59:59.000Z

7

Monitoring and Control Research Using a University Reactor and SBWR Test-Loop  

Science Conference Proceedings (OSTI)

The existing hybrid simulation capability of the Penn State Breazeale nuclear reactor was expanded to conduct research for monitoring, operations and control. Hybrid simulation in this context refers to the use of the physical time response of the research reactor as an input signal to a real-time simulation of power-reactor thermal-hydraulics which in-turn provides a feedback signal to the reactor through positioning of an experimental changeable reactivity device. An ECRD is an aluminum tube containing an absorber material that is positioned in the central themble of the reactor kinetics were used to expand the hybrid reactor simulation (HRS) capability to include out-of-phase stability characteristics observed in operating BWRs.

Robert M. Edwards

2003-09-28T23:59:59.000Z

8

Final Site Specific Decommissioning Inspection Report #2 for the University of Washington Research and Test Reactor, Seattle, Washington  

SciTech Connect

During the period of August through November 2006, ORISE performed a comprehensive IV at the University of Washington Research and Test Reactor Facility. The objective of the ORISE IV was to validate the licensee’s final status survey processes and data, and to assure the requirements of the DP and FSSP were met.

S.J. Roberts

2007-03-20T23:59:59.000Z

9

Brookhaven Medical Research Reactor  

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

Medical Research Reactor BMRR The last of the Lab's reactors, the Brookhaven Medical Research Reactor (BMRR), was shut down in December 2000. The BMRR was a three megawatt...

10

Research reactors - an overview  

SciTech Connect

A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

West, C.D.

1997-03-01T23:59:59.000Z

11

EXPERIMENT OPERATIONS PLAN FOR A LOSS-OF-COOLANT ACCIDENT SIMULATION IN THE NATIONAL RESEARCH UNIVERSAL REACTOR  

SciTech Connect

Pressurized water reactor loss-of-coolant accident phenomena are being simulated with a series of experiments in the U-2 loop of the National Research Universal Reactor at Chalk River, Ontario, Canada. The first of these experiments includes up to 45 parametric thermal-hydraulic tests to establish the relationship between the reflood delay time of emergency coolant, the reflooding rate, and the resultant fuel rod cladding peak temperature. This document contains both experiment proposal and assembly proposal information. The intent of this document is to supply information required by the Chalk River Nuclear Laboratories (CRNL), and to identify the planned procedures and data that will be used both to establish readiness to proceed from one test phase to the next and to operate the experiment. Operating control settings and limits are provided for both experimenter systems and CRNL systems. A hazards review summarizes safety issues that have been addressed during the development of the experiment plan.

Russcher, G. E.; Cannon, L. W.; Goodman, R. L.; Hesson, G. M.; King, L. L.; McDuffie, P. N.; Marshall, R. K.; Nealley, C.; Pilger, J. P.; Mohr, C. L.

1981-04-01T23:59:59.000Z

12

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

13

Foreign Research Reactor/Domestic Research Reactor Receipt Coordinator...  

National Nuclear Security Administration (NNSA)

Research ReactorDomestic Research Reactor Receipt Coordinator, Savannah River Nuclear Solutions | National Nuclear Security Administration Our Mission Managing the Stockpile...

14

J. Plasma Fusion Res. SERIES, Vol. 10 (2013) Flibe-Tritium Research for Fission or Fusion Reactors at Kyushu University  

E-Print Network (OSTI)

There is increasing interest in using ionic molten-salt Flibe not only as self-cooled tritium(T)-breeding material in a fusion reactor blanket but also as fuel solvent of molten-salt fission reactors. Application of Flibe to T-breeding fluid for a stellarator-type fusion reactor operated at a high magnetic field brings large simplification of its blanket structure, allowing continuous operation under high-beta plasma conditions. Using mixed Flibe-ThF 4+UF 4 fuel in molten salt fission reactors permits stable long-term operation without fuel exchange. When Flibe or Flinak is irradiated by neutrons, however, acid and corrosive TF is generated, and some T permeates through structural walls. In order to solve these problems, chemical conditions of Flibe are changed using the redox-control reaction, Be+2TF=BeF 2+T 2. In addition, permeation of hydrogen isotopes is lowered by enhancing T recovery rates. Part of Flibe-tritium researches are performed at Idaho National Laboratory (INL) under the Japan-US collaboration work of JUPITER-II. Our own contributions to the topics are shortly introduced in this paper.

Satoshi Fukada

2012-01-01T23:59:59.000Z

15

United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support  

SciTech Connect

The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

Douglas Morrell

2011-03-01T23:59:59.000Z

16

ADMINISTRATION OF ORNL RESEARCH REACTORS  

SciTech Connect

Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)

Casto, W.R.

1962-08-20T23:59:59.000Z

17

2009 University Coal Research Program  

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

2009 University Coal Research Program 2009 University Coal Research Program Description The University Coal Research (UCR) Program provides grants to U.S. colleges and universities to support fundamental research and to develop efficient and environmentally responsible fossil energy technologies. Funded by the U.S. Department of Energy (DOE) Office of Fossil Energy (FE), the program is carried out by DOE's National Energy Technology Laboratory (NETL).

18

Utilization of MIT research reactor by Boston-area universities. Final report, July 1, 1978-June 30, 1980  

SciTech Connect

The guest institutions which used the MITR reactor during 1978-1979 are listed. The participation during previous years since the program began at MIT is also indicated. A summary of the type and amount of participation by local institutions is given.

Clark, L. Jr.; Janghorbani, M.

1981-07-01T23:59:59.000Z

19

University Coal Research | Department of Energy  

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

University Coal Research University Coal Research Universities frequently win Fossil Energy research competitions or join with private companies to submit successful research...

20

Relicensing of the MIT Research Reactor  

SciTech Connect

The Massachusetts Institute of Technology (MIT) Research Reactor (MITR) is owned and operated by MIT, a nonprofit university. The current reactor, MITR-II, is a 5-MW, light water-cooled and heavy water-moderated reactor that uses materials test reactor-type fuel. Documents supporting application to the U.S. Nuclear Regulatory Commission (NRC) for relicensing of MITR were submitted in July 1999. A power upgrade from 5 to 6 MW was also requested. The relicensed reactor (MITR-III) will be the third reactor operated by MIT. This paper describes MITR-I and MITR-II, and design options considered for MITR-III. Selected problems addressed during the relicensing studies are also described, namely core tank aging evaluation, neutronic analysis, thermal-hydraulic analysis, and step reactivity insertion analysis.

Lin-Wen Hu; John A. Bernard; Susan Tucker

2000-06-04T23:59:59.000Z

Note: This page contains sample records for the topic "university research reactor" 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

Collaborative University Research Education | ORNL  

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

Collaborative University Research Collaborative University Research SHARE Collaborative University Research ORNL scientist Jonathan Mielenz works in an anaerobic chamber used to handle biomass-degrading microbes at the Joint Institute for Biological Sciences.Source: ORNL Flickr site With a strong commitment to education, ORNL maintains relationships with many educational institutions and organizations. Many student and faculty programs are administered through Oak Ridge Associated Universities (ORAU) and include opportunities for undergraduates, graduates, postgraduates, faculty, and some pre-college students. The lab also partners with the University of Tennessee in several joint research efforts and though programs aimed at training the next generation of interdisciplinary scientists. These collaborations include:

22

NETL: Onsite Research - University Projects  

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

Onsite Research University Projects The National Energy Technology Laboratory (NETL) is helping to overcome a growing national problem of a diminishing number of new energy...

23

University Turbine Systems Research Program  

SciTech Connect

The primary areas of university research were combustion, aerodynamics/heat transfer, and materials, with a few projects in the area of instrumentation, sensors and life (ISL).

Leitner, Robert; Wenglarz, Richard

2010-12-31T23:59:59.000Z

24

University Advanced Coal Generation Research  

Science Conference Proceedings (OSTI)

In 2012, the Electric Power Research Institute (EPRI) was a sponsor of projects conducted under the auspices of two consortia that support university research for coal-based power generation: the Biomass and Fossil Fuel Research Alliance (BF2RA) in the United Kingdom and the University Turbine System Research (UTSR) program of the United States Department of Energy (DOE). This technical update report describes the progress made in both of those ...

2012-12-12T23:59:59.000Z

25

Advanced Reactor Research and Development Funding Opportunity...  

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

Advanced Reactor Research and Development Funding Opportunity Announcement Advanced Reactor Research and Development Funding Opportunity Announcement The U.S. Department of Energy...

26

University Reactor Conversion Lessons Learned Workshop for the University of Florida  

Science Conference Proceedings (OSTI)

The Department of Energy’s (DOE) Idaho National Laboratory (INL), under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at the University of Florida. This project was successfully completed through an integrated and collaborative effort involving the INL, Argonne National Laboratory (ANL), DOE (Headquarters and Field Office), the Nuclear Regulatory Commission, the Universities, and contractors involved in analyses, fuel design and fabrication, and SNF shipping and disposition. With the work completed with these two universities, and in anticipation of other impending conversion projects, INL convened and engaged the project participants in a structured discussion to capture lessons learned. The objectives of this meeting were to capture the observations, insights, issues, concerns, and ideas of those involved in the reactor conversions so that future efforts can be conducted with greater effectiveness, efficiency, and with fewer challenges.

Eric C. Woolstenhulme; Dana M. Meyer

2007-04-01T23:59:59.000Z

27

University Coal Research | Department of Energy  

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

Science & Innovation Clean Coal Crosscutting Research University Coal Research University Coal Research Clean Coal Turbines Gasification Fuel Cells Hydrogen from Coal Coal...

28

2012 Annual Report Research Reactor Infrastructure Program  

SciTech Connect

The content of this report is the 2012 Annual Report for the Research Reactor Infrastructure Program.

Douglas Morrell

2012-11-01T23:59:59.000Z

29

International Research Reactor Decommissioning Project  

SciTech Connect

Many research reactors have been or will be shut down and are candidates for decommissioning. Most of the respective countries neither have a decommissioning policy nor the required expertise and funds to effectively implement a decommissioning project. The IAEA established the Research Reactor Decommissioning Demonstration Project (R{sup 2}D{sup 2}P) to help answer this need. It was agreed to involve the Philippine Research Reactor (PRR-1) as model reactor to demonstrate 'hands-on' experience as it is just starting the decommissioning process. Other facilities may be included in the project as they fit into the scope of R{sup 2}D{sup 2}P and complement to the PRR-1 decommissioning activities. The key outcome of the R{sup 2}D{sup 2}P will be the decommissioning of the PRR-1 reactor. On the way to this final goal the preparation of safety related documents (i.e., decommissioning plan, environmental impact assessment, safety analysis report, health and safety plan, cost estimate, etc.) and the licensing process as well as the actual dismantling activities could provide a model to other countries involved in the project. It is expected that the R{sup 2}D{sup 2}P would initiate activities related to planning and funding of decommissioning activities in the participating countries if that has not yet been done.

Leopando, Leonardo [Philippine Nuclear Research Institute, Quezon City (Philippines); Warnecke, Ernst [International Atomic Energy Agency, Vienna (Austria)

2008-01-15T23:59:59.000Z

30

University Coal Research | Department of Energy  

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

University Coal Research University Coal Research University Coal Research Universities frequently win Fossil Energy research competitions or join with private companies to submit successful research proposals. Today approximately 16 percent of the Office of Fossil Energy's annual R&D funding goes to academic institutions. The University Coal Research Program Universities have traditionally fared well in the Energy Department's open competitions for federal research grants and contracts. In 1979, however, the Department took an additional step to encourage greater university participation in its fossil energy program. The agency set aside funding for a special university-only competition that required professors to conduct cutting-edge research alongside students who were pursuing advanced

31

Reactor sharing experience at the MIT research reactor  

SciTech Connect

This paper provides a number of examples of how educational institutions in the Boston area and elsewhere that do not possess nuclear reactors for training and research purposes have successfully enriched their programs through utilization of the Massachusetts Institute of Technology Research Reactor (MITR) with assistance from the Reactor Sharing Program of the US Department of Energy (DOE).

Clark, L. Jr.; Fecych, W.; Young, H.H.

1985-01-01T23:59:59.000Z

32

Sodium fast reactor safety and licensing research plan. Volume II.  

SciTech Connect

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d'%C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

2012-05-01T23:59:59.000Z

33

Decommssioning Of Research Reactor: Problemsand Experience  

E-Print Network (OSTI)

The study of the preparation for decommissioning the Research Reactor in Salaspils (Latvia) and the experience of decommissioning the Research Reactor in Sosny (Belarus) show that the problem of decommissioning research reactors is acute for countries that have no NPPs or their own nuclear industry. It also is associated with regulatory framework, planning and design, dismantling technologies, decontamination of radioactive equipment and materials, spent fuel and radioactive waste management, etc. 1. INTRODUCTION According to the IAEA research reactor database, there are about 300 research reactors worldwide [1]. At present over 30% of them have lifetimes of more than 35 years, 60% of more than 25 years. After the Chernobyl accident, significant efforts were made by many countries to modernize old research reactors aiming, first of all, at ensuring safe operation. However, a large number of aging research reactors will be facing shutdown in the near future. The problem of decommis...

Alexander Mikhalevich

2000-01-01T23:59:59.000Z

34

Research universities for the 21st century  

SciTech Connect

The `public outcomes` from research universities are educated students and research that extends the frontiers of knowledge. Measures of these `public outcomes` are inadequate to permit either research or education consumers to select research universities based on quantitative performance data. Research universities annually spend over $20 billion on research; 60% of these funds are provided by Federal sources. Federal funding for university research has recently grown at an annual rate near 6% during a time period when other performers of Federal research have experienced real funding cuts. Ten universities receive about 25% of the Federal funds spent on university research. Numerous studies of US research universities are reporting storm clouds. Concerns include balancing research and teaching, the narrow focus of engineering education, college costs, continuing education, and public funding of foreign student education. The absence of research on the `public outcomes` from university research results in opinion, politics, and mythology forming the basis of too many decisions. Therefore, the authors recommend studies of other nations` research universities, studies of various economic models of university research, analysis of the peer review process and how well it identifies the most capable research practitioners and at what cost, and studies of research university ownership of intellectual property that can lead to increased `public outcomes` from publicly-funded research performed by research universities. They advocate two practices that could increase the `public outcomes` from university research. These are the development of science roadmaps that link science research to `public outcomes` and `public outcome` metrics. Changes in the university research culture and expanded use of the Internet could also lead to increased `public outcomes`. They recommend the use of tax incentives to encourage companies to develop research partnerships with research universities.

Gover, J. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); Huray, P.G. [Univ. of South Carolina, Columbia, SC (United States)] [Univ. of South Carolina, Columbia, SC (United States)

1998-05-01T23:59:59.000Z

35

BNL | Our History: Reactors as Research Tools  

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

> See also: Accelerators > See also: Accelerators Brookhaven History: Using Reactors as Research Tools BGRR Brookhaven Graphite Research Reactor The Brookhaven Graphite Research Reactor (BGRR) was the Laboratory's first big machine and the first peace-time reactor built in the United States following World War II. The reactor's primary mission was to produce neutrons for scientific experimentation and to refine reactor technology. At the time, the BGRR could accommodate more simultaneous experiments than any other reactor. Scientists and engineers from every corner of the U.S. came to use the reactor, which was not only a source of neutrons for experiments, but also an excellent training facility. Researchers used the BGRR's neutrons as tools for studying atomic nuclei and the structure of solids, and to investigate many physical, chemical and

36

Research Reactors Division | Neutron Science | ORNL  

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

is responsible for operation of the High Flux Isotope Reactor. Operating at 85 MW, HFIR is the highest flux reactor-based source of neutrons for research in the United States,...

37

Independent Confirmatory Survey Report for the University of Arizona Nuclear Reactor Laboratory, Tucson, Arizona  

SciTech Connect

The University of Arizona (University) research reactor is a TRIGA swimming pool type reactor designed by General Atomics and constructed at the University in 1958. The reactor first went into operation in December of 1958 under U.S. Nuclear Regulatory Commission (NRC) license R-52 until final shut down on May 18, 2010. Initial site characterization activities were conducted in February 2009 during ongoing reactor operations to assess the radiological status of the Nuclear Reactor Laboratory (NRL) excluding the reactor tank, associated components, and operating systems. Additional post-shutdown characterization activities were performed to complete characterization activities as well as verify assumptions made in the Decommissioning Plan (DP) that were based on a separate activation analysis (ESI 2009 and WMG 2009). Final status survey (FSS) activities began shortly after the issuance of the FSS plan in May 2011. The contractor completed measurement and sampling activities during the week of August 29, 2011.

Nick A. Altic

2011-11-11T23:59:59.000Z

38

History of Research Reactors at Brookhaven  

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

History of Research Reactors at Brookhaven History of Research Reactors at Brookhaven Brookhaven National Laboratory has three nuclear reactors on its site that were used for scientific research. The reactors are all shut down, and the Laboratory is addressing environmental issues associated with their operations. photo of BGRR Brookhaven Graphite Research Reactor - Beginning operations in 1950, the graphite reactor was used for research in medicine, biology, chemistry, physics and nuclear engineering. One of the most significant achievements at this facility was the development of technetium-99m, a radiopharmaceutical widely used to image almost any organ in the body. The graphite reactor was shut down in 1969. Parts of it have been decommissioned, with the remainder to be addressed by 2011. More history

39

Final report. U.S. Department of Energy University Reactor Sharing Program  

SciTech Connect

Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

Bernard, John A

2003-01-21T23:59:59.000Z

40

Brookhaven Graphite Research Reactor | Environmental Restoration...  

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

Brookhaven Graphite Research Reactor(BGRR) BGRR Overview BGRR Complex Description Decommissioning Decision BGRR Complex Cleanup Actions BGRR Documents BGRR Science &...

Note: This page contains sample records for the topic "university research reactor" 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

FOREIGN RESEARCH AND POWER REACTOR PRELIMINARY LIST  

SciTech Connect

Foreign research and power reactors are tabulated. Nuclear power buildup goals are given for each nation on which information is available. (J.H.D.)

Ullmann, J.W.

1959-02-26T23:59:59.000Z

42

Cleanup at the Brookhaven Graphite Research Reactor  

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

Graphite Research Reactor placeholder Remotely operated robot known as a BROKK manipulator In April 2005, the Department of Energy (DOE), the Lab, and the regulatory agencies...

43

Energy Research at the University of Regina  

E-Print Network (OSTI)

Energy Research at the University of Regina The University of Regina has long understood, there was recognition that the availability of energy is fundamental to that growth. For these reasons, the University made energy (as a part of energy and environment) one of its thematic research areas in 2000

Argerami, Martin

44

Low Dose Radiation Research Program: Universities  

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

Universities Universities | Duke University | Loma Linda University | Northwestern University | University of Chicago | University of California Davis | Northwestern University University of Chicago University of California Davis Effects of Low Dose Irradiation on NF-ÎşB Signaling Networks and Mitochondria Principal Investigator: Dr. Gayle Woloschak DOE Low Dose Research Program Projects Low dose-low dose rate irradiation leads to long term changes in numbers of mitochondria and mitochondrial genomes - Principal Investigator: Gayle Woloschak, Professor, Department of Radiation Oncology, Northwestern University, Chicago, IL, USA NF-ÎşB-mediated pro-survival network in low dose radiation-induced adaptive protection - Principal Investigator: Jian Jian Li, Professor, Department of Radiation Oncology, University of California Davis, Davis,

45

Conversion and standardization of US university reactor fuels using LEU, status 1989  

SciTech Connect

In 1986, the US Department of Energy initiated a program to change the fuel used in most of the US university research reactors using HEU (93%) to LEU({lt}20{percent}) in order to minimize the risk of theft or diversion of this weapons-useable material. An important consideration in the LEU conversion planning process has been the desire to standardize the fuels that are used and to enhance the performance and utilization of the reactors. This paper describes the current status of this conversion process and the plans and schedules to complete an orderly transition from HEU to LEU fuel in most of these reactors. To date, three university reactors have been converted to LEU fuel, completed safety documentation for three reactors is being evaluated by the USNRC, and work on the safety documentation for six reactors is in progress. 13 refs., 9 tabs.

Brown, K.R.; Matos, J.E. (EG and G Idaho, Inc., Idaho Falls, ID (USA); Argonne National Lab., IL (USA))

1989-01-01T23:59:59.000Z

46

Research - CECM - Simon Fraser University  

E-Print Network (OSTI)

Heinz Bauschke - Research. Research Interests. Optimization, Convexity, Functional Analysis, Monotone Operator Theory, Medical Imaging, Symbolic ...

47

Nanyang Technological University's New Energy Research Institute...  

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

Nanyang Technological University's New Energy Research Institute: Grids, Energy Systems and Sustainable Building Technologies Programs Speaker(s): King Jet Tseng Subodh Mhaisalkar...

48

WEB RESOURCES: Superalloy University Research Programs  

Science Conference Proceedings (OSTI)

Feb 8, 2007 ... This directory provides links to superalloy research programs at universities around the world. Two formats of the information are presented for ...

49

Applications from Universities and Other Research Institutions...  

Office of Science (SC) Website

Closed Funding Opportunity Announcements (FOAs) Closed Lab Announcements Award Search Peer Review Policies EFRCs FOA Applications from Universities and Other Research...

50

Conversion and standardization of university reactor fuels using low-enrichment uranium: Plans and schedules  

SciTech Connect

The highly-enriched uranium (HEU) fuel used in twenty United States university reactors can be viewed as contributing to the risk of theft or diversion of weapons-useable material. To minimize this risk, the US Nuclear Regulatory Commission issued its final rule on ''Limiting the Use of Highly Enriched Uranium in Domestically Licensed Research and Test Reactors,'' in February 1986. This paper describes the plans and schedules developed by the US Department of Energy to coordinate an orderly transition from HEU to LEU fuel in most of these reactors. An important element in the planning process has been the desire to standardize the LEU fuels used in US university reactors and to enhance the performance and utilization of a number of these reactors. The program is estimated to cost about $10 million and to last about five years.

Young, H.H.; Brown, K.R.; Matos, J.E.

1986-01-01T23:59:59.000Z

51

Reactor operations Brookhaven medical research reactor, Brookhaven high flux beam reactor informal monthly report  

SciTech Connect

This document is the April 1995 summary report on reactor operations at the Brookhaven Medical Research Reactor and the Brookhaven High Flux Beam Reactor. Ongoing experiments/irradiations in each are listed, and other significant operations functions are also noted. The HFBR surveillance testing schedule is also listed.

Hauptman, H.M.; Petro, J.N.; Jacobi, O. [and others

1995-04-01T23:59:59.000Z

52

CECM: Research - Simon Fraser University  

E-Print Network (OSTI)

Research. Symbolic Computation. These projects use symbolic computation in an essential way both in the process of discovery and proof. Each aims at ...

53

Research 2006 Michigan Technological University  

E-Print Network (OSTI)

. for thesis-based students, experience in conducting original scientific research and engineering design design and structured decision-making, which is of growing importance in all technical-social- political

54

Clark Atlanta Universities (CAU) Energy Related Research Capabilities...  

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

Clark Atlanta Universities (CAU) Energy Related Research Capabilities Clark Atlanta Universities (CAU) Energy Related Research Capabilities How energy related research has helped...

55

Storage research in industry and universities  

Science Conference Proceedings (OSTI)

We review activities at universities and industrial research centers in the storage area, but also briefly mention topics such as processor design, operating systems, databases, and performance analysis. Our starting point is the Berkeley RAID proposal ...

Alexander Thomasian

2010-06-01T23:59:59.000Z

56

Carnegie Mellon University Research Showcase  

E-Print Network (OSTI)

methods became a major concern of my research, and the present book began to evolve. The modern computer me that these characteristics form a sounder conceptual basis for programming than those. This implies that the programmer should master formal proof methods, not in order to give a formal proof

Reynolds, John C.

57

The Universe Adventure - Current Research  

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

Current Research Current Research When launched, the Supernova Acceleration Probe (SNAP) will study the effects of dark energy by surveying distant type Ia supernovae and making detailed measurements of weak gravitational lensing. With the new Large Hadron Collider (LHC) at CERN nearing full completion, experimentalists will soon be able to test certain elements of String Theory. While not definitive, these tests will cast some light upon the theory's parameters and may even provide clues into the identity of dark matter. Meanwhile, theorists continue to investigate the implications of String Theory for Big Bang cosmology, particularly the effects of strings on cosmic inflation. As particle physicists eagerly await the results from the new LHC, observational cosmologists are busy developing astronomical experiments,

58

Brookhaven Graphite Research Reactor | Environmental Restoration Projects |  

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

Brookhaven Graphite Research Reactor Documents Brookhaven Graphite Research Reactor Documents Feasibility Study (PDF) Proposed Remedial Action Plan (PDF) Record of Decision (PDF) RD/RA Work Plan for the BGRR Pile (PDF) RD/RA Work Plan for the Bioshield (PDF) RD/RA Work Plan for the BGRR Cap (PDF) Brookhaven Graphite Research Reactor Explanation of Significant Differences (PDF) (4/12) NYSDEC Approval Letter for BGRR ESD (PDF) (5/12) USEPA Approval Letter for BGRR ESD (PDF) (6/12) DOE BGRR ESD Transmittal Letter (PDF) (7/12) Remedial Design Implementation Report (PDF) (12/11) Completion Reports Removal of the Above-Ground Ducts and Preparation of the Instrument House (708) for Removal (PDF) - April 2002 Below-Ground Duct Outlet Air Coolers, Filters and Primary Liner Removal (PDF) - April 2005 Canal and Deep Soil Pockets Excavation and Removal (PDF) - August

59

License extension for the MIT research reactor  

Science Conference Proceedings (OSTI)

On February 8, 1995, the U.S. Nuclear Regulatory Commission (NRC) amended the operating license for the Massachusetts Institute of Technology (MIT) research reactor (MITR) by extending its expiration date from May 7, 1996, to August 8, 1999. This increase of 2.25 yr in the duration of the license was for the purpose of recapturing construction time. Extensions of this type have routinely been granted to power plants. The significance of the present action is that it is the first such extension ever granted to a research reactor. This paper describes the basis for the amendment request and the supporting safety analysis.

Bernard, J.A. [Massachusetts Institute of Technology, Cambridge, MA (United States)

1995-12-31T23:59:59.000Z

60

Scintillation Materials Research Center University of Tennessee  

E-Print Network (OSTI)

Conference (NSS-MIC) in Knoxville, TN, the NNSA NA-22 Office of Nonproliferation and Verification Research Materials" the NNSA NA-22 Office of Nonproliferation and Verification Research and Development, University and priorities. 2. NNSA: The SMRC staff participated in the NNSA NA-22 Office of Nonproliferation

Tennessee, University of

Note: This page contains sample records for the topic "university research reactor" 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

Safer nuclear reactors could result from Los Alamos research  

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

Calendar Video Newsroom News Releases News Releases - 2010 March Safer nuclear reactors could result from research Safer nuclear reactors could result from Los...

62

The triple axis spectrometer at the new research reactor OPAL ...  

Science Conference Proceedings (OSTI)

... The triple axis spectrometer at the new research reactor OPAL in Australia. ... The TAS will be based on a thermal beam at the reactor face. ...

63

University Research Consortium annual review meeting program  

Science Conference Proceedings (OSTI)

This brochure presents the program for the first annual review meeting of the University Research Consortium (URC) of the Idaho National Engineering Laboratory (INEL). INEL is a multiprogram laboratory with a distinctive role in applied engineering. It also conducts basic science research and development, and complex facility operations. The URC program consists of a portfolio of research projects funded by INEL and conducted at universities in the United States. In this program, summaries and participant lists for each project are presented as received from the principal investigators.

NONE

1996-07-01T23:59:59.000Z

64

Conversion and standardization of university reactor fuels using low-enrichment uranium - options and costs  

SciTech Connect

The highly-enriched uranium (HEU) fuel used in twenty United States university reactors can be viewed as contributing to the risk of theft or diversion of weapons-useable material. The US Nuclear Regulatory Commission has issued a policy statement expressing its concern and has published a proposed rule on limiting the use of HEU in NRC-licensed non-power reactors. The fuel options, functional impacts, licensing, and scheduling of conversion and standardization of these reactor fuels to use of low-enrichment uranium (LEU) have been assessed. The university reactors span a wide range in form and function, from medium-power intense neutron sources where HEU fuel may be required, to low-power training and research facilities where HEU fuel is unnecessary. Conversion provides an opportunity to standardize university reactor fuels and improve reactor utilization in some cases. The entire program is estimated to cost about $10 million and to last about five years. Planning for conversion and standardization is facilitated by the US Department of Energy. 20 refs., 1 tab.

Harris, D.R.; Matos, J.E.; Young, H.H.

1985-01-01T23:59:59.000Z

65

Basic and Applied Science Research Reactors - Reactors designed...  

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

BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th...

66

Research and Medical Isotope Reactor Supply | Y-12 National Security...  

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

Research and Medical ... Research and Medical Isotope Reactor Supply Our goal is to fuel research and test reactors with low-enriched uranium. Y-12 tops the short list of the...

67

University Coal Research/Historically Black Colleges and Universities &  

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

University Coal Research/Historically Black Colleges and Universities & Other Minority Institutions Contractor Review Mtg. University Coal Research/Historically Black Colleges and Universities & Other Minority Institutions Contractor Review Mtg. June 3, 2003 Table of Contents Disclaimer Papers and Presentations Day 1 - Session A Day 1 - Session B Day 2 - Session A Day 2 - Session B Posters - Project Accomplishments 2000 Awards Abstracts of 2002 Awards Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government or any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

68

University Coal Research / Historically Black Colleges and Universities &  

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

University Coal Research / Historically Black Colleges and Universities & Other Minority Institutions Contractors University Coal Research / Historically Black Colleges and Universities & Other Minority Institutions Contractors Review Meeting June 9-10, 2004 Table of Contents Disclaimer Papers and Presentations Opening Session Session A Session B Abstract Only Abstract & Poster Presentation of Project Accomplishments Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government or any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

69

FACT SHEET: Clean Coal University Research Awards and Project...  

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

FACT SHEET: Clean Coal University Research Awards and Project Descriptions FACT SHEET: Clean Coal University Research Awards and Project Descriptions As part of President Obama's...

70

EA-0965: Cancer Research Center Indiana University School of...  

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

5: Cancer Research Center Indiana University School of Medicine, Argonne, Illinois EA-0965: Cancer Research Center Indiana University School of Medicine, Argonne, Illinois SUMMARY...

71

LEHIGH UNIVERSITY RESEARCH AND TESTING AGREEMENT  

E-Print Network (OSTI)

, the Project. Article 4 - Costs, Billings and Other Support 4.1 It is agreed to and understood by the parties, the research and testing project contemplated by this Agreement is of mutual interest and benefit to University have the following meanings: 1.1 "Project" shall mean the project titled

Gilchrist, James F.

72

The University of Maryland Energy Research Center  

E-Print Network (OSTI)

. ElECTRoChEMiCAl ENERgy CoNvERSioN ANd SToRAgE Batteries Fluctuationsinrenewableenergy supply make new Energy Engineering works with industry to increase the efficiency of Heating, Ventilation, and AirThe University of Maryland Energy Research Center Join Us in Building a Sustainable Energy Future

Rubloff, Gary W.

73

Brookhaven Lab Completes Decommissioning of Graphite Research Reactor:  

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

Brookhaven Lab Completes Decommissioning of Graphite Research Brookhaven Lab Completes Decommissioning of Graphite Research Reactor: Reactor core and associated structures successfully removed; waste shipped offsite for disposal Brookhaven Lab Completes Decommissioning of Graphite Research Reactor: Reactor core and associated structures successfully removed; waste shipped offsite for disposal September 1, 2012 - 12:00pm Addthis The Brookhaven Graphite Research Reactor’s bioshield, which contains the 700-ton reactor core, is shown prior to decommissioning. The Brookhaven Graphite Research Reactor's bioshield, which contains the 700-ton reactor core, is shown prior to decommissioning. Pictured here is the Brookhaven Graphite Research Reactor, where major decommissioning milestones were recently reached after the remaining radioactive materials from the facility’s bioshield were shipped to a licensed offsite disposal facility.

74

Ames Laboratory Research Reactor Facility Ames, Iowa  

Office of Legacy Management (LM)

,, *' ; . Final Radiological Condition of the Ames Laboratory Research Reactor Facility Ames, Iowa _, . AGENCY: Office of Operational Safety, Department of Energy ' ACTION: Notice of Availability of Archival Information Package SUMMARY: The'Office of Operational Safety of the Department O i Energy (DOE) has reviewed documentation relating to the decontamination and decommissioning operations conducted at the Ames Laboratory Research Reactor Facility, Ames, Iowa and has prepared an archival informati0.n package to permanently document the results of the action and the site conditions and use restriction placed on the . site at the tim e of release. This review is based on post-decontamination survey data and other pertinent documentation referenced in and included in the archival package. The material and

75

University of Florida--US Department of Energy 1994-1995 reactor sharing program  

SciTech Connect

The grant support of $24,250 (1994-95?) was well used by the University of Florida as host institution to support various educational institutions in the use of UFTR Reactor. All users and uses were screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research was not funded by grants for contract funding from outside sources. Over 12 years, the program has been a key catalyst for renewing utilization of UFTR both by external users around the State of Florida and the Southeast and by various faculty members within the University of Florida. Tables provide basic information about the 1994-95 program and utilization of UFTR.

Vernetson, W.G.

1996-06-01T23:59:59.000Z

76

Sterile Neutrino Search Using China Advanced Research Reactor  

E-Print Network (OSTI)

We study the feasibility of a sterile neutrino search at the China Advanced Research Reactor by measuring $\\bar {\

Guo, Gang; Ji, Xiangdong; Liu, Jianglai; Xi, Zhaoxu; Zhang, Huanqiao

2013-01-01T23:59:59.000Z

77

Reactor operations: Brookhaven Medical Research Reactor, Brookhaven High Flux Beam Reactor. Informal report, June 1995  

Science Conference Proceedings (OSTI)

Part one of this report gives the operating history of the Brookhaven Medical Research Reactor for the month of June. Also included are the BMRR technical safety surveillance requirements record and the summary of BMRR irradiations for the month. Part two gives the operating histories of the Brookhaven High Flux Beam Reactor and the Cold Neutron Facility at HFBR for June. Also included are the HFBR technical safety surveillance requirements record and the summary of HFBR irradiations for the month.

NONE

1995-06-01T23:59:59.000Z

78

Reactor operations: Brookhaven Medical Research Reactor, Brookhaven High Flux Beam Reactor. Informal report, July 1995  

Science Conference Proceedings (OSTI)

Part one of this report gives the operating history for the Brookhaven Medical Research Reactor for the month of July. Also included are the BMRR technical safety surveillance requirements record and the summary of BMRR irradiations for the month. Part two gives the operating histories for the Brookhaven High Flux Beam Reactor and the Cold Neutron Source Facility for the month of July. Also included are the HFBR technical safety surveillance requirements record and the summary of HFBR irradiations for the month.

NONE

1995-07-01T23:59:59.000Z

79

SunShot Initiative: Multidisciplinary University Research Initiative: High  

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

Multidisciplinary University Multidisciplinary University Research Initiative: High Operating Temperature Fluids to someone by E-mail Share SunShot Initiative: Multidisciplinary University Research Initiative: High Operating Temperature Fluids on Facebook Tweet about SunShot Initiative: Multidisciplinary University Research Initiative: High Operating Temperature Fluids on Twitter Bookmark SunShot Initiative: Multidisciplinary University Research Initiative: High Operating Temperature Fluids on Google Bookmark SunShot Initiative: Multidisciplinary University Research Initiative: High Operating Temperature Fluids on Delicious Rank SunShot Initiative: Multidisciplinary University Research Initiative: High Operating Temperature Fluids on Digg Find More places to share SunShot Initiative: Multidisciplinary

80

Chicago Pile reactors create enduring research legacy - Argonne's  

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

Chicago Pile reactors create enduring research Chicago Pile reactors create enduring research legacy About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy

Note: This page contains sample records for the topic "university research reactor" 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

Research Universities: Core of the US Science and Technology System  

E-Print Network (OSTI)

Tuzin, “Equilibrium in the Research University”, Change,for Postwar Scientific Research. July 1945. Reprinted ingraduate programs. CSHE Research & Occasional Paper Series

Atkinson, Richard

2007-01-01T23:59:59.000Z

82

Industry/University Consortium for ATS research  

SciTech Connect

The Industry/University ATS research program is the result of two planning workshops. Workshop I was held April 8--10, 1991 and had the goal of identifying research needs for advanced gas turbine cycles that would permit rapid commercialization of cycles with significant improvements over the machines currently under development, in terms of the cost of electricity produced and the environmental burdens resulting from their use in power producing. Workshop II was held in January 1992 and continued the identification of the research needs to develop advanced gas turbine systems. The goals established for the ATS systems were: (1) efficiency exceeding 60% for large utility turbine system and 15% improvement in heat rate for industrial systems; (2) busbar energy costs 10% less than current state of the art and (3) fuel flexible designs. In addition Workshop II participants agreed that an industry driven research consortium was an acceptable mechanism to achieve base technology development needs.

Allen, R.P.; Golan, L.P.

1993-11-01T23:59:59.000Z

83

NETL: Events - 2011 University Turbine Systems Research Workshop  

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

University Turbine Systems Research Workshop October 25 - 27 2011 The Blackwell Inn - Ohio State University 2110 Tuttle Park Place Columbus, Ohio 43210 (614)247-4000 TABLE OF...

84

The role of Chinese universities in enterprise---university research collaboration  

Science Conference Proceedings (OSTI)

In this paper the role of Chinese universities in enterprise---university research collaboration is investigated. This study focuses on a special aspect of the collaboration--co-authored articles. The two cases are analyzed: (1) research collaboration ... Keywords: Chinese universities, Co-authored articles, Enterprise-university research collaboration, Mathematical orientation

Liming Liang; Lixin Chen; Yishan Wu; Junpeng Yuan

2012-01-01T23:59:59.000Z

85

Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program  

DOE Green Energy (OSTI)

Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.

Not Available

1987-05-01T23:59:59.000Z

86

Research Reactors Division | ORNL Neutron Sciences  

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

Reactors Division (RRD) is responsible for operation of the High Flux Isotope Reactor (HFIR). Operating at 85 MW, HFIR is the highest flux reactor-based source of neutrons for...

87

Research and Services at the Alabama A&M University Research...  

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

Research and Services at the Alabama A&M University Research Institute Research and Services at the Alabama A&M University Research Institute An overview of services and research...

