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Note: This page contains sample records for the topic "foreign 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
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1

SUPPLEMENT ANALYSIS OF FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL  

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

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

2

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

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

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

3

Foreign Research Reactor Spent Nuclear Fuel Acceptance Program  

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

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

4

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

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

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 ...............................................................................................................................

5

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

SciTech Connect (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

6

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

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

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

7

Radiation Exposures Associated with Shipments of Foreign Research Reactor Spent Nuclear Fuel  

SciTech Connect (OSTI)

Experience has shown that the analyses of marine transport of spent fuel in the Environmental Impact Statement (EIS) were conservative. It is anticipated that for most shipments. The external dose rate for the loaded transportation cask will be more in line with recent shipments. At the radiation levels associated with these shipments, we would not expect any personnel to exceed radiation exposure limits for the public. Package dose rates usually well below the regulatory limits and personnel work practices following ALARA principles are keeping human exposures to minimal levels. However, the potential for Mure shipments with external dose rates closer to the exclusive-use regulatory limit suggests that DOE should continue to provide a means to assure that individual crew members do not receive doses in excess of the public dose limits. As a minimum, the program will monitor cask dose rates and continue to implement administrative procedures that will maintain records of the dose rates associated with each shipment, the vessel used, and the crew list for the vessel. DOE will continue to include a clause in the contract for shipment of the foreign research reactor spent nuclear fuel requiring that the Mitigation Action Plan be followed.

MASSEY,CHARLES D.; MESSICK,C.E.; MUSTIN,T.

1999-11-01T23:59:59.000Z

8

Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel  

SciTech Connect (OSTI)

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

9

Radiological consequences of ship collisions that might occur in U.S. Ports during the shipment of foreign research reactor spent nuclear fuel to the United States in break-bulk freighters  

SciTech Connect (OSTI)

Accident source terms, source term probabilities, consequences, and risks are developed for ship collisions that might occur in U.S. ports during the shipment of spent fuel from foreign research reactors to the United States in break-bulk freighters.

Sprung, J.L.; Bespalko, S.J.; Massey, C.D.; Yoshimura, R. [Sandia National Laboratory, Albuquerque, NM (United States); Johnson, J.D. [GRAM Inc., Albuquerque, NM (United States); Reardon, P.C. [PCRT Technologies, Albuquerque, NM (United States); Ebert, M.W.; Gallagher D.W. [Science Applications International Corp., Reston, VA (United States)

1996-08-01T23:59:59.000Z

10

Research reactors - an overview  

SciTech Connect (OSTI)

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

Beginning Foreign Obligation Balances for the Power Reactors Presentation  

National Nuclear Security Administration (NNSA)

Beginning Foreign Obligation Balances Beginning Foreign Obligation Balances Beginning Foreign Obligation Balances Beginning Foreign Obligation Balances for the Power Reactors for the Power Reactors Michael J. Smith Michael J. Smith NAC International NAC International Obligations Accounting Implementation Workshop Obligations Accounting Implementation Workshop January 13, 2004 January 13, 2004 Crowne Crowne Plaza Plaza Ravinia Ravinia Atlanta, Georgia Atlanta, Georgia Project Purpose Project Purpose * Bridge the gap in foreign obligated (FO) inventory tracking for US power reactor RISs between 10/1/01 and 9/30/03 * Provide input for 10/1/03 FO beginning inventories in the NMMSS Obligations Accounting Implementation Workshop Obligations Accounting Implementation Workshop January 13, 2004 January 13, 2004 Crowne

12

Advanced Nuclear Research Reactor  

SciTech Connect (OSTI)

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

Nuclear Research Reactors  

Science Journals Connector (OSTI)

... their countries for the advent of nuclear power. A few countries had built large research reactors for the production of isotopes and to study the behaviour of nuclear fuel, but ... production of isotopes and to study the behaviour of nuclear fuel, but the small training reactor had not been developed. Since then, research ...

T. E. ALLIBONE

1963-07-20T23:59:59.000Z

14

Canadian university research reactors  

SciTech Connect (OSTI)

In Canada there are seven university research reactors: one medium-power (2-MW) swimming pool reactor at McMaster University and six low-power (20-kW) SLOWPOKE reactors at Dalhousie University, Ecole Polytechnique, the Royal Military College, the University of Toronto, the University of Saskatchewan, and the University of Alberta. This paper describes primarily the McMaster Nuclear Reactor (MNR), which operates on a wider scale than the SLOWPOKE reactors. The MNR has over a hundred user groups and is a very broad-based tool. The main applications are in the following areas: (1) neutron activation analysis (NAA); (2) isotope production; (3) neutron beam research; (4) nuclear engineering; (5) neutron radiography; and (6) nuclear physics.

Ernst, P.C.; Collins, M.F.

1989-11-01T23:59:59.000Z

15

Reactor Safety Research Programs  

SciTech Connect (OSTI)

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, 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 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 pipeto- 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-ofcoolant 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, 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.

1981-07-01T23:59:59.000Z

16

Advanced Reactor Research and Development Funding Opportunity...  

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

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

17

Japan opens up to foreign researchers  

Science Journals Connector (OSTI)

... pages of international science journals, and those who are hesitate to use them. Instead, Japan expects foreign scientists to learn about such opportunities from their embassy officials in Tokyo or ... to learn about such opportunities from their embassy officials in Tokyo or science organizations outside Japan, or through personal contacts with Japanese scientists (who often are equally ill-informed). ...

David Swinbanks

1993-04-29T23:59:59.000Z

18

2012 Annual Report Research Reactor Infrastructure Program  

SciTech Connect (OSTI)

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

Douglas Morrell

2012-11-01T23:59:59.000Z

19

BNL | Our History: Reactors as Research Tools  

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

20

History of Research Reactors at Brookhaven  

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

Note: This page contains sample records for the topic "foreign 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

Research Program of a Super Fast Reactor  

SciTech Connect (OSTI)

Research program of a supercritical-pressure light water cooled fast reactor (Super Fast Reactor) is funded by MEXT (Ministry of Education, Culture, Sports, Science and Technology) in December 2005 as one of the research programs of Japanese NERI (Nuclear Energy Research Initiative). It consists of three programs. (1) development of Super Fast Reactor concept; (2) thermal-hydraulic experiments; (3) material developments. The purpose of the concept development is to pursue the advantage of high power density of fast reactor over thermal reactors to achieve economic competitiveness of fast reactor for its deployment without waiting for exhausting uranium resources. Design goal is not breeding, but maximizing reactor power by using plutonium from spent LWR fuel. MOX will be the fuel of the Super Fast Reactor. Thermal-hydraulic experiments will be conducted with HCFC22 (Hydro chlorofluorocarbons) heat transfer loop of Kyushu University and supercritical water loop at JAEA. Heat transfer data including effect of grid spacers will be taken. The critical flow and condensation of supercritical fluid will be studied. The materials research includes the development and testing of austenitic stainless steel cladding from the experience of PNC1520 for LMFBR. Material for thermal insulation will be tested. SCWR (Supercritical-Water Cooled Reactor) of GIF (Generation-4 International Forum) includes both thermal and fast reactors. The research of the Super Fast Reactor will enhance SCWR research and the data base. The research period will be until March 2010. (authors)