88

Inspection methods for physical protection. Task II. Review of research reactor licensees' physical security practices  

SciTech Connect

Security systems and security procedures for the AFRRI reactor, the University of Maryland TRIGA reactor, and the University of Virginia CAVALIER and UVAR reactors are described.

1980-07-03T23:59:59.000Z

89

Abstracts and research accomplishments of university coal research projects  

SciTech Connect

The Principal Investigators of the grants supported by the University Coal Research Program were requested to submit abstracts and highlight accomplishments of their projects in time for distribution at a grantees conference. This book is a compilation of the material received in response to the request. Abstracts discuss the following area: coal science, coal surface science, reaction chemistry, advanced process concepts, engineering fundamentals and thermodynamics, environmental science.

Not Available

1991-06-01T23:59:59.000Z

90

Nuclear reactor and materials science research: Technical report, May 1, 1985-September 30, 1986  

Science Conference Proceedings (OSTI)

Throughout the 17-month period of its grant, May 1, 1985-September 30, 1986, the MIT Research Reactor (MITR-II) was operated in support of research and academic programs in the physical and life sciences and in related engineering fields. The reactor was operated 4115 hours during FY 1986 and for 6080 hours during the entire 17-month period, an average of 82 hours per week. Utilization of the reactor during that period may be classified as follows: neutron beam tube research; nuclear materials research and development; radiochemistry and trace analysis; nuclear medicine; radiation health physics; computer control of reactors; dose reduction in nuclear power reactors; reactor irradiations and services for groups outside MIT; MIT Research Reactor. Data on the above utilization for FY 1986 show that the MIT Nuclear Reactor Laboratory (NRL) engaged in joint activities with nine academic departments and interdepartmental laboratories at MIT, the Charles Stark Draper Laboratory in Cambridge, and 22 other universities and nonprofit research institutions, such as teaching hospitals.

Not Available

1987-05-11T23:59:59.000Z

91

Global estimation of potential unreported plutonium in thermal research reactors  

SciTech Connect

As of November, 1993, 303 research reactors (research, test, training, prototype, and electricity producing) were operational worldwide; 155 of these were in non-nuclear weapon states. Of these 155 research reactors, 80 are thermal reactors that have a power rating of 1 MW(th) or greater and could be utilized to produce plutonium. A previously published study on the unreported plutonium production of six research reactors indicates that a minimum reactor power of 40 MW (th) is required to make a significant quantity (SQ), 8 kg, of fissile plutonium per year by unreported irradiations. As part of the Global Nuclear Material Control Model effort, we determined an upper bound on the maximum possible quantity of plutonium that could be produced by the 80 thermal research reactors in the non-nuclear weapon states (NNWS). We estimate that in one year a maximum of roughly one quarter of a metric ton (250 kg) of plutonium could be produced in these 80 NNWS thermal research reactors based on their reported power output. We have calculated the quantity of plutonium and the number of years that would be required to produce an SQ of plutonium in the 80 thermal research reactors and aggregated by NNWS. A safeguards approach for multiple thermal research reactors that can produce less than 1 SQ per year should be conducted in association with further developing a safeguards and design information reverification approach for states that have multiple research reactors.

Dreicer, J.S.; Rutherford, D.A.

1996-09-01T23:59:59.000Z

92

Experimental and simulated dosimetry of the University of Utah triga reactor.  

E-Print Network (OSTI)

??Simulated neutron and gamma transport enable the gamma dose to be estimated at the surface of the University of Utah TRIGA Reactor UUTR pool. These… (more)

Marble, Benjamin James

2010-01-01T23:59:59.000Z

93

University Launches Website for FIU Research Sponsored by EM | Department  

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

University Launches Website for FIU Research Sponsored by EM University Launches Website for FIU Research Sponsored by EM University Launches Website for FIU Research Sponsored by EM July 11, 2013 - 12:00pm Addthis The Applied Research Center at Florida International University covers four major environmental cleanup areas: radioactive waste processing, facility deactivation and decommissioning, soil and groundwater remediation and information technology development for environmental management. The Applied Research Center at Florida International University covers four major environmental cleanup areas: radioactive waste processing, facility deactivation and decommissioning, soil and groundwater remediation and information technology development for environmental management. MIAMI - A new website features research performed under a cooperative

94

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL STUDIES  

E-Print Network (OSTI)

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL STUDIES PERCENT STUDENTS 1,643 4.4% #12;CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL.0% INTERNATIONAL STUDENTS 82 1.7% #12;CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL

de Lijser, Peter

95

University of Dayton Research Institute | Open Energy Information  

Open Energy Info (EERE)

Dayton Research Institute Jump to: navigation, search Name University of Dayton Research Institute Address 300 College Park Place Dayton, Ohio Zip 45469-0101 Website http:...

96

Brookhaven Graphite Research Reactor Workshop | Department of Energy  

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

Services » Site & Facility Restoration » Deactivation & Services » Site & Facility Restoration » Deactivation & Decommissioning (D&D) » D&D Workshops » Brookhaven Graphite Research Reactor Workshop Brookhaven Graphite Research Reactor Workshop The Brookhaven Graphite Research Reactor (BGRR) was the first reactor built in the U.S. for peacetime atomic research following World War II. Construction began in 1947 and the reactor started operating in August 1950. In the next 18 years, an estimated 25,000 scientific experiments were carried out at the BGRR using neutrons produced in the facility's 700-ton graphite core, made up of more than 60,000 individual graphite blocks. The BGRR was placed on standby in 1968 and then permanently shut down as the next-generation reactor, the High Flux Beam Reactor (HFBR), was

97

HAZARDS SUMMARY FOR THE L-77 LABORATORY REACTOR FOR THE UNIVERSITY OF NEVADA, RENO  

SciTech Connect

A hazards summary report for the planned installation and operation of an L-77 Laboratory Reactor of the University of Nevada is presented. Site data, including information on the geography, geology, seismology, climatology, and hydrology of the area in which the reactor will be installed are included. The reactor site and administiation of the reactor facility are described along with the reactor, its uses, and its performance characteristics. Analyses of the nuclear, radiation, and operational hazards are also included. (auth)

1962-09-14T23:59:59.000Z

98

Progress report on the conversion of the Purdue University reactor, PUR-1, from HEU to LEU  

Science Conference Proceedings (OSTI)

The effort for the conversion of the Purdue University Research Reactor, PUR-1, began in August, 2005, and will be completed in late 2007. Initial low-enriched uranium (LEU) assemblies will be inserted into the core in September, and the final core load is expected to be completed by October 2007. This paper summarizes the work performed to date, and the expectations for the work remaining to complete the project. The PUR-1 conversion has been a collaborative effort with Purdue, Idaho National Laboratory, Argonne National Laboratory participating under the auspices of the U.S. Department of Energy-Global Threat Reduction. Construction of PUR-1 began in 1961, and it was initially licensed by the U.S. Nuclear Regulatory Commission in August of 1962 for operation at 1kW. The primary missions of the reactor are training, education and research. Each graduate of the School of Nuclear Engineering at Purdue University will have operated the reactor in two or more separate experiments as part of their curriculum. Students were used extensively throughout all phases of this conversion project, providing additional learning opportunities to complete their education experience. (author)

Jenkins, J.H.; Merritt, E.C.; Revis, B. [School of Nuclear Engineering, Purdue University, 400 Central Dr., West Lafayette, IN 47907 (United States)

2008-07-15T23:59:59.000Z

99

The LEU conversion status of U.S. Research Reactors.  

SciTech Connect

This paper summarizes the conversion status of US research and test reactors and estimates uranium densities needed to convert reactors with power levels 21 MW from HEU ({ge} 20% U-235) to LEU (<20% U-235) fuels. Detailed conversion studies for each reactor need to be completed in order to establish the feasibility of using LEU fuels.

Matos, J. E.

1997-11-14T23:59:59.000Z

100

Brookhaven Graphite Research Reactor | Environmental Restoration Projects |  

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

Why Was the BGRR Decommissioned? Why Was the BGRR Decommissioned? BGRR The Brookhaven Graphite Research Reactor (BGRR) at Brookhaven National Laboratory (BNL) was decommissioned to ensure the complex is in a safe and stable condition and to reduce sources of groundwater contamination. The BGRR contained over 8,000 Curies of radioactive contaminants from past operations consisting of primarily nuclear activation products such as hydrogen-3 (tritium) and carbon-14 and fission products cesium-137 and strontium-90. The nature and extent of contamination varied by location depending on historic uses of the systems and components and releases, however, the majority of the contamination (over 99 percent) was bound within the graphite pile and biological shield. Radioactive contamination was identified in the fuel handling system deep

Note: This page contains sample records for the topic "university research reactor" 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

Brookhaven Graphite Research Reactor | Environmental Restoration Projects |  

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

- Cleanup Actions - Cleanup Actions Since the Brookhaven Graphite Research Reactor (BGRR) was shut down in 1968, many actions have been taken as part of the complex decommissioning. The actions undertaken throughout the BGRR complex ensure that the structures that remain are in a safe and stable condition and prepared it for long-term surveillance and maintenance. Regulatory Requirements The decommissioning of the BGRR was conducted under the federal Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). In 1992, an Interagency Agreement (PDF) among the DOE, the U.S. Environmental Protection Agency (EPA) and the New York State Department of Environmental Conservation (NYSDEC) became effective. The IAG provided the overall framework for conducting environmental restoration activities at

102

Abstract and research accomplishments of University Coal Research Projects  

Science Conference Proceedings (OSTI)

The Principal Investigators of the grants supported by the University Coal Research Program were requested to submit abstracts and highlight accomplishments of their respective projects in time for distribution at a conference on June 13--14, 1995 at Tennessee State University in Nashville, Tennessee. This book is a compilation of the material received in response to that request. For convenience, the 70 grants reported in this book are stored into eight technical areas, Coal Science, Coal Surface Science, Reaction Chemistry, Advanced Process Concepts, Engineering Fundamentals and Thermodynamics, Environmental Science, high Temperature Phenomena, and Special topics. Indexes are provided for locating projects by subject, principal investigators, and contracting organizations. Each extended abstract describes project objectives, work accomplished, significance to the Fossil Energy Program, and plans for the next year.

NONE

1995-06-01T23:59:59.000Z

103

Computer-Based Model of the MIT Research Reactor  

SciTech Connect

A description is given of a model of the Massachusetts Institute of Technology Research Reactor (MITR) in which both the reactor's neutronic and thermal-hydraulic behaviors are replicated. The purpose of the model is to support control studies and the development of techniques for the automated diagnosis of reactivity transients. In particular, comparison of the model's predictions with actual measurements from the reactor will allow determination of whether the reactor is functioning as expected.

John A. Bernard; Lin-Wen Hu

2000-11-12T23:59:59.000Z

104

Opportunities for the Precision Study of Reactor Antineutrinos at Very Short Baselines at US Research Reactors  

E-Print Network (OSTI)

: pieter.mumm@nist.gov #12;2 past reactor experiments HFIR, ORNL NBSR, NIST ATR, INL available baselines at US research reactors 3 neutrino fit 3+1 neutrino fit Tuesday, August 7, 12 NIST ILL HFIR ATR SONGSNIST ILL HFIR ATR SONGS 10. 100 1000 core size reactor power reactorpower(MWth) 1meter ILL HFIR NBSR

105

In accounts of seminal neutron research at ORNL's Graphite Reactor,  

E-Print Network (OSTI)

requested permission to set up an X-ray diffractometer he had brought from the University of Chicago for his of the Graphite Reactor. "I was a student at the University of Chicago in 1942 when Enrico Fermi was doing his. 25 Scrooge (OR Playhouse) Nov. 27 Football: UT vs. Kentucky Dec. 4 Fiddler on the Roof Dec. 11 Best

106

California State University, Fullerton Institutional Research and Analytical Studies  

E-Print Network (OSTI)

California State University, Fullerton Institutional Research and Analytical Studies Percent-Resident Alien (International) 1,452 4.5% #12;California State University, Fullerton Institutional Research.5% Unknown 319 9.3% Non-Resident Alien (International) 95 2.8% #12;California State University, Fullerton

de Lijser, Peter

107

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL STUDIES  

E-Print Network (OSTI)

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL STUDIES PERCENT 1,660 4.7% MULTIPLE RACE 841 2.4% #12;CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH 125 3.2% INTERNATIONAL STUDENTS 74 1.9% MULTIPLE RACE 150 3.8% #12;CALIFORNIA STATE UNIVERSITY

de Lijser, Peter

108

California State University, Fullerton Institutional Research and Analytical Studies  

E-Print Network (OSTI)

California State University, Fullerton Institutional Research and Analytical Studies Percent-Resident Alien (International) 1,666 4.5% #12;California State University, Fullerton Institutional Research.7% Unknown 282 6.8% Non-Resident Alien (International) 109 2.6% #12;California State University, Fullerton

de Lijser, Peter

109

California State University, Fullerton Institutional Research and Analytical Studies  

E-Print Network (OSTI)

California State University, Fullerton Institutional Research and Analytical Studies Percent-Resident Alien (International) 1,265 4.5% #12;California State University, Fullerton Institutional Research 276 10.0% Non-Resident Alien (International) 46 1.7% #12;California State University, Fullerton

de Lijser, Peter

110

California State University, Fullerton Institutional Research and Analytical Studies  

E-Print Network (OSTI)

California State University, Fullerton Institutional Research and Analytical Studies Percent-Resident Alien (International) 1,523 4.3% #12;California State University, Fullerton Institutional Research.3% Unknown 261 6.6% Non-Resident Alien (International) 92 2.3% #12;California State University, Fullerton

de Lijser, Peter

111

California State University, Fullerton Institutional Research and Analytical Studies  

E-Print Network (OSTI)

California State University, Fullerton Institutional Research and Analytical Studies Percent-Resident Alien (International) 1,465 4.5% #12;California State University, Fullerton Institutional Research.4% Unknown 263 7.3% Non-Resident Alien (International) 97 2.7% #12;California State University, Fullerton

de Lijser, Peter

112

California State University, Fullerton Institutional Research and Analytical Studies  

E-Print Network (OSTI)

California State University, Fullerton Institutional Research and Analytical Studies Percent-Resident Alien (International) 1,528 4.3% #12;California State University, Fullerton Institutional Research.7% Unknown 255 6.6% Non-Resident Alien (International) 107 2.8% #12;California State University, Fullerton

de Lijser, Peter

113

California State University, Fullerton Institutional Research and Analytical Studies  

E-Print Network (OSTI)

California State University, Fullerton Institutional Research and Analytical Studies Percent-Resident Alien (International) 1,421 4.4% #12;California State University, Fullerton Institutional Research.3% Unknown 247 7.6% Non-Resident Alien (International) 62 1.9% #12;California State University, Fullerton

de Lijser, Peter

114

California State University, Fullerton Institutional Research and Analytical Studies  

E-Print Network (OSTI)

California State University, Fullerton Institutional Research and Analytical Studies Percent-Resident Alien (International) 1,367 4.5% #12;California State University, Fullerton Institutional Research 335 11.6% Non-Resident Alien (International) 63 2.2% #12;California State University, Fullerton

de Lijser, Peter

115

FACT SHEET: Clean Coal University Research Awards and Project Descriptions  

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

FACT SHEET: Clean Coal University Research Awards and Project FACT SHEET: Clean Coal University Research Awards and Project Descriptions FACT SHEET: Clean Coal University Research Awards and Project Descriptions As part of President Obama's all-of-the-above approach to American energy, the Energy Department announced on June 6, 2012, that nine universities have won awards for research projects that will continue to support innovation and development of clean coal technologies. This fact sheet includes detailed project descriptions for each university-led research award. FACT SHEET_ Clean Coal University Project Descriptions_0.pdf More Documents & Publications University Coal Research Program 2013 Selections Report on Assessment of Environmentally--Assisted Fatigue for LWR Extended Service Conditions FAQS Reference Guide - Mechanical Systems

116

The University of Maryland Energy Research Center  

E-Print Network (OSTI)

.S. ranking in the 2007 DOE Solar Decathlon. The university's campus is a living laboratory of "smartgrid

Gruner, Daniel S.

117

Building a research university ecosystem: the case of software engineering education at Sofia University  

Science Conference Proceedings (OSTI)

This paper analyses the specifics and the tendencies in building the knowledge society as well as the role of the universities in this process. Some European policies and programs dedicated to the new role of the universities in realizing the Lisbon ... Keywords: research university ecosystem, software engineering education, universities in knowledge society

Roumen Nikolov; Sylvia Ilieva

2007-09-01T23:59:59.000Z

118

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research  

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

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program The Department of Energy's (DOE's) Light Water Reactor Sustainability (LWRS) Program is a five year effort that works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operation of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging

119

An Account of Oak Ridge National Laboratory's Thirteen Research Reactors  

Science Conference Proceedings (OSTI)

The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-metal fast burst reactor used for health physics studies. All of the others were light-water cooled and moderated, including the famous swimming-pool reactor that was copied dozens of times around the world. Two of the reactors were hoisted 200 feet into the air to study the shielding needs of proposed nuclear-powered aircraft. The final reactor, and the only one still operating today, is the High Flux Isotope Reactor (HFIR) that was built particularly for the production of californium and other heavy elements. With the world's highest flux and recent upgrades that include the addition of a cold neutron source, the 44-year-old HFIR continues to be a valuable tool for research and isotope production, attracting some 500 scientific visitors and guests to Oak Ridge each year. This report describes all of the reactors and their histories.

Rosenthal, Murray Wilford [ORNL

2009-08-01T23:59:59.000Z

120

DOE Announces Winners of Annual University Coal Research Grants |  

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

Winners of Annual University Coal Research Grants Winners of Annual University Coal Research Grants DOE Announces Winners of Annual University Coal Research Grants July 7, 2005 - 2:06pm Addthis Funding to Support Continued Research in Clean Coal Technology MORGANTOWN, WV -- Secretary of Energy Samuel Bodman today announced $3 million in funding under the University Coal Research Program (UCR), the department's longest-running student-teacher research grant initiative. Secretary Bodman made the announcement while visiting West Virginia University, a $200,000 awardee. "Coal is our most abundant source of energy and the University Coal Research Program helps us identify new ways to utilize coal in a more efficient and environmentally responsible way by tapping into the creativity and ambition of America's young scientists," Secretary Bodman

Note: This page contains sample records for the topic "university research reactor" 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

Uncovering Coal's Secrets Through the University Coal Research Program |  

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

Uncovering Coal's Secrets Through the University Coal Research Uncovering Coal's Secrets Through the University Coal Research Program Uncovering Coal's Secrets Through the University Coal Research Program December 18, 2013 - 10:38am Addthis Uncovering Coal’s Secrets Through the University Coal Research Program The challenges confronting the environmentally sound use of our country's fossil energy resources are best addressed through collaborative research and development. That's why this approach, which stretches federal dollars, is at the heart of the Office of Fossil Energy's University Coal Research (UCR) Program. Managed by the National Energy Technology Laboratory (NETL), the UCR program funds university research to improve understanding of the chemical and physical properties of coal, one of our nation's most abundant

122

DOE Announces Winners of Annual University Coal Research Grants |  

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

DOE Announces Winners of Annual University Coal Research Grants DOE Announces Winners of Annual University Coal Research Grants DOE Announces Winners of Annual University Coal Research Grants July 7, 2005 - 2:06pm Addthis Funding to Support Continued Research in Clean Coal Technology MORGANTOWN, WV -- Secretary of Energy Samuel Bodman today announced $3 million in funding under the University Coal Research Program (UCR), the department's longest-running student-teacher research grant initiative. Secretary Bodman made the announcement while visiting West Virginia University, a $200,000 awardee. "Coal is our most abundant source of energy and the University Coal Research Program helps us identify new ways to utilize coal in a more efficient and environmentally responsible way by tapping into the creativity and ambition of America's young scientists," Secretary Bodman

123

Maria Research Reactor loaded with LEU - Otwock, Poland | National Nuclear  

National Nuclear Security Administration (NNSA)

Maria Research Reactor loaded with LEU - Otwock, Poland | National Nuclear Maria Research Reactor loaded with LEU - Otwock, Poland | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Video Gallery > Maria Research Reactor loaded with LEU - ... Maria Research Reactor loaded with LEU - Otwock, Poland Maria Research Reactor loaded with LEU - Otwock, Poland

124

Research on Very High Temperature Gas Reactors  

Science Conference Proceedings (OSTI)

Very high temperature gas reactors are helium-cooled, graphite-moderated advanced reactors that show potential for generating low-cost electricity via gas turbines or cogeneration with process-heat applications. This investigation addresses the development status of advanced coatings for nuclear-fuel particles and high-temperature structural materials and evaluates whether these developments are likely to lead to economically competitive applications of the very high temperature gas reactor concept.

1991-08-08T23:59:59.000Z

125

Brookhaven Graphite Research Reactor | Environmental Restoration...  

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

of multiple structures and systems that were necessary to operate and maintain the reactor. The most recognizable features of the complex include the Building 701 officeshigh...

126

RERTR program reduces use of enriched uranium in research reactors  

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

RERTR program reduces use of enriched uranium in research reactors RERTR program reduces use of enriched uranium in research reactors worldwide Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share RERTR program reduces use of enriched uranium in research reactors worldwide The High Flux Reactor in Petten, the Netherlands READY TO CONVERT - The High Flux Reactor in Petten, the Netherlands, has

127

University Coal Research Program 2013 Selections | Department of Energy  

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

University Coal Research Program 2013 Selections University Coal Research Program 2013 Selections University Coal Research Program 2013 Selections Since the University Coal Research Program's inception in 1979, more than 728 research projects have been funded. With a combined value in excess of $132 million, these projects have provided new insights into coal's future use, and have given more than 1,800 students invaluable experience in understanding the science and technology of coal. Attached is the list of 2013 project selections under this program. UCR_Project_Selections_2013.pdf More Documents & Publications FACT SHEET: Clean Coal University Research Awards and Project Descriptions International Nuclear Energy Research Initiative: 2008 Annual Report 2013 Annual DOE-NE Materials Research Coordination Meeting

128

Pharmacotherapy Outcomes Research Center University of Utah College of Pharmacy  

E-Print Network (OSTI)

with the University of Utah Distinguished Teaching Award). Her teaching and research interests include the human sidePORC Pharmacotherapy Outcomes Research Center University of Utah College of Pharmacy MISSION STATEMENT Our mission is to design and conduct outcomes research studies that assess the value of therapy

Provancher, William

129

Center for Transportation Research University of Texas at Austin  

E-Print Network (OSTI)

Center for Transportation Research University of Texas at Austin Randy B. Machemehl, Ph.D., P.E. Nasser I. Al-Rashid Centennial Professor in Transportation Engineering, Director of the Center for Transportation Research, and SWUTC Executive Committee Member Center for Transportation Research University

130

Renewable Energy Research Laboratory University of Massachusetts, Amherst  

E-Print Network (OSTI)

by the Renewable Energy Research Laboratory (RERL) at the University of Massachusetts, Amherst. Wind monitoring/RERL_Fact_Sheet_6_Wind_resource_interpretation.pdf * 1 m/s = 2.237 mph. November 16, 2009 Renewable Energy Research Energy Research Laboratory Page 12 University of Massachusetts, Amherst Amherst, MA 01003 #12;Wind Roses

Massachusetts at Amherst, University of

131

Renewable Energy Research Laboratory University of Massachusetts, Amherst  

E-Print Network (OSTI)

Energy Research Laboratory (RERL) at the University of Massachusetts, Amherst. Wind monitoring equipment, and wind roses are included in APPENDIX B. July 24, 2009 Renewable Energy Research Laboratory Page 9, if the wind speed July 24, 2009 Renewable Energy Research Laboratory Page 13 University of Massachusetts

Massachusetts at Amherst, University of

132

Advanced Reactor Research and Development Funding Opportunity Announcement  

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

Reactor Research and Development Funding Opportunity Reactor Research and Development Funding Opportunity Announcement Advanced Reactor Research and Development Funding Opportunity Announcement The U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) sponsors a program of research, development, and demonstration related to advanced non-light water reactor concepts. A goal of the program is to facilitate greater engagement between DOE and industry. During FY12, DOE established a Technical Review Panel (TRP) process to identify R&D needs for viable advanced reactor concepts in order to inform DOE-NE R&D investment decisions. That process involved the use of a Request for Information (RFI) to solicit concept information from industry and engage technical experts to evaluate those concepts. Having completed this process, DOE desires to

133

Advanced Reactor Research and Development Funding Opportunity Announcement  

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

Advanced Reactor Research and Development Funding Opportunity Advanced Reactor Research and Development Funding Opportunity Announcement Advanced Reactor Research and Development Funding Opportunity Announcement The U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) sponsors a program of research, development, and demonstration related to advanced non-light water reactor concepts. A goal of the program is to facilitate greater engagement between DOE and industry. During FY12, DOE established a Technical Review Panel (TRP) process to identify R&D needs for viable advanced reactor concepts in order to inform DOE-NE R&D investment decisions. That process involved the use of a Request for Information (RFI) to solicit concept information from industry and engage technical experts to evaluate those concepts. Having completed this process, DOE desires to

134

NREL: Research Participant Program - University Relations  

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

University Relations program is dedicated to improving relationships with the higher education community. NREL wants to talk with talented students with areas of study in our...

135

REACTOR PHYSICS MODELING OF SPENT RESEARCH REACTOR FUEL FOR TECHNICAL NUCLEAR FORENSICS  

SciTech Connect

Technical nuclear forensics (TNF) refers to the collection, analysis and evaluation of pre- and post-detonation radiological or nuclear materials, devices, and/or debris. TNF is an integral component, complementing traditional forensics and investigative work, to help enable the attribution of discovered radiological or nuclear material. Research is needed to improve the capabilities of TNF. One research area of interest is determining the isotopic signatures of research reactors. Research reactors are a potential source of both radiological and nuclear material. Research reactors are often the least safeguarded type of reactor; they vary greatly in size, fuel type, enrichment, power, and burn-up. Many research reactors are fueled with highly-enriched uranium (HEU), up to {approx}93% {sup 235}U, which could potentially be used as weapons material. All of them have significant amounts of radiological material with which a radioactive dispersal device (RDD) could be built. Therefore, the ability to attribute if material originated from or was produced in a specific research reactor is an important tool in providing for the security of the United States. Currently there are approximately 237 operating research reactors worldwide, another 12 are in temporary shutdown and 224 research reactors are reported as shut down. Little is currently known about the isotopic signatures of spent research reactor fuel. An effort is underway at Savannah River National Laboratory (SRNL) to analyze spent research reactor fuel to determine these signatures. Computer models, using reactor physics codes, are being compared to the measured analytes in the spent fuel. This allows for improving the reactor physics codes in modeling research reactors for the purpose of nuclear forensics. Currently the Oak Ridge Research reactor (ORR) is being modeled and fuel samples are being analyzed for comparison. Samples of an ORR spent fuel assembly were taken by SRNL for analytical and radiochemical analysis. The fuel assembly was modeled using MONTEBURNS(MCNP5/ ORIGEN2.2) and MCNPX/CINDER90. The results from the models have been compared to each other and to the measured data.

Nichols, T.; Beals, D.; Sternat, M.

2011-07-18T23:59:59.000Z

136

Present Status Of Research Reactor Decommissioning Program In Indonesia  

E-Print Network (OSTI)

At present, Indonesia has 3 research reactors: MTR-type multipurpose reactor of 30 MW at Serpong site, TRIGA-type research reactor of 1 MW at Bandung site, and small TRIGA - type reactor of 100 kW at Yogyakarta Research Center. The oldest one is the TRIGA reactor at Bandung site, which went critical at 250 kW in 1964, then was operated at maximum of 1000 kW by 1971. The reactor has operated for a total of 35 years. There is no decision for decommissioning this reactor; however, slowly but surely, it will be an object for a near-future decommissioning program. Anticipation of the situation is necessary. For the Indonesian case, early decommissioning strategy for a research reactor and restricted use of the site for another nuclear installation is favorable under high land pricing, availability of radwaste repository, and cost analysis. Graphite from Triga reactor reflector is recommended for direct disposal after conditioning, without volume reduction treatment. Development of human ...

Mulyanto And Gunandjar

2000-01-01T23:59:59.000Z

137

Public Vs. Private Good Research at Land-Grant Universities  

E-Print Network (OSTI)

and Rausser, 1993). Public-private partner- ships cannot beinevitable outcome of public-private research collaboration.universities can use public-private partnerships to leverage

Rausser, Gordon C.; Simon, Leo K.; Stevens, Reid

2008-01-01T23:59:59.000Z

138

The Building Research Council at the University of Illinois ...  

Open Energy Info (EERE)

Partner Partnering Center within NREL Electricity Resources & Building Systems Integration LinkedIn Connections The Building Research Council at the University of Illinois is...

139

Twenty Years of Airborne Research at the University of Washington  

Science Conference Proceedings (OSTI)

Wherein is revealed the trials, tribulations, and triumphs of operating an aircraft for atmospheric research at a university over the past 20 years.

Peter V. Hobbs

1991-11-01T23:59:59.000Z

140

Sandia National Laboratories: Research: Facilities: Sandia Pulsed Reactor  

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

Sandia Pulsed Reactor Facility - Critical Experiments Sandia Pulsed Reactor Facility - Critical Experiments Sandia scientist John Ford places fuel rods in the Seven Percent Critical Experiment (7uPCX) at the Sandia Pulsed Reactor Facility Critical Experiments (SPRF/CX) test reactor - a reactor stripped down to its simplest form. The Sandia Pulsed Reactor Facility - Critical Experiments (SPRF/CX) provides a flexible, shielded location for performing critical experiments that employ different reactor core configurations and fuel types. The facility is also available for hands-on nuclear criticality safety training. Research and other activities The 7% series, an evaluation of various core characteristics for higher commercial-fuel enrichment, is currently under way at the SPRF/CX. Past critical experiments at the SPRF/CX have included the Burnup Credit

Note: This page contains sample records for the topic "university research reactor" 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

Research in Ghanaian public universities : perceptions and experiences of academic staff at the University of Ghana.  

E-Print Network (OSTI)

??With the advent of the knowledge economies, research is recognised as a catalyst for accelerated national growth. Many countries are therefore investing hugely in university… (more)

Gyan, George

2010-01-01T23:59:59.000Z

142

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL STUDIES  

E-Print Network (OSTI)

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL STUDIES PERCENT STUDENTS 1,722 4.7% MULTIPLE RACE 579 1.6% #12;CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL.6% UNKNOWN 162 4.0% INTERNATIONAL STUDENTS 84 2.1% MULTIPLE RACE 190 4.7% #12;CALIFORNIA STATE UNIVERSITY

de Lijser, Peter

143

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL STUDIES  

E-Print Network (OSTI)

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH AND ANALYTICAL STUDIES PERCENT 1,611 4.5% MULTIPLE RACE 1,145 3.2% #12;CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL.9% UNKNOWN 95 2.3% INTERNATIONAL STUDENTS 101 2.4% MULTIPLE RACE 216 5.1% #12;CALIFORNIA STATE UNIVERSITY

de Lijser, Peter

144

Transmutation Research Program University of Nevada, Las Vegas  

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

Transmutation Transmutation Research Program University of Nevada, Las Vegas University of Nevada, Las Vegas Transmutation Research Program Transmutation Research Program Anthony E. Hechanova Director http://aaa.nevada.edu Transmutation Research Program * Overview of UNLV Program * FY01 and FY02 in Review * Plans for FY03 * Future Outlook - Directions Outline Transmutation Research Program UNLV Transmutation Research Program Program Mission: To establish a world-class program at UNLV for transmutation research and education through faculty-supervised graduate student projects. Program Goals: * Build core competencies and facilities to promote UNLV's strategic growth * Increase UNLV's research activities * Attract students and faculty of the highest caliber Transmutation

145

Final report on the University of Florida U.S. Department of Energy 1995--96 Reactor Sharing Program  

SciTech Connect

Grant support has been well used by the University of Florida as host institution to support various educational institutions in the use of the reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over twelve million inhabitants throughout the State of Florida and still others throughout the nation. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research activities were not funded by grants for contract funding from outside sources. In some cases external grant funding is limited or is used up, in which case the Reactor Sharing Grant and frequent cost sharing by the UFTR facility and the University of Florida provide the necessary support to complete a project or to provide more results to make a complete project even better. In some cases this latter usage has aided renewal of external funding. The role of the Reactor Sharing Program, though relatively small in dollars, has been the single most important occurrence in assuring the rebirth and continued high utilization of the UFTR in a time when many better equipped and better placed facilities have ceased operations. Through dedicated and effective advertising efforts, the UFTR has seen nearly every four-year college and university in Florida make substantive use of the facility under the Reactor Sharing Program with many now regular users. Some have even been able to support usage from outside grants where the Reactor Sharing Grant has served as seed money; still others have been assisted when external grants were depleted.

Vernetson, W.G.

1996-11-01T23:59:59.000Z

146

Engineering activities at the MIT research reactor in support of power reactor technology  

SciTech Connect

The Massachusetts Institute of Technology (MIT) research reactor (MITR-II) is a 5-MW(thermal) light-water-cooled and-moderated reactor (LWR) with in-core neutron and gamma dose rates that closely approximate those in current LWRs. Compact in-pile loops that simulate pressurized water reactor (PWR) and boiling water reactor (BWR) thermal hydraulics and coolant chemistry have been designed for installation in the MITR-II. A PWR loop has been completed and is currently operating in the reactor. A BWR loop is under construction, and an in-pile facility for irradiation-assisted stress corrosion crack (IASCC) testing is being designed. Another major area of research and on-line testing is the closed-loop, nonlinear, digital control of various reactor parameters, including the power level, temperature, and net energy production.

Harling, O.K.; Bernard, J.A.; Driscoll, M.J.; Kohse, G.E.; Ballinger, R.G.

1989-01-01T23:59:59.000Z

147

Stirling engine research at national and university laboratories in Japan  

DOE Green Energy (OSTI)

Pacific Northwest Laboratory (PNL) reviewed research projects that are related to the development of Stirling engines and that are under way at Japanese national laboratories and universities. The research and development focused on component rather than on whole engine development. PNL obtained the information from a literature review and interviews conducted at the laboratories and universities. The universities have less equipment available and operate with smaller staffs for research than do the laboratories. In particular, the Mechanical Engineering Laboratory and the Aerospace Laboratory conduct high-quality component and fundamental work. Despite having less equipment, some of the researchers at the universities conduct high-quality fundamental research. As is typical in Japan, several of the university professors are very active in consulting and advisory capacities to companies engaged in Stirling engine development, and also with government and association advisory and technical committees. Contacts with these professors and selective examination of their research are good ways to keep abreast of Japanese Stirling developments.

Hane, G.J.; Hutchinson, R.A.

1987-09-01T23:59:59.000Z

148

Virtual University Research Initiative on Mobility  

Science Conference Proceedings (OSTI)

BT's technology acquisition has taken on an increasingly collaborative approach in recent years. This paper provides an insight into a long-running collaboration between BT and three universities in the mobility area.

R. M. Dennis; A. R. Beresford; K. M. Brown

2001-01-01T23:59:59.000Z

149

University Teams Lead Innovative Solar Research Projects | Department of  

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

University Teams Lead Innovative Solar Research Projects University Teams Lead Innovative Solar Research Projects University Teams Lead Innovative Solar Research Projects August 28, 2012 - 2:55pm Addthis A concentrating solar power system in Albuquerque, New Mexico. | Photo by Randy Montoya/Sandia National Laboratory. A concentrating solar power system in Albuquerque, New Mexico. | Photo by Randy Montoya/Sandia National Laboratory. Erin R. Pierce Erin R. Pierce Digital Communications Specialist, Office of Public Affairs What are the key facts? The Energy Department is investing in two university-led projects to improve the performance of concentrated solar power systems. Research teams at the University of California, Los Angeles and the University of Arizona are launching projects aimed at improving the performance and lowering costs of solar energy systems.

150

Nine Universities Begin Critical Turbine Systems Research | Department of  

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

Nine Universities Begin Critical Turbine Systems Research Nine Universities Begin Critical Turbine Systems Research Nine Universities Begin Critical Turbine Systems Research July 20, 2011 - 1:00pm Addthis Washington, D.C. -- The U.S. Department of Energy announced the selection of ten projects at nine universities under the Office of Fossil Energy's (FE) University Turbine Systems Research (UTSR) Program. The projects will develop technologies for use in the new generation of advanced turbines that operate cleanly and efficiently using fuels derived from coal and containing high amounts of hydrogen. The selected universities - located in California, Connecticut, Indiana, Michigan, North Dakota, Ohio, Pennsylvania, Tennessee, and Texas - will direct their efforts toward enabling technologies for high-hydrogen-fueled

151

Nine Universities Begin Critical Turbine Systems Research | Department of  

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

Nine Universities Begin Critical Turbine Systems Research Nine Universities Begin Critical Turbine Systems Research Nine Universities Begin Critical Turbine Systems Research July 20, 2011 - 1:00pm Addthis Washington, D.C. -- The U.S. Department of Energy announced the selection of ten projects at nine universities under the Office of Fossil Energy's (FE) University Turbine Systems Research (UTSR) Program. The projects will develop technologies for use in the new generation of advanced turbines that operate cleanly and efficiently using fuels derived from coal and containing high amounts of hydrogen. The selected universities - located in California, Connecticut, Indiana, Michigan, North Dakota, Ohio, Pennsylvania, Tennessee, and Texas - will direct their efforts toward enabling technologies for high-hydrogen-fueled

152

NETL Publications: 2013 UNIVERSITY COAL RESEARCH/HISTORICALLY BLACK  

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

2013 UNIVERSITY COAL RESEARCH/HISTORICALLY BLACK COLLEGES 2013 UNIVERSITY COAL RESEARCH/HISTORICALLY BLACK COLLEGES AND UNIVERSITIES AND OTHER MINORITY INSTITUTIONS CONTRACTORS REVIEW MEETING The Wyndham Grand, Pittsburgh Tuesday, June 11, 2013 Registration Opening Remarks Robert Romanosky, Technology Manager, Crosscutting Research SENSORS & CONTROL TECHNOLOGIES Moderator: Steven Markovich, HBCU Program Coordinator, Federal Project Manager, Fuels Division U.S. Department of Energy, National Energy Technology Laboratory High-Temperature Nano-Derived Micro-H2 and H2S Sensors [PDF-11.43MB] Edward Sabolsky, West Virginia University Development of High Temperature/High Sensitivity Novel Chemical Resistive Sensor [PDF-14.09MB]

153

Center for Transportation Research University of Texas at Austin  

E-Print Network (OSTI)

Center for Transportation Research University of Texas at Austin C. Michael Walton, Ph.D., P for Transportation Research University of Texas at Austin Austin, TX 78701 cmwalton@mail.utexas.edu (512) 471 pursued a career in transport systems engineering and policy analysis. Dr. Walton is a member

154

Renewable Energy Research Laboratory University of Massachusetts, Amherst  

E-Print Network (OSTI)

by the Renewable Energy Research Laboratory (RERL) at the University of Massachusetts, Amherst. Wind monitoring-month period. This graph shows the trends in the wind speed over the year. June 9, 2009 Renewable Energy Renewable Energy Research Laboratory Page 9 University of Massachusetts, Amherst Amherst, MA 01003 #12;Wind

Massachusetts at Amherst, University of

155

Renewable Energy Research Laboratory University of Massachusetts, Amherst  

E-Print Network (OSTI)

by the Renewable Energy Research Laboratory (RERL) at the University of Massachusetts, Amherst. Wind monitoring Energy Research Laboratory Page 9 University of Massachusetts, Amherst Amherst, MA 01003 #12;Wind Speed deviation, wind direction, temperature, and solar insolation. F1 > TF1 > F2 June 12, 2009 Renewable Energy

Massachusetts at Amherst, University of

156

DOE-NREL Minority University Research Associates Program  

SciTech Connect

The DOE-NREL Minority University Research Associates Program (MURA) encourages minority students to pursue careers in science and technology. In this program, undergraduate students work with principal investigators at their universities to perform research projects on solar technology. Then, students are awarded summer internships in industry or at national laboratories, such as NREL, during the summer. Because of its success, the program has been expanded to include additional minority-serving colleges and universities and all solar energy technologies.

Posey Eddy, F.

2005-01-01T23:59:59.000Z

157

EDUconnections Highlights Arizona State University Research | Department of  

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

EDUconnections Highlights Arizona State University Research EDUconnections Highlights Arizona State University Research EDUconnections Highlights Arizona State University Research December 6, 2010 - 5:47pm Addthis Andy Oare Andy Oare Former New Media Strategist, Office of Public Affairs For the past year, .EDUconnections has been the Office of Science and Technical Information's online portal for highlighting some of the amazing scientific research being done at our nation's universities and colleges. They're helping get the message out about how research and technical advancements through Department of Energy sponsored programs are propelling our future workforce to new discoveries in science, engineering, mathematics and many other technical disciplines. This month they're pleased to spotlight Arizona State University. ASU's

158

EDUconnections Highlights Arizona State University Research | Department of  

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

EDUconnections Highlights Arizona State University Research EDUconnections Highlights Arizona State University Research EDUconnections Highlights Arizona State University Research December 6, 2010 - 5:47pm Addthis Andy Oare Andy Oare Former New Media Strategist, Office of Public Affairs For the past year, .EDUconnections has been the Office of Science and Technical Information's online portal for highlighting some of the amazing scientific research being done at our nation's universities and colleges. They're helping get the message out about how research and technical advancements through Department of Energy sponsored programs are propelling our future workforce to new discoveries in science, engineering, mathematics and many other technical disciplines. This month they're pleased to spotlight Arizona State University. ASU's

159

Automated startup of the MIT research reactor  

SciTech Connect

This summary describes the development, implementation, and testing of a generic method for performing automated startups of nuclear reactors described by space-independent kinetics under conditions of closed-loop digital control. The technique entails first obtaining a reliable estimate of the reactor's initial degree of subcriticality and then substituting that estimate into a model-based control law so as to permit a power increase from subcritical on a demanded trajectory. The estimation of subcriticality is accomplished by application of the perturbed reactivity method. The shutdown reactor is perturbed by the insertion of reactivity at a known rate. Observation of the resulting period permits determination of the initial degree of subcriticality. A major advantage to this method is that repeated estimates are obtained of the same quantity. Hence, statistical methods can be applied to improve the quality of the calculation.

Kwok, K.S. (Massachusetts Inst. of Tech., Cambridge (United States))

1992-01-01T23:59:59.000Z

160

Energy Secretary Hails University of Maine's Wind Research | Department of  

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

Hails University of Maine's Wind Research Hails University of Maine's Wind Research Energy Secretary Hails University of Maine's Wind Research June 16, 2010 - 10:51am Addthis Stephen Graff Former Writer & editor for Energy Empowers, EERE Energy Secretary Steven Chu praised the University of Maine on Monday, calling the school's offshore wind technology program "truly impressive." Secretary Chu visited the university's Orono campus to learn more about its 10-year plan to design and deploy deepwater wind technology, an effort that could pave the way for the first floating commercial wind farm in the United States. "It's part of the leadership Maine has shown in going toward a sustainable economy," Chu told the university's newspaper. Invited by Maine Sen. Susan Collins, Chu was given a tour of the

Note: This page contains sample records for the topic "university research reactor" 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

LEHIGH UNIVERSITY RESEARCH AND TESTING AGREEMENT  

E-Print Network (OSTI)

, the Project. Article 4 - Costs, Billings and Other Support 4.1 It is agreed to and understood by the parties and testing project contemplated by this Agreement is of mutual interest and benefit to University have the following meanings: 1.1 "Project" shall mean the project titled

Gilchrist, James F.

162

Four Minority Universities Selected for Fossil Energy Research Grants |  

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

Four Minority Universities Selected for Fossil Energy Research Four Minority Universities Selected for Fossil Energy Research Grants Four Minority Universities Selected for Fossil Energy Research Grants July 28, 2011 - 1:00pm Addthis Washington, DC - The Department of Energy has selected four universities to receive grants under the department's annual competition for fossil energy research ideas from Historically Black Colleges and Universities and Other Minority Institutions (HBCU/OMI). "I want to congratulate the winners of this year's competition, and thank them for their hard work," said Charles McConnell, Chief Operating Officer of DOE's Office of Fossil Energy. "Identifying the next generation of leaders and innovators is one of the keys to strengthening our economy and creating the clean energy jobs of tomorrow."

163

NETL Publications: The 2011 University Coal Research/Historically Black  

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

011 University Coal Research/Historically Black Colleges and Universities and Other Minority Institutions Contractors Review Conference. 011 University Coal Research/Historically Black Colleges and Universities and Other Minority Institutions Contractors Review Conference. June 7-8, 2011 Table of Contents Disclaimer Session 1 Session 2 Session 3 Session 4 PRESENTATIONS Introduction and Opening Remarks Robert Romanosky, Technology Manager, Advanced Research Power Systems, U.S. Department of Energy, National Energy Technology Laboratory Presentation [PDF-883KB] Keynote Address Dr. Ahsan Choudhuri, Director of the University of Texas at El Paso's NASA Center for Space Exploration and Technology Research Presentation [PDF-3.18MB] Session 1 Moderator: Susan Maley, Project Manager, Gasification Division, U.S. Department of Energy, National Energy Technology Laboratory Plasmonics Based Harsh Environment Compatible Chemical Sensors

164

Argonne's pyroprocessing and advanced reactor research featured on WGN  

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

Argonne's pyroprocessing and advanced reactor research featured on WGN Argonne's pyroprocessing and advanced reactor research featured on WGN radio Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share Argonne's pyroprocessing and advanced reactor research featured on WGN radio Uranium dendrites These tiny branches, or "dendrites," of pure uranium form when engineers

165

FACT SHEET: Clean Coal University Research Awards and Project Descriptions  

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

SHEET: Clean Coal University Research Awards and SHEET: Clean Coal University Research Awards and Project Descriptions IMPROVED ALLOYS By substantially increasing the pressure and temperature of the steam used to produce power, advanced ultrasupercritical (AUSC) coal-fired power plants improve generation efficiency, use less coal and release less carbon pollution. The implementation of AUSC boilers requires materials with high-temperature oxidation, corrosion and deformation resistance. These selected projects will develop new surface modification techniques or optimize existing techniques for the protection of high-temperature alloys used in AUSC coal-fired boilers and in advanced gas turbines. Southern Illinois University (Carbondale, Ill.) - Southern Illinois University Carbondale

166

UNIVERSITY TURBINE SYSTEMS RESEARCH PROGRAM SUMMARY AND DIRECTORY  

Science Conference Proceedings (OSTI)

The South Carolina Institute for Energy Studies (SCIES), administratively housed at Clemson University, has participated in the advancement of combustion turbine technology for over a decade. The University Turbine Systems Research Program, previously referred to as the Advanced Gas Turbine Systems Research (AGTSR) program, has been administered by SCIES for the U.S. DOE during the 1992-2003 timeframe. The structure of the program is based on a concept presented to the DOE by Clemson University. Under the supervision of the DOE National Energy Technology Laboratory (NETL), the UTSR consortium brings together the engineering departments at leading U.S. universities and U.S. combustion turbine developers to provide a solid base of knowledge for the future generations of land-based gas turbines. In the UTSR program, an Industrial Review Board (IRB) (Appendix C) of gas turbine companies and related organizations defines needed gas turbine research. SCIES prepares yearly requests for university proposals to address the research needs identified by the IRB organizations. IRB technical representatives evaluate the university proposals and review progress reports from the awarded university projects. To accelerate technology transfer technical workshops are held to provide opportunities for university, industry and government officials to share comments and improve quality and relevancy of the research. To provide educational growth at the Universities, in addition to sponsored research, the UTSR provides faculty and student fellowships. The basis for all activities--research, technology transfer, and education--is the DOE Turbine Program Plan and identification, through UTSR consortium group processes, technology needed to meet Program Goals that can be appropriately researched at Performing Member Universities.

Lawrence P. Golan; Richard A. Wenglarz

2004-07-01T23:59:59.000Z

167

SOLERAS - University Research Project. Progress report 2  

Science Conference Proceedings (OSTI)

Progress to date on each of the research efforts in direct solar energy applications at public and private institutions of higher education and research in the United States is addressed. Some research topics covered include: concentrating optics for PV conversion; wind power; solar ponds; photosynthesis; amorphous silicon alloys; passive cooling; crystal growth of gallium arsenides; and solar insolation. The period of work covered by these reports is June 1984 through February 1985.

Not Available

1985-03-01T23:59:59.000Z

168

University Research Management: An Exploratory Literature Review  

E-Print Network (OSTI)

as Process. Routledge, London. Hockey, J. , Allen-Collinson,for successful research (Hockey and Allen-Collinson 2009).qualities, and experience (Hockey and Allen-Collinson 2009:

Schuetzenmeister, Falk

2010-01-01T23:59:59.000Z

169

JOANNEUM RESEARCH and Vienna University of ...  

Science Conference Proceedings (OSTI)

... Georg Schwendt? ? JOANNEUM RESEARCH, DIGITAL – Institute for ... [15] “OpenCV library,” http://opencv ... of SPIE-IS&T Electronic Imaging, A. Said ...

2012-01-10T23:59:59.000Z

170

Nuclear reactor and materials science research: Final technical report, May 1, 1985-September 30, 1986. [Academic and research utilization of reactor  

SciTech Connect

Throughout the 17-month period of the grant, May 1, 1985 - September 30, 1986, the MIT Research Reactor (MITR-II) was operated in support of research and academic programs in the physical and life sciences and in related engineering fields. The period encompassed MIT's fiscal year utilization of the reactor during that period may be classified as follows: neutron beam tube research, nuclear materials research and development, radiochemistry and trace analysis, nuclear medicine, radiation health physics, computer control of reactors, dose reduction in nuclear power reactors, reactor irradiations and services for groups outside MIT, and MIT research reactor. This paper provides detailed information on this research academic utilization.

Harling, O.K.

1987-05-11T23:59:59.000Z

171

Energy Research at the University of Bath  

E-Print Network (OSTI)

the potential energy demand reductions that are achievable across the whole of the UK industrial sector of Science Review' in industrial energy efficiency commissioned by the UK Government's Office of Science oil and research into an "intelligent" lubrication oil system. This research is on target to reduce

Collomosse, John

172

Uncovering Coal's Secrets Through the University Coal Research Program  

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

8, 2013 8, 2013 Uncovering Coal's Secrets Through the University Coal Research Program Uncovering Coal's Secrets Through the University Coal Research Program The challenges confronting the environmentally sound use of our country's fossil energy resources are best addressed through collaborative research and development. That's why this approach, which stretches federal dollars, is at the heart of the Office of Fossil Energy's University Coal Research (UCR) Program. Managed by the National Energy Technology Laboratory (NETL), the UCR program funds university research to improve understanding of the chemical and physical properties of coal, one of our nation's most abundant resources. The program has forged partnerships between academia and the private sector that have led to advances not only in how we use coal, but

173

Four Minority Universities Selected for Fossil Energy Research Grants |  

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

May 20, 2010 - 1:00pm May 20, 2010 - 1:00pm Addthis Washington, DC - Innovative fossil energy research projects will be investigated by students and faculty from four winning institutions in the Department of Energy's annual competition for fossil energy research ideas from the nation's Historically Black Colleges and Universities and Other Minority Institutions (HBCU/OMI). Students and faculty from the chosen universities - the University of Texas, El Paso; Southern University and A&M College; Tennessee State University; and the University of Texas, San Antonio - will investigate projects dealing with computational energy sciences, material sciences, and sensors and controls for use in fossil fuel power systems. Established in 1984, the HBCU/OMI program was designed to encourage

174

Research at the Institute for Environmental Science & Policy - University  

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

Research at the Institute for Environmental Science & Policy - University Research at the Institute for Environmental Science & Policy - University of Illinois at Chicago August 8, 2013 Speakers: Thomas L. Theis Director, Institute for Environmental Science & Policy (IESP) University of Illinois at Chicago David H. Wise Associate Director, IESP University of Illinois at Chicago Date: Thursday, August 8, 2013 Time: 2:00-3:00 pm Location: Argonne National Laboratory TCS Building 240 Room 1404/1405 The Institute for Environmental Science and Policy (IESP) at the University of Illinois at Chicago was created in 1999 to catalyze interdisciplinary research addressing the increasingly complex environmental problems of the 21st century. IESP envisions an academy in which the constraints and limitations imposed by disciplinary perspectives are eased, while their

175

Center for Transportation Research University of Texas at Austin  

E-Print Network (OSTI)

Center for Transportation Research University of Texas at Austin Chandra Bhat, Ph.D. Director, Center for Transportation Research Adnan Abou-Ayyash Centennial Professor in Transportation Engineering-4535 Biography Dr. Chandra R. Bhat is the Director of the Center for Transportation Research (CTR) and the Adnan

176

Renewable Energy Research Laboratory University of Massachusetts, Amherst  

E-Print Network (OSTI)

by the Renewable Energy Research Laboratory (RERL) at the University of Massachusetts, Amherst. Wind monitoring. This graph shows the trends in the wind speed over the year. March 18, 2008 Renewable Energy Research and diurnal average plots, and wind roses are included in APPENDIX B. March 18, 2008 Renewable Energy Research

Massachusetts at Amherst, University of

177

DISMANTLING OF THE REACTOR BLOCK OF THE FRJ-1 RESEARCH REACTOR (MERLIN)  

SciTech Connect

This report describes the past procedure in dismantling the reactor block of the FRJ-1 research reactor (MERLIN). Furthermore, it gives an outlook on future activities up to the final removal of the reactor block. MERLIN is an abbreviation for Medium Energy Research Light Water Moderated Industrial Nuclear Reactor. The FRJ-1 (MERLIN) was shut down in 1985 and the fuel elements removed from the facility. After dismantling the coolant loops and removing the reactor tank internals with subsequent draining of the reactor tank water, the first activities for dismantling the reactor block were carried out in summer 2001. The relevant license was granted in late July 2001 by the licensing authority specifying 8 incidental provisions. After dismantling the reactor extension (gates of the thermal columns and steel platforms surrounding the reactor block), a heavy-load platform including a casing around the reactor block was constructed. Two ventilation systems with a volume flow of 10,000 and 2 ,000 m3/h will, moreover, serve to avoid a spread of contamination. The reactor block will be dismantled in three phases divided according to upper, central and bottom sections. Dismantling the upper section started in August 2002. This section as well as the bottom section can probably be completely measured for clearance. For this reason, the activities have so far been carried out manually using mechanical and thermal techniques. The central section will probably have to be largely disposed of as radioactive waste. This is the region of the former reactor core in which the experimental devices are also integrated. Most of this work will probably have to be carried out by remote handling. More than 80 % of the dismantled materials of the reactor block can probably be measured for clearance. For this purpose, a clearance measurement device was taken into operation in the FRJ-1. On this occasion, the limits of clearance measurement have become evident. For concrete, which constitutes the largest portion of the dismantled materials by volume, an additional conditioning step has become necessary to fulfill the clearance criteria, whereas waste packages with steel components largely have to be reconditioned once more at a later stage. Material measured for clearance will be disposed of conventionally (recycling, landfill) after inspection by the official expert and clearance by the regulatory authority. Dismantled parts that cannot be measured for clearance will be transferred to the Decontamination Department of the Research Centre. From the present perspective, the dismantling of the reactor block will be completed within the first six months of 2003.

Stahn, B.; Matela, K.; Zehbe, C.; Poeppinghaus, J.; Cremer, J.

2003-02-27T23:59:59.000Z

178

LEU conversion status of US research reactors, September 1996  

SciTech Connect

This paper summarizes the conversion status of research and test reactors in the United States from the use of fuels containing highly- enriched uranium (HEU, greater than or equal to 20%) to the use of fuels containing low-enriched uranium (LEU, < 20%). Estimates of the uranium densities required for conversion are made for reactors with power levels greater than or equal to 1 MW that are not currently involved in the LEU conversion process.

Matos, J.E.

1996-10-07T23:59:59.000Z

179

LWZ-0023 - In the Matter of Universities Research Association, Inc. |  

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

LWZ-0023 - In the Matter of Universities Research Association, Inc. LWZ-0023 - In the Matter of Universities Research Association, Inc. LWZ-0023 - In the Matter of Universities Research Association, Inc. Universities Research Association, Inc. (URA) is the management and operating contractor for the Department of Energy's (the DOE) Superconducting Super Collider Laboratory (the Laboratory) in Waxahachie, Texas. On February 4, 1993, Dr. Naresh C. Mehta, a former physicist at the Laboratory, filed complaint SSC-93-0001 against URA under 10 C.F.R. Part 708 (the "Whistleblower Regulations"). In his complaint, Mehta alleged that URA had terminated his employment because he had charged URA officials with mismanaging the Laboratory's hypercube computer. 1/ The DOE referred Mehta's complaint to its Office of Contractor Employee

180

University Teams Lead Innovative Solar Research Projects | Department of  

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

Lead Innovative Solar Research Projects Lead Innovative Solar Research Projects University Teams Lead Innovative Solar Research Projects August 28, 2012 - 2:55pm Addthis A concentrating solar power system in Albuquerque, New Mexico. | Photo by Randy Montoya/Sandia National Laboratory. A concentrating solar power system in Albuquerque, New Mexico. | Photo by Randy Montoya/Sandia National Laboratory. Erin R. Pierce Erin R. Pierce Digital Communications Specialist, Office of Public Affairs What are the key facts? The Energy Department is investing in two university-led projects to improve the performance of concentrated solar power systems. Research teams at the University of California, Los Angeles and the University of Arizona are launching projects aimed at improving the performance and lowering costs of solar energy systems.

Note: This page contains sample records for the topic "university research reactor" 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

Building Energy and Environment Research in Tianjin University...  

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

Building Energy and Environment Research in Tianjin University and Biological Particle Filtration and Removal Speaker(s): Guanyi Chen Junjie Liu Date: June 28, 2007 - 12:00pm...

182

LWA-0003 - In the Matter of Universities Research Association, Inc. |  

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

In the Matter of Universities Research Association, Inc. In the Matter of Universities Research Association, Inc. LWA-0003 - In the Matter of Universities Research Association, Inc. Universities Research Association, Inc. (URA) manages and operates the Department of Energy's Superconducting Super Collider Laboratory (the Laboratory) in Waxahachie, Texas. On October 27, 1992, URA notified Dr. Naresh Mehta, a physicist at the Laboratory, that it was dismissing him from his employment. Mehta subsequently filed a complaint of reprisal under the provisions of the Department of Energy's Contractor Employee Protection Program, 10 C.F.R. Part 708 (the Whistleblower Regulations). In his complaint, Mehta alleged that URA had dismissed him because he had charged URA with mismanaging the Laboratory's hypercube computer.

183

An NSF Industry/University Cooperative Research Program CCMC PROSPECTUS  

E-Print Network (OSTI)

An NSF Industry/University Cooperative Research Program CCMC PROSPECTUS May 2005 CERAMIC ........................................................................................21 #12;PROSPECTUS, MAY 2005 3 EXECUTIVE SUMMARY Ceramic and Composite Materials Center NSF Industry...................................................................................................................8 Industrial Advisory Board

184

Biomedical Engineering Bionanosystems Research at Louisiana Tech University  

DOE Green Energy (OSTI)

The nature of this project is to equip and support research in nanoengineered systems for biomedical, bioenvironmental, and bioenergy applications. Funds provided by the Department of Energy (DoE) under this Congressional Directive were used to support two ongoing research projects at Louisiana Tech University in biomedical, bioenvironmental, and bioenergy applications. Two major projects (Enzyme Immobilization for Large Scale Reactors to Reduce Cellulosic Ethanol Costs, and Nanocatalysts for Coal and Biomass Conversion to Diesel Fuel) and to fund three to five additional seed projects were funded using the project budget. The project funds also allowed the purchase and repair of sophisticated research equipment that will support continued research in these areas for many years to come. Project funds also supported faculty, graduate students, and undergraduate students, contributing to the development of a technically sophisticated work force in the region and the State. Descriptions of the technical accomplishments for each funded project are provided. Biofuels are an important part of the solution for sustainable transportation fuel and energy production for the future. Unfortunately, the country's appetite for fuel cannot be satisfied with traditional sugar crops such as sugar cane or corn. Emerging technologies are allowing cellulosic biomass (wood, grass, stalks, etc.) to also be converted into ethanol. Cellulosic ethanol does not compete with food production and it has the potential to decrease greenhouse gas (GHG) emissions by 86% versus current fossil fuels (current techniques for corn ethanol only reduce greenhouse gases by 19%). Because of these advantages, the federal government has made cellulosic ethanol a high priority. The Energy Independence and Security Act of 2007 (EISA) requires a minimum production of at least 16 billion gallons of cellulosic ethanol by 2022. Indeed, the Obama administration has signaled an ambitious commitment of achieving 2 billion gallons of cellulosic ethanol by 2013. Louisiana is well positioned to become a national contributor in cellulosic ethanol, with an excellent growing season, a strong pulp/paper industry, and one of the nation's first cellulosic ethanol demonstration plants. Dr. Palmer in Chemical Engineering at Louisiana Tech University is collaborating with Drs. Lvov and Snow in Chemistry and Dr. Hegab in Mechanical Engineering to capitalize on these advantages by applying nanotechnology to improve the cellulosic ethanol processes. In many of these processes, expensive enzymes are used to convert the cellulose to sugars. The nanotechnology processes developed at Louisiana Tech University can immobilize these enzymes and therefore significantly reduce the overall costs of the process. Estimates of savings range from approximately $32 million at each cellulosic ethanol plant, to $7.5 billion total if the 16 billion gallons of cellulosic ethanol is achieved. This process has the advantage of being easy to apply in a large-scale commercial environment and can immobilize a wide variety or mixture of enzymes for production. Two primary objectives with any immobilization technique are to demonstrate reusability and catalytic activity (both reuse of the immobilized enzyme and reuse of the polymer substrate). The scale-up of the layering-by-layering process has been a focus this past year as some interesting challenges in the surface chemistry have become evident. Catalytic activity of cellulase is highly dependent upon how the feed material is pretreated to enhance digestion. Therefore, efforts this year have been performed this year to characterize our process on a few of the more prevalent pretreatment methods.

Palmer, James; Lvov, Yuri; Hegab, Hisham; Snow, Dale; Wilson, Chester; McDonald, John; Walker, Lynn; Pratt, Jon; Davis, Despina; Agarwal, Mangilal; DeCoster, Mark; Feng, June; Que, Long; O'Neal, Chad; Guilbeau, Eric; Zivanovic, Sandra; Dobbins, Tabbetha; Gold, Scott; Mainardi, Daniela; Gowda, Shathabish; Napper, Stan

2010-03-25T23:59:59.000Z

185

University of Arizona Research Computing 2012  

E-Print Network (OSTI)

in High Performance Computing and High Throughput Computing (HPC/HTC) and storage will greatly advance, the new Research Data Center houses our next generation of High Performance Computing (HPC), High on interdisciplinary concepts and on collaborations with industry. Our reliance on high performance computing

Lega, Joceline

186

University Crystalline Silicon Photovoltaics Research and Development  

DOE Green Energy (OSTI)

The overall goal of the program is to advance the current state of crystalline silicon solar cell technology to make photovoltaics more competitive with conventional energy sources. This program emphasizes fundamental and applied research that results in low-cost, high-efficiency cells on commercial silicon substrates with strong involvement of the PV industry, and support a very strong photovoltaics education program in the US based on classroom education and hands-on training in the laboratory.

Ajeet Rohatgi; Vijay Yelundur; Abasifreke Ebong; Dong Seop Kim

2008-08-18T23:59:59.000Z

187

Reduced enrichment for research and test reactors: Proceedings  

SciTech Connect

The international effort to develop new research reactor fuel materials and designs based on the use of low-enriched uranium, instead of highly-enriched uranium, has made much progress during the eight years since its inception. To foster direct communication and exchange of ideas among the specialist in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the ninth of a series which began in 1978. All previous meetings of this series are listed on the facing page. The focus of this meeting was on the LEU fuel demonstration which was in progress at the Oak Ridge Research (ORR) reactor, not far from where the meeting was held. The visit to the ORR, where a silicide LEU fuel with 4.8 g A/cm/sup 3/ was by then in routine use, illustrated how far work has progressed.

1988-05-01T23:59:59.000Z

188

Obama Administration Announces Clean Coal Research Awards for Universities  

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

Obama Administration Announces Clean Coal Research Awards for Obama Administration Announces Clean Coal Research Awards for Universities Across the Country Obama Administration Announces Clean Coal Research Awards for Universities Across the Country June 6, 2012 - 12:18pm Addthis News Media Contact (202) 586-4940 WASHINGTON, D.C.- As part of President Obama's all-of-the-above approach to American energy, the Energy Department announced that nine universities have won awards for research projects that will continue to support innovation and development of clean coal technologies. The awards, which will leverage student-led teams across the country as they continue research and development of new technologies and materials that will advance clean coal energy production, are part of the Administration's focus on ensuring we can rely on a broad range of energy sources as we move

189

Obama Administration Announces Clean Coal Research Awards for Universities  

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

Clean Coal Research Awards for Clean Coal Research Awards for Universities Across the Country Obama Administration Announces Clean Coal Research Awards for Universities Across the Country June 6, 2012 - 12:18pm Addthis News Media Contact (202) 586-4940 WASHINGTON, D.C.- As part of President Obama's all-of-the-above approach to American energy, the Energy Department announced that nine universities have won awards for research projects that will continue to support innovation and development of clean coal technologies. The awards, which will leverage student-led teams across the country as they continue research and development of new technologies and materials that will advance clean coal energy production, are part of the Administration's focus on ensuring we can rely on a broad range of energy sources as we move

190

Boise State University, CAES Energy Efficiency Research Institute | Open  

Open Energy Info (EERE)

Boise State University, CAES Energy Efficiency Research Institute Boise State University, CAES Energy Efficiency Research Institute Jump to: navigation, search Name Boise State University, CAES Energy Efficiency Research Institute Address 1910 University Drive Place Boise, Idaho Zip 83725 Coordinates 43.6056603°, -116.2059975° 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":43.6056603,"lon":-116.2059975,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

191

NETL Publications: 2011 University Turbine Systems Research Workshop  

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

2011 University Turbine Systems Research Workshop 2011 University Turbine Systems Research Workshop October 25-27, 2011 PRESENTATIONS Tuesday, October 25, 2011 H2 Turbine Development for IGCC with CCS: Project Overviews and Technical Issues [PDF-1.12MB] Susan Scofield, Siemens Energy, Inc. GE Energy's DOE Advanced IGCC/Hydrogen Gas Turbine Program [PDF-1.16MB] Roger Schonewald, GE Energy DOE FE Hydrogen Turbine Program Overview [PDF-1.66MB] Richard Dennis, U.S. Department of Energy, National Energy Technology Laboratory Natural Gas Combined Cycle Power Generation [PDF-1.56MB] Robert Steele, Electric Power Research Institute Overview of Gas Turbine R&D at The Ohio State University [PDF-6.02MB] Meyer (Mike) Benzakein, Director of The Ohio State University's Center for Propulsion and Power An Experimental and Chemical Kinetics Study of the Combustion of Syngas and High Hydrogen Content Fuels [PDF-1.61MB]

192

NETL: News Release - Secretary Abraham Announces University Coal Research  

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

June 11, 2003 June 11, 2003 Secretary Abraham Announces University Coal Research Grants for 2003 Student-Based Projects Combine Education with Fundamental Studies of Coal Science & Technology WASHINGTON, DC - Seventeen universities in 14 states will receive $2.8 million in fossil energy research grants through a Department of Energy (DOE) program that brings science, university students and their professors together to advance the study of new clean and efficient coal-use technologies and concepts. "This is just one of the many steps the Department of Energy has taken to ensure that clean coal technology remains an effective element in President Bush?s Clear Skies Initiative," Secretary Spencer Abraham said. "We?ve already achieved many successes in the clean coal program, and I expect the 2003 University Coal Research projects will take us even further towards reducing air pollution and improving air quality throughout the nation."

193

NETL: News Release - Six Minority Universities Win Fossil Energy Research  

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

August 7, 1995 August 7, 1995 DOE Adds New Fossil Energy Projects to Historically Black Colleges and Universities Grant Program WASHINGTON, DC - As part of its efforts to encourage more participation by minority college students and teachers in its national energy program, the Department of Energy (DOE) has selected seven natural gas, oil, and coal research projects to be carried out by teacher-student teams at historically black colleges and universities. The institutions will receive Federal research grants, each totalling $100,000 to $200,000, for fundamental research in topics ranging from improved oil and gas recovery and to the environmentally cleaner use of coal. One university, Clark Atlanta University, will also receive a separate smaller grant for a 1-year exploratory effort in oil processing.

194

NETL Publications: 2012 University Coal Research/ Historically Black  

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

2012 University Coal Research/ Historically Black Colleges and Universities and Other Minority Institutions Contractors Review Conference 2012 University Coal Research/ Historically Black Colleges and Universities and Other Minority Institutions Contractors Review Conference May 30-31, 2012 Table of Contents Disclaimer Sensors & Controls Advanced Materials (Day 1) Advanced Materials (Day 2) Computational Energy Sciences PRESENTATIONS Introduction and Opening Remarks Robert Romanosky, Technology Manager, Crosscutting Research Robie Lewis, UCR Program Coordinator, Federal Project Manager, Fuels Division Steven Markovich, HBCU Program Coordinator, Federal Project Manager, Fuels Division Presentation [PDF-783KB] Sensor & Controls Moderator: Rick Dunst, Federal Project Manager, Gasification Division U.S. Department of Energy, National Energy Technology Laboratory Heat Activated Plasmonics Based Harsh Environment Chemical Sensors

195

Reactor Safety Research: Semiannual report, July-December 1986  

DOE Green Energy (OSTI)

Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of the accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance and behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the tehcnology base supporting licensing decisions.

Not Available

1987-11-01T23:59:59.000Z

196

Research capacity development of individuals at three South African university research centres.  

E-Print Network (OSTI)

?? In South Africa, there has been recognition of the need for increasing research capacity at South African universities and within the national science system.… (more)

Dison, Arona.

2007-01-01T23:59:59.000Z

197

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

198

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.

199

Center for Transportation Training and Research Texas Southern University  

E-Print Network (OSTI)

Center for Transportation Training and Research Texas Southern University Khosro Godazi Associate Director, Center for Transportation Training and Research, and SWUTC Associate Director for Transportation.S. in City Planning. He is Director of 4-week Texas Summer Transportation Institute that has been held

200

Center for Transportation Training and Research Texas Southern University  

E-Print Network (OSTI)

Center for Transportation Training and Research Texas Southern University Carol Lewis, Ph.D. Director, Center for Transportation Training and Research, and SWUTC Executive Committee Member Texas is an Associate Professor in Transportation Studies and Direc- tor of the Center for Transportation Training

Note: This page contains sample records for the topic "university research reactor" 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

Renewable Energy Research Laboratory University of Massachusetts, Amherst  

E-Print Network (OSTI)

by the Renewable Energy Research Laboratory (RERL) at the University of Massachusetts, Amherst. Wind monitoring/RERL_Fact_Sheet_6_Wind_resource_interpretation.pdf * 1 m/s = 2.237 mph. July 17, 2009 Renewable Energy Research 5 0 Figure 2 ­ Wind Speed Time Series, March 1, 2009 ­ May 31, 2009 July 17, 2009 Renewable Energy

Massachusetts at Amherst, University of

202

Renewable Energy Research Laboratory University of Massachusetts, Amherst  

E-Print Network (OSTI)

Distributions Figure 3­ Wind Speed Distribution, March 1, 2008 ­ May 31, 2008. August 21, 2008 Renewable Energy Average Wind Speeds, 30 m, March 1, 2008 ­ May 31, 2008. August 21, 2008 Renewable Energy Research Energy Research Laboratory Page 20 University of Massachusetts, Amherst Amherst, MA 01003 Wind Rose Data

Massachusetts at Amherst, University of

203

DOE - Office of Legacy Management -- Brown University - Metcalf Research  

Office of Legacy Management (LM)

Brown University - Metcalf Research Brown University - Metcalf Research Lab - RI 01 FUSRAP Considered Sites Site: Brown University (Metcalf Research Lab.) (RI.01 ) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Providence , Rhode Island RI.01-1 Evaluation Year: 1987 RI.01-1 Site Operations: Research/Development on the preparation of pure halides of heavy metals, Bench Scale Process, and Sample & Analysis. RI.01-1 Site Disposition: Eliminated - Potential for residual radioactive contamination from small quantities of radioactive material is considered remote RI.01-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium, Thorium RI.01-1 Radiological Survey(s): None Indicated

204

RERTR 2009 (Reduced Enrichment for Research and Test Reactors)  

SciTech Connect

The U.S. Department of Energy/National Nuclear Security Administration's Office of Global Threat Reduction in cooperation with the China Atomic Energy Authority and International Atomic Energy Agency hosted the 'RERTR 2009 International Meeting on Reduced Enrichment for Research and Test Reactors.' The meeting was organized by Argonne National Laboratory, China Institute of Atomic Energy and Idaho National Laboratory and was held in Beijing, China from November 1-5, 2009. This was the 31st annual meeting in a series on the same general subject regarding the conversion of reactors within the Global Threat Reduction Initiative (GTRI). The Reduced Enrichment for Research and Test Reactors (RERTR) Program develops technology necessary to enable the conversion of civilian facilities using high enriched uranium (HEU) to low enriched uranium (LEU) fuels and targets.

Totev, T.; Stevens, J.; Kim, Y. S.; Hofman, G.; Matos, J.; Hanan, N.; Garner, P.; Dionne, B.; Olson, A.; Feldman, E.; Dunn, F.; Nuclear Engineering Division; Atomic Research Center; Inst. of Nuclear Physics; LLNL; INL; Korea Atomic Energy Research Inst.; Comisi?n Nacional de Energ?a At?mica; Nuclear Reactor Lab.; Inst. of Atomic Energy-Poland; AECL-Canada; Hungarian Academy of Sciences KFKI Atomic Energy Research Inst.; Japan Atomic Energy Agency; Nuclear Power Inst. of China; Kyoto Univ. Research Reactor Inst.

2010-03-01T23:59:59.000Z

205

Research Results and Further Opportunities Resulting from Collaboration with Electricity Research Centre, University College Dublin  

Science Conference Proceedings (OSTI)

In 2010, the Electric Power Research Institute (EPRI) research program on Integration of Bulk System Variable Generation (Program 173) funded the Electricity Research Centre (ERC). The ERC is an industry/university research collaboration, funded by 14 industry entities as well as other government funding agencies, based in electrical engineering at University College Dublin with an energy economics branch at Trinity College Dublin. The work performed focuses primarily on renewable generation integration;...

2011-08-30T23:59:59.000Z

206

Reactor Safety Research Programs Quarterly Report October - December 1980  

SciTech Connect

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from October 1 through December 31, 1980, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining structural graphite strength, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NOE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation and postaccident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S K

1981-04-01T23:59:59.000Z

207

The Government-University-Industry Research Roundtable 1996 annual report  

SciTech Connect

The Government-University-Industry Research Roundtable was created just over a decade ago to provide a unique forum for dialogue among top government, university, and industry leaders in the national science and technology enterprise. The purpose is to facilitate personal working relationships and exchange of ideas about issues, problems, and promising opportunities facing those charged with developing and deploying science and technology resources. In 1996, Council meetings focused on the following: (1) the impact of information technology on the structure of research and educational organizations; (2) ways to improve communication between the science and engineering community and the public; and (3) new approaches both to measuring the results of research investments, and to communicating those metrics to non-technical decision-makers and to the public. Significant milestones were also achieved in four major projects, representing, impart, follow-up activity from previous Council Meeting discussions: (1) facilitating the Federal Demonstration Partnership, designed to maximize the efficiency of the federal research support system; (2) compiling results of a regional workshop on experiences in industry-university collaborative organization; (3) publishing the results of a study comparing the cost structures for research performed in the industrial, academic, and government laboratory sector; and (4) catalyzing, and participating in, a series of campus-based convocations on stresses being experienced in the research university environment.

1996-12-31T23:59:59.000Z

208

The Government-University-Industry Research Roundtable 1995 annual report  

SciTech Connect

The Government-University-Industry Research Roundtable was created just over a decade ago to provide a unique forum for dialogue among top government, university, and industry leaders of the national science and technology enterprise. The purpose is to facilitate personal working relationships and exchange of ideas about issues, problems, and promising opportunities that are facing those charged with developing and deploying science and technology resources. The open dialogue and informal exchange of ideas preclude a process of making formal recommendations or offering specific advice. Instead, the Roundtable seeks to stimulate new approaches by dissemination of its discussions, and pro-active contacts with organizations that may want to build on the idea base it establishes. After introductory material on the structure and operation of the Roundtable, accomplishments on current projects are described. Projects include: Stresses on research and education at colleges and universities; Formulating US research policies within an international context; The Federal Demonstration project, designed to improve the management of federally-funded research; Analysis of the costs of research in industrial, academic, and federal labs; Industry-university research collaborations; and Public stakeholding in America`s investment in science and technology.