Oka, Yoshiaki; Ishiwatari, Yuki; Liu, Jie; Terai, Takayuki; Nagasaki, Shinya; Muroya, Yusa; Abe, Hiroaki [Nuclear Professional School / Department of Nuclear Engineering and Management, The University of Tokyo, Tokaimura, Naka-gun, Ibaraki, 319-1188 (Japan); Mori, Hideo [Department of Mechanical Engineering, Kyushu University (Japan); Akiba, Masato; Akimoto, Hajime; Okumura, Keisuke; Akasaka, Naoaki [Japan Atomic Energy Agency (Japan); GOTO, Shoji [Tokyo Electric Power Company (Japan)

2006-07-01T23:59:59.000Z

22

University Research Reactor Task Force to the Nuclear Energy Research  

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

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

23

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

SciTech Connect (OSTI)

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.

NONE

1994-03-25T23:59:59.000Z

24

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

......System for Research Reactor (IRSRR). Available...System for Research Reactor (IRSRR). Available...76. 7 Manual on reliability data collection for research reactor PSAs. (1992) IAEA...probabilistic safety analysis of incidents in nuclear......

Valdir Maciel Lopes; Gian Maria Agostinho Angelo Sordi; Mauricio Moralles; Tufic Madi Filho

2012-06-01T23:59:59.000Z

25

Brookhaven Graphite Research Reactor | Environmental Restoration Projects |  

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

26

Corrosion Minimization for Research Reactor Fuel  

SciTech Connect (OSTI)

Existing university research reactors are being converted to use low-enriched uranium fue to eliminate the use of highly-enriched uranium. These conversions require increases in fuel loading that will result in the use of elements with more fuel plates, resulting in a net decrease in the water annulus between fuel plates. The proposed decrease in the water annulus raises questions about the requirements and stability of the surface hydroxide on the aluminum fuel cladding and the potential for runaway corrosion resulting in fuel over-temperature incidents. The Nuclear Regulatory Commission (NRC), as regulator for these university reactors, must ensure that proposed fuel modifications will not result in any increased risk or hazard to the reactor operators or the public. This document reviews the characteristics and behavior of aluminum hydroxides, analyzes the drivers for fuel plate corrosion, reviews relevant historical incidents, and provides recommendations on fuel design, surface treatment, and reactor operational practices to avoid corrosion issues.

Eric Shaber; Gerard Hofman

2005-06-01T23:59:59.000Z

27

Environmental Management Brookhaven Graphite Research Reactor  

E-Print Network [OSTI]

-out report · Transition to long-term surveillance and maintenance · Office of Environmental ManagementEnvironmental Management Brookhaven Graphite Research Reactor (BGRR) Project Completion John Sattler Federal Project Director Office of Environmental Management U.S. Department of Energy BNL

Homes, Christopher C.

28

Brookhaven Lab Completes Decommissioning of Graphite Research Reactor:  

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

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.

29

MANAGEMENT OF RESEARCH AND TEST REACTOR ALUMINUM SPENT NUCLEAR FUEL - A TECHNOLOGY ASSESSMENT  

SciTech Connect (OSTI)

The Department of Energy's Environmental Management (DOE-EM) Program is responsible for the receipt and storage of aluminum research reactor spent nuclear fuel or used fuel until ultimate disposition. Aluminum research reactor used fuel is currently being stored or is anticipated to be returned to the U.S. and stored at DOE-EM storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper assesses the technologies and the options for safe transportation/receipt and interim storage of aluminum research reactor spent fuel and reviews the comprehensive strategy for its management. The U.S. Department of Energy uses the Appendix A, Spent Nuclear Fuel Acceptance Criteria, to identify the physical, chemical, and isotopic characteristics of spent nuclear fuel to be returned to the United States under the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The fuel is further evaluated for acceptance through assessments of the fuel at the foreign sites that include corrosion damage and handleability. Transport involves use of commercial shipping casks with defined leakage rates that can provide containment of the fuel, some of which are breached. Options for safe storage include wet storage and dry storage. Both options must fully address potential degradation of the aluminum during the storage period. This paper focuses on the various options for safe transport and storage with respect to technology maturity and application.

Vinson, D.

2010-07-11T23:59:59.000Z

30

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 {\

Gang Guo; Fang Han; Xiangdong Ji; Jianglai Liu; Zhaoxu Xi; Huanqiao Zhang

2013-06-18T23:59:59.000Z

31

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

32

OSTI Brings Foreign Research to U.S. Science Community | OSTI, US Dept of  

Office of Scientific and Technical Information (OSTI)

Brings Foreign Research to U.S. Science Community Brings Foreign Research to U.S. Science Community August 19, 2005 Oak Ridge, TN - Each year the U.S. Department of Energy (DOE) Office of Scientific and Technical Information (OSTI) - through its participation in two multilateral R&D information exchange agreements - gains access to approximately 80,000 foreign energy-related research summaries. One agreement is under the auspices of the International Energy Agency (IEA) in Paris while the other is under the auspices of the International Atomic Energy Agency (IAEA) in Vienna. The IEA information collection, which totals more than 3.5 million items, is made available to U.S. researchers by OSTI, an Office of Science program located in Oak Ridge, TN. This agreement, called the Energy Technology Data Exchange (ETDE), is managed by

33

Chicago Pile reactors create enduring research legacy - Argonne's  

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

34

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

SciTech Connect (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

35

Brookhaven Graphite Research Reactor Workshop | Department of Energy  

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

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

36

German Pebble Bed Research Reactor Highly Enriched Uranium (HEU...  

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

Potential Acceptance and Disposition of German Pebble Bed Research Reactor Highly Enriched Uranium (HEU) Fuel Environmental Assessment Maxcine Maxted, DOE-SR Used Nuclear Fuel...

37

Annular Core Research Reactor - Critical to Science-Based Weapons...  

National Nuclear Security Administration (NNSA)

Annular Core Research Reactor - Critical to Science-Based Weapons Design, Certification | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People...

38

Health physics research reactor reference dosimetry  

SciTech Connect (OSTI)

Reference neutron dosimetry is developed for the Health Physics Research Reactor (HPRR) in the new operational configuration directly above its storage pit. This operational change was physically made early in CY 1985. The new reference dosimetry considered in this document is referred to as the 1986 HPRR reference dosimetry and it replaces any and all HPRR reference documents or papers issued prior to 1986. Reference dosimetry is developed for the unshielded HPRR as well as for the reactor with each of five different shield types and configurations. The reference dosimetry is presented in terms of three different dose and six different dose equivalent reporting conventions. These reporting conventions cover most of those in current use by dosimetrists worldwide. In addition to the reference neutron dosimetry, this document contains other useful dosimetry-related data for the HPRR in its new configuration. These data include dose-distance measurements and calculations, gamma dose measurements, neutron-to-gamma ratios, ''9-to-3 inch'' ratios, threshold detector unit measurements, 56-group neutron energy spectra, sulfur fluence measurements, and details concerning HPRR shields. 26 refs., 11 figs., 31 tabs.

Sims, C.S.; Ragan, G.E.

1987-06-01T23:59:59.000Z

39

Brookhaven Graphite Research Reactor | Environmental Restoration Projects |  

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

40

Brookhaven Graphite Research Reactor | Environmental Restoration Projects |  

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

Note: This page contains sample records for the topic "foreign 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

(Liquid metal reactor/fast breeder reactor research and development)  

SciTech Connect (OSTI)

The second meeting of the UJCC was held in Japan on June 6--8, 1990. The first day was devoted to presentations of the status of the US and Japanese Fast Breeder Reactor (FBR) programs and the status of specific areas of cooperative work. Briefly, the Japanese are following the FBR development program which has been in place since the 1970s. This program includes an FBR test reactor (JOYO), a pilot-scale reactor (MONJU), a demonstration-scale plant, and commercial-scale plants by about 2020. The US program has been redirected toward an actinide recycle mission using metal fuel and pyroprocessing of spent fuel to recovery both Pu and the higher actinides for return to the Liquid Metal Reactor (LMR). The second day was spent traveling from Tokyo to Tsuruga for a tour of the MONJU reactor. The tour was especially interesting. The third day was spent writing the minutes of the meeting and the return trip to Tokyo.

Homan, F.J.

1990-06-20T23:59:59.000Z

42

Diversion assumptions for high-powered research reactors  

SciTech Connect (OSTI)

This study deals with diversion assumptions for high-powered research reactors -- specifically, MTR fuel; pool- or tank-type research reactors with light-water moderator; and water, beryllium, or graphite reflectors, and which have a power level of 25 MW(t) or more. The objective is to provide assistance to the IAEA in documentation of criteria and inspection observables related to undeclared plutonium production in the reactors described above, including: criteria for undeclared plutonium production, necessary design information for implementation of these criteria, verification guidelines including neutron physics and heat transfer, and safeguards measures to facilitate the detection of undeclared plutonium production at large research reactors.

Binford, F.T.

1984-01-01T23:59:59.000Z

43

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research  

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

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

44

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

45

RERTR program reduces use of enriched uranium in research reactors  

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

46

Advanced Reactor Research and Development Funding Opportunity Announcement  

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

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

47

Advanced Reactor Research and Development Funding Opportunity Announcement  

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

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

48

Sandia National Laboratories: Research: Facilities: Sandia Pulsed Reactor  

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

49

Research needs and data acquisition to apply US technology to foreign coals: Quarterly report, October-December 1986. [Foreign  

SciTech Connect (OSTI)

The National Coal Technology Data Center (NCTDC) at the Pittsburgh Energy Technology Center is currently addressing the recognized need for technical and scientific information on international coal characteristics and coal conversion technologies adopted in foreign countries. At NCTDC, the present database on domestic coals and coal conversion technologies is being supplemented with data on international coals through the development of a comprehensive international database on foreign coals and coal conversion technologies. DOE plans to utilize this information to develop strategic planning and policy options and assist the private sector in determining the utility of its products and services in the international market place. It is hoped, that through the better understanding of their foreign coal resources, advanced US coal preparation, conversion and utilization technologies can be applied to these coals, promoting not only US technology transfer but also addressing the immediate energy needs of the developing countries.

Not Available

1986-01-01T23:59:59.000Z

50

NUCLEAR POWER AND RESEARCH REACTORS 1939 1942 1943 1944  

E-Print Network [OSTI]

#12;#12;11 #12;2 NUCLEAR POWER AND RESEARCH REACTORS 1939 1942 1943 1944 Nuclear fission discovered Oak Ridge selected as site for World War II Manhattan Project First sustained and controlled nuclear 430 nuclear power reactors are operating in the world, and 103 nuclear power plants produce 20

Pennycook, Steve

51

Photoneutron effects on pulse reactor kinetics for the Annular Core Research Reactor (ACRR).  

SciTech Connect (OSTI)

The Annular Core Research Reactor (ACRR) is a swimming-pool type pulsed reactor that maintains an epithermal neutron flux and a nine-inch diameter central dry cavity. One of its uses is neutron and gamma-ray irradiation damage studies on electronic components under transient reactor power conditions. In analyzing the experimental results, careful attention must be paid to the kinetics associated with the reactor to ensure that the transient behavior of the electronic device is understood. Since the ACRR fuel maintains a substantial amount of beryllium, copious quantities of photoneutrons are produced that can significantly alter the expected behavior of the reactor power, especially following a reactor pulse. In order to understand these photoneutron effects on the reactor kinetics, the KIFLE transient reactor-analysis code was modified to include the photoneutron groups associated with the beryllium. The time-dependent behavior of the reactor power was analyzed for small and large pulses, assuming several initial conditions including following several pulses during the day, and following a long steady-state power run. The results indicate that, for these types of initial conditions, the photoneutron contribution to the reactor pulse energy can have a few to tens of percent effect.

Parma, Edward J., Jr.

2009-06-01T23:59:59.000Z

52

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

......ICRP-64. INTRODUCTION Nuclear research reactors are considered important tools in nuclear science. For more than...as well as prevention policy, have stimulated the development...level 3 in the International Nuclear Events Scale (INES) of......

Valdir Maciel Lopes; Gian Maria Agostinho Angelo Sordi; Mauricio Moralles; Tufic Madi Filho

2012-06-01T23:59:59.000Z

53

Managerial Aspects of BNCT at a Nuclear Research Reactor  

Science Journals Connector (OSTI)

All BNCT facilities worldwide, performing clinical trials, are presently located at a nuclear research reactor. They are nevertheless, to all ... 43/EURATOM which stipulates that radiotherapy quality assurance programmes

Wolfgang A. G. Sauerwein; Ray Moss

2012-01-01T23:59:59.000Z

54

Argonne's pyroprocessing and advanced reactor research featured on WGN  

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

55

Research and educational activities at the MIT Research Reactor : Fiscal year 1968  

E-Print Network [OSTI]

A report of research and educational activities which utilized the Massachusetts Institute of Technology, five-megawatt, heavy water, research reactor during fiscal year 1968 has been prepared for administrative use at MIT ...