1995-12-31T23:59:59.000Z

209

NETL: News Release - Six Minority Universities Win Fossil Energy Research  

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

May 24, 2000 May 24, 2000 Six Minority Universities Win Fossil Energy Research Grants to Advance Use of Oil, Coal, Gas Richardson, Browner Announce Government "Showcase" Project As part of the Department of Energy's continuing efforts to increase the involvement of the nation's minority institutions in energy research, Energy Secretary Bill Richardson today announced that six historically black universities and other minority institutions will share nearly $1 million in federal funding for fossil energy projects ranging from oil reservoir characterization to burner design for low-emission burners to pollution reduction from car engines. The winning schools are: Prairie View A&M University, Prairie View, TX, (2 projects): one for research into a new way of determining the geologic characteristics of complex oil reservoirs; the other for testing a new data analysis technique based on neural networks that could simplify modeling of the way fuel burns in a compression ignition engine, such as a diesel engine;

210

NETL: News Release - Six Minority Universities Selected for Energy Research  

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

November 28, 2005 November 28, 2005 Six Minority Universities Selected for Energy Research Grants Projects to Advance Methane Hydrate Research, Produce Hydrogen, and Improve Oil Recovery Among Selections Washington, DC - The Department of Energy has selected six institutions to receive grants for energy research through its Historically Black Colleges and Universities and Other Minority Institutions (HBCU/OMI) program. Carried out under the Energy Department's Office of Fossil Energy, the program gives students hands-on experience in developing technologies to promote the efficient and environmentally safe use of coal, oil, and natural gas. "I'm pleased to see the strong interest of faculty in conducting this research and training a promising group of college students," said Mark Maddox, Principal Deputy Assistant Secretary for Fossil Energy. "Their activities promote our nation's energy security and the educational growth of future energy researchers."

211

DOE - Office of Legacy Management -- University of Utah Medical Research  

Office of Legacy Management (LM)

Utah Medical Research Utah Medical Research Center - UT 02 FUSRAP Considered Sites Site: UNIVERSITY OF UTAH, MEDICAL RESEARCH CENTER (UT.02) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Salt Lake City , Utah UT.02-2 Evaluation Year: 1987 UT.02-1 Site Operations: Research and development on animal inhalation of uranium dust during the 1950s. UT.02-2 Site Disposition: Eliminated - Radiation levels below criteria UT.02-1 UT.02-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium UT.02-2 Radiological Survey(s): Yes UT.02-2 Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to UNIVERSITY OF UTAH, MEDICAL RESEARCH CENTER UT.02-1 - DOE Letter; Fiore to Schiager; Subject: Elimination of

212

Development of Technical Nuclear Forensics for Spent Research Reactor Fuel  

E-Print Network (OSTI)

Pre-detonation technical nuclear forensics techniques for research reactor spent fuel were developed in a collaborative project with Savannah River National Lab ratory. An inverse analysis method was employed to reconstruct reactor parameters from a spent fuel sample using results from a radiochemical analysis. In the inverse analysis, a reactor physics code is used as a forward model. Verification and validation of different reactor physics codes was performed for usage in the inverse analysis. The verification and validation process consisted of two parts. The first is a variance analysis of Monte Carlo reactor physics burnup simulation results. The codes used in this work are MONTEBURNS and MCNPX/CINDER. Both utilize Monte Carlo transport calculations for reaction rate and flux results. Neither code has a variance analysis that will propagate through depletion steps, so a method to quantify and understand the variance propagation through these depletion calculations was developed. The second verification and validation process consisted of comparing reactor physics code output isotopic compositions to radiochemical analysis results. A sample from an Oak Ridge Research Reactor spent fuel assembly was acquired through a drilling process. This sample was then dissolved in nitric acid and diluted in three different quantities, creating three separate samples. A radiochemical analysis was completed and the results were compared to simulation outputs at different levels ofdetail. After establishing a forward model, an inverse analysis was developed to re-construct the burnup, initial uranium isotopic compositions, and cooling time of a research reactor spent fuel sample. A convergence acceleration technique was used that consisted of an analytical calculation to predict burnup, initial 235U, and 236U enrichments. The analytic calculation results may also be used stand alone or in a database search algorithm. In this work, a reactor physics code is used as a for- ward model with the analytic results as initial conditions in a numerical optimization algorithm. In the numerical analysis, the burnup and initial uranium isotopic com- positions are reconstructed until the iterative spent fuel characteristics converge with the measured data. Upon convergence of the sample’s burnup and initial uranium isotopic composition, the cooling time can be reconstructed. To reconstruct cooling time, the standard decay equation is inverted and solved for time. Two methods were developed. One method uses the converged burnup and initial uranium isotopic compositions along in a reactor depletion simulation. The second method uses an isotopic signature that does not decay out of its mass bin and has a simple production chain. An example would be 137Cs which decays into the stable 137Ba. Similar results are achieved with both methods, but extended shutdown time or time away from power results in over prediction of the cooling time. The over prediction of cooling time and comparison of different burnup reconstruction isotope results are indicator signatures of extended shutdown or time away from power. Due to dynamic operation in time and function, detailed power history reconstruction for research reactors is very challenging. Frequent variations in power, repeated variable shutdown time length, and experimentation history affect the spectrum an individual assembly is burned with such that full reactor parameter reconstruction is difficult. The results from this technical nuclear forensic analysis may be used with law enforcement, intelligence data, macroscopic and microscopic sample characteristics in a process called attribution to suggest or exclude possible sources of origin for a sample.

Sternat, Matthew 1982-

2012-12-01T23:59:59.000Z

213

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH & ANALYTICAL STUDIES  

E-Print Network (OSTI)

CALIFORNIA STATE UNIVERSITY, FULLERTON INSTITUTIONAL RESEARCH & ANALYTICAL STUDIES NUMBER OF CALIFORNIA HIGH SCHOOL GRADUATES IN SELECTED COUNTIES/REGIONS Data from the State of California, Department,741 46% 171,201 45% 171,029 46% California Total 298,602 100% 382,924 100% 368,011 100% #12;CALIFORNIA

de Lijser, Peter

214

Center for Transportation Training and Research Texas Southern University  

E-Print Network (OSTI)

Center for Transportation Training and Research Texas Southern University Lei Yu, Ph.D., P.E. Professor of Transportation and Dean College of Science and Technology, and SWUTC Executive Committee Member and Technology, Industrial Technol- ogy, Mathematics, Physics, and Transportation Studies. He also oversees

215

Reactor core design and modeling of the MIT research reactor for conversion to LEU  

SciTech Connect

Feasibility design studies for conversion of the MIT Research Reactor (MITR) to LEU are described. Because the reactor fuel has a rhombic cross section, a special input processor was created in order to model the reactor in great detail with the REBUS-PC diffusion theory code, in 3D (triangular-z) geometry. Comparisons are made of fuel assembly power distributions and control blade worth vs. axial position, between REBUS-PC results and Monte Carlo predictions from the MCNP code. Results for the original HEU core at zero burnup are also compared with measurement. These two analysis methods showed remarkable agreement. Ongoing fuel cycle studies are summarized. A status report will be given as to results thus far that affect key design decisions. Future work plans and schedules to achieve completion of the conversion are presented. (author)

Newton, Thomas H. Jr. [Nuclear Reactor Laboratory, Massachusetts Institute of Technology, 138 Albany St., Cambridge, MA 02139 (United States); Olson, Arne P.; Stillman, John A. [RERTR Program, Argonne National Laboratory, Argonne, IL 60439 (United States)

2008-07-15T23:59:59.000Z

216

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

SciTech Connect

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

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

2010-01-21T23:59:59.000Z

217

Design and optimization of a high thermal flux research reactor via Kriging-based algorithm  

E-Print Network (OSTI)

In response to increasing demands for the services of research reactors, a 5 MW LEU-fueled research reactor core is developed and optimized to provide high thermal flux within specified limits upon thermal hydraulic ...

Kempf, Stephanie Anne

2011-01-01T23:59:59.000Z

218

Friction pressure drop measurements and flow distribution analysis for LEU conversion study of MIT Research Reactor  

E-Print Network (OSTI)

The MIT Nuclear Research Reactor (MITR) is the only research reactor in the United States that utilizes plate-type fuel elements with longitudinal fins to augment heat transfer. Recent studies on the conversion to low-enriched ...

Wong, Susanna Yuen-Ting

2008-01-01T23:59:59.000Z

219

NETL: News Release - Six Minority Universities Win Fossil Energy Research  

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

August 3, 1996 August 3, 1996 Seven Historically Black Colleges Win Support for Fossil Energy R&D WASHINGTON, DC - As part of its efforts to encourage more participation by minority college students and teachers in its national energy program, the Department of Energy (DOE) has selected seven coal, natural gas, and oil research projects to be carried out by student-teacher teams at six Historically Black Colleges and Universities (HBCU). Six of the winning schools will partner with private sector companies and receive Federal research grants totaling $100,000 to $200,000 each. The industry-university partnerships will focus on environmental research in natural gas and oil exploration and production, advanced methods for cleaning sulfur and nitrogen pollutants from coal, and innovative coal use technologies.

220

NETL: News Release - Six Minority Universities Selected for Energy Research  

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

June 21, 2005 June 21, 2005 Eight Minority Universities Selected for Fossil Energy Research Grants College Students to Focus on Projects for Clean, Efficient Use of Coal WASHINGTON, DC - The Department of Energy has awarded grants to eight institutions for energy research through the Historically Black Colleges and Universities and Other Minority Institutions (HBCU) program. "It is a pleasure to see strong interest and participation in the HBCU program by such a promising group of college students," said Mark Maddox, principal deputy assistant secretary for fossil energy. "These bright minds are the key to fossil energy research of the future. The opportunity to participate in the program will not only benefit the students' educational growth but will also help secure our Nation's energy future."

Note: This page contains sample records for the topic "university research reactor" 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

MODULAR PEBBLE BED REACTOR PROJECT UNIVERSITY RESEARCH CONSORTIUM  

E-Print Network (OSTI)

of plant, steady-state thermal hydraulics model has been developed to represent all major components.1.1 Plant Description ..................................................................... 48 4.1.2 Power is to be adequately represented. Table 2-5. Results from Thermal Model Calculations Pebble Power! Axial Location! Loc

222

Initiation of a phase-I trial of neutron capture therapy at the MIT research reactor  

Science Conference Proceedings (OSTI)

The Massachusetts Institute of Technology (MIT), the New England Medical Center (NEMC), and Boston University Medical Center (BUMC) initiated a phase-1 trial of boron neutron capture therapy (BNCT) on September 6, 1994, at the 5-MW(thermal) MIT research reactor (MITR). A novel form of experimental cancer therapy, BNCT is being developed for certain types of highly malignant brain tumors such as glioblastoma and melanoma. The results of the phase-1 trials on patients with tumors in the legs or feet are described.

Harling, O.K.; Bernard, J.A.; Yam, Chun-Shan [Massachussets Institute of Technology, Cambridge, MA (United States)] [and others

1995-12-31T23:59:59.000Z

223

Heat Island Research at the University of Athens  

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

Heat Island Research at the University of Athens Heat Island Research at the University of Athens Speaker(s): Mattheos Santamouris Date: June 4, 2008 - 12:00pm Location: 90-3122 Seminar Host/Point of Contact: Hashem Akbari Athens, as many other metropolitan areas, is experiencing a severe summer heat island. We will present measurements of urban canyon heat islands in Athens and discuss the effects on building energy use, urban environment, and air quality. Appropriate heat-island mitigation technologies include use of cool materials for urban surfaces (roofs and pavements) and shade trees. Advances in development of cool roofing and paving materials including traditional cool surfaces (white and light-colored materials), near-infrared cool colored materials, and experimental highly reflecting thermochromic coatings will be discussed. Finally, we will discuss the

224

NETL: 2010 Conference Proceedings - University Turbine Systems Research  

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

University Turbine Systems Research Workshop University Turbine Systems Research Workshop October 19-21, 2010 Table of Contents Disclaimer Presentations Tuesday, October 19, 2010 Keynote Presentations Combustion Aero/Heat Transfer Wednesday, October 20, 2010 Keynote Presentations Aerodynamics/Heat Transfer Materials Combustion Thursday, October 21, 2010 Keynote Presentations Combustion Materials and Aerodynamics/Heat Transfer Poster Presenters PRESENTATIONS Tuesday, October 19. 2010 Keynote Presentations GE Perspectives - Advanced IGCC/Hydrogen Gas Turbine Development [PDF-629KB] Reed Anderson, GE Energy Siemens Perspectives - Advanced IGCC/Hydrogen Gas Turbine Development [PDF-2.2MB] Joe Fadok, Siemens Energy, Inc DOE Advanced Turbines Program Overview [PDF-284KB] Richard Dennis, National Energy Technology Laboratory

225

NETL: News Release - Universities Begin Critical Turbine Systems Research  

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

30, 2008 30, 2008 Universities Begin Critical Turbine Systems Research WASHINGTON, D.C. - The U.S. Department of Energy announced the selection of four projects under the Office of Fossil Energy's University Turbine Systems Research (UTSR) Program. The projects will develop technologies for use in the new generation of advanced turbines that operate cleanly and efficiently when fueled with coal-derived synthesis gas and hydrogen fuels. The overall goal of the Department of Energy's (DOE) Turbine Program is to provide high-efficiency, near-zero emissions and lower-cost turbines for coal-based stationary power systems. Developing turbine technology to operate on high hydrogen content (HHC) fuels derived from coal synthesis gas is critical to the development of advanced, near-zero-emission integrated gasification combined cycle (IGCC) power generation plants that separate and capture carbon dioxide (CO2).

226

SUPPLEMENT ANALYSIS OF FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL  

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

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

227

Advanced sodium fast reactor accident source terms : research needs.  

Science Conference Proceedings (OSTI)

An expert opinion elicitation has been used to evaluate phenomena that could affect releases of radionuclides during accidents at sodium-cooled fast reactors. The intent was to identify research needed to develop a mechanistic model of radionuclide release for licensing and risk assessment purposes. Experts from the USA, France, the European Union, and Japan identified phenomena that could affect the release of radionuclides under hypothesized accident conditions. They qualitatively evaluated the importance of these phenomena and the need for additional experimental research. The experts identified seven phenomena that are of high importance and have a high need for additional experimental research: High temperature release of radionuclides from fuel during an energetic eventEnergetic interactions between molten reactor fuel and sodium coolant and associated transfer of radionuclides from the fuel to the coolantEntrainment of fuel and sodium bond material during the depressurization of a fuel rod with breached claddingRates of radionuclide leaching from fuel by liquid sodiumSurface enrichment of sodium pools by dissolved and suspended radionuclidesThermal decomposition of sodium iodide in the containment atmosphereReactions of iodine species in the containment to form volatile organic iodides. Other issues of high importance were identified that might merit further research as development of the mechanistic model of radionuclide release progressed.

Powers, Dana Auburn; Clement, Bernard [IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France] IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France; Denning, Richard [Ohio State University, Columbus, OH] Ohio State University, Columbus, OH; Ohno, Shuji [Japan Atomic Energy Agency, Ibaraki, Japan] Japan Atomic Energy Agency, Ibaraki, Japan; Zeyen, Roland [Institute for Energy Petten, Saint-Paul-lez-Durance, France] Institute for Energy Petten, Saint-Paul-lez-Durance, France

2010-09-01T23:59:59.000Z

228

Advanced sodium fast reactor accident source terms : research needs.  

SciTech Connect

An expert opinion elicitation has been used to evaluate phenomena that could affect releases of radionuclides during accidents at sodium-cooled fast reactors. The intent was to identify research needed to develop a mechanistic model of radionuclide release for licensing and risk assessment purposes. Experts from the USA, France, the European Union, and Japan identified phenomena that could affect the release of radionuclides under hypothesized accident conditions. They qualitatively evaluated the importance of these phenomena and the need for additional experimental research. The experts identified seven phenomena that are of high importance and have a high need for additional experimental research: High temperature release of radionuclides from fuel during an energetic eventEnergetic interactions between molten reactor fuel and sodium coolant and associated transfer of radionuclides from the fuel to the coolantEntrainment of fuel and sodium bond material during the depressurization of a fuel rod with breached claddingRates of radionuclide leaching from fuel by liquid sodiumSurface enrichment of sodium pools by dissolved and suspended radionuclidesThermal decomposition of sodium iodide in the containment atmosphereReactions of iodine species in the containment to form volatile organic iodides. Other issues of high importance were identified that might merit further research as development of the mechanistic model of radionuclide release progressed.

Powers, Dana Auburn; Clement, Bernard [IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France] IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France; Denning, Richard [Ohio State University, Columbus, OH] Ohio State University, Columbus, OH; Ohno, Shuji [Japan Atomic Energy Agency, Ibaraki, Japan] Japan Atomic Energy Agency, Ibaraki, Japan; Zeyen, Roland [Institute for Energy Petten, Saint-Paul-lez-Durance, France] Institute for Energy Petten, Saint-Paul-lez-Durance, France

2010-09-01T23:59:59.000Z

229

Geothermal studies at the University of Utah Research Institute  

SciTech Connect

The University of Utah Research Institute (WRI) is a self-supporting corporation organized in December 1972 under the Utah Non-Profit Corporation Association Act. Under its charter, the Institute is separate in its operations and receives no direct financial support from either the University of Utah or the State of Utah. The charter includes provisions for WRI to conduct both public and proprietary scientific work for governmental agencies, academic institutions, private industry, and individuals. WRI is composed of five divisions, shown in Figure 1: the Earth Science Laboratory (ESL), the Environmental Studies Laboratory (EVSL), the Center for Remote Sensing and Cartography (CRSC), the Engineering Technology Laboratory (ETL) and the Atmospheric Physics Laboratory (APL). The Earth Science Laboratory has a staff of geologists, geochemists and geophysicists who have a broad range of experience in geothermal research and field projects as well as in mineral and petroleum exploration. The Environmental Studies Laboratory offers a variety of technical services and research capabilities in the areas of air quality and visibility, acid precipitation, surface and groundwater contamination, and environmentally caused stress in vegetation. The Center for Remote Sensing and Cartography offers applied research and services with a full range of remote sensing and mapping capability, including satellite and airborne imagery processing and interpretation. The Engineering Technology Laboratory is currently studying the interaction of the human body with electromagnetic radiation. The Atmospheric Physics Laboratory is developing hygroscopic droplet growth theory and orographic seeding models for dispersal of fog.

None

1988-07-01T23:59:59.000Z

230

Eastern Europe Research Reactor Initiative nuclear education and training courses - Current activities and future challenges  

Science Conference Proceedings (OSTI)

The Eastern Europe Research Reactor Initiative was established in January 2008 to enhance cooperation between the Research Reactors in Eastern Europe. It covers three areas of research reactor utilisation: irradiation of materials and fuel, radioisotope production, neutron beam experiments, education and training. In the field of education and training an EERRI training course was developed. The training programme has been elaborated with the purpose to assist IAEA Member States, which consider building a research reactor (RR) as a first step to develop nuclear competence and infrastructure in the Country. The major strength of the reactor is utilisation of three different research reactors and a lot of practical exercises. Due to high level of adaptability, the course can be tailored to specific needs of institutions with limited or no access to research reactors. (authors)

Snoj, L. [Josef Stefan Inst., Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Sklenka, L.; Rataj, J. [Dept. of Nuclear Reactor, Czech Technical Univ. in Prague, V Holesovickach 2, 180 00 Prague 8 (Czech Republic); Boeck, H. [Vienna Univ. of Technology/Atominstitut, Stadionallee 2, 1020 Vienna (Austria)

2012-07-01T23:59:59.000Z

231

Role of research reactors in training of NPP personnel with special focus on training reactor VR-1  

Science Conference Proceedings (OSTI)

Research reactors play an important role in providing key personnel of nuclear power plants a hands-on experience from operation and experiments at nuclear facilities. Training of NPP (Nuclear Power Plant) staff is usually deeply theoretical with an extensive utilisation of simulators and computer visualisation. But a direct sensing of the reactor response to various actions can only improve the personnel awareness of important aspects of reactor operation. Training Reactor VR-1 and its utilization for training of NPP operators and other professionals from Czech Republic and Slovakia is described. Typical experimental exercises and good practices in organization of a training program are demonstrated. (authors)

Sklenka, L.; Rataj, J.; Frybort, J.; Huml, O. [Dept. of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical Univ. in Prague, V Holesovickach 2, Prague 8, 180 00 (Czech Republic)

2012-07-01T23:59:59.000Z

232

Colorado State University Center for Geosciences/Atmospheric Research (CG/AR)  

E-Print Network (OSTI)

Colorado State University Center for Geosciences/Atmospheric Research (CG/AR) Quarterly Report No research of Professor Steven Reising, of the Electrical and Computer Engineering Department (located under at Colorado State University, please access our web page at http

233

EA-0912: Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear  

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

2: Urgent-Relief Acceptance of Foreign Research Reactor Spent 2: Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel EA-0912: Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel SUMMARY This EA evaluates the environmental impacts of a proposal to accept 409 spent fuel elements from eight foreign research reactors in seven European countries. The spent fuel would be shipped across the ocean in spent fuel transportation casks from the country of origin to one or more United States eastern seaboard ports. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 22, 1994 EA-0912: Finding of No Significant Impact Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel April 22, 1994 EA-0912: Final Environmental Assessment Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel

234

NREL: Wind Research - Kansas State University Videos Explore...  

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

Kansas State University Videos Explore Wind Energy January 29, 2013 A Kansas State University journalism student recently produced two videos related to wind energy. "Students...

235

FUEL ELEMENTS FOR THE ARGONNE ADVANCED RESEARCH REACTOR  

SciTech Connect

The core design and the fuel element concept for the high-flux Argonne Advanced Research Reactor are presented. The core is cooled and moderated by light water and utilizes beryllium as a reflector. The fuel element assembly is rhomboidal in cross section and consists of 27 plates fastened together at their edges by dovetailed locking keys, and at each end by end fittings. Each fuel plate is 40 mils thick and contains a uniform dispersion of highly enriched UO/ sub 2/ particles, up to a maximum of 37 wt%, in a matrix of sintered stainless steel powder. A 5 mil thick stainless steel cladding is metallurgically bonded to each side of the fueled matrix. (N.W.R.)

Adolph, N.R.; Silberstein, M.S.; Weinstein, A.

1962-01-01T23:59:59.000Z

236

MCNP-model for the OAEP Thai Research Reactor  

SciTech Connect

An MCNP input was prepared for the Thai Research Reactor, making extensive use of the MCNP geometry`s lattice feature that allows a flexible and easy rearrangement of the core components and the adjustment of the control elements. The geometry was checked for overdefined or undefined zones by two-dimensional plots of cuts through the core configuration with the MCNP geometry plotting capabilities, and by a three-dimensional view of the core configuration with the SABRINA code. Cross sections were defined for a hypothetical core of 67 standard fuel elements and 38 low-enriched uranium fuel elements--all filled with fresh fuel. Three test calculations were performed with the MCNP4B-code to obtain the multiplication factor for the cases with control elements fully inserted, fully withdrawn, and at a working position.

Gallmeier, F.X.; Tang, J.S.; Primm, R.T. III

1998-06-01T23:59:59.000Z

237

Sodium fast reactor fuels and materials : research needs.  

SciTech Connect

An expert panel was assembled to identify gaps in fuels and materials research prior to licensing sodium cooled fast reactor (SFR) design. The expert panel considered both metal and oxide fuels, various cladding and duct materials, structural materials, fuel performance codes, fabrication capability and records, and transient behavior of fuel types. A methodology was developed to rate the relative importance of phenomena and properties both as to importance to a regulatory body and the maturity of the technology base. The technology base for fuels and cladding was divided into three regimes: information of high maturity under conservative operating conditions, information of low maturity under more aggressive operating conditions, and future design expectations where meager data exist.

Denman, Matthew R.; Porter, Douglas (Idaho National Laboratory, Idaho Falls, ID); Wright, Art (Argonne National Laboratory Argonne, IL); Lambert, John (Argonne National Laboratory Argonne, IL); Hayes, Steven (Idaho National Laboratory, Idaho Falls, ID); Natesan, Ken (Argonne National Laboratory Argonne, IL); Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Garner, Frank (Radiation Effects Consulting. Richland, WA); Walters, Leon (Advanced Reactor Concepts, Idaho Falls, ID); Yacout, Abdellatif (Argonne National Laboratory Argonne, IL)

2011-09-01T23:59:59.000Z

238

Foreign Research Reactor Spent Nuclear Fuel Acceptance Program  

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

Global Threat Reduction Initiative: Global Threat Reduction Initiative: U.S. Nuclear Remove Program Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance 2007 DOE TEC Meeting Chuck Messick DOE/NNSA/SRS 2 Contents * Program Objective and Policy * Program implementation status * Shipment Information * Operational Logistics * Lessons Learned * Conclusion 3 U.S. Nuclear Remove Program Objective * To play a key role in the Global Threat Reduction Remove Program supporting permanent threat reduction by accepting program eligible material. * Works in conjunction with the Global Threat Reduction Convert Program to accept program eligible material as an incentive to core conversion providing a disposition path for HEU and LEU during the life of the Acceptance Program. 4 Reasons for the Policy

239

High uranium density dispersion fuel for the reduced enrichment of research and test reactors program.  

E-Print Network (OSTI)

??This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to… (more)

[No author

2006-01-01T23:59:59.000Z

240

The inverse kinetics method and PID compensation of the Annular Core Research Reactor.  

E-Print Network (OSTI)

??This thesis explores the development of a model describing the Annular Core Research Reactor (ACRR), the application of the inverse kinetics method to calculate the… (more)

Garnas, Benjamin

2008-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "university research reactor" 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

Sodium fast reactor safety and licensing research plan. Volume I.  

SciTech Connect

This report proposes potential research priorities for the Department of Energy (DOE) with the intent of improving the licensability of the Sodium Fast Reactor (SFR). In support of this project, five panels were tasked with identifying potential safety-related gaps in available information, data, and models needed to support the licensing of a SFR. The areas examined were sodium technology, accident sequences and initiators, source term characterization, codes and methods, and fuels and materials. It is the intent of this report to utilize a structured and transparent process that incorporates feedback from all interested stakeholders to suggest future funding priorities for the SFR research and development. While numerous gaps were identified, two cross-cutting gaps related to knowledge preservation were agreed upon by all panels and should be addressed in the near future. The first gap is a need to re-evaluate the current procedures for removing the Applied Technology designation from old documents. The second cross-cutting gap is the need for a robust Knowledge Management and Preservation system in all SFR research areas. Closure of these and the other identified gaps will require both a reprioritization of funding within DOE as well as a re-evaluation of existing bureaucratic procedures within the DOE associated with Applied Technology and Knowledge Management.

Sofu, Tanju (Argonne National Laboratory, Argonne, IL); LaChance, Jeffrey L.; Bari, R. (Brokhaven National Laboratory Upton, NY); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.; Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN)

2012-05-01T23:59:59.000Z

242

The initial results of research on two-step cascades in the Dalat research reactor  

E-Print Network (OSTI)

By the financial support of Vietnam Atomic Energy Commission and kind cooperation of Frank Laboratory, in the year of 2005 a measure system based on summation of amplitude pulses was established on the tangential channel of Dalat Research Reactor. After a serial of testing, the measure system was explored. In this, we would like to show the initial results were gotten with 36-Cl isotope.

Nguyen Xuan Hai; Pham Dinh Khang; Vuong Huu Tan; Ho Huu Thang; A. M. Sukhovoj; V. A. Khitrov

2013-07-11T23:59:59.000Z

243

University Research National Labs | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

About » University About » University Research & National Labs » University Research National Labs Alpha Listing High Energy Physics (HEP) HEP Home About Staff Organization Chart .pdf file (170KB) HEP Budget HEP Committees of Visitors Directions Jobs University Research & National Labs University Research National Labs Alpha Listing Research Facilities Science Highlights Benefits of HEP Funding Opportunities Advisory Committees News & Resources Contact Information High Energy Physics U.S. Department of Energy SC-25/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3624 F: (301) 903-2597 E: sc.hep@science.doe.gov More Information » University Research & National Labs University Research National Labs Alpha Listing Print Text Size: A A A RSS Feeds

244

Independent Verification of Research Reactor Operation (Analysis of the Georgian IRT-M Reactor by the Isotope Ratio Method)  

SciTech Connect

The U.S. Department of Energy’s Office of Nonproliferation and International Security (NA-24) develops technologies to aid in implementing international nuclear safeguards. The Isotope Ratio Method (IRM) was successfully developed in 2005 – 2007 by Pacific Northwest National Laboratory (PNNL) and the Republic of Georgia’s Andronikashvili Institute of Physics as a generic technology to verify the declared operation of water-moderated research reactors, independent of spent fuel inventory. IRM estimates the energy produced over the operating lifetime of a fission reactor by measuring the ratios of the isotopes of trace impurity elements in non-fuel reactor components.The Isotope Ratio Method is a technique for estimating the energy produced over the operating lifetime of a fission reactor by measuring the ratios of the isotopes of impurity elements in non-fuel reactor components.

Cliff, John B.; Frank, Douglas P.; Gerlach, David C.; Gesh, Christopher J.; Little, Winston W.; Reid, Bruce D.; Tsiklauri, Georgi V.; Abramidze, Sh; Rostomashvili, Z.; Kiknadze, G.; Dzhavakhishvily, O.; Nabakhtiani, G.

2010-08-11T23:59:59.000Z

245

Fission neutron/gamma irradiation of Bacillus thuringiensis bacteria at the Texas A&M University Nuclear Science Center Reactor  

E-Print Network (OSTI)

The objective of this research is to fully characterize the effectiveness of the Texas A&M University Nuclear Science Center Reactor (TAMU NSCR) neutrons for bacterial sterilization, and to assess the secondary gamma flux produced when neutrons collide with nuclei in biological materials. Sterilization of bacteria by exposure to gamma rays and charged particles is fairly well understood. Exposure to neutrons and gamma rays from fission as a means of sterilization has not to date been adequately characterized. The lack of data on the relationship between biological detriment resulting from thermal or fast neutron exposures and absorbed doses as applied in countermeasures to weapons of mass destruction (WMD) is the primary motivation for this investigation of neutron doses to endospores. Bacillus thuringiensis (Bt) spores were irradiated after producing and sampling them using standard microbiological procedures. Irradiation was accomplished using neutrons and gamma rays from the 1-MW TRIGA reactor at the TAMU NSCR using a reactor power of 100 kilowatts (kW). The combination of neutron and gamma-ray absorbed dose provided an effective means of sterilization of these types of spores; it yielded a 100-percent kill for the first study. Survival curves have been developed, from subsequent experiments, for these energy dependent neutron interactions with biological materials using a combination of radiation dosimetry, microbiological culture techniques, and computer modeling (Monte Carlo Neutral Particle history modeling - MCNP). Survival curves indicate a D?? value of 321.08 Gy. Additional work is needed to investigate the specific bacteria used in biological weapons in order to understand agent-specific radiation sensitivity. Once this is done, more effective and meaningful experiments can be conducted in order to tailor the neutron source strength to the robustness of the threat.

Hearnsberger, David Wayne

2001-01-01T23:59:59.000Z

246

SNL-University of Guadalajara Research and Development MOU | Open Energy  

Open Energy Info (EERE)

SNL-University of Guadalajara Research and Development MOU SNL-University of Guadalajara Research and Development MOU Jump to: navigation, search Name SNL-University of Guadalajara Research and Development MOU Agency/Company /Organization Sandia National Laboratories, University of Guadalajara Topics Background analysis Website https://share.sandia.gov/news/ Country Mexico, United States UN Region Latin America and the Caribbean, Northern America References SNL-University of Guadalajara Research and Development MOU[1] This article is a stub. You can help OpenEI by expanding it. References ↑ "SNL-University of Guadalajara Research and Development MOU" Retrieved from "http://en.openei.org/w/index.php?title=SNL-University_of_Guadalajara_Research_and_Development_MOU&oldid=374473" Categories:

247

The Challenges and Rewards of Industry/University Collaborative Research  

E-Print Network (OSTI)

This talk describes some successful Industry/University collaboration models currently being used at the Massachusetts Institute of Technology.

Palacios, Tomas

248

Development and transfer of fuel fabrication and utilization technology for research reactors  

SciTech Connect

Approximately 300 research reactors supplied with US-enriched uranium are currently in operation in about 40 countries, with a variety of types, sizes, experiment capabilities and applications. Despite the usefulness and popularity of research reactors, relatively few innovations in their core design have been made in the last fifteen years. The main reason can be better understood by reviewing briefly the history of research reactor fuel technology and enrichment levels. Stringent requirements on the enrichment of the uranium to be used in research reactors were considered and a program was launched to assist research reactors in continuing their operation with the new requirements and with minimum penalties. The goal of the new program, the Reduced Enrichment Research and Test Reactor (RERTR) Program, is to develop the technical means to utilize LEU instead of HEU in research reactors without significant penalties in experiment performance, operating costs, reactor modifications, and safety characteristics. This paper reviews briefly the RERTR Program activities with special emphasis on the technology transfer aspects of interest to this conference.

Travelli, A.; Domagala, R.F.; Matos, J.E.; Snelgrove, J.L.

1982-01-01T23:59:59.000Z

249

DOE-FE: 20th Year of University Coal Research Grants  

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

May 5, 1999 May 5, 1999 DOE Funds 20th Year of University Coal Grants Students, Teachers Team to Explore Greenhouse Gas Reduction, Coal Science and Technologies for Pollution Free Power Plant The U.S. Department of Energy announced today that 17 university-proposed projects will share in $2.8 million in federal coal research funds - marking the 20th year of a program that combines science education for students with research that can reveal cleaner and more effective ways to use the nation's plentiful coal reserves. The winning colleges and universities include: Arizona State University Brigham Young University Brown University Carnegie Mellon University Clarkson University Colorado School of Mines Georgia Institute of Technology Kansas State University Ohio University

250

The Future of University Nuclear Engineering Programs and University  

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

The Future of University Nuclear Engineering Programs and The Future of University Nuclear Engineering Programs and University Research and Training Reactors The Future of University Nuclear Engineering Programs and University Research and Training Reactors Nuclear engineering programs and departments with an initial emphasis in fission were formed in the late 1950's and 1960's from interdisciplinary efforts in many of the top research universities, providing the manpower for this technical discipline. In the same time period, for many of these programs, university nuclear reactors were constructed and began their operation, providing some of the facilities needed for research and training of students engaged in this profession. However, over the last decade, the U.S. nuclear science and engineering educational structure has not only stagnated but has reached a state of

251

The Future of University Nuclear Engineering Programs and University  

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

The Future of University Nuclear Engineering Programs and The Future of University Nuclear Engineering Programs and University Research and Training Reactors The Future of University Nuclear Engineering Programs and University Research and Training Reactors Nuclear engineering programs and departments with an initial emphasis in fission were formed in the late 1950's and 1960's from interdisciplinary efforts in many of the top research universities, providing the manpower for this technical discipline. In the same time period, for many of these programs, university nuclear reactors were constructed and began their operation, providing some of the facilities needed for research and training of students engaged in this profession. However, over the last decade, the U.S. nuclear science and engineering educational structure has not only stagnated but has reached a state of

252

U.S. Department of Energy Program of International Technical Cooperation for Research Reactor Utilization  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration (DOE/NNSA) has initiated collaborations with the national nuclear authorities of Egypt, Peru, and Romania for the purpose of advancing the commercial potential and utilization of their respective research reactors. Under its Office of International Safeguards ''Sister Laboratory'' program, DOE/NNSA has undertaken numerous technical collaborations over the past decade intended to promote peaceful applications of nuclear technology. Among these has been technical assistance in research reactor applications, such as neutron activation analysis, nuclear analysis, reactor physics, and medical radioisotope production. The current collaborations are intended to provide the subject countries with a methodology for greater commercialization of research reactor products and services. Our primary goal is the transfer of knowledge, both in administrative and technical issues, needed for the establishment of an effective business plan and utilization strategy for the continued operation of the countries' research reactors. Technical consultation, cooperation, and the information transfer provided are related to: identification, evaluation, and assessment of current research reactor capabilities for products and services; identification of opportunities for technical upgrades for new or expanded products and services; advice and consultation on research reactor upgrades and technical modifications; characterization of markets for reactor products and services; identification of competition and estimation of potential for market penetration; integration of technical constraints; estimation of cash flow streams; and case studies.

Chong, D.; Manning, M.; Ellis, R.; Apt, K.; Flaim, S.; Sylvester, K.

2004-10-03T23:59:59.000Z

253

DOE-Fossil Energy: 1998 University Coal Research Selections  

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

DOE FOSSIL ENERGY TECHLINE Issued on April 16, 1998 DOE Funds University Coal Grants, Selects Ideas For "Vision 21," Greenhouse Gas Reduction and Coal Science Secretary of Energy...

254

Stanford University Researchers Represented in the E-print Network  

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

PatBrownLabHomePagePapers.html Brubaker, Ben - Department of Mathematics, Stanford University http:math.stanford.edubrubaker Brunet, Anne - Department...

255

Research Activities at the Vienna University of Technology on...  

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

to increase the share of renewables and to reinforce competition in the European electricity market. The Energy Economics Group of Vienna University of Technology is...

256

Gas release driven dynamics in research reactors piping  

SciTech Connect

Analysis of the physical and chemical processes of radiolysis gas production, air absorption, diffusion controlled gas release and transport in the coolant cleaning system of the research reactor FRM II, which is now being in routine power operation in Munich, Germany, lead to the following conclusions: 1) The steady state pressure distribution in the siphon pipe allows that the horizontal part of the siphon pipe is filled with air. The air is isolated by about 1 m water column from the main pipe of the coolant cleaning system (CCS). This is a stable steady state. It has two positive impacts on the normal operation of the CCS: (a) there is effectively no bypass flow; (b) The air can not be transported through the pipe and therefore no deterioration of the pump performance is expected from the function of the siphon pipe. 2) Radiolysis gas production for coolant, that initially does not contain dissolved air, does not lead to any problem for the system. The gases are dissolved in the coolant at 2.2 bar and are not released for pressures reduction to about 1 bar, which is the minimum pressure in the CCS. 3) Assuming hypothetically a radiolysis gas production for coolant, which initially does contain dissolved air close to its saturation, leads to gas slug formation and its transport up to the pump. This could reduce the pump head and could lead to distortion of the normal operation. Systematic measurement of the hydrogen in the primary system at 100% power indicated, that this state is not realized in the system. The observed H{sub 2} concentration was between 0.016 e-6 and 0.380 e-6 which is of no concern at all. (authors)

Kolev, Nikolay Ivanov; Roloff-Bock, Iris; Schlicht, Gerhard [Framatome ANP, P.O. Box 3220, D-91058, Erlangen (Germany)

2006-07-01T23:59:59.000Z

257

USA NRC/RSR Data Bank System and Reactor Safety Research Data Repository (RSRDR)  

SciTech Connect

The United States Nuclear Regulatory Commission (NRC), through its Division of Reactor Safety Research (RSR) of the Office of Nuclear Regulatory Research, has established the NRC/RSR Data Bank Program to collect, process, and make available data from the many domestic and foreign water reactor safety research programs. An increasing number of requests for data and/or calculations generated by NRC Contractors led to the initiation of the program which allows timely and direct access to water reactor safety data in a manner most useful to the user. The program consists of three main elements: data sources, service organizations, and a data repository.