Massachusetts Institute of Technology. Department of Nuclear Engineering; 7102 Massachusetts Institute of Technology. Research Reactor. Staff; U.S. Atomic Energy Commission

1968-01-01T23:59:59.000Z

56

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

SciTech Connect (OSTI)

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

57

RERTR 2009 (Reduced Enrichment for Research and Test Reactors)  

SciTech Connect (OSTI)

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

58

Yale High Energy Physics Research: Precision Studies of Reactor Antineutrinos  

SciTech Connect (OSTI)

This reports presents experimental research at the intensity frontier of particle physics with particular focus on the study of reactor antineutrinos and the precision measurement of neutrino oscillations. The experimental neutrino physics group of Professor Heeger and Senior Scientist Band at Yale University has had leading responsibilities in the construction and operation of the Daya Bay Reactor Antineutrino Experiment and made critical contributions to the discovery of non-zero$\\theta_{13}$. Heeger and Band led the Daya Bay detector management team and are now overseeing the operations of the antineutrino detectors. Postdoctoral researchers and students in this group have made leading contributions to the Daya Bay analysis including the prediction of the reactor antineutrino flux and spectrum, the analysis of the oscillation signal, and the precision determination of the target mass yielding unprecedented precision in the relative detector uncertainty. Heeger's group is now leading an R\\&D effort towards a short-baseline oscillation experiment, called PROSPECT, at a US research reactor and the development of antineutrino detectors with advanced background discrimination.

Heeger, Karsten M [Yale University

2014-09-13T23:59:59.000Z

59

Status of reduced enrichment program for research reactors in Japan  

SciTech Connect (OSTI)

The status of reduced enrichment program for research reactors in Japan will be reviewed. The reduced enrichment programs for the JRR-3M, JRR-4 and JMTR of Japan Atomic Energy Agency (JAEA, former name is Japan Atomic Energy Research Institute (JAERI)) has been completed by 1999, and the reactors are being satisfactory operated using LEU fuels. The KUR of Kyoto University Research Reactor Institute (KURRI) has been partially completed and is still in progress under the Joint Study Program with Argonne National Laboratory (ANL). The JRR-3M using LEU silicide fuel elements have done a functional test by the Japanese Government in 2000, and the property of the reactor core was satisfied. JAEA has established a 'U-Mo fuel ad hoc committee' and has been studying the U-Mo fuel installation plan by carefully observing the development situation of the U-Mo fuel. In KURRI, the KUR has terminated its operation using HEU fuel on February 2006. The HEU KUR spent fuel elements will be sent to the U.S. by March 2008. Licensing for the full core conversion of KUR to LEU fuel is under progress and the core conversion to LEU is expected to be completed in 2008. (author)

Unesaki, Hironobu [Research Reactor Institute, Kyoto University, Asashiro-nishi 2-1010, Kumatori-cho, Sennan-gun, Osaka 590-0494 (Japan); Ohta, Kazunori; Inoue, Takeshi [Japan Atomic Energy Agency, Shirakata Shirane 2-4, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 (Japan)

2008-07-15T23:59:59.000Z

60

Dry Storage of Research Reactor Spent Nuclear Fuel - 13321  

SciTech Connect (OSTI)

Spent fuel from domestic and foreign research reactors is received and stored at the Savannah River Site's L Area Material Storage (L Basin) Facility. This DOE-owned fuel consists primarily of highly enriched uranium in metal, oxide or silicide form with aluminum cladding. Upon receipt, the fuel is unloaded and transferred to basin storage awaiting final disposition. Disposition alternatives include processing via the site's H Canyon facility for uranium recovery, or packaging and shipment of the spent fuel to a waste repository. A program has been developed to provide a phased approach for dry storage of the L Basin fuel. The initial phase of the dry storage program will demonstrate loading, drying, and storage of fuel in twelve instrumented canisters to assess fuel performance. After closure, the loaded canisters are transferred to pad-mounted concrete overpacks, similar to those used for dry storage of commercial fuel. Unlike commercial spent fuel, however, the DOE fuel has high enrichment, very low to high burnup, and low decay heat. The aluminum cladding presents unique challenges due to the presence of an oxide layer that forms on the cladding surface, and corrosion degradation resulting from prolonged wet storage. The removal of free and bound water is essential to the prevention of fuel corrosion and radiolytic generation of hydrogen. The demonstration will validate models predicting pressure, temperature, gas generation, and corrosion performance, provide an engineering scale demonstration of fuel handling, drying, leak testing, and canister backfill operations, and establish 'road-ready' storage of fuel that is suitable for offsite repository shipment or retrievable for onsite processing. Implementation of the Phase I demonstration can be completed within three years. Phases II and III, leading to the de-inventory of L Basin, would require an additional 750 canisters and 6-12 years to complete. Transfer of the fuel from basin storage to dry storage requires integration with current facility operations, and selection of equipment that will allow safe operation within the constraints of existing facility conditions. Examples of such constraints that are evaluated and addressed by the dry storage program include limited basin depth, varying fuel lengths up to 4 m, (13 ft), fissile loading limits, canister closure design, post-load drying and closure of the canisters, instrument selection and installation, and movement of the canisters to storage casks. The initial pilot phase restricts the fuels to shorter length fuels that can be loaded to the canister directly underwater; subsequent phases will require use of a shielded transfer system. Removal of the canister from the basin, followed by drying, inerting, closure of the canister, and transfer of the canister to the storage cask are completed with remotely operated equipment and appropriate shielding to reduce personnel radiation exposure. (authors)

Adams, T.M.; Dunsmuir, M.D.; Leduc, D.R.; Severynse, T.F.; Sindelar, R.L. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States); Moore, E.N. [Moore Nuclear Energy, LLC (United States)] [Moore Nuclear Energy, LLC (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

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

62

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

SciTech Connect (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

63

Research in nondestructive evaluation techniques for nuclear reactor concrete structures  

SciTech Connect (OSTI)

The purpose of the Materials Aging and Degradation (MAaD) Pathway of the Department of Energy's Light Water Reactor Sustainability (LWRS) Program is to develop the scientific basis for understanding and predicting longterm environmental degradation behavior of material in nuclear power plants and to provide data and methods to assess the performance of systems, structures, and components (SSCs) essential to safe and sustained nuclear power plant operations. The understanding of aging-related phenomena and their impacts on SSCs is expected to be a significant issue for any nuclear power plant planning for long-term operations (i.e. service beyond the initial license renewal period). Management of those phenomena and their impacts during long-term operations can be better enable by improved methods and techniques for detection, monitoring, and prediction of SSC degradation. The MAaD Pathway R and D Roadmap for Concrete, 'Light Water Reactor Sustainability Nondestructive Evaluation for Concrete Research and Development Roadmap', focused initial research efforts on understanding the recent concrete issues at nuclear power plants and identifying the availability of concrete samples for NDE techniques evaluation and testing. [1] An overview of the research performed by ORNL in these two areas is presented here.

Clayton, Dwight; Smith, Cyrus [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)

2014-02-18T23:59:59.000Z

64

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

SciTech Connect (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

65

Sixteenth water reactor safety information meeting: Proceedings: Volume 5, NUREG-1150, accident managment, recent advances in severe accident research, TMI-2, BWR Mark l shell failure  

SciTech Connect (OSTI)

This five-volume report contains 141 papers out of the 175 that were presented at the Sixteenth Water Reactor Safety Information Meeting held at the National Institute of Standards and Technology, Gaithersburg, Maryland, during the week of October 24--27, 1988. 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 twenty different papers presented by researchers from Germany, Italy, Japan, Sweden, Switzerland, Taiwan and the 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. This document, Volume 5, discusses NUREG-1150, Accident Management, Recent Advances in Severe Accident Research, BWR Mark I Shell Failure, and the Three Mile Island-2 Reactor.

Weiss, A.J. (comp.)

1989-03-01T23:59:59.000Z

66

IGORR-IV -- Proceedings of the fourth meeting of the International Group on Research Reactors  

SciTech Connect (OSTI)

The International Group on Research Reactors was formed to facilitate the sharing of knowledge and experience among those institutions and individuals who are actively working to design, build, and promote new research reactors or to make significant upgrades to existing facilities. Twenty-nine papers were presented in five sessions and written versions of the papers or hard copies of the vugraphs used are published in these proceedings. The five sessions were: (1) Operating Research Reactors and Facility Upgrades; (2) Research Reactors in Design and Construction; (3) ANS Closeout Activities; (4) and (5) Research, Development, and Analysis Results.

Rosenbalm, K.F. [comp.] [comp.

1995-12-31T23:59:59.000Z

67

E-Print Network 3.0 - application research reactor Sample Search...  

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

Nuclear Technologies 28 Research Aptitude Problem 1 Scavenging of aerosol particles by ice crystals Summary: strategies that would be required to operate these reactor systems....

68

PHYSICS AND SAFETY ANALYSIS FOR THE NIST RESEARCH REACTOR.  

SciTech Connect (OSTI)

Detailed reactor physics and 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 analyses provide an update to the Final Safety Analysis Report (FSAR) and employ state-of-the-art calculational methods. Three-dimensional Monte Carlo neutron and photon transport calculations were performed with the MCNP code to determine the safety parameters for the NBSR. The core depletion and determination of the fuel compositions were performed with MONTEBURNS. MCNP calculations were performed to determine the beginning, middle, and end-of-cycle power distributions, moderator temperature coefficient, and shim safety arm, beam tube and void reactivity worths. The calculational model included a plate-by-plate description of each fuel assembly, axial mid-plane water gap, beam tubes and the tubular geometry of the shim safety arms. The time-dependent analysis of the primary loop was determined with a RELAP5 transient analysis model that includes the pump, heat exchanger, fuel element geometry, and flow channels for both the six inner and twenty-four outer fuel elements. The statistical analysis used to assure protection from critical heat flux (CHF) was performed using a Monte Carlo simulation of the uncertainties contributing to the CHF calculation. The power distributions used to determine the local fuel conditions and margin to CHF were determined with MCNP. Evaluations were performed for the following accidents: (1) the control rod withdrawal startup accident, (2) the maximum reactivity insertion accident, (3) loss-of-flow resulting from loss of electrical power, (4) loss-of-flow resulting from a primary pump seizure, (5) loss-of-flow resulting from inadvertent throttling of a flow control valve, (6) loss-of-flow resulting from failure of both shutdown cooling pumps and (7) misloading of a fuel element. In both the startup and maximum reactivity insertion accidents, the core power transient is terminated by a reactor trip at 26 MW. The calculations show that both the peak reactor power and the excursion energy depend on the negative reactivity insertion from reactor trip. In one of the loss-of-flow accidents offsite electrical power is assumed lost to the three operating primary pumps. A slightly delayed reactor scram is initiated as a result of primary flow coast down. The RELAP5 results indicate that there is adequate margin to CHF and no damage to the fuel will occur, because of the momentum of the coolant flowing through the fuel channels and the negative scram reactivity insertion. For both the primary pump seizure and inadvertent throttling of a flow control valve, the RELAP5 analyses indicate that the reduction in power following the trip is sufficient to ensure that there is adequate margin to CHF and that the fuel cladding does not fail. The analysis of the loss-of-flow accident in the extremely unlikely case where both shutdown pumps fail, shows that the cooling provided by the D{sub 2}O is sufficient to ensure the cladding does not fail. The power distributions were examined for a set of fuel misloadings in which a fresh fuel element is moved from a peripheral low-reactivity location to a central high-reactivity location. The calculations show that there is adequate margin to CHF and the cladding does not fail. An additional analysis was performed to simulate the operation at low power (500 kW) without forced flow cooling. The result indicates that natural convection cooling is adequate for operation of the NBSR at a power level of 500 kW.

CHENG,L.HANSON,A.DIAMOND,D.XU,J.CAREW,J.RORER,D.

2004-03-31T23:59:59.000Z

69

Nuclear plant-aging research on reactor protection systems  

SciTech Connect (OSTI)

This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed.

Meyer, L.C.

1988-01-01T23:59:59.000Z

70

MODULAR PEBBLE BED REACTOR PROJECT UNIVERSITY RESEARCH CONSORTIUM  

E-Print Network [OSTI]

Annual Report Page ii MODULAR PEBBLE BED REACTOR ABSTRACT This project is developing a fundamental. Publication of an archival journal article covering this work is being prepared. · Detailed gas reactor Abstract

71

Diversion assumptions for high-powered research reactors. ISPO C-50 Phase 1  

SciTech Connect (OSTI)

This study deals with diversion assumptions for high-powered research reactors -- specifically, MTR fuel; pool- or tank-type research reactors with light-water moderator; and water, beryllium, or graphite reflectors, and which have a power level of 25 MW(t) or more. The objective is to provide assistance to the IAEA in documentation of criteria and inspection observables related to undeclared plutonium production in the reactors described above, including: criteria for undeclared plutonium production, necessary design information for implementation of these criteria, verification guidelines including neutron physics and heat transfer, and safeguards measures to facilitate the detection of undeclared plutonium production at large research reactors.

Binford, F.T.

1984-01-01T23:59:59.000Z

72

Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs  

SciTech Connect (OSTI)

This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. 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 France, Germany, Japan, Russia, Switzerland, Taiwan, 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. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors.