Maskewitz, B.F.; Bankert, S.F.

1979-01-01T23:59:59.000Z

258

Risk management at the Oak Ridge National Laboratory research reactors  

SciTech Connect

In November of 1986, the High Flux Isotope Reactor (HFIR) was shut down by Oak Ridge National Laboratory (ORNL) due to a concern regarding embrittlement of the reactor vessel. A massive review effort was undertaken by ORNL and the Department of Energy (DOE). This review resulted in an extensive list of analyses and design modifications to be completed before restart could take place. The review also focused on the improvement of management practices including implementation of several of the Institute of Nuclear Power Operations (INPO) requirements. One of the early items identified was the need to perform a Probabilistic Risk Assessment (PRA) on the reactor. It was decided by ORNL management that this PRA would not be just an exercise to assess the ``bottom`` line in order to restart, but would be used to improve the overall safety of the reactor, especially since resources (both manpower and dollars) were severely limited. The PRA would become a basic safety tool to be used instead of a more standard deterministic approach to safety used in commercial reactor power plants. This approach was further reinforced, because the reactor was nearly 25 years old at this time, and the design standards and regulations had changed significantly since the original design, and many of the safety issues could not be addressed by compliance to codes and standards.

Flanagan, G.F.; Linn, M.A.; Proctor, L.D.; Cook, D.H.

1994-12-31T23:59:59.000Z

259

Reactor Safety Research Programs Quarterly Report July - September 1981  

SciTech Connect

This document summarizes the work performed by Pacific Northwest laboratory (PNL) from July 1 through September 30, 1981, for the Division of Accident Evaluation, U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR} steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S. K.

1982-01-01T23:59:59.000Z

260

Universities: At the Center of U.S. Research  

E-Print Network (OSTI)

the vital center of the U.S. research system. On this point,At the Center of U.S. Research Richard C. Atkinson There hasthe role of government in research, including his assertion

Atkinson, Richard

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "university research reactor" 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

Thermal-hydraulic aspects of flow inversion in a research reactor  

SciTech Connect

PARET, a neutronics and thermal-hydraulics computer code, has been modified to account for natural convection in a reactor core. The code was then used to analyze the flow inversion that occurs in a reactor with heat removal by forced convection in the downward direction after a pump failure. Typical results are shown for a number of parameters. Research reactors normally operating much above ten MW are predicted to experience nucleate boiling in the event of a flow inversion. Comparison with experimental results from the Belgian BR2 reactor indicated general agreement although nucleate boiling that was analytically predicted was not noted in the BR2 data.

Smith, R.S.; Woodruff, W.L.

1986-11-01T23:59:59.000Z

262

Light Water Reactor Fuel Cladding Research and Testing | ornl.gov  

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

Light Water Reactor Fuel Cladding Research Light Water Reactor Fuel Cladding Research June 01, 2013 Severe Accident Test Station ORNL is the focus point for Light Water Reactor (LWR) fuel cladding research and testing. The purpose of this research is to furnish U.S. industry (EPRI, Areva, Westinghouse), and regulators (NRC) with much-needed data supporting safe and economical nuclear power generation and used fuel management. LWR fuel cladding work is tightly integrated with ORNL accident tolerant fuel development and used fuel disposition programs thereby providing a powerful capability that couples basic materials science research with the nuclear applications research and development. The ORNL LWR fuel cladding program consists of five complementary areas of research: Accident tolerant fuel and cladding material testing under design

263

Secretary Chu Announces Funding for 71 University-Led Nuclear Research and  

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

Secretary Chu Announces Funding for 71 University-Led Nuclear Secretary Chu Announces Funding for 71 University-Led Nuclear Research and Development Projects Secretary Chu Announces Funding for 71 University-Led Nuclear Research and Development Projects May 6, 2009 - 1:49pm Addthis U.S. Energy Secretary Steven Chu today announced the selection of 71 university research project awards as part of the Department of Energy's investments in cutting-edge nuclear energy research and development (R&D). Under the Nuclear Energy University Program (NEUP), these 71 projects will receive approximately $44 million over three years to advance new nuclear technologies in support of the nation's energy goals. By helping to develop the next generation of advanced nuclear technologies, the Nuclear Energy University Program will play a key role in addressing the global climate

264

Secretary Chu Announces Funding for 71 University-Led Nuclear Research and  

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

Chu Announces Funding for 71 University-Led Nuclear Chu Announces Funding for 71 University-Led Nuclear Research and Development Projects Secretary Chu Announces Funding for 71 University-Led Nuclear Research and Development Projects May 6, 2009 - 12:00am Addthis WASHINGTON, DC - U.S. Energy Secretary Steven Chu today announced the selection of 71 university research project awards as part of the Department of Energy's investments in cutting-edge nuclear energy research and development (R&D). Under the Nuclear Energy University Program (NEUP), these 71 projects will receive approximately $44 million over three years to advance new nuclear technologies in support of the nation's energy goals. By helping to develop the next generation of advanced nuclear technologies, the Nuclear Energy University Program will play a key role in

265

University Turbine Systems Research Workshop, 2010: Scientific Poster Presentations  

DOE Data Explorer (OSTI)

The use of gases produced from coal as gas turbine fuel offers an attractive means for efficiently generating electric power from our Nation's most abundant fossil fuel resource. DOE’s Fossil Energy Program is developing key technologies that will enable advanced turbines to operate cleanly and efficiently when fueled with coal derived synthesis gas and hydrogen fuels. Developing this turbine technology is critical to the creation of near-zero emission power generation technologies. [Copied with editing from http://www.fossil.energy.gov/programs/powersystems/turbines/index.html]. The 2010 University Turbine Systems Research Workshop was held at Penn State October 19-22, 2010. All of these scientific and technical posters are available online at the NETL website. The title list includes: 1) Evaporative Metal Bonding of CM247LC to Kanthal APMT; 2) Development of Electrically Mediated Electrophoretic Deposition for Thermal Barrier Coatings; 3) Novel Coating Methods for Unique TBC/Bond Coat Architectures for Elevated Temperature Operation; 4) Tailored Microstructure of EB-PVD YSZ Thermal Barrier Coatings (TVC); 5) Characterization of Rust for Turbine Component Studies; 6) Flowfield Measurements in a Single Row of Low Aspect Ratio Pin-Fins; 7) Forced Flame Response of a Lean Premixed Multi Nozzle Can Combustor; 8) Comparison Between Self-Excited and Forced Flame Response of an Industrial Lean Premixed Gas Turbine Injector; 9) Fuel-Forced Flame Response of a Lean-Premixed Combustor; 10) Effect of Pressure on the Flame Transfer Function of a Lean Premixed Combustor; 11) High Temperature Unique Low Thermal Conductivity Thermal Barrier Coating (TBC) Architectures; 12) Thermally Sprayed Materials for High Temperature Thermal Barrier Coating Systems; 13) Oxidation of SiC/BN/SiC Composites in Reduced Oxygen Partial Pressures; 14) Advanced Cooling Turbine Blades; 15) Water Guided Laser Drilling of High Temperature Alloys; 16) Vane Clocking Effects on Compressor Stage Efficiency; 17) A Novel Micro Circuit Based Film Cooling Design For a Ceramic Combustor Liner; 18) High Temperature Bond and Thermal Barrier Coatings; 19) Updated H2/O2 Model to Address High-Pressure Flame Burning Rate Discrepancies; 20) Progress on a Methodology for the Formulation of Jet Fuel Surrogates; 21) Monitoring Compliance of Thermal Barrier Coatings: Application to Coating Design and Assessment of Their Repeatability.

266

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program  

SciTech Connect

The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin next year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.

Smith, Cyrus M [ORNL; Nanstad, Randy K [ORNL; Clayton, Dwight A [ORNL; Matlack, Katie [Georgia Institute of Technology; Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL); Light, Glenn [Southwest Research Institute, San Antonio

2012-09-01T23:59:59.000Z

267

Effect of reduced enrichment on the fuel cycle for research reactors  

SciTech Connect

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

Travelli, A.

1982-01-01T23:59:59.000Z

268

Colorado State University Center for Geosciences/Atmospheric Research (CG/AR)  

E-Print Network (OSTI)

prediction in the atmosphere. Masters thesis, Department of Electrical and Computer Engineering, ColoradoColorado State University Center for Geosciences/Atmospheric Research (CG/AR) Quarterly Report No on the DoD Center for Geosciences/Atmospheric Research at Colorado State University, please access our web

269

Energy Department Awards Universities $7.5 Million for Basic Research |  

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

Universities $7.5 Million for Basic Universities $7.5 Million for Basic Research Energy Department Awards Universities $7.5 Million for Basic Research March 28, 2007 - 12:17pm Addthis WASHINGTON, DC -- The Department of Energy has awarded grants totaling $7.5 million to universities in New Hampshire, Maine, Delaware and Kentucky for research ranging from nanomaterials to biofuels. The states will match at least 50 percent of this funding. The grants are part of an experimental program to improve the capability of universities to conduct nationally competitive energy-related research in states that have historically received less federal research and development funding. "As President Bush so forcefully stated in his 2006 State of the Union address, 'we must continue to lead the world in human talent and

270

Demonstration of the reactivity constraint approach on SNL's annual core research reactor  

Science Conference Proceedings (OSTI)

This paper reports on the initial demonstration of the reactivity constraint approach and its implementing algorithm, the MIT-CSDL Non-Linear Digital Controller, on the annual core research reactor (ACCR) that is operated by the Sandia National Laboratories. This demonstration constituted the first use of reactivity constraints for the closed-loop, digital control of reactor power on a facility other than the Massachusetts Institute of Technology's (MIT's) research reactor (MITR-II). Also, because the ACRR and the MITR-II are of very different design, these trials established the generic nature of the reactivity constraint approach.

Bernard, J.A.; Kwok, K.S.; Wyant, F.J.; Thome, F.V.

1989-01-01T23:59:59.000Z

271

A Brief History i-l Research Reactors  

E-Print Network (OSTI)

stainless steel sam- ples in the High Flux Isotope Reactor (HFIR) at tem- peratures of 380 to 680" with up/cm' to balance the gas pressure were used m their calculation. A comparison of the results with HFIR and the HFIR ex- perimental data is presented in section 5. Applications of the model to various fusion designs

272

Marketing Research Design and Analysis University of Michigan Business School  

E-Print Network (OSTI)

. Section 3: Specific Research Questions The AWARE research team will present this project in Washington DC. The prototype software will be made available and will run on any Windows or PalmOS machine. Additionally

Michalek, Jeremy J.

273

The University of Texas at Arlington Research Institute Lieutenant General, US Army (Retired)  

E-Print Network (OSTI)

The University of Texas at Arlington Research Institute UTARI Rick Lynch Lieutenant General, US of Texas at Arlington Research Institute Vision Statement By 2017, UTARI becomes a global leader of Texas at Arlington Research Institute Mission Statement UTARI bridges the gap between academic research

Texas at Arlington, University of

274

Renewable Energy Research Laboratory University of Massachusetts, Amherst  

E-Print Network (OSTI)

/RERL_Fact_Sheet_6_Wind_resource_interpretation.pdf * 1 m/s = 2.237 mph. April 10, 2008 Renewable Energy Research Average Wind Speeds, Dec 1, 2007 ­ February 9, 2008. April 10, 2008 Renewable Energy Research Laboratory­ Turbulence Intensity vs. Wind Speed, Dec 1, 2007 ­ February 9, 2008. April 10, 2008 Renewable Energy Research

Massachusetts at Amherst, University of

275

Go8 Backgrounder 20 Role of research universities  

E-Print Network (OSTI)

to a strong, innovative health system. Such alignment and integration will be essential for Australia's future recurrent funding is needed, to optimise the research outcomes following investment in research facilities for the benefit of Australians' health. Adequate funding for excellent medical research is essential for continued

276

SOLERAS - University Research Project. Progress report 1, December 1984  

Science Conference Proceedings (OSTI)

Progress to date on each of the research efforts in direct solar energy applications at public and private institutions of higher education and research in the United States is addressed. Some research topics covered include: concentrating optics for PV conversion; wind power; solar ponds; photosynthesis; amorphous silicon alloys; passive cooling; crystal growth of gallium arsenides; and solar insolation.

Not Available

1984-12-01T23:59:59.000Z

277

Materials Research Needs for Near-Term Nuclear Reactors  

Science Conference Proceedings (OSTI)

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

John R. Weeks

278

DOE Announces up to $4 Million for University Research into Advanced  

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

4 Million for University Research into 4 Million for University Research into Advanced Biomass Conversion DOE Announces up to $4 Million for University Research into Advanced Biomass Conversion April 11, 2008 - 10:50am Addthis FONTANA, Calif. - U.S. Department of Energy (DOE) Under Secretary Clarence "Bud" Albright today announced up to $4 million in funding available to U.S. universities for research and development of cost-effective, environmentally friendly biomass conversion technologies. Advancing biomass technology is critical to diversifying our nation's energy sources in an effort to reduce greenhouse gas emissions and dependence on foreign oil. Combined with a university cost share of 20%, up to $5 million would be invested in these projects. "As world demand for energy continues to grow, so too must our supply of

279

The words of Thomas 42 | Michigan Technological University Engineering Research 2009 | 4342 | Michigan Technological University  

E-Print Network (OSTI)

of this work are found in induced seismicity, deep earthquakes, as well as oil and gas exploration. In the 1980s, at the University of Texas at Austin, he studied the relationship of earthquakes to oil and gas techniques to improve the identification of, and production from, oil and gas reservoirs. Since 1994, he has

280

Off Site University Research (OSUR) | Princeton Plasma Physics...  

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

Join Our Mailing List A Collaborative National Center for Fusion & Plasma Research Search form Search Search Home About Overview Learn More Visiting PPPL History...

Note: This page contains sample records for the topic "university research reactor" 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

NIST/University of Colorado Researchers Create Bose ...  

Science Conference Proceedings (OSTI)

... The researchers cooled a gas of potassium atoms (potassium isotope 40) with lasers ... founded in 1876 and is known for its strong programs in the ...

2010-11-18T23:59:59.000Z

282

Thermal hydraulic limits analysis for the MIT Research Reactor low enrichment uranium core conversion using statistical propagation of parametric uncertainties  

E-Print Network (OSTI)

The MIT Research Reactor (MITR) is evaluating the conversion from highly enriched uranium (HEU) to low enrichment uranium (LEU) fuel. In addition to the fuel element re-design from 15 to 18 plates per element, a reactor ...

Chiang, Keng-Yen

2012-01-01T23:59:59.000Z

283

Conference on energy research at historically black universities  

DOE Green Energy (OSTI)

A conference was convened to present and discuss significant research and development in Historically Black Institutions (current and past); areas that show potential for inter-institutional collaboration and the sharing of facilities; existing capabilities to sustain funded research activities and future potential for expansion and enhancement; and appropriate arrangements for maximum interaction with industry and government agencies. Papers were presented at small group meetings in various energy research areas, and abstracts of the projects or programs are presented. The Solar Energy small group provided contributions in the areas of photovoltaics, biomass, solar thermal, and wind. Research reported on by the Fossil Fuel small group comprises efforts in the areas of fluidized bed combustion of coal, coal liquefaction, and oil shale pyrolysis. Five research programs reported on by the Conservation Research small group involve a summer workshop for high school students on energy conservation; use of industrial waste heat for a greenhouse; solar energy and energy conservation research and demonstration; energy efficiency and management; and a conservation program targeted at developing a model for educating low income families. The Environment Impact groups (2) presented contributions on physical and chemical impacts and biological monitors and impacts. The Policy Research group presented four papers on a careful analysis of the Equity issues; one on a model for examining the economic issue in looking at the interaction between energy technology and the state of the economy; and a second paper examined the institutional constraints on environmental oriented energy policy. Six additional abstracts by invited participants are presented. (MCW)

Not Available

1980-01-01T23:59:59.000Z

284

Decommissioning Anddismantling Of The Research Reactor Salaspils. I. Conceptual Study And The First Results.  

E-Print Network (OSTI)

In May 1995, the Latvian government decided to shut down the Research Reactor Salaspils (SRR) and to dis pense with nuclear energy in future. The reactor is out of operation since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und Umweltlechnik GmbH at 1998-1999 years. The Latvian government decided in October 26 1999 to start the direct dismantling to "green field" at 2001 year. The first decommissioning and dismantling results from preparation measures in 1999 year are presented and discussed. The main efforts was devoted to collecting and conditioning of "historical" radioactive wastes from different storages outside and inside of reactor hall. All non-radioactive equipments and materials outside of reactor buildings were free-released and dismantled for reusing and conventional disposing. Weakly contaminated materials from reactor hall were collected and removed for free-release measurements. 1.0 INTRODUCTION The res...

Andris Abramenkovs Ministry; Andris Abramenkovs; Arnis Ezergailis; State Enterprise “vides Projekti; Dzintars Kalninš

2000-01-01T23:59:59.000Z

285

Modular Pebble-Bed Reactor Project: Laboratory-Directed Research and Development Program FY 2002 Annual Report  

Science Conference Proceedings (OSTI)

This report documents the results of our research in FY-02 on pebble-bed reactor technology under our Laboratory Directed Research and Development (LDRD) project entitled the Modular Pebble-Bed Reactor. The MPBR is an advanced reactor concept that can meet the energy and environmental needs of future generations under DOE’s Generation IV initiative. Our work is focused in three areas: neutronics, core design and fuel cycle; reactor safety and thermal hydraulics; and fuel performance.

Petti, David Andrew; Dolan, Thomas James; Miller, Gregory Kent; Moore, Richard Leroy; Terry, William Knox; Ougouag, Abderrafi Mohammed-El-Ami; Oh, Chang H; Gougar, Hans D

2002-11-01T23:59:59.000Z

286

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

287

University of Cape Town-Energy Research Centre | Open Energy Information  

Open Energy Info (EERE)

Town-Energy Research Centre Town-Energy Research Centre Jump to: navigation, search Logo: University of Cape Town-Energy Research Centre Name University of Cape Town-Energy Research Centre Address Energy Research Centre Room 6.46 6th Floor Menzies Building (Via 5th floor) Upper Campus University of Cape Town Rondebosch Cape Town Place Cape Town, South Africa Website http://www.erc.uct.ac.za/index References http://www.erc.uct.ac.za/index.htm No information has been entered for this organization. Add Organization "The Centre is an African-based multi-disciplinary energy research centre which pursues excellence in technology, policy and sustainable development research, education and capacity building programmes at a local and international level. The organisation's core activity is energy. Under the umbrella of this

288

Secretary Chu Announces $38 Million for 42 University-Led Nuclear Research  

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

8 Million for 42 University-Led Nuclear 8 Million for 42 University-Led Nuclear Research and Development Projects Secretary Chu Announces $38 Million for 42 University-Led Nuclear Research and Development Projects May 20, 2010 - 12:00am Addthis Washington, D.C. - U.S. Secretary of Energy Steven Chu today announced the selection of 42 university-led research and development projects for awards totaling $38 million. These projects, funded over three to four years through the Department's Nuclear Energy University Program, will help advance nuclear education and develop the next generation of nuclear technologies. "We are taking action to restart the nuclear industry as part of a broad approach to cut carbon pollution and create new clean energy jobs," said Secretary Chu. "These projects will help us develop the nuclear

289

Secretary Chu Announces $38 Million for 42 University-Led Nuclear Research  

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

$38 Million for 42 University-Led Nuclear $38 Million for 42 University-Led Nuclear Research and Development Projects Secretary Chu Announces $38 Million for 42 University-Led Nuclear Research and Development Projects May 20, 2010 - 12:05pm Addthis WASHINGTON, D.C. - U.S. Secretary of Energy Steven Chu today announced the selection of 42 university-led research and development projects for awards totaling $38 million. These projects, funded over three to four years through the Department's Nuclear Energy University Program, will help advance nuclear education and develop the next generation of nuclear technologies. "We are taking action to restart the nuclear industry as part of a broad approach to cut carbon pollution and create new clean energy jobs," said Secretary Chu. "These projects will help us develop the nuclear

290

MITR-III: Upgrade and relicensing studies for the MIT Research Reactor. Second annual report  

SciTech Connect

The current operating license of the MIT research reactor will expire on May 7, 1996 or possibly a few years later if the US Nuclear Regulatory Commission agrees that the license period can start with the date of initial reactor operation. Driven by the imminent expiration of the operating license, a team of nuclear engineering staff and students have begun a study of the future options for the MIT Research Reactor. These options have included the range from a major rebuilding of the reactor to its decommissioning. This document reports the results of a two year intensive activity which has been supported by a $148,000 grant from the USDOE contract Number DEFG0293ER75859, approximately $100,000 of internal MIT funds and Nuclear Engineering Department graduate student fellowships as well as assistance from international visiting scientists and engineers.

Trosman, H.G. [ed.; Lanning, D.D.; Harling, O.K.

1994-08-01T23:59:59.000Z

291

Whitehead Biomedical Research Building at Emory University, Atlanta...  

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

will cover the additional first cost. Project Description The Whitehead Biomedical Research Facility is an eight-story, 325,000 gross ft 2 (212,264 net ft 2 ) laboratory...

292

Undergraduate research experience through the NASA Microgravity University program  

Science Conference Proceedings (OSTI)

Meaningful Research Experiences for Undergraduates (REU) is known to provide many benefits including enhancing enrollment and retention, supporting richer experiential education, improving students' personal, professional and cognitive skills, and encouraging ...

Kwok-Bun Yue; Sharon Hall; Christopher Burns; Ryan Page; Jarrett Lockridge; Paul Cusco; Lei Wu; Nathanial Wiggins

2013-04-01T23:59:59.000Z

293

Analyses for conversion of the Georgia Tech Research Reactor from HEU to LEU fuel  

SciTech Connect

The 5 MW Georgia Tech Research Reactor (GTRR) is a heterogeneous, heavy water moderated and cooled reactor, fueled with highly-enriched uranium aluminum alloy fuel plates. The GTRR is required to convert to low enrichment (LEU) fuel in accordance with USNRC policy. Results of design and safety analyses performed by the RERTR Program at the Argonne National Laboratory for LEU conversion of the GTRR are summarized. Only those parameters which could change as a result of replacing the fuel are addressed. The performance of the reactor and all safety margins with LEU fuel are expected to be about the same as those with the current HEU fuel.

Matos, J.E.; Mo, S.C.; Woodruff, W.L.

1992-01-01T23:59:59.000Z

294

Analyses for conversion of the Georgia Tech Research Reactor from HEU to LEU fuel  

Science Conference Proceedings (OSTI)

The 5 MW Georgia Tech Research Reactor (GTRR) is a heterogeneous, heavy water moderated and cooled reactor, fueled with highly-enriched uranium aluminum alloy fuel plates. The GTRR is required to convert to low enrichment (LEU) fuel in accordance with USNRC policy. Results of design and safety analyses performed by the RERTR Program at the Argonne National Laboratory for LEU conversion of the GTRR are summarized. Only those parameters which could change as a result of replacing the fuel are addressed. The performance of the reactor and all safety margins with LEU fuel are expected to be about the same as those with the current HEU fuel.

Matos, J.E.; Mo, S.C.; Woodruff, W.L.

1992-12-31T23:59:59.000Z

295

Leu conversion status of U.S. research reactors: September 1996  

SciTech Connect

At the request of the Department of Energy, the RERTR Program has summarized the conversion status of research and test reactors in the United States and has made estimates of the uranium densities that would be needed to convert the reactors with power levels greater than or equal to 1 MW from Highly Enriched Uranium (HEU) (greater than or equal to 20% U-235) to Lightly Enriched Uranium (LEU) (less than 20% U-235) fuels. Detailed conversion studies for each of the reactors need to be completed in order to establish the feasibility of using LEU fuels.

Matos, J.E.

1996-09-01T23:59:59.000Z

296

Education program at the Massachusetts Institute of Technology research reactor for pre-college science teachers  

Science Conference Proceedings (OSTI)

A Pre-College Science Teacher (PCST) Seminar program has been in place at the Massachusetts Institute of Technology (MIT) Nuclear Reactor Laboratory for 4 yr. The purpose of the PCST program is to educate teachers in nuclear technology and to show teachers, and through them the community, the types of activities performed at research reactors. This paper describes the background, content, and results of the MIT PCST program.

Hopkins, G.R.; Fecych, W.; Harling, O.K.

1989-01-01T23:59:59.000Z

297

Princeton University -Energy secretary announces U.S. participation in fusion research effort  

E-Print Network (OSTI)

Princeton University - Energy secretary announces U.S. participation in fusion research effort a tour of the lab facilities as Spencer Abraham, U.S. secretary of energy, looks on. photo: Elle Starkman feedback © 2002 The Trustees of Princeton University #12;Princeton - News - Energy secretary announces U.S

298

Teaching medical students dermatology research skills: Six years of experience with the University of Texas Medical Branch dermatology non-degree research honors program, 2001-2006  

E-Print Network (OSTI)

1. Wagner RF, Ioffe B. Medical student dermatology researchTeaching medical students dermatology research skills: Sixwith the University of Texas Medical Branch dermatology non-

Jr, Richard F Wagner; Lewis, Simon A

2006-01-01T23:59:59.000Z

299

Using low-enriched uranium in research reactors: The RERTR program  

SciTech Connect

The goal of the RERTR program is to minimize and eventually eliminate use of highway enriched uranium (HEU) in research and test reactors. The program has been very successful, and has developed low-enriched uranium (LEU) fuel materials and designs which can be used effectively in approximately 90 percent of the research and test reactors which used HEU when the program began. This progress would not have been possible without active international cooperation among fuel developers, commercial vendors, and reactor operators. The new tasks which the RERTR program is undertaking at this time include development of new and better fuels that will allow use of LEU fuels in all research and test reactors; cooperation with Russian laboratories, which will make it possible to minimize and eventually eliminate use of HEU in research reactors throughout the world, irrespective of its origin; and development of an LEU-based process for the production of {sup 99}Mo. Continuation and intensification of international cooperation are essential to the achievement of the ultimate goals of the RERTR program.

Travelli, A.

1994-05-01T23:59:59.000Z

300

The University of Texas at Dallas Advanced Network Research Labs 1 Generalized Burst Assembly and Scheduling Techniques for  

E-Print Network (OSTI)

The University of Texas at Dallas Advanced Network Research Labs 1 Generalized Burst Assembly Jason P. Jue, and Biao Chen Advanced Network Research Labs The University of Texas at Dallas, USA #12;The University of Texas at Dallas Advanced Network Research Labs 2 Outline · Optical Burst Switching

Vokkarane, Vinod M.

Note: This page contains sample records for the topic "university research reactor" 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

Major Safety Aspects of Advanced Candu Reactor and Associated Research and Development  

Science Conference Proceedings (OSTI)

The Advanced Candu{sup R} Reactor design is built on the proven technology of existing Candu plants and on AECL's knowledge base acquired over decades of nuclear power plant design, engineering, construction and research. Two prime objectives of ACR-700TM1 are cost reduction and enhanced safety. To achieve them some new features were introduced and others were improved from the previous Candu 6 and Candu 9 designs. The ACR-700 reactor design is based on the modular concept of horizontal fuel channels surrounded by a heavy water moderator, the same as with all Candu reactors. The major novelty in the ACR-700 is the use of slightly enriched fuel and light water as coolant circulating in the fuel channels. This results in a more compact reactor design and a reduction of heavy water inventory, both contributing to a significant decrease in cost compared to Candu reactors, which employ natural uranium as fuel and heavy water as coolant. The reactor core design adopted for ACR-700 also has some features that have a bearing on inherent safety, such as negative power and coolant void reactivity coefficient. Several improvements in engineered safety have been made as well, such as enhanced separation of the safety support systems. Since the ACR-700 design is an evolutionary development of the currently operating Candu plants, limited research is required to extend the validation database for the design and the supporting safety analysis. A program of safety related research and development has been initiated to address the areas where the ACR-700 design is significantly different from the Candu designs. This paper describes the major safety aspects of the ACR-700 with a particular focus on novel features and improvements over the existing Candu reactors. It also outlines the key areas where research and development efforts are undertaken to demonstrate the effectiveness and robustness of the design. (authors)

Bonechi, M.; Wren, D.J.; Hopwood, J.M. [Atomic Energy of Canada Limited, 2251 Speakman Drive, Mississauga, Ontario, L5K 1B2 (Canada)

2002-07-01T23:59:59.000Z

302

Directory of Federal Agencies and University Research Centers conducting R D in Environmental and Waste Management  

Science Conference Proceedings (OSTI)

In October 1990 PAR Enterprises, Incorporated was awarded a contract by the Department of Energy to conduct a survey and prepare a Directory of Federal Agencies and University Research Centers involved in environmental restoration and waste management research and development. To conduct the survey and organize the Directory, data from 50 Federal agencies and 100 universities was collected, evaluated and summarized. The purpose of the survey and Directory is to describe the activities and provide a reference base of Federal Agencies and University Research Cantors involved in environmental restoration and waste management research and development. The Directory contains (1) the Foreword, (2) an Introduction, (3) a Description of the Survey Organization and Research Approach, (4) the EM/OTD Key Word Networks, (5) a series of matrices that show the relationship between the OTD technical requirements and the Federal Agency/University EM capabilities, (6) the Federal Agency and University Research Center EM R D Capabilities Profiles, (7) a Glossary, and (8) an Appendix that describes the EM activities of the DOE National Laboratories and related research facilities. The survey and Directory was prepared for the Office of Technology Development (OTD), a major R D component of DOE's Office of Environmental Restoration and Waste Management.

Not Available

1991-12-01T23:59:59.000Z

303

Thermal hydraulics analysis of the MIT research reactor in support of a low enrichment uranium (LEU) core conversion.  

E-Print Network (OSTI)

??The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density… (more)

Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology

2008-01-01T23:59:59.000Z

304

Evaluation of the thermal-hydraulic operating limits of the HEU-LEU transition cores for the MIT Research Reactor.  

E-Print Network (OSTI)

??The MIT Research Reactor (MITR) is in the process of conducting a design study to convert from High Enrichment Uranium (HEU) fuel to Low Enrichment… (more)

Wang, Yunzhi (Yunzhi Diana)

2009-01-01T23:59:59.000Z

305

N-Reactor Department research and development budget for FY-1967 and revision of budget for FY-1966  

SciTech Connect

This report provides the N-Reactor research and development budget for fiscal year 1967 and modifications of the budget for fiscal year 1966.

1965-04-19T23:59:59.000Z

306

Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors  

SciTech Connect

The international effort to develop and implement new research reactor fuels utilizing low-enriched uranium, instead of highly- enriched uranium, continues to make solid progress. This effort is the cornerstone of a widely shared policy aimed at reducing, and possibly eliminating, international traffic in highly-enriched uranium and the nuclear weapon proliferation concerns associated with this traffic. To foster direct communication and exchange of ideas among the specialists in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at Argonne National Laboratory, sponsored this meeting as the eleventh of a series which began 1978. Individual papers presented at the meeting have been cataloged separately.

1993-07-01T23:59:59.000Z

307

A neutronics feasibility study for the LEU conversion of Poland's Maria research reactor.  

SciTech Connect

The MARIA reactor is a high-flux multipurpose research reactor which is water-cooled and moderated with both beryllium and water. Standard HEU (80% {sup 235}U)fuel assemblies consist of six concentric fuel tubes of a U-Al alloy clad in aluminum. Although the inventory of HEU (80%) fuel is nearly exhausted, a supply of highly-loaded 36%-enriched fuel assemblies is available at the reactor site. Neutronic equilibrium studies have been made to determine the relative performance of fuels with enrichments of 80%, 36% and 19.7%. These studies indicate that LEU (19.7%) densities of about 2.5 gU/cm{sup 3} and 3.8 gU/cm{sup 3} are required to match the performance of the MARIA reactor with 80%-enriched and with 36%-enriched fuels, respectively.

Bretscher, M. M.

1998-10-14T23:59:59.000Z

308

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

309

Comprehensive Thermal Hydraulics Research of the Very High Temperature Gas Cooled Reactor  

SciTech Connect

The Idaho National Laboratory (INL), under the auspices of the U.S. Department of Energy, is conducting research on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core will be either a prismatic graphite block type core or a pebble bed core. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during reactor core-accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission, and Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, perform research and development (R&D) that will be critical to the success of the NGNP, primarily in the areas of: • High temperature gas reactor fuels behavior • High temperature materials qualification • Design methods development and validation • Hydrogen production technologies • Energy conversion. This paper presents current R&D work that addresses fundamental thermal hydraulics issues that are relevant to a variety of possible NGNP designs.

Chang Oh; Eung Kim; Richard Schultz; Mike Patterson; David Petti; Hyung Kang

2010-10-01T23:59:59.000Z

310

Development of a Fissile Materials Irradiation Capability for Advanced Fuel Testing at the MIT Research Reactor  

SciTech Connect

A fissile materials irradiation capability has been developed at the Massachusetts Institute of Technology (MIT) Research Reactor (MITR) to support nuclear engineering studies in the area of advanced fuels. The focus of the expected research is to investigate the basic properties of advanced nuclear fuels using small aggregates of fissile material. As such, this program is intended to complement the ongoing fuel evaluation programs at test reactors. Candidates for study at the MITR include vibration-packed annular fuel for light water reactors and microparticle fuels for high-temperature gas reactors. Technical considerations that pertain to the design of the MITR facility are enumerated including those specified by 10 CFR 50 concerning the definition of a research reactor and those contained in a separate license amendment that was issued by the U.S. Nuclear Regulatory Commission to MIT for these types of experiments. The former includes limits on the cross-sectional area of the experiment, the physical form of the irradiated material, and the removal of heat. The latter addresses experiment reactivity worth, thermal-hydraulic considerations, avoidance of fission product release, and experiment specific temperature scrams.

Hu Linwen; Bernard, John A.; Hejzlar, Pavel; Kohse, Gordon [Massachusetts Institute of Technology (United States)

2005-05-15T23:59:59.000Z

311

Research Reactor Preparations for the Air Shipment of Highly Enriched Uranium from Romania  

SciTech Connect

In June 2009 two air shipments transported both unirradiated (fresh) and irradiated (spent) Russian-origin highly enriched uranium (HEU) nuclear fuel from two research reactors in Romania to the Russian Federation for conversion to low enriched uranium. The Institute for Nuclear Research at Pitesti (SCN Pitesti) shipped 30.1 kg of HEU fresh fuel pellets to Dimitrovgrad, Russia and the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH) shipped 23.7 kilograms of HEU spent fuel assemblies from the VVR S research reactor at Magurele, Romania, to Chelyabinsk, Russia. Both HEU shipments were coordinated by the Russian Research Reactor Fuel Return Program (RRRFR) as part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), were managed in Romania by the National Commission for Nuclear Activities Control (CNCAN), and were conducted in cooperation with the Russian Federation State Corporation Rosatom and the International Atomic Energy Agency. Both shipments were transported by truck to and from respective commercial airports in Romania and the Russian Federation and stored at secure nuclear facilities in Russia until the material is converted into low enriched uranium. These shipments resulted in Romania becoming the 3rd country under the RRRFR program and the 14th country under the GTRI program to remove all HEU. This paper describes the research reactor preparations and license approvals that were necessary to safely and securely complete these air shipments of nuclear fuel.

K. J. Allen; I. Bolshinsky; L. L. Biro; M. E. Budu; N. V. Zamfir; M. Dragusin; C. Paunoiu; M. Ciocanescu

2010-03-01T23:59:59.000Z

312

Research Output from Pakistan This analysis takes into account the Publications from Pakistani Universities,  

E-Print Network (OSTI)

Research Output from Pakistan This analysis takes into account the Publications from Pakistani NONE 01 68. University of Management & Technology NONE 01 Other Institutions 1. Pakistan Institute of Nuclear Science & Technology 106 171 2. Pakistan Council for Scientific & Industrial Research 38 110 3

Siddiqi, Sajjad Ahmed

313

Final Closeout Report University Research Program in Robotics for Environmental Restoration and Waste Management  

Science Conference Proceedings (OSTI)

The report covers the 2003-04 contract period, with a retrospective of the 11 years for the contract, from 1993 to 2004. This includes personnel, technical publications and reports, plus research laboratories employed. Specific information is given in eight research areas, reporting on all technology developed and/or deployed by the University of Florida.

James S. Tulenko; Carl Crane

2004-08-24T23:59:59.000Z

314

SOLERAS - University Research Project. Progress report No. 3, 1984-85 annual report  

Science Conference Proceedings (OSTI)

The accomplishments of solar energy research projects maintained by nine US universities are summarized. Some research topics covered include: photosynthesis; passive cooling; crystal growth of gallium arsenides; concentrating optics for PV conversion; amorphous silicon alloys; solar insolation; solar ponds; and wind power. (BCS)

Not Available

1985-09-01T23:59:59.000Z

315

DOE Selects Nine New University Coal Research Projects to Advance Coal-Based Power  

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

Selects Nine New University Coal Research Projects to Advance Coal-Based Power Selects Nine New University Coal Research Projects to Advance Coal-Based Power Systems Nine new projects selected by the U.S. Department of Energy (DOE) under the University Coal Research program will seek long-term solutions for the clean and efficient use of our nation's abundant coal resources. The announcement today of the selections marks the 34 th round of the Department's longest-running coal program, which began in 1979. This research continues DOE efforts to improve the understanding of the chemical and physical processes governing coal conversion and utilization, and support the technological development of the advanced coal power systems of the future. These advanced systems include ultra-clean

316

Foreign research reactor irradiated nuclear fuel inventories containing HEU and LEU of United States origin  

SciTech Connect

This report provides estimates of foreign research reactor inventories of aluminum-based and TRIGA irradiated nuclear fuel elements containing highly enriched and low enriched uranium of United States origin that are anticipated in January 1996, January 2001, and January 2006. These fuels from 104 research reactors in 41 countries are the same aluminum-based and TRIGA fuels that were eligible for receipt under the Department of Energy`s Offsite Fuels Policy that was in effect in 1988. All fuel inventory and reactor data that were available as of December 1, 1994, have been included in the estimates of approximately 14,300 irradiated fuel elements in January 1996, 18,800 in January 2001, and 22,700 in January 2006.

Matos, J.E.

1994-12-01T23:59:59.000Z

317

Environmental Assessment of Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel  

Science Conference Proceedings (OSTI)

The Department of Energy has completed the Environmental Assessment (EA) of Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel and issued a Finding of No Significant Impact (FONSI) for the proposed action. The EA and FONSI are enclosed for your information. The Department has decided to accept a limited number of spent nuclear fuel elements (409 elements) containing uranium that was enriched in the United States from eight research reactors in Austria, Denmark, Germany, Greece, the Netherlands, Sweden, and Switzerland. This action is necessary to maintain the viability of a major US nuclear weapons nonproliferation program to limit or eliminate the use of highly enriched uranium in civil programs. The purpose of the EA is to maintain the cooperation of the foreign research reactor operators with the nonproliferation program while a more extensive Environmental Impact Statement (EIS) is prepared on a proposed broader policy involving the acceptance of up to 15,000 foreign research reactor spent fuel elements over a 10 to 15 year period. Based on an evaluation of transport by commercial container liner or chartered vessel, five eastern seaboard ports, and truck and train modes of transporting the spent fuel overland to the Savannah River Sits, the Department has concluded that no significant impact would result from any combination of port and made of transport. In addition, no significant impacts were found from interim storage of spent fuel at the Savannah River Site.

Not Available

1994-04-01T23:59:59.000Z

318

Analyses for conversion of the Georgia Tech Research Reactor from HEU to LEU fuel  

SciTech Connect

This document presents information concerning: analyses for conversion of the Georgia Tech Research Reactor from HEU to LEU; changes to technical specifications mandated by the conversion of the GTRR to low enrichment fuel; changes in the Safety Analysis Report mandated by the conversion of the GTRR to low enrichment fuel; and copies of all changed pages of the SAR and the technical specifications.

Matos, J.E.; Mo, S.C.; Woodruff, W.L.

1992-09-01T23:59:59.000Z

319

MYRRHA a multi-purpose hybrid research reactor for high-tech applications  

SciTech Connect

MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is the flexible experimental accelerator driven system (ADS) in development at SCK-CEN. MYRRHA is able to work both in subcritical (ADS) as in critical mode. In this way, MYRRHA will allow fuel developments for innovative reactor systems, material developments for generation IV (GEN IV) systems, material developments for fusion reactors, radioisotope production and industrial applications, such as Si-doping. MYRRHA will also demonstrate the ADS full concept by coupling the three components (accelerator, spallation target and subcritical reactor) at reasonable power level to allow operation feedback, scalable to an industrial demonstrator and allow the study of efficient transmutation of high-level nuclear waste. MYRRHA is based on the heavy liquid metal technology and so it will contribute to the development of lead fast reactor (LFR) technology and in critical mode, MYRRHA will play the role of European technology pilot plant in the roadmap for LFR. In this paper the historical evolution of MYRRHA and the rationale behind the design choices is presented and the latest configuration of the reactor core and primary system is described. (authors)

Abderrahim, H. A.; Baeten, P. [SCK CEN, Boeretang 200, 2400 Mol (Belgium)

2012-07-01T23:59:59.000Z

320

Qualitative and Quantitative Management Tools Used by Financial Officers in Public Research Universities  

E-Print Network (OSTI)

This dissertation set out to identify effective qualitative and quantitative management tools used by financial officers (CFOs) in carrying out their management functions of planning, decision making, organizing, staffing, communicating, motivating, leading and controlling at a public research university. In addition, impediments to the use of these tools were identified which may assist in breaking down barriers to the implementation of these tools within higher education. The research endeavor also provided additional significance through the CFOs identifying benefits from the use of quantitative and qualitative management tools. Finally, the study undertook the task of identifying quantitative and qualitative management tools the important to public research university CFOs in carrying out their management functions in the future. In this study, the Delphi method was used to gain consensus from a panel of fifteen public research university CFOs who were experts on qualitative and quantitative management tools. The experts were self-identified through their response to a questionnaire on their use of the management tools and represented 12 different states. Due to the nature of the research, a computer-based Delphi method was used to facilitate a four round, electronically based Delphi study. The questionnaires were based upon a review of the literature and tested by a pilot group of higher education CFOs. Through a series of four electronic questionnaires, the Delphi panel identified twenty-three qualitative and quantitative management tools which they believe are moderately effective for use by public research university CFOs in carrying out their functions of planning, decision making, organizing, staffing, communicating, motivating, leading and controlling. Additionally, the panel of experts identified sixteen barriers/impediments to the use of qualitative and quantitative tools in carrying out the above functions. The panel also identified eighteen benefits that the tools provide to public research university CFOs in carrying out their management functions. Finally, the Delphi panel identified three qualitative and quantitative management tools that will be highly important, and twenty qualitative and quantitative management tools that the panel of experts considered to be important, for public research university CFOs in carrying out their management functions in the future. This dissertation study is significant because the results are expected to provide public research university CFOs qualitative and quantitative management tools that they may use to assist them in carrying out their management functions. The barriers/impediments and benefits noted also provide CFOs with knowledge to assess whether the tools can be used at their institutions, knowing the specific climate and culture which exists. The qualitative and quantitative management tools which were identified as being important in the future can serve as a guide to develop training programs to enhance the knowledge of public research university CFOs.

Trexler, Grant 1961-

2012-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "university research reactor" 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

UNIVERSITY TURBINE SYSTEMS RESEARCH-HIGH EFFICIENCY ENGINES AND TURBINES (UTSR-HEET)  

Science Conference Proceedings (OSTI)

In 2002, the U S Department of Energy established a cooperative agreement for a program now designated as the University Turbine Systems (UTSR) Program. As stated in the cooperative agreement, the objective of the program is to support and facilitate development of advanced energy systems incorporating turbines through a university research environment. This document is the first annual, technical progress report for the UTSR Program. The Executive Summary describes activities for the year of the South Carolina Institute for Energy Studies (SCIES), which administers the UTSR Program. Included are descriptions of: Outline of program administrative activities; Award of the first 10 university research projects resulting from a year 2001 RFP; Year 2002 solicitation and proposal selection for awards in 2003; Three UTSR Workshops in Combustion, Aero/Heat Transfer, and Materials; SCIES participation in workshops and meetings to provide input on technical direction for the DOE HEET Program; Eight Industrial Internships awarded to higher level university students; Increased membership of Performing Member Universities to 105 institutions in 40 states; Summary of outreach activities; and a Summary table describing the ten newly awarded UTSR research projects. Attachment A gives more detail on SCIES activities by providing the monthly exceptions reports sent to the DOE during the year. Attachment B provides additional information on outreach activities for 2002. The remainder of this report describes in detail the technical approach, results, and conclusions to date for the UTSR university projects.

Lawrence P. Golan; Richard A. Wenglarz; William H. Day

2003-03-01T23:59:59.000Z

322

Research Activities at the Vienna University of Technology on Promotion of  

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

Research Activities at the Vienna University of Technology on Promotion of Research Activities at the Vienna University of Technology on Promotion of Renewables and Decentralised Energy Supply Speaker(s): Amela Ajanovic Reinhard Haas Date: June 19, 2009 - 12:00pm Location: 90-3122 Currently, in Europe many efforts are undertaken especially by European policy makers to reduce CO2 emissions, to enhance energy efficiency, to increase the share of renewables and to reinforce competition in the European electricity market. The Energy Economics Group of Vienna University of Technology is involved in several projects funded by the European Commission and by national authorities which deal with these specific topics. In this presentation some insight will be provided on projects and research work with the following major focuses: (i) Promotion

323

Nuclear nonproliferation: Concerns with US delays in accepting foregin research reactors` spent fuel  

SciTech Connect

One key US nonproliferation goal is to discourage use of highly enriched uranium fuel (HEU), which can be used to make nuclear bombs, in civilian nuclear programs worldwide. DOE`s Off-Site Fuels Policy for taking back spent HEU from foreign research reactors was allowed to expire due to environmental reasons. This report provides information on the effects of delays in renewing the Off-Site Fuels Policy on US nonproliferation goals and programs (specifically the reduced enrichment program), DOE`s efforts to renew the fuels policy, and the price to be charged to the operators of foreign reactors for DOE`s activities in taking back spent fuel.

1994-03-25T23:59:59.000Z

324

Monte Carlo simulation of the Massachusetts Institute of Technology Research Reactor  

SciTech Connect

The three-dimensional continuous-energy MCNP Monte Carlo code is used to develop a versatile and accurate reactor physics model of the Massachusetts Institute of Technology Research Reactor 2 (MITR-2). The validation of the model against existing experimental data is presented. Core multiplication factors as well as fast neutron in-core flux measurements were used in the validation process. The agreement between the MCNP predictions and the experimentally determined values is very good, which indicates that the Monte Carlo model is correctly simulating the MITR-2.

Redmond, E.L. II; Yanch, J.C.; Harling, O.K. (Massachusetts Inst. of Tech., Cambridge, MA (United States). Nuclear Engineering Dept.)

1994-04-01T23:59:59.000Z

325

Neutronic safety parameters and transient analyses for potential LEU conversion of the Budapest Research Reactor.  

SciTech Connect

An initial safety study for potential LEU conversion of the Budapest Research Reactor was completed. The study compares safety parameters and example transients for reactor cores with HEU and LEU fuels. Reactivity coefficients, kinetic parameters and control rod worths were calculated for cores with HEU(36%) UAl alloy fuel and UO{sub 2}-Al dispersion fuel, and with LEU (19.75%)UO{sub 2}-Al dispersion fuel that has a uranium density of about 2.5 g/cm{sup 3}. A preliminary fuel conversion plan was developed for transition cores that would convert the BRR from HEU to LEU fuel after the process is begun.

Pond, R. B.; Hanan, N. A.; Matos, J. E.; Maraczy, C.

1999-09-27T23:59:59.000Z

326

Strategic Plan for Light Water Reactor Research and Development  

Science Conference Proceedings (OSTI)

The purpose of this strategic plan is to establish a framework that will allow the Department of Energy (DOE) and the nuclear power industry to jointly plan the nuclear energy research and development (R&D) agenda important to achieving the Nation's energy goals. This strategic plan has been developed to focus on only those R&D areas that will benefit from a coordinated government/industry effort. Specifically, this plan focuses on safely sustaining and expanding the electricity output from currently operating nuclear power plants and expanding nuclear capacity through the deployment of new plants. By focusing on R&D that addresses the needs of both current and future nuclear plants, DOE and industry will be able to take advantage of the synergism between these two technology areas, thus improving coordination, enhancing efficiency, and further leveraging public and private sector resources. By working together under the framework of this strategic plan, DOE and the nuclear industry reinforce their joint commitment to the future use of nuclear power and the National Energy Policy's goal of expanding its use in the United States. The undersigned believe that a public-private partnership approach is the most efficient and effective way to develop and transfer new technologies to the marketplace to achieve this goal. This Strategic Plan is intended to be a living document that will be updated annually.

None

2004-02-01T23:59:59.000Z

327

Bangladesh: Case Studies Bangladesh: Case Studies Renewable Energy Research Centre, Dhaka University, Bangladesh  

Open Energy Info (EERE)

Renewables in Renewables in Utilization of Renewables in Bangladesh: Case Studies Bangladesh: Case Studies Renewable Energy Research Centre, Dhaka University, Bangladesh Renewable Energy Research Centre, Dhaka University, Bangladesh Case Study I: Solar market electrification LGED has successfully completed Solar Market Electrification in Gangutia growth center under Sailkupa Thana in Jhenaidha district. This activity has been taken under sustainable rural energy (SRE) Project. The objectives of this project are to install a demonstrative plant of a centralized solar photovoltaic system for electrification of a rural market in the off-grid area and to assess its technical and economic viability in the context of rural Bangladesh. Gangutia growth center has been selected for solar

328

Fresh and Spent Nuclear Fuel Repatriation from the IRT-2000 Research Reactor Facility, Sofia, Bulgaria  

SciTech Connect

The IRT 2000 research reactor, operated by the Bulgarian Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped all of their Russian-origin nuclear fuel from the Republic of Bulgaria to the Russian Federation beginning in 2003 and completing in 2008. These fresh and spent fuel shipments removed all highly enriched uranium (HEU) from Bulgaria. The fresh fuel was shipped by air in December 2003 using trucks and a commercial cargo aircraft. One combined spent fuel shipment of HEU and low enriched uranium (LEU) was completed in July 2008 using high capacity VPVR/M casks transported by truck, barge, and rail. The HEU shipments were assisted by the Russian Research Reactor Fuel Return Program (RRRFR) and the LEU spent fuel shipment was funded by Bulgaria. This report describes the work, approvals, organizations, equipment, and agreements required to complete these shipments and concludes with several major lessons learned.

K. J. Allen; T. G. Apostolov; I. S. Dimitrov

2009-03-01T23:59:59.000Z

329

Radiological survey support activities for the decommissioning of the Ames Laboratory Research Reactor Facility, Ames, Iowa  

SciTech Connect

At the request of the Engineering Support Division of the US Department of Energy-Chicago Operations Office and in accordance with the programmatic overview/certification responsibilities of the Department of Energy Environmental and Safety Engineering Division, the Argonne National Laboratory Radiological Survey Group conducted a series of radiological measurements and tests at the Ames Laboratory Research Reactor located in Ames, Iowa. These measurements and tests were conducted during 1980 and 1981 while the reactor building was being decontaminated and decommissioned for the purpose of returning the building to general use. The results of these evaluations are included in this report. Although the surface contamination within the reactor building could presumably be reduced to negligible levels, the potential for airborne contamination from tritiated water vapor remains. This vapor emmanates from contamination within the concrete of the building and should be monitored until such time as it is reduced to background levels. 2 references, 8 figures, 6 tables.

Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

1984-09-01T23:59:59.000Z

330

STORED ENERGY: GROWTH AND ANNEALING STATUS OF GRAPHITE MODERATOR IN THE BNL RESEARCH REACTOR. Final Report  

SciTech Connect

The present sthtus, past annealing procedures and experiences, future annealing procedures, annealing sehedule, revised annealing procedure (1958), procedure for combating a graphite fire in fuel channel, high-temperature stored energy, and graphite burning experiments are reportcd for the BNL Research Reactor. The following subjccts are discussed in the appendixes: control of radiation damage in a graphitc reactor; annealing of graphite moderator structure in the BNL; annealing operation in BNL graphite reactor; effect of pile radiation on mechanical and other properties of graphite; neutron sensing instrumentation; instrumentation for sensing fuel failures; thermocouple pattern for enriched fuel loading; environmental hazard from a molten fuel element; retention of volatile flssion products on filters; retention of volatile fission products on water tube coolers; retention of volatile fission products in molten fuel plates; and release of the lowtemperature stored energy in the BEPO Pile. (W.L.H.)

1959-10-31T23:59:59.000Z

331

A Review of Previous Research in Direct Energy Conversion Fission Reactors  

DOE Green Energy (OSTI)

From the earliest days of power reactor development, direct energy conversion was an obvious choice to produce high efficiency electric power generation. Directly capturing the energy of the fission fragments produced during nuclear fission avoids the intermediate conversion to thermal energy and the efficiency limitations of classical thermodynamics. Efficiencies of more than 80% are possible, independent of operational temperature. Direct energy conversion fission reactors would possess a number of unique characteristics that would make them very attractive for commercial power generation. These reactors would be modular in design with integral power conversion and operate at low pressures and temperatures. They would operate at high efficiency and produce power well suited for long distance transmission. They would feature large safety margins and passively safe design. Ideally suited to production by advanced manufacturing techniques, direct energy conversion fission reactors could be produced more economically than conventional reactor designs. The history of direct energy conversion can be considered as dating back to 1913 when Moseleyl demonstrated that charged particle emission could be used to buildup a voltage. Soon after the successful operation of a nuclear reactor, E.P. Wigner suggested the use of fission fragments for direct energy conversion. Over a decade after Wigner's suggestion, the first theoretical treatment of the conversion of fission fragment kinetic energy into electrical potential appeared in the literature. Over the ten years that followed, a number of researchers investigated various aspects of fission fragment direct energy conversion. Experiments were performed that validated the basic physics of the concept, but a variety of technical challenges limited the efficiencies that were achieved. Most research in direct energy conversion ceased in the US by the late 1960s. Sporadic interest in the concept appears in the literature until this day, but there have been no recent significant programs to develop the technology.

DUONG,HENRY; POLANSKY,GARY F.; SANDERS,THOMAS L.; SIEGEL,MALCOLM D.

1999-09-22T23:59:59.000Z

332

U.S. Department of Energy Instrumentation and Controls Technology Research for Advanced Small Modular Reactors  

Science Conference Proceedings (OSTI)

Instrumentation, controls, and human-machine interfaces (ICHMI) are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The U.S. Department of Energy (DOE) has recognized that ICHMI research, development, and demonstration (RD&D) is needed to resolve the technical challenges that may compromise the effective and efficient utilization of modern ICHMI technology and consequently inhibit realization of the benefits offered by expanded utilization of nuclear power. Consequently, key DOE programs have substantial ICHMI RD&D elements to their respective research portfolio. This article describes current ICHMI research to support the development of advanced small modular reactors.

Wood, Richard Thomas [ORNL

2012-01-01T23:59:59.000Z

333

Geothermal Technologies Program Geoscience and Supporting Technologies 2001 University Research Summaries  

SciTech Connect

The U.S. Department of Energy Office of Wind and Geothermal Technologies (DOE) is funding advanced geothermal research through University Geothermal Research solicitations. These solicitations are intended to generate research proposals in the areas of fracture permeability location and characterization, reservoir management and geochemistry. The work funded through these solicitations should stimulate the development of new geothermal electrical generating capacity through increasing scientific knowledge of high-temperature geothermal systems. In order to meet this objective researchers are encouraged to collaborate with the geothermal industry. These objectives and strategies are consistent with DOE Geothermal Energy Program strategic objectives.

Creed, Robert John; Laney, Patrick Thomas

2002-06-01T23:59:59.000Z

334

Geothermal Technologies Program Geoscience and Supporting Technologies 2001 University Research Summaries  

DOE Green Energy (OSTI)

The U.S. Department of Energy Office of Wind and Geothermal Technologies (DOE) is funding advanced geothermal research through University Geothermal Research solicitations. These solicitations are intended to generate research proposals in the areas of fracture permeability location and characterization, reservoir management and geochemistry. The work funded through these solicitations should stimulate the development of new geothermal electrical generating capacity through increasing scientific knowledge of high-temperature geothermal systems. In order to meet this objective researchers are encouraged to collaborate with the geothermal industry. These objectives and strategies are consistent with DOE Geothermal Energy Program strategic objectives.

Creed, R.J.; Laney, P.T.

2002-05-14T23:59:59.000Z

335

REACTOR  

DOE Patents (OSTI)

A pressurized water reactor in which automatic control is achieved by varying the average density of the liquid moderator-cooiant is patented. Density is controlled by the temperature and power level of the reactor ftself. This control can be effected by the use of either plate, pellet, or tubular fuel elements. The fuel elements are disposed between upper and lower coolant plenum chambers and are designed to permit unrestricted coolant flow. The control chamber has an inlet opening communicating with the lower coolant plenum chamber and a restricted vapor vent communicating with the upper coolant plenum chamber. Thus, a variation in temperature of the fuel elements will cause a variation in the average moderator density in the chamber which directly affects the power level of the reactor.

Roman, W.G.

1961-06-27T23:59:59.000Z

336

Colorado State University Title: Graduate Research Assistantship in Remote Sensing of  

E-Print Network (OSTI)

Colorado State University Title: Graduate Research Assistantship in Remote Sensing of Vegetation vegetation Evapotranspiration (ET) using Remote Sensing (RS) methods. The focus will be on determining actual content sensors and remote sensing/GIS is desirable but not required. Experience or familiarity

337

American Institute of Aeronautics and Astronautics Wave Rotor Research Program at Michigan State University  

E-Print Network (OSTI)

turbines, and water refrigeration systems. In collaboration with the research team at Warsaw University, and other design and analysis tools are discussed. I. Introduction here is a continual demand to increase, propulsion, refrigeration, and car engine supercharging. References 4-7 have comprehensively reviewed

MĂĽller, Norbert

338

20Fact Book 2011-2012 Office of Institutional Research (Source: Iowa State University Library)  

E-Print Network (OSTI)

20Fact Book 2011-2012 Library Office of Institutional Research (Source: Iowa State University journals and books, local collections, online indexes, electronic course reserves and guides, and a broad in Library 2,856,787 Books purchased annually 23,148 Journal titles received annually 117,559 Microform units

Beresnev, Igor

339

DOE-NREL Minority University Research Associates Program FY 2005 Accomplishments  

DOE Green Energy (OSTI)

The DOE-NREL Minority University Research Associates (MURA) Program encourages minority students to pursue careers in science and technology. In 2003, eight minority-serving institutions were awarded 3-year subcontracts that began in the summer/fall of FY 2004. This paper lists accomplishments made in the project's first phase.

Eddy, F. P.

2005-11-01T23:59:59.000Z

340

A neutronic feasibility study for LEU conversion of the Budapest research reactor.  

SciTech Connect

A neutronic feasibility study for conversion of the Budapest Research Reactor (BRR) from HEU to LEU fuel was performed at Argonne National Laboratory in cooperation with the KFKI Atomic Energy Research Institute in Hungary. Comparisons were made of the reactor performance with the current HEU (36%) fuel and with a proposed LEU (19.75%) fuel. Cycle lengths, thermal neutron fluxes, and rod worths were calculated in equilibrium-type cores for each type of fuel. Relative to the HEU fuel, the LEU fuel has up to a 50% longer fuel cycle length, but a 7-10% smaller thermal neutron flux in the experiment locations. The rod worths are smaller with the LEU fuel, but are still large enough to easily satisfy the BRR shutdown margin criteria. Irradiation testing of four VVR-M2 LEU fuel assemblies that are nearly the same as the proposed BRR LEU fuel assemblies is currently in progress at the Petersburg Nuclear Physics Institute.

Pond, R. B.

1998-10-16T23:59:59.000Z

Note: This page contains sample records for the topic "university research reactor" 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

DEVELOPMENT OF A FAST-RELEASE ELECTRO-MAGNET FOR POOL-TYPE RESEARCH REACTORS  

SciTech Connect

Experimental data and observations of the design parameters and physical configurations which lead to faster-release cylindrical flat-faced electromagnets are given. Detailed drawings and operating characteristics are presented for an electromagnet suited to the requirements of a pool-type research reactor using either gravity drop or additional accelerating force. This electromagnet embodies the experimentally developed techniques for attaining fast release. (auth)

Michelson, C.

1958-02-14T23:59:59.000Z

342

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report  

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01T23:59:59.000Z

343

A simple setup for neutron tomography at the Portuguese Nuclear Research Reactor  

E-Print Network (OSTI)

A simple setup for neutron radiography and tomography was recently installed at the Portuguese Research Reactor. The objective of this work was to determine the operational characteristics of the installed setup, namely the irradiation time to obtain the best dynamic range for individual images and the spatial resolution. The performance of the equipment was demonstrated by imaging a fragment of a 17th century decorative tile.

M. A. Stanojev Pereira; J. G. Marques; R. Pugliesi

2012-05-15T23:59:59.000Z

344

Nuclear mass inventory, photon dose rate and thermal decay heat of spent research reactor fuel assemblies  

SciTech Connect

This document has been prepared to assist research reactor operators possessing spent fuel containing enriched uranium of United States origin to prepare part of the documentation necessary to ship this fuel to the United States. Data are included on the nuclear mass inventory, photon dose rate, and thermal decay heat of spent research reactor fuel assemblies. Isotopic masses of U, Np, Pu and Am that are present in spent research reactor fuel are estimated for MTR, TRIGA and DIDO-type fuel assembly types. The isotopic masses of each fuel assembly type are given as functions of U-235 burnup in the spent fuel, and of initial U-235 enrichment and U-235 mass in the fuel assembly. Photon dose rates of spent MTR, TRIGA and DIDO-type fuel assemblies are estimated for fuel assemblies with up to 80% U-235 burnup and specific power densities between 0.089 and 2.857 MW/kg[sup 235]U, and for fission product decay times of up to 20 years. Thermal decay heat loads are estimated for spent fuel based upon the fuel assembly irradiation history (average assembly power vs. elapsed time) and the spent fuel cooling time.

Pond, R.B.; Matos, J.E.

1996-12-31T23:59:59.000Z

345

Publications and geothermal sample library facilities of the Earth Science Laboratory, University of Utah Research Institute  

DOE Green Energy (OSTI)

The Earth Science Laboratory of the University of Utah Research Institute has been involved in research in geothermal exploration and development for the past eleven years. Our work has resulted in the publication of nearly 500 reports, which are listed in this document. Over the years, we have collected drill chip and core samples from more than 180 drill holes in geothermal areas, and most of these samples are available to others for research, exploration and similar purposes. We hope that scientists and engineers involved in industrial geothermal development will find our technology transfer and service efforts helpful.

Wright, Phillip M.; Ruth, Kathryn A.; Langton, David R.; Bullett, Michael J.

1990-03-30T23:59:59.000Z

346

University Research National Labs | U.S. DOE Office of Science...  

Office of Science (SC) Website

link Kansas Kansas State University External link University of Kansas External link Kentucky University of Louisville External link Louisiana Louisiana State University...

347

Reactor physics teaching and research in the Swiss nuclear engineering master  

Science Conference Proceedings (OSTI)

Since 2008, a Master of Science program in Nuclear Engineering (NE) has been running in Switzerland, thanks to the combined efforts of the country's key players in nuclear teaching and research, viz. the Swiss Federal Inst.s of Technology at Lausanne (EPFL) and at Zurich (ETHZ), the Paul Scherrer Inst. (PSI) at Villigen and the Swiss Nuclear Utilities (Swissnuclear). The present paper, while outlining the academic program as a whole, lays emphasis on the reactor physics teaching and research training accorded to the students in the framework of the developed curriculum. (authors)

Chawla, R. [Swiss Federal Inst. of Technology EPFL, CH-1015 Lausanne (Switzerland); Paul Scherrer Inst., CH-5232 Villigen PSI (Switzerland)

2012-07-01T23:59:59.000Z

348

Submission – House of Representatives Standing Committee on Industry, Science and Innovation Inquiry into Research Training and Research Workforce Issues in Australian Universities  

E-Print Network (OSTI)

The contribution that Australian universities make to research training in Australia a) Contribution of research training programs to Australia’s competitiveness in the areas of science, research and innovation Australian universities are clearly the primary research training platform in regards to science, research and innovation. Commonwealth research training scheme funding is accessed by The University of Notre Dame Australia (UNDA) to provide, primarily, relief from tuition fees for higher degree by research students. Only a very minimal amount of RTS funding is used to fund skills acquisition and professional development for research active staff and students at UNDA. Other programs within UNDA that are linked to RTS include a limited injection of funding into student research project costs and general research capacity building. UNDA has undergone a sustained growth in its research student population; our enrolled research students have increased seven-fold between 2002 and 2008. RTS funding has significantly supported this growth and, as a result, the capacity to support research in other ways has remained limited. One example of where the University has achieved success on a limited budget has been in the implementation of a “Research Incentive Scheme ” that rewards research output and acts as a catalyst for future research initiatives. In the context of seeking to achieve excellence in niche research UNDA has expanded its research program in the

unknown authors

2008-01-01T23:59:59.000Z

349

$18.8 Million Award for Power Systems Engineering Research Center Continues Collaboration of 13 Universities and 35 Utilities for Electric Power Research, Building the Nation's Energy Workforce  

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

The Department of Energy awarded a cooperative agreement on January 16, 2009, to the Arizona State University (ASU) Board of Regents to operate the Power Systems Engineering Research Center (PSERC). PSERC is a collaboration of 13 universities with 35 electricity industry member organizations including utilities, transmission companies, vendors and research organizations...

350

IGORR-1: Proceedings of the first meeting of the international group on research reactors  

SciTech Connect

Many organizations, in several countries, are planning or implementing new or upgraded research reactor projects, but there has been no organized forum devoted entirely to discussion and exchange of information in this field. Over the past year or so, informal discussions resulted in widespread agreement that such a forum would serve a useful purpose. Accordingly, a proposal to form a group was submitted to the leading organizations known to be involved in projects to build or upgrade reactor facilities. Essentially all agreed to join in the formation of the International Group on Research Reactors (IGORR) and nominated a senior staff member to serve on its international organizing committee. The first IGORR meeting took place on February 28--March 2, 1990. It was very successful and well attended; some 52 scientists and engineers from 25 organizations in 10 countries participated in 2-1/2 days of open and informative presentations and discussions. Two workshop sessions offered opportunities for more detailed interaction among participants and resulted in identification of common R D needs, sources of data, and planned new facilities. Individual papers have been cataloged separately.

West, C.D. (comp.)

1990-05-01T23:59:59.000Z

351

Evaluation of the thermal-hydraulic operating limits of the HEU-LEU transition cores for the MIT Research Reactor  

E-Print Network (OSTI)

The MIT Research Reactor (MITR) is in the process of conducting a design study to convert from High Enrichment Uranium (HEU) fuel to Low Enrichment Uranium (LEU) fuel. The currently selected LEU fuel design contains 18 ...

Wang, Yunzhi (Yunzhi Diana)

2009-01-01T23:59:59.000Z

352

Thermal hydraulics analysis of the MIT research reactor in support of a low enrichment uranium (LEU) core conversion  

E-Print Network (OSTI)

The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density monolithic UMo fuel. The design of an optimum LEU core for the ...

Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology

2008-01-01T23:59:59.000Z

353

NUMERICAL SIMULATION FOR MECHANICAL BEHAVIOR OF U10MO MONOLITHIC MINIPLATES FOR RESEARCH AND TEST REACTORS  

Science Conference Proceedings (OSTI)

This article presents assessment of the mechanical behavior of U-10wt% Mo (U10Mo) alloy based monolithic fuel plates subject to irradiation. Monolithic, plate-type fuel is a new fuel form being developed for research and test reactors to achieve higher uranium densities within the reactor core to allow the use of low-enriched uranium fuel in high-performance reactors. Identification of the stress/strain characteristics is important for understanding the in-reactor performance of these plate-type fuels. For this work, three distinct cases were considered: (1) fabrication induced residual stresses (2) thermal cycling of fabricated plates; and finally (3) transient mechanical behavior under actual operating conditions. Because the temperatures approach the melting temperature of the cladding during the fabrication and thermal cycling, high temperature material properties were incorporated to improve the accuracy. Once residual stress fields due to fabrication process were identified, solution was used as initial state for the subsequent simulations. For thermal cycling simulation, elasto-plastic material model with thermal creep was constructed and residual stresses caused by the fabrication process were included. For in-service simulation, coupled fluid-thermal-structural interaction was considered. First, temperature field on the plates was calculated and this field was used to compute the thermal stresses. For time dependent mechanical behavior, thermal creep of cladding, volumetric swelling and fission induced creep of the fuel foil were considered. The analysis showed that the stresses evolve very rapidly in the reactor. While swelling of the foil increases the stress of the foil, irradiation induced creep causes stress relaxation.

Hakan Ozaltun & Herman Shen

2011-11-01T23:59:59.000Z

354

This paper has been downloaded from the Building and Environmental Thermal Systems Research Group at Oklahoma State University  

E-Print Network (OSTI)

, HVAC&R Research, 17:6, 891-894 ©ASHRAE, www.ashrae.org. Reprinted by permission from HVAC&R Research without ASHRAE's permission. #12;This article was downloaded by: [Oklahoma State University] On: 16 Bernier PhD b a Fellow ASHRAE, Oklahoma State University b Member ASHRAE, Ecole Polytechnique de Montréal

355

Neutronic safety parameters and transient analyses for Poland's MARIA research reactor.  

SciTech Connect

Reactor kinetic parameters, reactivity feedback coefficients, and control rod reactivity worths have been calculated for the MARIA Research Reactor (Swierk, Poland) for M6-type fuel assemblies with {sup 235}U enrichments of 80% and 19.7%. Kinetic parameters were evaluated for family-dependent effective delayed neutron fractions, decay constants, and prompt neutron lifetimes and neutron generation times. Reactivity feedback coefficients were determined for fuel Doppler coefficients, coolant (H{sub 2}O) void and temperature coefficients, and for in-core and ex-core beryllium temperature coefficients. Total and differential control rod worths and safety rod worths were calculated for each fuel type. These parameters were used to calculate generic transients for fast and slow reactivity insertions with both HEU and LEU fuels. The analyses show that the HEU and LEU cores have very similar responses to these transients.

Bretscher, M. M.; Hanan, N. A.; Matos, J. E.; Andrzejewski, K.; Kulikowska, T.

1999-09-27T23:59:59.000Z

356

RELAP5 Application to Accident Analysis of the NIST Research Reactor  

Science Conference Proceedings (OSTI)

Detailed safety analyses have been performed for the 20 MW D{sub 2}O moderated research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The time-dependent analysis of the primary system is determined with a RELAP5 transient analysis model that includes the reactor vessel, the pump, heat exchanger, fuel element geometry, and flow channels for both the six inner and twenty-four outer fuel elements. A post-processing of the simulation results has been conducted to evaluate minimum critical heat flux ratio (CHFR) using the Sudo-Kaminaga correlation. Evaluations are performed for the following accidents: (1) the control rod withdrawal startup accident and (2) the maximum reactivity insertion accident. In both cases the RELAP5 results indicate that there is adequate margin to CHF and no damage to the fuel will occur because of sufficient coolant flow through the fuel channels and the negative scram reactivity insertion.

Baek, J.; Cuadra Gascon, A.; Cheng, L.Y.; Diamond, D.

2012-03-18T23:59:59.000Z

357

ORNL/TM-2012/380 Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research  

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

2/380 2/380 Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program September 2012 Prepared by Cyrus Smith Randy Nanstad Robert Odette Dwight Clayton Katie Matlack Pradeep Ramuhalli Glenn Light DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of Energy (DOE) Information Bridge. Web site http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source. National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900

358

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

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

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

359

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

Science Conference Proceedings (OSTI)

The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2ĽCr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

360

Regulatory Experiences for the Decommissioning of the Research Reactor in Korea  

Science Conference Proceedings (OSTI)

The first research reactor in Korea (KRR-1, TRIGA Mark-II) has operated since 1962, and the second one (KRR-2, TRIGA Mark-III), since 1972. Both of them were phased out in 1995 due to their lives and the operation of a new research reactor, HANARO (30 MW thermal power) operated by KAERI (Korea Atomic Energy Research Institute). After deciding the shutdown by the Nuclear Development and Utilization Committee in March 1996, KAERI began to prepare the decommissioning plan, including the environmental impact assessment, and submitted the plan to the Ministry of Science and Technology (MOST) in December 1998. Korea Institute of Nuclear Safety (KINS) reviewed document and prepared the review report in 1999. KINS is an organization of technical expertise which performs regulatory functions, entrusted by the MOST in accordance with the Atomic Energy Act and its Enforcement Decree. The review report written by KINS was consulted by the Special Committee on Nuclear Safety in January 2000. The committee submitted their consultation results to the Nuclear Safety Commission for the final approval by the Minister of MOST. The license was issued in November 2000. With the consent of the Korean government to the US Record of Decision, the spent fuel of KRR-1 and 2 was safely transported to the United States in July 1998. The decontamination and dismantling of KRR-2 was completed at the end of 2005 but the decommissioning of KRR-1 has been suspended by the problem for the memorial of the reactor. After the decommissioning of the research reactor is finished, the site will be returned to the site owner, Korea Electric Power Corporation (KEPCO). In this paper, the state-of-art and lessons learnt from recent regulatory activities for decommissioning of KRR- 2 are summarized. In conclusion: since the shutdown of KRR-1 and 2 had been decided, the safe assessment and licensing review were carried out after applying for decommissioning plan of those research reactors by operator. Through the safety assessment and license review, the plan was approved in 2000. The D and D of KRR-2 except Reactor hall of KRR-1 has been performed safely and completed in 2005. On the other hand the integrated safety for the decommissioning has been confirmed by regulatory team inspection. The radioactive waste arising from the dismantling work has been packed mainly in a 4 m{sup 3} containers and stored on site, reactor hall of KRR-2, until the LILW disposal facility is operational. For the whole dismantling work, with respect to the ALARA principle, not only worker protection from radiation and industrial hazard, but also the environment protection should be the first priority. Also much attention has been paid to the record keeping for the future decommissioning of nuclear power plants.

CHOI, Kyung-Woo [Korea Institute of Nuclear Safety, P.O Box 114, Yuseong, Daejeon (Korea, Republic of)

2008-01-15T23:59:59.000Z

Note: This page contains sample records for the topic "university research reactor" from the National Library of EnergyBeta (NLEBeta).
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361

Texas Tech University Accomplishments 2011: Research http://www.depts.ttu.edu/communications/test/accomplishments/research.php[3/22/2011 2:37:35 PM  

E-Print Network (OSTI)

Texas Tech University Accomplishments 2011: Research http://www.depts.ttu.edu/communications/test/accomplishments/research.php[3/22/2011 2:37:35 PM] YEAR IN REVIEW STUDENTS RESEARCH OUTREACH EXCELLENCE Texas Tech researchers scientists and scholars will continue to find the answers that matter. Texas Tech is included in a $5

Rock, Chris

362

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices  

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01T23:59:59.000Z

363

Evaluation of differential shim rod worth measurements in the Oak Ridge Research Reactor  

Science Conference Proceedings (OSTI)

Reasonable agreement between calculated and measured differential shim rod worths in the Oak Ridge Research Reactor (ORR) has been achieved by taking into account the combined effects of negative reactivity contributions from changing fuel-moderator temperatures and of delayed photoneutrons. A method has been developed for extracting the asymptotic period from the shape of the initial portion of the measured time-dependent neutron flux profile following a positive reactivity insertion. In this region of the curve temperature-related reactivity feedback effects are negligibly small. Results obtained by applying this technique to differential shim rod worth measurements made in a wide variety of ORR cores are presented.

Bretscher, M.M.