Monteleone, S. [Brookhaven National Lab., Upton, NY (United States)] [comp.

1994-04-01T23:59:59.000Z

73

PHYSICS AND SAFETY ANALYSIS FOR THE NIST RESEARCH REACTOR.  

SciTech Connect (OSTI)

Detailed reactor physics and 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 analyses provide an update to the Final Safety Analysis Report (FSAR) and employ state-of-the-art calculational methods. Three-dimensional MCNP Monte Carlo neutron and photon transport calculations were performed to determine the safety parameters for the NBSR. The core depletion and determination of the fuel compositions were performed with MONTEBURNS. MCNP calculations were performed to determine the beginning, middle, and end-of-cycle power distributions, moderator temperature coefficient, and shim arm, beam tube and void reactivity worths. The calculational model included a plate-by-plate description of each fuel assembly, axial mid-plane water gap, beam tubes and the tubular geometry of the shim arms. The time-dependent analysis of the primary loop was determined with a RELAP5 transient analysis model including the pump, heat exchanger, fuel element geometry, and flow channels for both the six inner and twenty-four outer fuel elements. The statistical analysis used to assure protection from critical heat flux (CHF) was performed using a Monte Carlo simulation of the uncertainties contributing to the CHF calculation. The power distributions used to determine the local fuel conditions and margin to CHF were determined with MCNP. Evaluations were performed for the following accidents: (1) the control rod withdrawal startup accident, (2) the maximum reactivity insertion accident, (3) loss-of-flow resulting from loss of electrical power, (4) loss-of-flow resulting from a primary pump seizure, (5) loss-of-flow resulting from inadvertent throttling of a flow control valve, (6) loss-of-flow resulting from failure of both shutdown cooling pumps and (7) misloading of a fuel element. In both the startup and maximum reactivity insertion accidents, the core power transient is terminated by a reactor trip at 30 MW. The calculations show that both the peak reactor power and the excursion energy depend on the negative reactivity insertion from reactor trip. Two cases were considered for loss of electrical power. In the first case offsite power is lost, resulting in an immediate scram caused by loss of power to the control rod system. In the second case power is lost to only the three operating primary pumps, resulting in a slightly delayed scram when loss-of-flow is detected as the pumps coast down. In both instances, RELAP5 results indicate that there is adequate margin to CHF and no damage to the fuel will occur, because of the momentum of the coolant flowing through the fuel channels and the negative scram reactivity insertion. For both the primary pump seizure and inadvertent throttling of a flow control valve, the RELAP5 analyses indicate that the reduction in power following the trip is sufficient to ensure that there is adequate margin to CHF and the fuel cladding does not fail. The analysis of the loss-of-flow accident in the extremely unlikely case where both shutdown pumps fail shows that the cooling provided by the D{sub 2}O is sufficient to ensure the cladding does not fail. The power distributions were examined for a set of fuel misloadings in which a fresh fuel element is moved from a peripheral low-reactivity location to a central high-reactivity location. The calculations show that there is adequate margin to CHF and the cladding does not fail.

CAREW,J.CHENG,L.HANSON,AXU,J.RORER,D.DIAMOND,D.

2003-08-26T23:59:59.000Z

74

Instrumentation for Neutron Scattering at the Missouri University Research Reactor Paul F. Miceli  

E-Print Network [OSTI]

Instrumentation for Neutron Scattering at the Missouri University Research Reactor Paul F. Miceli Research Reactor (MURR) provides significant thermal neutron flux, which enables neutron scattering]. There are presently 5 instruments located on the beam port floor that are dedicated to neutron scattering: (1) TRIAX

Montfrooij, Wouter

75

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

SciTech Connect (OSTI)

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

76

NREL: Foreign Nationals  

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

Foreign Nationals Foreign Nationals At the National Renewable Energy Laboratory (NREL), collaboration is key to conducting scientific research at our institution in Golden, Colorado. Because an international scope is essential to our development program, we invite outstanding scholars from other countries to become an integral part of our organization through the Foreign National Assignment Program. This program enables people with new ideas and talents from around the world to contribute to research of mutual interest at the Laboratory while also contributing to the transfer of the technology resulting from that research. As a foreign national, you'll need information about immigration and the various types of visas. You can also find numerous helpful links to the State Department, U.S. Citizenship and Immigration Services, the Social

77

Medical isotope production: A new research initiative for the Annular Core Research Reactor  

SciTech Connect (OSTI)

An investigation has been performed to evaluate the capabilities of the Annular Core Research Reactor and its supporting Hot Cell Facility for the production of {sup 99}Mo and its separation from the fission product stream. Various target irradiation locations for a variety of core configurations were investigated, including the central cavity, fuel and reflector locations, and special target configurations outside the active fuel region. Monte Carlo techniques, in particular MCNP using ENDF B-V cross sections, were employed for the evaluation. The results indicate that the reactor, as currently configured, and with its supporting Hot Cell Facility, would be capable in meeting the current US demand if called upon. Modest modifications, such as increasing the capacity of the external heat exchangers, would permit significantly higher continuous power operation and even greater {sup 99}Mo production ensuring adequate capacity for future years.

Coats, R.L.; Parma, E.J.

1993-12-31T23:59:59.000Z

78

A RESEARCH ON SEAMLESS PLATFORM CHANGE OF REACTOR PROTECTION SYSTEM FROM PLC TO FPGA  

E-Print Network [OSTI]

A RESEARCH ON SEAMLESS PLATFORM CHANGE OF REACTOR PROTECTION SYSTEM FROM PLC TO FPGA JUNBEOM YOO1 1. INTRODUCTION A safety grade PLC is an industrial digital computer used to develop safety-critical systems such as RPS (Reactor Protection System) for nuclear power plants. The software loaded into a PLC

79

Reactor Safety Research Programs Quarterly Report October - December 1981  

SciTech Connect (OSTI)

This document summarizes the work performed by Pacific Northwest laboratory (PNL) from October 1 through December 31, 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 serviceinduced 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 post accident 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.