1987-01-01T23:59:59.000Z

364

Assessment of the DOE/NREL Historically Black College and University Photovoltaic Research Associates Program  

DOE Green Energy (OSTI)

This report details the DOE/NREL Historically Black College and University (HBCU) Photovoltaic Research Associates Program, a small but remarkable program that directly affected dozens of minority undergraduate students in ways that changed many of their lives. The progress and accomplishments of undergraduates within the nine participating universities were monitored and assessed through their presentations at an annual NREL-sponsored HBCU conference. Although the funding was small, typically $400,000 per year, the money made a significant impact. The best students sometimes went on to the nation's top graduate schools (e.g., MIT) or important management positions in large companies. Other students had opportunities to learn how renewable energy could positively affect their lives and their neighbors' lives. A few were lucky enough to install photovoltaic lighting and water-pumping systems in Africa, and to see and feel firsthand the technical and emotional benefits of this technology for families and villages. Two of the schools, Texas Southern University and Central State University, were particularly successful in leveraging their DOE/NREL funding to obtain additional funding for expanded programs.

Posey-Eddy, F.; McConnell, R. D.

2002-08-01T23:59:59.000Z

365

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

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production, with an outlet gas temperature in the range of 750°C, and a design service life of 60 years. The reactor design will be a graphite-moderated, helium-cooled, prismatic, or pebble bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. This technology development plan details the additional research and development (R&D) required to design and license the NGNP RPV, assuming that A 508/A 533 is the material of construction. The majority of additional information that is required is related to long-term aging behavior at NGNP vessel temperatures, which are somewhat above those commonly encountered in the existing database from LWR experience. Additional data are also required for the anticipated NGNP environment. An assessment of required R&D for a Grade 91 vessel has been retained from the first revision of the R&D plan in Appendix B in somewhat less detail. Considerably more development is required for this steel compared to A 508/A 533 including additional irradiation testing for expected NGNP operating temperatures, high-temperature mechanical properties, and extensive studies of long-term microstructural stability.

J. K. Wright; R. N. Wright

2010-07-01T23:59:59.000Z

366

Seminar on Uncertainty & Decision Making Ghent University and Belgian Nuclear Research Centre  

E-Print Network (OSTI)

Matemáticas, UCM "Soft Computing and Nuclear Reactor Control" ABSTRACT: The need for on-line reactor operator, as a means of expressing linguistic expressions mathematically, has been recently applied to nuclear reactor) for controlling the power level of a nuclear reactor, the study was intended to assess the applicability of fuzzy

Tradacete, Pedro

367

Technologies development for environmental restoration and waste management: International university and research institution and industry partnerships  

SciTech Connect

The Institute for Central and Eastern European Cooperative Environmental Research (ICEECER) at Florida State University was formed in 1990 soon after the end of the Cold War. ICEECER consists of a number of joint centers which link FSU, and US as well as international funding agencies, to academic and research institutions in Hungary, Poland, the Czech Republic, Russia, and the other countries of Central and Eastern Europe and the Newly Independent States. Areas of interest include risk assessment, toxicology, contaminated site remediation/characterization, waste management, emergency response, environmental technology development/demonstration/transfer, and some specialized areas of research (e.g., advanced chemical separations). Through ICEECER, numerous international conferences, symposia, training courses, and workshops have also been conducted on a variety of environmental topics. This paper summarizes the mission, structure, and administration of ICEECER and provides information on the projects conducted through this program at FSU.

Herndon, R.C.; Moerlins, J.E.; Kuperberg, J.M.

1996-12-31T23:59:59.000Z

368

Problems associated with the establishment of a whole body counter at a university reactor  

E-Print Network (OSTI)

A widd variety of difficulties can arise in bringing a ics. whole body counting chair into operation for screening radiation workers. Problems can arise in the mechanical operation of the chair, in fabrication of phantom source bottles, and in calibrating the detectors. This project addressed all of these factors. Applied Physical Technology, Inc was once a manufacturer of whole body counting chairs. One of the chairs, Model WBC-6000 with three associated NaI(T1) detectors, was donated to Texas A&M University. In order to bring it into operation, physical repairs to the control box and emergency release mechanism were completed. The block phantom that accompanied the chair did not have source bottles. After establishing a set of procedures, several sets of source bottles were fabricated for use in the lung, Gl tract, and thyroid regions of the phantoms. With the radionuclide sources created, the equipment was assembled and a series of counts was performed in various source configurations. From the information collected in the counts, all three of the detectors were calibrated according to the guidelines established in ANSI N 13.30 and NCRP Report 57, using guidance from NUREG 8.9. The primary results of this project were: 1) a knowledge of how to establish procedures for generating radionuclides and manipulating the activities for use as a phantom source; 2) an intimate knowledge of gamma spectroscopy, including the creation of calibration efficiencies; and 3) a calibrated whole body counting system capable of confidently measuring internal radioactive contamination in personnel.

Fairchild, Gregory R

1999-01-01T23:59:59.000Z

369

A detailed neutronics comparison of the university of Florida training reactor (UFTR) current HEU and proposed LEU cores  

SciTech Connect

For over 35 years, the UFTR highly-enriched core has been safely operated. As part of the Reduced Enrichment for Research and Test Reactors Program, the core is currently being converted to low-enriched uranium fuel. The analyses presented in this paper were performed to verify that, from a neutronic perspective, a proposed low-enriched core can be operated as safely and as effectively as the highly-enriched core. Detailed Monte Carlo criticality calculations are performed to determine: i) Excess reactivity for different core configurations, ii) Individual integral blade worth and shutdown margin, iii) Reactivity coefficients and kinetic parameters, and iv) Flux profiles and core six-factor formula parameters. (authors)

Dionne, B.; Haghighat, A.; Yi, C.; Smith, R.; Ghita, G.; Manalo, K.; Sjoden, G.; Huh, J.; Baciak, J.; Mock, T.; Wenner, M. [Dept. of Nuclear and Radiological Engineering, Univ. of Florida, Gainesville, FL (United States); Matos, J.; Stillman, J. [Reduced Enrichment for Research and Test Reactors Program, Argonne National Laboratory, Argonne, IL (United States)

2006-07-01T23:59:59.000Z

370

A disposition strategy for highly enriched, aluminum-based fuel from research and test reactors  

SciTech Connect

The strategy proposed in this paper offers the Department of Energy an approach for disposing of aluminum-based, highly enriched uranium (HEU) spent fuels from foreign and domestic research reactors. The proposal is technically, socially, and economically sound. If implemented, it would advance US non-proliferation goals while also disposing of the spent fuel`s waste by timely and proven methods using existing technologies and facilities at SRS without prolonged and controversial storage of the spent fuel. The fuel would be processed through 221-H. The radioactive fission products (waste) would be treated along with existing SRS high level waste by vitrifying it as borosilicate glass in the Defense Waste Processing Facility (DWPF) for disposal in the national geological repository. The HEU would be isotopically diluted, during processing, to low-enriched uranium (LEU) which can not be used to make weapons, thus eliminating proliferation concerns. The LEU can be sold to fabricators of either research reactor fuel or commercial power fuel. This proposed processing-LEU recycle approach has several important advantages over other alternatives, including: Lowest capital investment; lowest net total cost; quickest route to acceptable waste form and final geologic disposal; and likely lowest safety, health, and environmental impacts.

McKibben, J.M.; Gould, T.H.; McDonell, W.R.; Bickford, W.E.

1994-11-01T23:59:59.000Z

371

Thermal-hydraulic calculations for the conversion to LEU of a research reactor core  

SciTech Connect

The thermal-hydraulic analysis performed for the needs of the conversion of the open pool 5MW Greek Research Reactor (GRR-1) to a pure Low Enrichment (LEU) configuration is presented. The methodology was based on a complete set of neutronic calculations performed for the new core configuration, in compliance with pre-defined Operation Limiting Conditions. The hottest channel analysis approach was adopted, and peaking factors were used to account for fabrication or measuring uncertainties. Calculations were carried out using the numerical codes NATCON, PLTEMP and PARET provided by Argonne National Laboratory (ANL). Two main different classes of conditions were considered, namely i) steady state normal operating conditions and ii) transient cases related to accidental events including reactivity feedback effects. For steady state operating conditions the behaviour of the new configuration was examined both for forced and natural convection cooling modes. Transient calculations considered several initiating events including reactivity insertion accidents (slow or fast reactivity insertion) and total or partial loss-of-flow accidents, i.e. in accordance to guidelines provided by the IAEA for research Reactors. (author)

Grigoriadis, D. [National Center for Scientific Research 'DEMOKRITOS', 153 10 Aghia Paraskevi (Greece); Department of Mechanical and Manufacturing Engineering, University of Cyprus, P.O. Box 20537, Nicosia 1678 (Cyprus); Varvayanni, M.; Catsaros, N.; Stakakis, E. [National Center for Scientific Research 'DEMOKRITOS', 153 10 Aghia Paraskevi (Greece)

2008-07-15T23:59:59.000Z

372

An analysis of radionuclide behavior in water pools during accidents at the Annular Core Research Reactor  

SciTech Connect

Physical and chemical phenomena that will affect the behavior of radionuclides released from fuel in the Annular Core Research Reactor during a hypothetical, core disruptive accident are described. The phenomena include boiling of water on heated clad, metal-water reactions, vapor nucleation to form aerosol particles, coagulation of aerosol particles, aerosol deposition within bubbles rising through the shield pool, vapor dissolution in the shield pool, and revaporization of radionuclides from the shield pool. A model of these phenomena is developed and applied to predict the release of radionuclides to the confinement building of the Annular Core Research Reactor. It is found that the shield pool provides overall decontamination factors for particulate of about 2.8 {times} 10{sup 5} and decontamination factors for noble gases of about 2.5--3.7. These results are found to be sensitive to the predicted clad temperature and bubble behavior in the shield pool. Slow revalorization of krypton, xenon and iodine from the shield pool is shown to create a prolonged, low-intensity source term of radioactive material to the confinement atmosphere.

Powers, D.A.

1992-08-01T23:59:59.000Z

373

Nuclear mass inventory, photon dose rate and thermal decay heat of spent research reactor fuel assemblies  

SciTech Connect

As part of the Department of Energy`s spent nuclear fuel acceptance criteria, the mass of uranium and transuranic elements in spent research reactor fuel must be specified. These data are, however, not always known or readily determined. It is the purpose of this report to provide estimates of these data for some of the more common research reactor fuel assembly types. The specific types considered here are MTR, TRIGA and DIDO fuel assemblies. The degree of physical protection given to spent fuel assemblies is largely dependent upon the photon dose rate of the spent fuel material. These data also, are not always known or readily determined. Because of a self-protecting dose rate level of radiation (dose rate greater than 100 ren-x/h at I m in air), it is important to know the dose rate of spent fuel assemblies at all time. Estimates of the photon dose rate for spent MTR, TRIGA and DIDO-type fuel assemblies are given in this report.

Pond, R.B.; Matos, J.E.

1996-05-01T23:59:59.000Z

374

A neutronic feasibility study for LEU conversion of the Brookhaven Medical Research Reactor (BMRR).  

SciTech Connect

A neutronic feasibility study for converting the Brookhaven Medical Research Reactor from HEU to LEU fuel was performed at Argonne National Laboratory in cooperation with Brookhaven National Laboratory. Two possible LEU cores were identified that would provide nearly the same neutron flux and spectrum as the present HEU core at irradiation facilities that are used for Boron Neutron Capture Therapy and for animal research. One core has 17 and the other has 18 LEU MTR-type fuel assemblies with uranium densities of 2.5g U/cm{sup 3} or less in the fuel meat. This LEU fuel is fully-qualified for routine use. Thermal hydraulics and safety analyses need to be performed to complete the feasibility study.

Hanan, N. A.

1998-01-14T23:59:59.000Z

375

Supercritical Water Reactor (SCWR) - Survey of Materials Research and Development Needs to Assess Viability  

SciTech Connect

Supercritical water-cooled reactors (SCWRs) are among the most promising advanced nuclear systems because of their high thermal efficiency [i.e., about 45% vs. 33% of current light water reactors (LWRs)] and considerable plant simplification. SCWRs achieve this with superior thermodynamic conditions (i.e., high operating pressure and temperature), and by reducing the containment volume and eliminating the need for recirculation and jet pumps, pressurizer, steam generators, steam separators and dryers. The reference SCWR design in the U.S. is a direct cycle, thermal spectrum, light-water-cooled and moderated reactor with an operating pressure of 25 MPa and inlet/outlet coolant temperature of 280/500 °C. The inlet flow splits, partly to a down-comer and partly to a plenum at the top of the reactor pressure vessel to flow downward through the core in special water rods to the inlet plenum. This strategy is employed to provide good moderation at the top of the core, where the coolant density is only about 15-20% that of liquid water. The SCWR uses a power conversion cycle similar to that used in supercritical fossil-fired plants: high- intermediate- and low-pressure turbines are employed with one moisture-separator re-heater and up to eight feedwater heaters. The reference power is 3575 MWt, the net electric power is 1600 MWe and the thermal efficiency is 44.8%. The fuel is low-enriched uranium oxide fuel and the plant is designed primarily for base load operation. The purpose of this report is to survey existing materials for fossil, fission and fusion applications and identify the materials research and development needed to establish the SCWR viabilitya with regard to possible materials of construction. The two most significant materials related factors in going from the current LWR designs to the SCWR are the increase in outlet coolant temperature from 300 to 500 °C and the possible compatibility issues associated with the supercritical water environment. • Reactor pressure vessel • Pumps and piping

Philip E. MacDonald

2003-09-01T23:59:59.000Z

376

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

SciTech Connect

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

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

1994-07-01T23:59:59.000Z

377

Jeanne Wright, RN, BSN, MT, CCRP, CIM, RAC, SoCRA Research Analyst Lead, University of Michigan, Michigan Institute for Clinical and Health Research  

E-Print Network (OSTI)

Jeanne Wright, RN, BSN, MT, CCRP, CIM, RAC, SoCRA Research Analyst Lead, University of Michigan&D. CERTIFICATIONS Regulatory Affairs Certification (2012) National Association of IRB Managers (CIM), 2009

Eustice, Ryan

378

Reactor Sharing Program  

Science Conference Proceedings (OSTI)

Progress achieved at the University of Florida Training Reactor (UFTR) facility through the US Department of Energy's University Reactor Sharing Program is reported for the period of 1991--1992.

Vernetson, W.G.

1993-01-01T23:59:59.000Z

379

Department of Energy Awards $3.8 Million in Funding to 38 U.S. Universities for Nuclear Research Infrastructure  

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

WASHINGTON, DC - The U.S. Department of Energy (DOE) today strengthened its commitment to advancing nuclear power by awarding $100,000 to 38 universities to enhance nuclear research and development...

380

Decommissioning of the Austrian 10 MW Research Reactor, Results and Lessons learned Paper  

SciTech Connect

After the decision to shut down the 10 MW ASTRA-MTR Research Reactor was reached in May 1998, the possible options and required phases for decommissioning and removal of the radioactive components were evaluated in a decommissioning study. To support the decisions at each phase, an estimate of the activity inventory in the various parts of the reactor and the waste volume to be expected was performed. Of the possible options an immediate dismantling to phase 1 of IAEA Technical Guide Lines after the immediately following, continued dismantling to phase 2 of these guide lines was identified as the most reasonable and under the auspices optimum choice. The actual decommissioning work on the ASTRA-Reactor began in January 2000 after its final shutdown on July 31, 1999. Preliminary evaluations of the activity inventory gave an estimated amount of 320 kg of intermediate level waste, of about 60 metric tons of contaminated and another 100 metric tons of activated low level radioactive waste. The activities were roughly estimated to be at 200 TBq in the intermediate level and 6 GBq in the low level. The structure of the decommissioning process was decided against cost-, time- and risk-optimization following the basic layout of the main tasks, e.g. the removing of the fuel, the recovering and the treatment of the intermediate level activities in the vicinity of the core, the handling and conditioning of the neutron exposed graphite and the Beryllium-elements. As an example, the dismantling of approx. 1400 metric tons of the biological shield is described in more detail from the determination of the dismantling technique to the clearing procedures and the deposition. The process of dismantling of the biological shield is presented in fast motion. The dismantling of the pump-room installations of the primary loop, the processing of the contaminated or activated metals, the dismantling of the ventilation system and the radiological clearance of the reactor building was done under optimized conditions and is explained in the following. Spent fuel was generally delivered to the US Department of Energy - DOE in several shipments over the operational time of the ASTRA reactor. With the last shipment in May 2001 all the remaining spent fuel elements out of the ASTRA reactor consignment were transferred to DOE. To reduce waste from concrete shielding, German regulations Dt.StrSchV, annex IV, table 1, two clearance values referring to 'clearance restricted for permanent deposit' and to a clearance for unrestricted re-use were used. In order to reduce the amount of an estimated 60 tons of slightly contaminated metals, it was determined that introducing re-melting procedures were the most economical way. To obtain radiological clearance of the reactor building, compliance with the release limits according to Austrian Radiation Protection Ordinance had to be proved to the regulatory body. There, in general, the limits for unrestricted release were defined as a maximum dose rate of 10 {mu}Sv effective for an individual person per year. The results of the regular yearly medical examinations of the staff indicated no influence of the work related to decommissioning. The readings of the personal dosimeters over the entire project amounted to a total of 85.6 mSv, averaging to 1.07 mSv per year and person. After finishing the decommissioning process, the material balance showed 89.6 % for unrestricted reuse, 6.6 % for conventional mass-dumping and 3.8 % of ILW and LLW. The project was covered by an extensive documentation. All operations within NES followed ISO 9000 quality insurance standards. Experiences and knowledge were presented to and shared with the community, e.g. AFR and IAEA throughout the project. (authors)

Hillebrand, G.; Meyer, F. [Nuclear Engineering Seibersdorf GmbH (NES), Seibersdorf, Austria, Europe (Austria)

2008-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "university research reactor" 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

EA-0921; Environmental Assessment and FONSI Ambulatory Research and Education Center, Oregon Health Sciences University  

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

21; Environmental Assessment and FONSI Ambulatory Research 21; Environmental Assessment and FONSI Ambulatory Research and Education Center, Oregon Health Sciences University TABLE OF CONTENTS 1.0 DOCUMENT SUMMARY 2.0 PURPOSE AND NEED 3.0 DESCRIPTION OF ALTERNATIVES INCLUDING THE PROPOSED ACTION 3.1 Proposed Action 3.2 Project Description 3.2.1 Construction Activities 3.2.2 Operations Activities 3.3 No Action Alternative 3.4 Site Alternatives 4.0 AFFECTED ENVIRONMENT 5.0 ENVIRONMENTAL IMPACTS 5.1 Construction 5.1.1 Sensitive Resources 5.1.1.1 Historic/Archeological Resources 5.1.1.2 Federal/State-Listed or Proposed Protected Species or Critical Habitats 5.1.1.3 Flood Plains/Wetlands 5.1.1.4 National Forest, Parks, Trails, etc. 5.1.1.5 Prime Farmland 5.1.1.6 Special Sources of Water

382

UNIVERSITY RESEARCH PROGRAM IN ROBOTICS, Final Technical Annual Report, Project Period: 9/1/04 - 8/31/05  

Science Conference Proceedings (OSTI)

The University Research Program in Robotics (URPR) Implementation Plan is an integrated group of universities performing fundamental research that addresses broad-based robotics and automation needs of the NNSA Directed Stockpile Work (DSW) and Campaigns. The URPR mission is to provide improved capabilities of robotics science and engineering to meet the future needs of all weapon systems and other associated NNSA/DOE activities.

James S. Tulenko; Carl D. Crane III

2006-02-15T23:59:59.000Z

383

Record of Decision for the Final EIS on Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel  

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

5091 5091 Friday May 17, 1996 Part IV Department of Energy Record of Decision for the Final Environmental Impact Statement on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel; Notice 25092 Federal Register / Vol. 61, No. 97 / Friday, May 17, 1996 / Notices DEPARTMENT OF ENERGY Record of Decision for the Final Environmental Impact Statement on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel AGENCY: Department of Energy. ACTION: Record of decision. SUMMARY: DOE, in consultation with the Department of State, has decided to implement a new foreign research reactor spent fuel acceptance policy as specified in the Preferred Alternative contained in the Final Environmental Impact Statement on a Proposed

384

N-Reactor Department Research and Development budget for FY 1966 and revision of budget for FY 1965  

SciTech Connect

The N-Reactor Department Research and Development Program for FY 1965, 1966, and later years is structured to achieve the following general goals. (1) Assurance of a high level of nuclear safety; (2) Assurance of achieving full plant life; (3) Reduction in operating costs for a given production rate; (4) Increase in production rate without proportionate increase in operating costs; (5) Savings in capital outlays necessary to achieve stated reductions in operating cost or increases in production; (6) Production of new products of value; (7) Savings in capital outlays or operating costs to achieve a given level of plant safety. The program is divided into three general categories; Reactor, Metallurgy, and Co-Product. The Reactor category is further divided into physics studies, thermal hydraulics studies, zircaloy process tube development, control, instrument and system analyses, chemistry, engineering research and development, gas, atmosphere studies, graphite studies, and nuclear safety research.

1964-03-25T23:59:59.000Z

385

A neutronic feasibility study for LEU conversion of the WWR-SM research reactor in Uzbekistan.  

SciTech Connect

The WWR-SM research reactor in Uzbekistan has operated at 10 MW since 1979, using Russian-supplied IRT-3M fuel assemblies containing 90% enriched uranium. Burnup tests of three full-sized IRT-3M FA with 36% enrichment were successfully completed to a burn up of about {approximately}50% in 1987-1989. In August 1998, four IRT-3M FA with 36% enriched uranium were loaded into the core to initiate conversion of the entire core to 36% enriched fuel. This paper presents the results of equilibrium fuel cycle comparisons of the reactor using HEU (90%) and HEU (36%) IRT-3M fuel and compares results with the performance of IRT-4M FA containing LEU (19.75%). The results show that an LEU (19.75%) density of 3.8 g/cm{sup 3} is required to match the cycle length of the HEU (90%) core and an LEU density 3.9 g/cm{sup 3} is needed to match the cycle length of the HEU (36%) core.

Rakhmanov, A.

1998-10-19T23:59:59.000Z

386

A neutronic feasibility study for LEU conversion of the IR-8 research reactor.  

SciTech Connect

Equilibrium fuel cycle comparisons for the IR-8 research reactor were made for HEU(90%), HEU(36%), and LEU (19.75%) fuel assembly (FA) designs using three dimensional multi-group diffusion theory models benchmarked to detailed Monte Carlo models of the reactor. Comparisons were made of changes in reactivity, cycle length, average {sup 235}U discharge burnup, thermal neutron flux, and control rod worths for the 90% and 36% enriched IRT-3M fuel assembly and the 19.75% enriched IRT-4M fuel assembly with the same fuel management strategy. The results of these comparisons showed that a uranium density of 3.5 g/cm{sup 3} in the fuel meat would be required in the LEU IRT-4M fuel assembly to match the cycle length of the HEU(90%) IRT-3M FA and an LEU density of 3.7 g/cm{sup 3} is needed to match the cycle length of the HEU(36%) IRT-3M FA.

Deen, J. R.

1998-10-22T23:59:59.000Z

387

DOE/EA-1622: Final Environmental Assessment for University of Nevada, Las Vegas Research Foundation Solar Technology Center (January 2009)  

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

University of Nevada, Las Vegas University of Nevada, Las Vegas Research Foundation SOLAR TECHNOLOGY CENTER January 2009 Final Environmental Assessment and Finding of No Significant Impact DOE/EA-1622 U.S. Department of Energy Golden Field Office National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401 This Environmental Assessment was prepared on behalf of the U.S. Department of Energy by the University of Nevada, Las Vegas Research Foundation with contractual assistance from Ninyo & Moore, Inc. and MBP Consulting, LLC. Finding of No Significant Impact Solar Technology Center January 2009 Finding of No Significant Impact Solar Technology Center January 2009 Finding of No Significant Impact Solar Technology Center

388

Progressive Application Decommissioning Models for U.S. Power and Research Reactors  

SciTech Connect

This paper presents progressive engineering techniques and experiences in decommissioning projects performed by Bums and Roe Enterprises within the last fifteen years. Specifically, engineering decommissioning technical methods and lessons learned are discussed related to the Trojan Large Component Removal Project, San Onofre Nuclear Generating Station (SONGS) Decommissioning Project and the Brookhaven Graphite Research Reactor (BGRR) Decommissioning Project Study. The 25 years since the 1979 TMI accident and the events following 9/11 have driven the nuclear industry away from excessive, closed/elitist conservative methods towards more pragmatic results-oriented and open processes. This includes the essential recognition that codes, standards and regulatory procedures must be efficient, effective and fit for purpose. Financial and open-interactive stakeholder pressures also force adherence to aggressive risk reduction posture in the area of a safety, security and operations. The engineering methods and techniques applied to each project presented unique technical solutions. The decommissioning design for each project had to adopt existing design rules applicable to construction of new nuclear power plants and systems. It was found that the existing ASME, NRC, and DOE codes and regulations for deconstruction were, at best, limited or extremely conservative in their applicability to decommissioning. This paper also suggests some practical modification to design code rules in application for decommissioning and deconstruction. The representative decommissioning projects, Trojan, SONGS and Brookhaven, are discussed separately and the uniqueness of each project, in terms of engineering processes and individual deconstruction steps, is discussed. Trojan Decommissioning. The project included removal of entire NSSS system. The engineering complexity was mainly related to the 1200 MW Reactor. The approach, process of removal, engineering method related to protect the worker against excessive radiation exposure, transportation, and satisfying applicable rules and regulations, were the major problems to overcome. The project's successful completed earned a patent award. SONGS Decommissioning. The reactor's spherical containment and weakened integrity was the scope of this decommissioning effort. The aspects of structure stability and method of deconstruction is the major part of the presentation. The economical process of deconstruction, aspects of structural stability, worker safety, and the protection of the surrounding environment from contamination is highlighted in this section. BGRR Decommissioning Study. BREI was commissioned by Brookhaven National Laboratory (BNL) to evaluate and analyze the stability, and progressive decommissioning, and removal of BGRR components. This analysis took the form of several detailed decommissioning studies that range from disassembly and removal of the unit's graphite pile to the complete environmental restoration of the reactor site. While most of the facility's decommissioning effort is conventional, the graphite pile and its biological shield present the greatest challenge. The studies develop a unique method of removing high-activity waste trapped in the graphite joints. (authors)

Studnicka, Z.; Lacy, N.H.; Nicholas, R.G.; Campagna, M.; Morgan, R.D. [Bums and Roe Enterprises, Inc., 800 Kinderkamack Road, Oradell, NJ 07649 (United States); Sawruk, W. [ABS Consulting, Inc., 5 Birdsong Court, Shillington, PA 19607 (United States)

2006-07-01T23:59:59.000Z

389

Fuel development activities of the US RERTR Program. [Reduced Enrichment Research and Test Reactor  

SciTech Connect

Progress in the development and irradiation testing of high-density fuels for use with low-enriched uranium in research and test reactors is reported. Swelling and blister-threshold temperature data obtained from the examination of miniature fuel plates containing UAl/sub x/, U/sub 3/O/sub 8/, U/sub 3/Si/sub 2/, or U/sub 3/Si dispersed in an aluminum matrix are presented. Combined with the results of metallurgical examinations, these data show that these four fuel types will perform adequately to full burnup of the /sup 235/U contained in the low-enriched fuel. The exothermic reaction of the uranium-silicide fuels with aluminum has been found to occur at about the same temperature as the melting of the aluminum matrix and cladding and to be essentially quenched by the melting endotherm. A new series of miniature fuel plate irradiations is also discussed.

Snelgrove, J.L.; Domagala, R.F.; Wiencek, T.C.; Copeland, G.L.

1983-01-01T23:59:59.000Z

390

Transient analyses and thermal-hydraulic safety margins for the Greek Research Reactor (GRRI)  

Science Conference Proceedings (OSTI)

Various core configurations for the Greek research reactor (GRR1) have been considered in assessing the safety issues of adding a beryllium reflector to the existing water reflected HEU core and the transition from HEU to an all LEU core. The assessment has included both steady-state and transient analyses of safety margins and limits. A small all fresh Be reflected HEU core with a rather large nuclear peaking factor can still be operated safely, and thus adding a Be reflector to the larger depleted HEU core should not pose a problem. The transition mixed core with 50% LEU elements has larger void and Doppler coefficients than the HEU reference core and gives a lower peak clad temperature under transient conditions. The transition cores should give ever increasing margins to plate melting and fission product release as LEU elements are added to the core.

Woodruff, W.L.; Deen, J.R. [Argonne National Lab., IL (United States); Papastergiou, C. [National Centre for Scientific Research Demokritos, Athens (Greece)

1995-02-01T23:59:59.000Z

391

Reactor pressure vessel integrity research at the Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only key safety-related component of the plant for which a duplicate or redundant backup system does not exist. It is therefore imperative to understand and be able to predict the integrity inherent in the RPV. For this reason, the U.S. Nuclear Regulatory Commission has established the related research programs at ORNL described herein to provide for the development and confirmation of the methods used for: (1) establishing the irradiation exposure conditions within the RPV in the Embrittlement Data Base and Dosimetry Evaluation Program, (2) assessing the effects of irradiation on the RPV materials in the Heavy-Section Steel Irradiation Program, and (3) developing overall structural and fracture analyses of RPVs in the Heavy-Section Steel Technology Program.

Corwin, W.R.; Pennell, W.E.; Pace, J.V.

1995-12-31T23:59:59.000Z

392

Neutronic safety and transient analyses for potential LEU conversion of the IR-8 research reactor.  

SciTech Connect

Kinetic parameters, isothermal reactivity feedback coefficients and three transients for the IR-8 research reactor cores loaded with either HEU(90%), HEU(36%), or LEU (19.75%) fuel assemblies (FA) were calculated using three dimensional diffusion theory flux solutions, RELAP5/MOD3.2 and PARET. The prompt neutron generation time and effective delayed neutron fractions were calculated for fresh and beginning-of-equilibrium-cycle cores. Isothermal reactivity feedback coefficients were calculated for changes in coolant density, coolant temperature and fuel temperature in fresh and equilibrium cores. These kinetic parameters and reactivity coefficients were used in transient analysis models to predict power histories, and peak fuel, clad and coolant temperatures. The transients modeled were a rapid and slow loss-of-flow, a slow reactivity insertion, and a fast reactivity insertion.

Deen, J. R.; Hanan, N. A.; Smith, R. S.; Matos, J. E.; Egorenkov, P. M.; Nasonov, V. A.

1999-09-27T23:59:59.000Z

393

Preliminary neutronics calculations for conversion of the Tehran research reactor core from HEU to LEU fuel  

SciTech Connect

The 5-MW highly enriched uranium (HEU)-fueled Tehran Research Reactor is considered for conversion to high-density, low-enriched uranium (LEU) fuel. A preliminary neutronics calculation is performed as part of the conversion goal. In this study, two cores are considered: the HEU reference core and a proposed LEU core similar to the reference core, and a proposed LEU core similar to the reference core, using standardized U[sub 3]Si[sub 2] plates with the option of different [sup 235]U loadings. Various possibilities are investigated for the conversion of HEU to LEU fuel elements with 20% enriched [sup 235]U loadings of 207 to 297 g [sup 235]U/element. For the same equilibrium cycle length, the fuels are compared for flux, power distribution, burnup, and reactivity.

Nejat, S.M.R. (McMaster Univ., Hamilton, Ontario (Canada). Dept. of Engineering Physics.)

1993-08-01T23:59:59.000Z

394

Characterization of wastes in and around early reactors at the Hanford Site: The use of historical research  

SciTech Connect

This paper will present the waste characterization knowledge that has been gained in the first, ``Large-Scale Remediation Study`` to be performed on the reactor areas (100 Areas) of the Hanford Site. Undertaken throughout the past year, this research project has identified thousands of pieces of buried hardware, as well as the volumes of liquid wastes in burial sites in the reactor areas. The author of this landmark study, Dr. Michele Gerber, will discuss historical research as a safe and cost-effective characterization tool.

Gerber, M.S.

1993-10-01T23:59:59.000Z

395

Very High Temperature Reactor (VHTR) Survey of Materials Research and Development Needs to Support Early Deployment  

DOE Green Energy (OSTI)

The VHTR reference concept is a helium-cooled, graphite moderated, thermal neutron spectrum reactor with an outlet temperature of 1000 C or higher. It is expected that the VHTR will be purchased in the future as either an electricity producing plant with a direct cycle gas turbine or a hydrogen producing (or other process heat application) plant. The process heat version of the VHTR will require that an intermediate heat exchanger (IHX) and primary gas circulator be located in an adjoining power conversion vessel. A third VHTR mission - actinide burning - can be accomplished with either the hydrogen-production or gas turbine designs. The first ''demonstration'' VHTR will produce both electricity and hydrogen using the IHX to transfer the heat to either a hydrogen production plant or the gas turbine. The plant size, reactor thermal power, and core configuration will be designed to assure passive decay heat removal without fuel damage during accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. The purpose of this report is to identify the materials research and development needs for the VHTR. To do this, we focused on the plant design described in Section 2, which is similar to the GT-MHR plant design (850 C core outlet temperature). For system or component designs that present significant material challenges (or far greater expense) there may be some viable design alternatives or options that can reduce development needs or allow use of available (cheaper) materials. Nevertheless, we were not able to assess those alternatives in the time allotted for this report and, to move forward with this material research and development assessment, the authors of this report felt that it was necessary to use a GT-MHR type design as the baseline design.

Eric Shaber; G. Baccaglini; S. Ball; T. Burchell; B. Corwin; T. Fewell; M. Labar; P. MacDonald; P. Rittenhouse; Russ Vollam; F. Southworth

2003-01-01T23:59:59.000Z

396

Directory of Federal Agencies and University Research Centers conducting R&D in Environmental and Waste Management  

Science Conference Proceedings (OSTI)

In October 1990 PAR Enterprises, Incorporated was awarded a contract by the Department of Energy to conduct a survey and prepare a Directory of Federal Agencies and University Research Centers involved in environmental restoration and waste management research and development. To conduct the survey and organize the Directory, data from 50 Federal agencies and 100 universities was collected, evaluated and summarized. The purpose of the survey and Directory is to describe the activities and provide a reference base of Federal Agencies and University Research Cantors involved in environmental restoration and waste management research and development. The Directory contains (1) the Foreword, (2) an Introduction, (3) a Description of the Survey Organization and Research Approach, (4) the EM/OTD Key Word Networks, (5) a series of matrices that show the relationship between the OTD technical requirements and the Federal Agency/University EM capabilities, (6) the Federal Agency and University Research Center EM R&D Capabilities Profiles, (7) a Glossary, and (8) an Appendix that describes the EM activities of the DOE National Laboratories and related research facilities. The survey and Directory was prepared for the Office of Technology Development (OTD), a major R&D component of DOE`s Office of Environmental Restoration and Waste Management.

Not Available

1991-12-01T23:59:59.000Z

397

C-1 coproduct development for N Reactor: Excerpts from N-Reactor Department research and development budget for FY-1967 and revision of budget for FY-1966  

SciTech Connect

This report discusses the production of weapon grade plutonium and tritium as an economically attractive mode of operation for N-Reactor. With the successful completion of the proposed research and development program coproduct production in N-Reactor could begin in January 1967. Approximately 5 kg of tritium could be produced at a reduction in unit total cost of up to $7 per gram equivalent when compared to other modes of operation of N-Reactor that yield only-weapon grade plutonium. Achieving this production level and unit cost requires a fuel and target design that will subject the materials to more severe temperature and exposure conditions than for the tube-in-tube design. Analyses of existing knowledge and experimental results obtained to date are very encouraging. However, there is a continuing need for additional experimental verification of the limiting conditions for both fuel and target to permit the specification of a production fuel and target design. The incremental cost of this program is estimated to be $1,055 million in FY-1965, $0.796 million in FY-1966 and $0.450 million in FY-1967 for a total of $2.3 million. The principal benefits to be derived from this expenditure of research and development funds are lower unit grade plutonium. When the reactor reaches equilibrium operation as a costs for both tritium and weapon dual-purpose reactor producing process steam for credit, it will be a highly competitive producer of plutonium and tritium in the AEC complex.

1965-04-19T23:59:59.000Z

398

Energy Research at UC Santa Barbara Energy is one of the most important challenges of the century. Energy research at the University of  

E-Print Network (OSTI)

Energy Research at UC Santa Barbara Energy is one of the most important challenges of the century. Energy research at the University of California Santa Barbara (UC Santa Barbara) is largely focused on developing new technologies that increase energy efficiency, thereby reducing energy consumption. UC Santa

Akhmedov, Azer

399

Manhattan Project: Production Reactor (Pile) Design, Met Lab, 1942  

Office of Scientific and Technical Information (OSTI)

Schematic of the X-10 Graphite Reactor, Oak Ridge PRODUCTION REACTOR (PILE) DESIGN Schematic of the X-10 Graphite Reactor, Oak Ridge PRODUCTION REACTOR (PILE) DESIGN (Met Lab, 1942) Events > The Plutonium Path to the Bomb, 1942-1944 Production Reactor (Pile) Design, 1942 DuPont and Hanford, 1942 CP-1 Goes Critical, December 2, 1942 Seaborg and Plutonium Chemistry, 1942-1944 Final Reactor Design and X-10, 1942-1943 Hanford Becomes Operational, 1943-1944 By 1942, scientists had established that some of the uranium exposed to radioactivity in a reactor (pile) would eventually decay into plutonium, which could then be separated by chemical means from the uranium. Important theoretical research on this was ongoing, but the work was scattered at various universities from coast to coast. In early 1942, Arthur Compton arranged for all pile research to be moved to the Met Lab at the University of Chicago.

400

THE ENERGY CAMPUS The University of Houston is developing the Energy Research Park (ERP) on 74 acres adjacent to  

E-Print Network (OSTI)

THE ENERGY CAMPUS The University of Houston is developing the Energy Research Park (ERP) on 74 acres adjacent to I-45 as a unique campus dedicated to energy research and education. Public partnerships on one site. ENERGY TO MARKET The park's first corporate partner, SuperPower Inc., is working

Bittner, Eric R.

Note: This page contains sample records for the topic "university research reactor" 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

University Center of Excellence for Photovoltaics Research and Education: Annual report  

DOE Green Energy (OSTI)

This is a second annual report since the University Center of Excellence for Photovoltaics Research and Education was established at Georgia Tech. The major focus of the center is crystalline silicon, and the mission of the Center is to improve the fundamental understanding of the science and technology of advanced photovoltaic devices and materials, to fabricate high-efficiency cells, and develop low-cost processes, to provide training and enrich the equational experience of students in this field, and to increase US competitiveness by providing guidelines to industry and DOE to achieve cost-effective and high-efficiency photovoltaic devices. This report outlines the work of the Center from July 1993--June 1994.