1982-03-01T23:59:59.000Z

80

Risk management at the Oak Ridge National Laboratory research reactors  

SciTech Connect (OSTI)

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

Note: This page contains sample records for the topic "foreign 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

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

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

82

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

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

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

83

Effect of reduced enrichment on the fuel cycle for research reactors  

SciTech Connect (OSTI)

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

84

Climate research in the former Soviet Union. FASAC: Foreign Applied Sciences Assessment Center technical assessment report  

SciTech Connect (OSTI)

This report assesses the state of the art in several areas of climate research in the former Soviet Union. This assessment was performed by a group of six internationally recognized US experts in related fields. The areas chosen for review are: large-scale circulation processes in the atmosphere and oceans; atmospheric radiative processes; cloud formation processes; climate effects of natural atmospheric disturbances; and the carbon cycle, paleoclimates, and general circulation model validation. The study found an active research community in each of the above areas. Overall, the quality of climate research in the former Soviet Union is mixed, although the best Soviet work is as good as the best corresponding work in the West. The best Soviet efforts have principally been in theoretical studies or data analysis. However, an apparent lack of access to modern computing facilities has severely hampered the Soviet research. Most of the issues considered in the Soviet literature are known, and have been discussed in the Western literature, although some extraordinary research in paleoclimatology was noted. Little unusual and exceptionally creative material was found in the other areas during the study period (1985 through 1992). Scientists in the former Soviet Union have closely followed the Western literature and technology. Given their strengths in theoretical and analytical methods, as well as their possession of simplified versions of detailed computer models being used in the West, researchers in the former Soviet Union have the potential to make significant contributions if supercomputers, workstations, and software become available. However, given the current state of the economy in the former Soviet Union, it is not clear that the computer gap will be bridged in the foreseeable future.

Ellingson, R.G.; Baer, F.; Ellsaesser, H.W.; Harshvardhan; Hoffert, M.I.; Randall, D.A.

1993-09-01T23:59:59.000Z

85

German concept and status of the disposal of spent fuel elements from German research reactors  

SciTech Connect (OSTI)

Eight research reactors with a power {>=} 100 kW are currently being operated in the Federal Republic of Germany. These comprise three TRIGA-type reactors (power 100 kW to 250 kW), four swimming-pool reactors (power 1 MW to 10 MW) and one DIDO type reactor (power 23 MW). The German research reactors are used for neutron scattering for basic research in the field of solid state research, neutron metrology, for the fabrication of isotopes and for neutron activation analysis for medicine and biology, for investigating the influence of radiation on materials and for nuclear fuel behavior. It will be vital to continue current investigations in the future. Further operation of the German research reactors is therefore indispensable. Safe, regular disposal of the irradiated fuel elements arising now and in future operation is of primary importance. Furthermore, there are several plants with considerable quantities of spent fuel, the safe disposal of which is a matter of urgency. These include above all the VKTA facilities in Rossendorf and also the TRIGA reactors, where disposal will only be necessary upon decommissioning. The present paper report is concerned with the disposal of fuel from the German research reactors. It briefly deals with the situation in the USA since the end of 1988, describes interim solutions for current disposal requirements and then mainly concentrates on the German disposal concept currently being prepared. This concept initially envisages the long-term (25--50 years) dry interim storage of fuel elements in special containers in a central German interim store with subsequent direct final disposal without reprocessing of the irradiated fuel.

Komorowski, K. [Bundesministerium fuer Bildung Wissenschaft, Bonn (Germany); Storch, S.; Thamm, G. [Forschungszentrum Juelich GmbH (Germany)

1995-12-31T23:59:59.000Z

86

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

SciTech Connect (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 DOEs 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

87

Materials Research Needs for Near-Term Nuclear Reactors  

Science Journals Connector (OSTI)

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

John R. Weeks

88

Mo-99 production at the Annular Core Research Reactor - recent calculative results  

SciTech Connect (OSTI)

Significant progress has been made over the past year in understanding the chemistry and processing challenges associated with {sup 99}Mo production using Cintichem type targets. Targets fabricated at Los Alamos National Laboratory have been successfully irradiated in fuel element locations at the Annular Core Research Reactor (ACRR) and processed at the Sandia Hot Cell Facility. The next goal for the project is to remove the central cavity experiment tube from the reactor core, allowing for the irradiation of up to 37 targets. After the in-core work is complete, the reactor will be capable of producing significant quantities of {sup 99}Mo.

Parma, E.J.

1997-11-01T23:59:59.000Z

89

Proceedings of the 1990 International Meeting on Reduced Enrichment for Research and Test Reactors  

SciTech Connect (OSTI)

The global effort to reduce, and possibly, eliminate the international traffic in highly-enriched uranium caused by its use in research reactors requires extensive cooperation and free exchange of information among all participants. To foster this free exchange of information, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at Argonne National Laboratory, sponsored this meeting as the thirteenth of a series which began in 1978. The common effort brought together, past, a large number of specialists from many countries. On hundred twenty-three participants from 26 countries, including scientists, reactor operators, and personnel from commercial fuel suppliers, research centers, and government organizations, convened in Newport, Rhode Island to discuss their results, their activities, and their plans relative to converting research reactors to low-enriched fuels. As more and more reactors convert to the use of low-enriched uranium, the emphasis of our effort has begun to shift from research and development to tasks more directly related to implementation of the new fuels and technologies that have been developed, and to refinements of those fuels and technologies. It is appropriate, for this reason, that the emphasis of this meeting was placed on safety and on conversion experiences. This individual papers in this report have been cataloged separately.

Not Available

1993-07-01T23:59:59.000Z

90

6 - Other nuclear energy applications: Hydrogen for transport desalination ships space research reactors for radioisotopes  

Science Journals Connector (OSTI)

Publisher Summary This chapter describes several nuclear energy applications. Hydrogen itself is likely to be an important future fuel; like electricity, it is an energy carrier. Nuclear energy can be used to make hydrogen electrolytically; and in the future, high-temperature reactors are likely to be used for thermochemical production. Desalination is energy-intensive. Nuclear energy is already being used for desalination, and nuclear energy has the potential for much greater use. Nuclear power has also revolutionized the navy; it is particularly suitable for vessels that need to be at sea for long periods without refueling, or for powerful submarine propulsion. After a gap of several years, there is a revival of interest in the use of nuclear fission power for space missions as well. Many of the world's nuclear reactors are used for research and training, materials testing, or the production of radioisotopes for medicine and industry. Research reactors are much smaller than power reactors or those propelling ships, and many are on university campuses. Research reactors are simpler than power reactors and operate at lower temperatures.

Ian Hore-Lacy

2007-01-01T23:59:59.000Z

91

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

SciTech Connect (OSTI)

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

92

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

93

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

SciTech Connect (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

94

Utilization of the Philippine Research Reactor as a training facility for nuclear power plant operators  

SciTech Connect (OSTI)

The Philippines has a 1-MW swimming-pool reactor facility operated by the Philippine Atomic Energy Commission (PAEC). The reactor is light-water moderated and cooled, graphite reflected, and fueled with 90% enriched uranium. Since it became critical in 1963 it has been utilized for research, radioisotope production, and training. It was used initially in the training of PAEC personnel and other research institutions and universities. During the last few years, however, it has played a key role in training personnel for the Philippine Nuclear Power Project (PNPP).

Palabrica, R.J.