Rohatgi, A.; Crotty, G.; Cai, L.; Sana, P.; Doolittle, A.; Ropp, M.; Krygowski, T.; Narasimha, S. [Georgia Inst. of Tech., Atlanta, GA (United States). School of Electrical and Computer Engineering

1995-09-01T23:59:59.000Z

402

An Overview of Recent Logging Research at The University of Texas Petroleum Engineering Department  

SciTech Connect

Logging research at The University of Texas has been carried out in several areas. We have studied how rock resistivity varies with water saturation when other variables, such as rock wettability, stress, saturation history, and shale content are varied. Both experimental and theoretical work have been done. Rock wettability (oil or water wet) has by far the largest effect. Shale content and saturation history are also important. Rock stress is the least important, at least in the Berea sandstones and glass bed packs we have studied. We have published several papers and theses which describe this work in detail. We have also studied the effect of certain trace elements (boron, mainly) on the neutron log. Boron has a very high thermal neutron capture cross Section. Analyses of a number of Frio formation cores from the Texas Gulf Coast area show that boron occurs frequently in these rocks in amounts (up to 100 ppm or more) that would seriously affect several procedures in neutron log interpretation. It could, for example, reduce or even eliminate the neutron log--density log porosity reversal that is commonly used as a gas indicator. A recent paper reports details of our work in the Frio. We are currently extending our trace element studies to the West Texas area. The lower porosities occurring there make a given boron content in the rock even more important than in the higher porosity Gulf Coast area. Another effort has been the application of logging data to obtain better estimates of rock type, and inferentially, rock permeability. The work is semi-empirical, and results are usually limited in application geographically. These results can be very important, however; for example, when extrapolating core data to parts of a field where no cores were taken. Several papers have reported details of this work, which is continuing. Finally, we have advised the Department of Energy on logging programs and problems in the Geothermal-Geopressured research effort. In the early phases of the work we studied why water resistivities calculated from the self potential log were so often wrong. and showed that most of the error came from use of incorrect mud filtrate resistivities in the calculation. Several papers and theses give details of this research. A recent problem has been the estimation of free gas saturation in a deep, thick, geopressured sand in the Hulin Well in South Louisiana. A pulsed neutron log run recently in this well supports free gas indications from open hole resistivity logs run in this well earlier by Superior Oil Company. The presence of free gas here is important, since the gas/water ratio from this zone will be much larger if free gas is present. Future logging research under consideration or being started at The University of Texas includes (1) petrophysical problems in tight gas sands (bimodal porosity systems, trace element effects, etc.), (2) resistivity versus water saturation relations at high desaturation pressures (1500 psi), and (3) improved theoretical and computer modeling of rock resistivity as affected by water saturation, rock wettability, saturation history, etc. Support of logging research at The University of Texas is currently from the Department of Energy and from a consortium of companies and organizations (Gas Research Institute, logging companies, and oil companies).

Dunlap, H.F.

1989-03-21T23:59:59.000Z

403

Status report on the Small Secure Transportable Autonomous Reactor (SSTAR) /Lead-cooled Fast Reactor (LFR) and supporting research and development.  

SciTech Connect

This report provides an update on development of a pre-conceptual design for the Small Secure Transportable Autonomous Reactor (SSTAR) Lead-Cooled Fast Reactor (LFR) plant concept and supporting research and development activities. SSTAR is a small, 20 MWe (45 MWt), natural circulation, fast reactor plant for international deployment concept incorporating proliferation resistance for deployment in non-fuel cycle states and developing nations, fissile self-sufficiency for efficient utilization of uranium resources, autonomous load following making it suitable for small or immature grid applications, and a high degree of passive safety further supporting deployment in developing nations. In FY 2006, improvements have been made at ANL to the pre-conceptual design of both the reactor system and the energy converter which incorporates a supercritical carbon dioxide Brayton cycle providing higher plant efficiency (44 %) and improved economic competitiveness. The supercritical CO2 Brayton cycle technology is also applicable to Sodium-Cooled Fast Reactors providing the same benefits. One key accomplishment has been the development of a control strategy for automatic control of the supercritical CO2 Brayton cycle in principle enabling autonomous load following over the full power range between nominal and essentially zero power. Under autonomous load following operation, the reactor core power adjusts itself to equal the heat removal from the reactor system to the power converter through the large reactivity feedback of the fast spectrum core without the need for motion of control rods, while the automatic control of the power converter matches the heat removal from the reactor to the grid load. The report includes early calculations for an international benchmarking problem for a LBE-cooled, nitride-fueled fast reactor core organized by the IAEA as part of a Coordinated Research Project on Small Reactors without Onsite Refueling; the calculations use the same neutronics computer codes and methodologies applied to SSTAR. Another section of the report details the SSTAR safety design approach which is based upon defense-in-depth providing multiple levels of protection against the release of radioactive materials and how the inherent safety features of the lead coolant, nitride fuel, fast neutron spectrum core, pool vessel configuration, natural circulation, and containment meet or exceed the requirements for each level of protection. The report also includes recent results of a systematic analysis by LANL of data on corrosion of candidate cladding and structural material alloys of interest to SSTAR by LBE and Pb coolants; the data were taken from a new database on corrosion by liquid metal coolants created at LANL. The analysis methodology that considers penetration of an oxidation front into the alloy and dissolution of the trailing edge of the oxide into the coolant enables the long-term corrosion rate to be extracted from shorter-term corrosion data thereby enabling an evaluation of alloy performance over long core lifetimes (e.g., 30 years) that has heretofore not been possible. A number of candidate alloy specimens with special treatments or coatings which might enhance corrosion resistance at the temperatures at which SSTAR would operate were analyzed following testing in the DELTA loop at LANL including steels that were treated by laser peening at LLNL; laser peening is an approach that alters the oxide-metal bonds which could potentially improve corrosion resistance. LLNL is also carrying out Multi-Scale Modeling of the Fe-Cr system with the goal of assisting in the development of cladding and structural materials having greater resistance to irradiation.

Sienicki, J. J.; Moisseytsev, A.; Yang, W. S.; Wade, D. C.; Nikiforova, A.; Hanania, P.; Ryu, H. J.; Kulesza, K. P.; Kim, S. J.; Halsey, W. G.; Smith, C. F.; Brown, N. W.; Greenspan, E.; de Caro, M.; Li, N.; Hosemann, P.; Zhang, J.; Yu, H.; Nuclear Engineering Division; LLNL; LANL; Massachusetts Inst. of Tech.; Ecole des Mines de Paris; Oregon State Univ.; Univ.of California at Berkley

2008-06-23T23:59:59.000Z

404

Awareness, Preference, Utilization, and Messaging Research for the Spallation Neutron Source and High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

Oak Ridge National Laboratory (ORNL) offers the scientific community unique access to two types of world-class neutron sources at a single site - the Spallation Neutron Source (SNS) and the High Flux Isotope Reactor (HFIR). The 85-MW HFIR provides one of the highest steady-state neutron fluxes of any research reactor in the world, and the SNS is one of the world's most intense pulsed neutron beams. Management of these two resources is the responsibility of the Neutron Sciences Directorate (NScD). NScD commissioned this survey research to develop baseline information regarding awareness of and perceptions about neutron science. Specific areas of investigative interest include the following: (1) awareness levels among those in the scientific community about the two neutron sources that ORNL offers; (2) the level of understanding members of various scientific communities have regarding benefits that neutron scattering techniques offer; and (3) any perceptions that negatively impact utilization of the facilities. NScD leadership identified users of two light sources in North America - the Advanced Photon Source (APS) at Argonne National Laboratory and the National Synchrotron Light Source (NSLS) at Brookhaven National Laboratory - as key publics. Given the type of research in which these scientists engage, they would quite likely benefit from including the neutron techniques available at SNS and HFIR among their scientific investigation tools. The objective of the survey of users of APS, NSLS, SNS, and HFIR was to explore awareness of and perceptions regarding SNS and HFIR among those in selected scientific communities. Perceptions of SNS and FHIR will provide a foundation for strategic communication plan development and for developing key educational messages. The survey was conducted in two phases. The first phase included qualitative methods of (1) key stakeholder meetings; (2) online interviews with user administrators of APS and NSLS; and (3) one-on-one interviews and traditional and online focus groups with scientists. The latter include SNS, HFIR, and APS users as well as scientists at ORNL, some of whom had not yet used HFIR and/or SNS. These approaches informed development of the second phase, a quantitative online survey. The survey consisted of 16 questions and 7 demographic categorizations, 9 open-ended queries, and 153 pre-coded variables and took an average time of 18 minutes to complete. The survey was sent to 589 SNS/HFIR users, 1,819 NSLS users, and 2,587 APS users. A total of 899 individuals provided responses for this study: 240 from NSLS; 136 from SNS/HFIR; and 523 from APS. The overall response rate was 18%.

Bryant, Rebecca [Bryant Research, LLC; Kszos, Lynn A [ORNL

2011-03-01T23:59:59.000Z

405

Optimization of irradiation conditions for {sup 177}Lu production at the LVR-15 research reactor  

Science Conference Proceedings (OSTI)

The use of lutetium in medicine has been increasing over the last few years. The {sup 177}Lu radionuclide is commercially available for research and test purposes as a diagnostic and radiotherapy agent in the treatment of several malignant tumours. The yield of {sup 177}Lu from the {sup 176}Lu(n,{gamma}){sup 177}Lu nuclear reaction depends significantly on the thermal neutron fluence rate. The capture cross-sections of both reaction {sup 176}Lu(n,{gamma}){sup 177}Lu and reaction {sup 177}Lu(n,{gamma}){sup 178}Lu are very high. Therefore a burn-up of target and product nuclides should be taken into account when calculating {sup 177}Lu activity. The maximum irradiation time, when the activity of the {sup 177}Lu radionuclide begins to decline, was found for different fluence rates. Two vertical irradiation channels at the LVR-15 nuclear research reactor were compared in order to choose the channel with better irradiation conditions, such as a higher thermal neutron fluence rate in the irradiation volume. In this experiment, lutetium was irradiated in a titanium capsule. The influence of the Ti capsule on the neutron spectrum was monitored using activation detectors. The choice of detectors was based on requirements for irradiation time and accurate determination of thermal neutrons. The following activation detectors were selected for measurement of the neutron spectrum: Ti, Fe, Ni, Co, Ag and W. (authors)

Lahodova, Z.; Viererbl, L.; Klupak, V. [Research Centre Rez Ltd., Husinec-130, Rez 250 67 (Czech Republic); Srank, J. [Nuclear Physics Inst. of the Academy of Sciences, Husinec-130, Rez 250 67 (Czech Republic)

2012-07-01T23:59:59.000Z

406

Comparison of shell-and-tube with frame-and-plate-type heat exchangers for the MIT research reactor upgrade  

SciTech Connect

This paper discusses a comparison of shell-and-tube with frame-and-plate-type heat exchangers for the proposed upgrade of the Massachusetts Institute of Technology research reactor (MITR). The comparison is based on the following considerations: thermal-hydraulic performance, maintenance, personnel dose rate, and pricing.

Ser, Yorick, Hu, Lin-Wen [Massachusetts Institute of Technology, Cambridge, MA (United States)

1997-12-01T23:59:59.000Z

407

Analysis of in-core experiment activities for the MIT Research Reactor using the ORIGEN computer code  

E-Print Network (OSTI)

The objective of this study is to devise a method for utilizing the ORIGEN-S computer code to calculate the activation products generated in in-core experimental assemblies at the MIT Research Reactor (MITR-II). ORIGEN-S ...

Helvenston, Edward M. (Edward March)

2006-01-01T23:59:59.000Z

408

DISPERSIONS OF URANIUM CARBIDES IN ALUMINUM PLATE-TYPE RESEARCH REACTOR FUEL ELEMENTS  

DOE Green Energy (OSTI)

The technical feasibility of employing uranium carbide aluminun dispersions in aluminum-base research reactor fuel elements was investigated This study was motivated by the need to obtain higher uranium loadings in these fuel elements. Although toe MTR-type unit, containing a 13 18 wt% U-Al alloy is a proven reactor component, fabrication problems of considerable magnitude arise when attempts are made to increase the uranium investment in the alloy to more than 25 wt.%. Au approach to these fabrication difficulties is to select a compound with significantly higher density tban UAl/sub 4/ or UAl/sub 3/ compounds of the alloy system which when dispersed in aluminum powder, will reduce the volume occupied by the brittle, fissile phase. The uranium carbides, with densities ranging from 11.68 to 13.63 g/cm/sup 3/), appear to be suited for this application and were selected for development as a fuel material for aluminum-base dispersions. Studies were conducted at 580 to 620 deg C to determine the chemical compatibility of carbides with aluminum in sub-size cold- pressed comparts as well as in full-size fabricated fuel plates. Procedures were also developed to prepare uranium carbides, homogernously disperse the compounds in aluminum, roll clad the dispersions to form composite plates, and braze the plates into fuel assemblies. Corrosion tests of the fuel material were conducted in 20 and 60 deg C water to determine the integrity of the fuel material in the event of sin inadventent cladding failure. In addition, specimens were prepared to evaluate penformance under extensive irradiation Prior to studying the uranium carbide-aluminum system, methods for preparing the carbides were investigated. Are melting uranium and carnon was satisfactory for obtaining small quantities of various carbides. Later, reaction of graphite with UO/sub 2/ was successfully employed in the preparation of large quantities of UC/sub 2/, Studies of the chemical compatibility of cold-pressed compacts containing 50 wt% uranium carbide dispersed in aluminum revealed a marked trend toward stebifity as the carbon content of the uranium carbide increased from 446 to 9.20% C. Severe volume increases occurred in monocarbide dispersions with attendant formation of large quantities of the uranium-allumnim inter-metallic compounds. Dicarbide dispersions, on the other band, exhibited negligible reaction with aluminum after extended periods at 580 and 620 deg C. However, it was demonstrated that hydrogen can promote a reaction in UC/sub 2/-Al compacts. The hydrogen appears to reduce the UC/sub 2/ to UC which can subsequently react with aluminum producing the previously noted deleterious effects. A growth study at 605 deg C of composite fuel plates containing 59 wt.% UC/sub 2/ revealed insignificant changes within processing periods envisioned for fuel element processing. However, plate elongations as high as 2.5% were observed after 100 hr at this temperature. Severe blistering which occurred on fuel plates fabricated in the initial stages of the investigation was attributed to gaseous hydrocarbons, and the condition was ellminated by vacuum degasification of cold-pressed compacts. With the exception of the degasification requirement, procedures for manufacturing UC- bearing fuel elements were identical to those specified for the Geneva Conference Reactor fuel elements. Dispersions of uranium dicarbide corroded catastrophically in 20 and 60 deg C water, thus limiting the application of this material However, spocimens were prepared and insented in the MTR to evaluate the irradiation behavior of this fuel because of its potential application in onganic- cooled reactors. (auth)

Thurber, W.C.; Beaver, R.J.

1959-11-19T23:59:59.000Z

409

81.114- University Reactor Infrastructure and Education Support / Prompt Gamma-ray Activation Analysis of Lithioum Ion Battery Cathodes  

Science Conference Proceedings (OSTI)

This project focuses on the use of the Prompt Gamma-ray Activation Analysis (PGAA) technique available at the Nuclear Engineering Teaching Laboratory of the University of Texas at Austin to precisely determine the hydrogen (proton) contents in layered oxide cathode samples obtained by chemical lithium extraction in order to obtain a better understanding of the factors limiting the practical capacities and overall performance of lithium ion battery cathodes. The project takes careful precautionary experimental measures to avoid proton contamination both from solvents used in chemical delithiation and from ambient moisture. The results obtained from PGAA are complemented by the data obtained from other techniques such as thermogravimetric analysis, redox titration, atomic absorption spectroscopy, X-ray diffraction, and mass spectroscopic analysis of the evolved gas on heating. The research results broaden our understanding of the structure-property-performance relationships of lithium ion battery cathodes and could aid the design and development of new better performing lithium ion batteries for consumer (portable and electric vehicles), military, and space applications.

Manthiram, Arumugam; Landsberger, S.

2006-11-11T23:59:59.000Z

410

License amendment for neutron capture therapy at the MIT research reactor  

SciTech Connect

This paper reports the issuance by the U.S. Nuclear Regulatory Commission (NRC) of a license amendment to the Massachusetts Institute of Technology (MIT) for the use of the MIT Research Reactor's (MITR-II) medical therapy facility beam for the treatment of humans using neutron capture therapy (NCT). This amendment is one of 11 required approvals. The others are those of internal MIT committees, review panels of the Tufts-New England Medical Center (NEMC), which is directing the program jointly with MIT, that of the U.S. Food and Drug Administration, and an NRC amendment to the NEMC hospital license. This amendment is the first of its type to be issued by NRC, and as such it establishes a precedent for the conduct of human therapy using neutron beams. Neutron capture therapy is a bimodal method for treating cancer that entails the administration of a tumor-seeking boronated drug followed by the irradiation of the target organ with neutrons. The latter cause boron nuclei to fission and thereby release densely ionizing helium and lithium nuclei, which destroy cancerous cells while leaving adjacent healthy cells undamaged. Neutron capture therapy is applicable to glioblastoma multiforme (brain tumors) and metastasized melanoma (skin cancer). Both Brookhaven National Laboratory and MIT conducted trials of NCT more than 30 yr ago. These were unsuccessful because the available boron drugs did not concentrate sufficiently in tumor and because the thermal neutron beams that were used did not enable neutrons to travel deep enough into the brain.

Bernard, J.A. (Massachusetts Institute of Technology, Cambride, MA (United States))

1993-01-01T23:59:59.000Z

411

Department of Energy Issues Request for Pre-Applications to U.S. Universities for Nuclear Energy - Related Research and Development Proposals  

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

The U.S. Department of Energy’s Nuclear Energy University Programs (NEUP) is now accepting pre-applications from universities interested in conducting nuclear energy- related research and development (R&D) projects.

412

Department of Energy Issues Call for Proposals to U.S. Universities for Nuclear Energy-Related Integrated Research Project Proposals  

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

The U.S. Department of Energy’s Nuclear Energy University Programs is now accepting applications from universities interested in conducting nuclear energy-related Integrated Research Projects.

413

Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel  

SciTech Connect

This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

1994-10-01T23:59:59.000Z

414

Light Water Reactor Sustainability Research and Development Program Plan -- Fiscal Year 2009–2013  

SciTech Connect

Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60-year operating licenses. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary this year. U.S. regulators have begun considering extended operations of nuclear power plants and the research needed to support long-term operations. The Light Water Reactor Sustainability (LWRS) Research and Development (R&D) Program, developed and sponsored by the Department of Energy, is performed in close collaboration with industry R&D programs. The purpose of the LWRS R&D Program is to provide technical foundations for licensing and managing long-term, safe and economical operation of the current operating nuclear power plants. The LWRS R&D Program vision is captured in the following statements: Existing operating nuclear power plants will continue to safely provide clean and economic electricity well beyond their first license- extension period, significantly contributing to reduction of United States and global carbon emissions, enhancement of national energy security, and protection of the environment. There is a comprehensive technical basis for licensing and managing the long-term, safe, economical operation of nuclear power plants. Sustaining the existing operating U.S. fleet also will improve its international engagement and leadership on nuclear safety and security issues.

Idaho National Laboratory

2009-12-01T23:59:59.000Z

415

Light Water Reactor Sustainability Research and Development Program Plan -- Fiscal Year 2009–201/span>3  

Science Conference Proceedings (OSTI)

Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60-year operating licenses. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary this year. U.S. regulators have begun considering extended operations of nuclear power plants and the research needed to support long-term operations. The Light Water Reactor Sustainability (LWRS) Research and Development (R&D) Program, developed and sponsored by the Department of Energy, is performed in close collaboration with industry R&D programs. The purpose of the LWRS R&D Program is to provide technical foundations for licensing and managing long-term, safe and economical operation of the current operating nuclear power plants. The LWRS R&D Program vision is captured in the following statements: Existing operating nuclear power plants will continue to safely provide clean and economic electricity well beyond their first license- extension period, significantly contributing to reduction of United States and global carbon emissions, enhancement of national energy security, and protection of the environment. There is a comprehensive technical basis for licensing and managing the long-term, safe, economical operation of nuclear power plants. Sustaining the existing operating U.S. fleet also will improve its international engagement and leadership on nuclear safety and security issues.

Idaho National Laboratory

2009-12-01T23:59:59.000Z

417

Support of nuclear engineering education and research at the University of Michigan  

Science Conference Proceedings (OSTI)

This report describes progress on four different projects in the fission reactor area that have been supported by the grant during the past year. These projects are: Accelerator transmutation of nuclear waste (Steve Pearson); neutronic analysis of the Ford Nuclear Reactor (Brent Renkema); developing Monte Carlo benchmarks for commercial LWR configurations (Jie Du); Monte Carlo depletion capability for massively parallel processors (Amit Majumdar); these tasks are briefly described and progress to date is presented.

Martin, W.R.

1993-03-01T23:59:59.000Z

418

A monthly report on transportation research, education, and outreach activities at the University of Minnesota Green freight innovations ...... 2  

E-Print Network (OSTI)

. The second session looked at future approaches for transportation finance: Lee Munnich, director of the StateA monthly report on transportation research, education, and outreach activities at the University 4 CEO continued on page 4 Legislators attend transportation seminars CTS redesigns Web site

Minnesota, University of

419

Fudan University HSK level 6  

E-Print Network (OSTI)

of King Mongkut's University of Technology Thonburi 0 Australian National University Plasma Research

Takada, Shoji

420

EA-0896; Research in Alzheimer's Disease Health Sciences Center - West Virginia University Environmental Assessment and (FONSI) Center For Nuclear Medicine Research In Alzheimer's Disease Health Sciences Center - West Virginia University  

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

6; Research in Alzheimer's Disease Health Sciences Center - West 6; Research in Alzheimer's Disease Health Sciences Center - West Virginia University Environmental Assessment and (FONSI) Center for Nuclear Medicine Research in Alzheimer's Disease Health Sciences Center - West Virginia University TABLE OF CONTENTS 1.0 DOCUMENT SUMMARY 1.1. Description 1.2 Alternatives 1.3 Affected Environment 1.4 Construction Impacts 1.5 Operating Impacts 2.0 PURPOSE AND NEED FOR AGENCY ACTION 3.0 DESCRIPTION OF ALTERNATIVES INCLUDING THE PROPOSED ACTION 3.1 Description of the Proposed Action 3.2.1 Construction Activities 3.2.2 Operation Activities 3.3 The No Action Alternative 3.4 Site Alternatives 4.0 THE AFFECTED ENVIRONMENT 5.0 ENVIRONMENTAL CONSEQUENCES OF THE PROPOSED ACTION AND ALTERNATIVES 5.1 Construction Impacts 5.1.1 Sensitive Resources

Note: This page contains sample records for the topic "university research reactor" from the National Library of EnergyBeta (NLEBeta).
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421

Exploratory Energy Research Program of the University of Hawaii at Manoa. Quarterly progress report  

DOE Green Energy (OSTI)

Project objectives and research progress are briefly summarized for solar energy, biomass, hydrogen, and geothermal energy research projects.

Not Available

1984-01-02T23:59:59.000Z

422

Light Water Reactor Sustainability (LWRS) Program | Department of Energy  

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

Light Water Reactor Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program The Light Water Reactor Sustainability (LWRS) Program is developing the scientific basis to extend existing nuclear power plant operating life beyond the current 60-year licensing period and ensure long-term reliability, productivity, safety, and security. The program is conducted in collaboration with national laboratories, universities, industry, and international partners. Idaho National Laboratory serves as the Technical Integration Office and coordinates the research and development (R&D) projects in the following pathways: Materials Aging and Degradation Assessment, Advanced Instrumentation, Information, and Control Systems

423

Epithermal beam development at the BMRR (Brookhaven Medical Research Reactor): Dosimetric evaluation  

SciTech Connect

The utilization of an epithermal neutron beam for neutron capture therapy (NCT) is desirable because of the increased tissue penetration relative to a thermal neutron beam. Over the past few years, modifications have been and continue to be made at the Brookhaven Medical Research Reactor (BMRR) by changing its filter components to produce an optimal epithermal beam. An optimal epithermal beam should contain a low fast neutron contamination and no thermal neutrons in the incident beam. Recently a new moderator for the epithermal beam has been installed at the epithermal port of the BMRR and has accomplished this task. This new moderator is a combination of alumina (Al{sub 2}O{sub 3}) bricks and aluminum (Al) plates. A 0.51 mm thick cadmium (Cd) sheet has reduced the thermal neutron intensity drastically. Furthermore, an 11.5 cm thick bismuth (Bi) plate installed at the port surface has reduced the gamma dose component to negligible levels. Foil activation techniques have been employed by using bare gold and cadmium-covered gold foil to determine thermal as well as epithermal neutron fluence. Fast neutron fluence has been determined by indium foil counting. Fast neutron and gamma dose in soft tissue, free in air, is being determined by the paired ionization chamber technique, using tissue equivalent (TE) and graphite chambers. Thermoluminescent dosimeters (TLD-700) have also been used to determine the gamma dose independently. This paper describes the methods involved in the measurements of the above mentioned parameters. Formulations have been developed and the various corrections involved have been detailed. 12 refs.

Saraf, S.K.; Fairchild, R.G.; Kalef-Ezra, J.; Laster, B.H.; Fiarman, S.; Ramsey, E. (Brookhaven National Lab., Upton, NY (USA); Ioannina Univ. (Greece); Brookhaven National Lab., Upton, NY (USA); State Univ. of New York, Stony Brook, NY (USA). Health Science Center)

1989-08-24T23:59:59.000Z

424

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

SciTech Connect

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

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

2012-09-30T23:59:59.000Z

425

Novel, Magnetically Fluidized-Bed Reactor Development for the Looping Process: Coal to Hydrogen Production Research and Development  

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

Novel, Magnetically Fluidized-Bed Novel, Magnetically Fluidized-Bed Reactor Development for the Looping Process: Coal to Hydrogen Production Research and Development Background The U.S. Department of Energy (DOE) National Energy Technology Laboratory (NETL) is committed to improving methods for co-producing power and chemicals, fuels, and hydrogen (H2). Gasification is a process by which fuels such as coal can be used to produce synthesis gas (syngas), a mixture of H2, carbon monoxide (CO), and carbon

426

Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior  

SciTech Connect

This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting.

Monteleone, S. [comp.

1995-04-01T23:59:59.000Z

427

Conceptual Design of Molten Salt Loop Experiment for MIT Research Reactor  

E-Print Network (OSTI)

Molten salt is a promising coolant candidate for Advanced High Temperature Reactor (AHTR) Gen-IV designs. The low neutron absorption, high thermal capacity, chemical inertness, and high boiling point at low pressure of ...

Bean, Malcolm K.

2011-08-01T23:59:59.000Z

428

Applied research at Coventry University Issue 8 Autumn 2010 Creating a digital  

E-Print Network (OSTI)

reduce their energy consumption 24 street talk Using a range of feedback devices to improve the use of public spaces 26 bUsIness braIns how the University has helped with a strategic analysis of one communities Managing editor Karen Smith, Deputy Director of Marketing for Coventry University edited

Low, Robert

429

Comparison of independent research of China's top universities using bibliometric indicators  

Science Conference Proceedings (OSTI)

The institutionally independent publications of Tsinghua University and Peking University were compared by two main indicators namely peak-year citations per publication and h-index, based on the data extracted from the Science Citation Index ... Keywords: Peak-year citations per publication, Science indicators, Scientometrics, Web of science, h-Index

Hui-Zhen Fu; Yuh-Shan Ho

2013-07-01T23:59:59.000Z

430

Nuclear physics research at the University of Richmond. Progress report, November 1, 1994--October 31, 1995  

SciTech Connect

Summarized in this report is the progress achieved during the period from November 1, 1994 to October 31, 1995. The experimental work described in this report is in electromagnetic and heavy-ion nuclear physics. The effort in electromagnetic nuclear physics is in preparation for the research program at the Continuous Electron Beam Accelerator Facility (CEBAF) and is focused on the construction and use of the CEBAF Large Acceptance Spectrometer (CLAS). The heavy-ion experiments were performed at the Argonne National Laboratory ATLAS facility and SUNY, Stony Brook. The physics interests driving these efforts at CEBAF are in the study of the structure, interactions, and nuclear-medium modifications of mesons and baryons. This year, an extension of the experiment to measure the magnetic form factor of the neutron was approved by the CEBAF Program Advisory Committee Nine (PAC9) for beam at 6 GeV. The authors also submitted updates to PAC9 on the experiments to measure inclusive {eta} photoproduction in nuclei and electroproduction of the {Lambda}, {Lambda}*(1520), and f{sub 0}(975). In addition to these experiments, the authors collaborated on a proposal to measure rare radiative decays of the {phi} meson which was also approved by PAC9. Their contributions to the construction of the CLAS include the development of the drift-chamber gas system, drift-chamber software, and controls software. Major has been leading the effort in the construction of the gas system. In the last year, the Hall B gas shed was constructed and the installation of the gas system components built at the University of Richmond has begun. Over the last six years, the efforts in low-energy heavy-ion physics have decreased due to the change in focus to electromagnetic nuclear physics at CEBAF. Most of the heavy-ion work is completed and there are now new experiments planned. Included in this report are two papers resulting from collaborations on heavy-ion experiments.

Vineyard, M.F.; Gilfoyle, G.P.; Major, R.W.

1995-12-31T23:59:59.000Z

431

Development of refined MCNPX-PARET multi-channel model for transient analysis in research reactors  

SciTech Connect

Reactivity insertion transients are often analyzed (RELAP, PARET) using a two-channel model, representing the hot assembly with specified power distribution and an average assembly representing the remainder of the core. For the analysis of protected by the reactor safety system transients and zero reactivity feedback coefficients this approximation proves to give adequate results. However, a more refined multi-channel model representing the various assemblies, coupled through the reactivity feedback effects to the whole reactor core is needed for the analysis of unprotected transients with excluded over power and period trips. In the present paper a detailed multi-channel PARET model has been developed which describes the reactor core in different clusters representing typical BR2 fuel assemblies. The distribution of power and reactivity feedback in each cluster of the reactor core is obtained from a best-estimate MCNPX calculation using the whole core geometry model of the BR2 reactor. The sensitivity of the reactor response to power, temperature and energy distributions is studied for protected and unprotected reactivity insertion transients, with zero and non-zero reactivity feedback coefficients. The detailed multi-channel model is compared vs. simplified fewer-channel models. The sensitivities of transient characteristics derived from the different models are tested on a few reactivity insertion transients with reactivity feedback from coolant temperature and density change. (authors)

Kalcheva, S.; Koonen, E. [SCK-CEN, BR2 Reactor Dept., Boeretang 200, 2400 Mol (Belgium); Olson, A. P. [RERTR Program, Nuclear Engineering Div., Argonne National Laboratory, Cass Avenue, Argonne, IL 60439 (United States)

2012-07-01T23:59:59.000Z

432

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

Science Conference Proceedings (OSTI)

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

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

2004-12-15T23:59:59.000Z

433

Brief of American Social Scinence Researchers in Fisher v. University of Texas  

E-Print Network (OSTI)

passim Hopwood v. Texas, 78 F.3d 932 (5th Cir.Petitioner, v. UNIVERSITY OF TEXAS AT AUSTIN, ET AL. ,in Higher Education and the Texas Top 10% Law, 4 Race & Soc.

American Social Science Researchers as Amici Curiae

2012-01-01T23:59:59.000Z

434

NREL: Wind Research - University of Maine Launches First U.S...  

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

Map Printable Version University of Maine Launches First U.S. Grid-Connected Offshore Wind Turbine June 3, 2013 DOE has recognized the nation's first grid-connected offshore...

435

Expanding and optimizing fuel management and data analysis capabilities of MCODE-FM in support of MIT research reactor (MITR-II) LEU conversion  

E-Print Network (OSTI)

Studies are underway in support of the MIT research reactor (MITR-II) conversion from high enriched Uranium (HEU) to low enriched Uranium (LEU), as required by recent non-proliferation policy. With the same core configuration ...

Horelik, Nicholas E. (Nicholas Edward)

2012-01-01T23:59:59.000Z

436

Development of a core design optimization tool and analysis in support of the planned LEU conversion of the MIT Research Reactor (MITR-II)  

E-Print Network (OSTI)

The MIT Research Reactor (MITR-II) is currently undergoing analysis for the planned conversion from high enriched uranium (HEU) to low enriched uranium (LEU), as part of a global effort to minimize the availability of ...

Connaway, Heather M. (Heather Moira)

2012-01-01T23:59:59.000Z

437

PROCEEDINGS OF THE AEC SYMPOSIUM FOR CHEMICAL PROCESSING OF IRRADIATED FUELS FROM POWER, TEST, AND RESEARCH REACTORS, RICHLAND, WASHINGTON, OCTOBER 20 AND 21, 1959  

SciTech Connect

A review is presented in this symposium of the technology currently available for processing spent fuels from research, test, and power reactors. Twenty-one papers are included. Separate abstracts have been prepared for each paper. (W.L.H.)

1960-01-01T23:59:59.000Z

438

PRELIMINARY HAZARDS SUMMARY REPORT ON THE BROOKHAVEN HIGH FLUX BEAM RESEARCH REACTOR  

SciTech Connect

The High Flux Beam Reactor, HFBR, is cooled, moderated, and reflected by heavy water and designed to produce 40 Mw with a total epithermal flux of ~1.6 X 10/sup 15/cm/sup -2/ sec/sup -1/ and a flector thermal maximum flux of 7 X 10/sup 14/ cm/sup -2/ sec/sup -1/, using a core formed by ETR plate-type fuel elements in a close-packed array. The hazards summary is given in terms of site description, reactor design, building design, plant operation, disposal of radioactive wastes and effluents, and safety analysis. (B.O.G.)

Hendrie, J.M.; Kouts, H.J.C.

1961-05-01T23:59:59.000Z

439

Final Report for The University of Texas at Arlington Optical Medical Imaging Section of Advanced Imaging Research Center  

SciTech Connect

The goal of this project was to create state-of-the-art optical medical imaging laboratories for the Biomedical Engineering faculty and student researchers of the University of Texas at Arlington (UTA) on the campus of the University of Texas Southwestern Medical Center (UTSW). This has been successfully achieved. These laboratories provide an unprecedented opportunity for the bioengineers (from UTA) to bring about new breakthroughs in medical imaging using optics. Specifically, three major laboratories have been successfully established and state-of-the-art scientific instruments have been placed in the labs. As a result of this grant, numerous journal and conference publications have been generated, patents for new inventions have been filed and received, and many additional grants for the continuation of the research has been received.

Khosrow Behbehani

2013-02-26T23:59:59.000Z

440

The "Last Universal Scientist" Takes Charge - Argonne's Nuclear Science  

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

The "Last Universal Scientist" Takes Charge The "Last Universal Scientist" Takes Charge About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy

Note: This page contains sample records for the topic "university research reactor" 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

M. Uesaka, H. Iijima, Y. Muroya, T. Ueda, A. Sakumi, Nuclear Engineering Research Laboratory, University of Tokyo  

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

width measurement and control width measurement and control M. Uesaka, H. Iijima, Y. Muroya, T. Ueda, A. Sakumi, Nuclear Engineering Research Laboratory, University of Tokyo H. Tomizawa, N. Kumagai SPring-8, Japan Synchrotron Radiation Institute June 26, 2004 International Symposium on Ultrafast Accelerators for Pulse Radiolysis Femtosecond Electron Bunch Diagnostics Incoherent Radiation Coherent Radiation Streak Camera or Single-shot Acquisition of Spectrum Bunch Form Factor Bunch Shape Fluctuation Method 2nd Order Correlation Bunch Form Factor

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Multi-University Southeast INIE Consortium  

SciTech Connect

2 Project Summary: The Multi-University Southeast INIE Consortium (MUSIC) was established in response to the US Department of Energy’s (DOE) Innovations in Nuclear Infrastructure and Education (INIE) program. MUSIC was established as a consortium composed of academic members and national laboratory partners. The members of MUSIC are the nuclear engineering programs and research reactors of Georgia Institute of Technology (GIT), North Carolina State University (NCSU), University of Maryland (UMD), University of South Carolina (USC), and University of Tennessee (UTK). The University of Florida (UF), and South Carolina State University (SCSU) were added to the MUSIC membership in the second year. In addition, to ensure proper coordination between the academic community and the nation’s premier research and development centers in the fields of nuclear science and engineering, MUSIC created strategic partnerships with Oak Ridge National Laboratory (ORNL) including the Spallation Neutron Source (SNS) project and the Joint Institute for Neutron Scattering (JINS), and the National Institute of Standards and Technology (NIST). A partnership was also created with the Armed Forces Radiobiology Research Institute (AFRRI) with the aim of utilizing their reactor in research if funding becomes available. Consequently, there are three university research reactors (URRs) within MUSIC, which are located at NCSU (1-MW PULSTAR), UMD (0.25-MW TRIGA) and UF (0.10-MW Argonaut), and the AFRRI reactor (1-MW TRIGA MARK F). The overall objectives of MUSIC are: a) Demonstrate that University Research Reactors (URR) can be used as modern and innovative instruments of research in the basic and applied sciences, which include applications in fundamental physics, materials science and engineering, nondestructive examination, elemental analysis, and contributions to research in the health and medical sciences, b) Establish a strong technical collaboration between the nuclear engineering faculty and the MUSIC URRs. This will be achieved by involving the faculty in the development of state-of-the-art research facilities at the URRs and subsequently, in the utilization of these facilities, c) Facilitate the use of the URRs by the science and engineering faculty within the individual institutions and by the general community of science and engineering, d) Develop a far-reaching educational component that is capable of addressing the needs of the nuclear science and engineering community. Specifically, the aim of this component will be to perform public outreach activities, contribute to the active recruitment of the next generation of nuclear professionals, strengthen the education of nuclear engineering students, and promote nuclear engineering education for minority students.

Ayman Hawari; Nolan Hertel; Mohamed Al-Sheikhly; Laurence Miller; Abdel-Moeze Bayoumi; Ali Haghighat; Kenneth Lewis

2010-12-29T23:59:59.000Z

443

MIT Modular Pebble Bed Reactor (MPBR) A Summary of Research Activities and Accomplishments  

E-Print Network (OSTI)

operation #12;MIT MPBR Specifications Thermal Power 250 MW - 120 Mwe Target Thermal Efficiency 45 % Core for a pebble bed reactor power plant system with high efficiency and minimum capital cost ­ Net efficiency > 45;Plant With Space Frames #12;#12;For 1150 MW Electric Power Station Turbine Hall Boundary Admin Training

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