1981-01-01T23:59:59.000Z

95

On the operator action analysis to reduce operational risk in research reactors  

Science Journals Connector (OSTI)

Abstract Human errors during operation and the resulting increase in operational risk are major concerns for nuclear reactors, just as they are for all industries. Additionally, human reliability analysis together with probabilistic risk analysis is a key element in reducing operational risk. The purpose of this paper is to analyze human reliability using appropriate methods for the probabilistic representation and calculation of human error to be used alongside probabilistic risk analysis in order to reduce the operational risk of the reactor operation. We present a technique for human error rate prediction and standardized plant analysis risk. Human reliability methods have been utilized to quantify different categories of human errors, which have been applied extensively to nuclear power plants. The Tehran research reactor is selected here as a case study, and after consultation with reactor operators and engineers human errors have been identified and adequate performance shaping factors assigned in order to calculate accurate probabilities of human failure.

Ramin Barati; Saeed Setayeshi

2014-01-01T23:59:59.000Z

96

Photo of the Week: The Brookhaven Graphite Research Reactor ...  

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

which is a research collaboration between institutions from the U.S., Brazil, U.K., Germany, Spain and Switzerland. The survey aims to explore the dynamics of the universe's...

97

RERTR Program: goals, progress and plans. [Reduced Enrichment Research and Test Reactor  

SciTech Connect (OSTI)

The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and schedules project the uranium density of qualified RERTR fuels for plate-type reactors to grow by approximately 1 g U/cm/sup 3/ each year, from the nearly null value of 1982 to the 7.0 g U/cm/sup 3/ which will be reached in early 1989. The technical needs of research reactors for HEU exports are also estimated to undergo a gradual but dramatic decline in the coming years.

Travelli, A.

1984-09-25T23:59:59.000Z

98

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

SciTech Connect (OSTI)

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

99

Research Reactors and Radiation Facilities for Joint Use Program  

E-Print Network [OSTI]

Observatory, a facility of the Graduate School of Science of Kyoto University, was constructed in 1968's current main research target is to unveil the origin of the solar magnetic activities that govern science and technology, material science, radiation life science, and radiation medical science

Takada, Shoji

100

Analysis of ITU TRIGA Mark II research reactor using Monte Carlo method  

Science Journals Connector (OSTI)

Abstract Research reactors include many complicated components with various shapes and sizes. Such complex parts also observed in TRIGA core are modelled by the researchers as simplified physical geometries when a particle transport computer code is used to analyse the reactors. These models are used to gain information on possible modifications in the reactors with no cost except a certain computational time demand. Besides, they can be used to understand the fabrication uncertainties of the core components and the methodologies used in the design process. The main objective of this study is to make a detailed three-dimensional full-core model of ITU (Istanbul Technical University) TRIGA Mark II research reactor for the use of Monte Carlo method and making a comparison of the simulation with the experimental observations. In case of lacking of experimental values reported, Final Safety Analysis Report values are used as reference. Furthermore, it is aimed to observe possible influences of using various neutron cross-section libraries (ENDF/Bs and JEFFs) onto the simulation results. The Monte Carlo simulations are carried out by using MCNP5 radiation transport code. All unsteady conditions are ignored, assuming the reactor operates at cold-zero power under the steady-state condition. For comparison, effective core multiplication factor (keff) and effective delayed neutron fraction (?eff) are computed. Reactivity worth ($) of control rods with rod position is presented. Pin power distribution within the fuel elements, axial power peaking distribution along the fuel length and normalized distribution of fast/thermal neutron flux throughout the core are analysed. The simulation results show that MCNP5 model of the reactor is properly established with sufficient detail in such a way that all simulation results are in an excellent agreement with the experimental data (or FSAR values). Results also show that the model yields more or less the same value even different neutron libraries are used.

Mehmet Trkmen; ner olak

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

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

SciTech Connect (OSTI)

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

102

Experience with the operation, maintenance and utilisation of the 3 MW TRIGA Mark-II research reactor of Bangladesh  

Science Journals Connector (OSTI)

The 3 MW TRIGA (Training, Research, Isotope, General Atomics) Mark-II research reactor of the Bangladesh Atomic Energy Commission (BAEC) has been operating at Atomic Energy Research Establishment (AERE), Savar, Dhaka, since September 1986. Since its commissioning, the reactor has been used in various fields of research and utilisation, such as Neutron Activation Analysis (NAA), Neutron Radiography (NRG), Neutron Scattering (NS), manpower training and education, and production of radioisotopes for medical applications. The reactor facility encountered a couple of incidents, which were successfully handled by BAEC personnel. In some cases, the help of experts from various local organisations/institutions as well as from the International Atomic Energy Agency (IAEA) was obtained. The upgrading of the Safety Analysis Report (SAR) of the reactor facility was completed in 2005 as per the format of the IAEA Safety Guide, SG-35-G1. The cooling system of the reactor as well as some parts of the instrumentations used in the reactor systems were also upgraded/modified during this period. The paper highlights the experience with the operation, maintenance and utilisation of the research reactor for the last 21 years. It also presents some of the modification and upgrading works carried out to enhance the operational safety of the research reactor.

M.A. Zulquarnain; M.M. Haque; M.A. Salam; M.S. Islam; P.K. Saha; M.A. Sarder; A. Haque; M.A.M. Soner; M.M. Uddin; M.M. Rahman; I. Kamal; M.N. Islam; S.M. Hossain

2009-01-01T23:59:59.000Z

103

Strategic Plan for Light Water Reactor Research and Development  

SciTech Connect (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

104

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

SciTech Connect (OSTI)

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 Universitys 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 Users 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. Users 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

105

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

SciTech Connect (OSTI)

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

106

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

107

IAEA coordinated research project on thermal-hydraulics of Supercritical Water-Cooled Reactors (SCWRs)  

SciTech Connect (OSTI)

The Supercritical Water-Cooled Reactor (SCWR) is an innovative water-cooled reactor concept, which uses supercritical pressure water as reactor coolant. It has been attracting interest of many researchers in various countries mainly due to its benefits of high thermal efficiency and simple primary systems, resulting in low capital cost. The IAEA started in 2008 a Coordinated Research Project (CRP) on Thermal-Hydraulics of SCWRs as a forum to foster the exchange of technical information and international collaboration in research and development. This paper summarizes the activities and current status of the CRP, as well as major progress achieved to date. At present, 15 institutions closely collaborate in several tasks. Some organizations have been conducting thermal-hydraulics experiments and analysing the data, and others have been participating in code-to-test and/or code-to-code benchmark exercises. The expected outputs of the CRP are also discussed. Finally, the paper introduces several IAEA activities relating to or arising from the CRP. (authors)

Yamada, K. [Vienna International Centre, P.O. Box 100, 1400 Vienna (Austria); Aksan, S. N. [International Atomic Energy Agency, 1400 Vienna (Austria)

2012-07-01T23:59:59.000Z

108

Revised ROD for FEIS on Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel (  

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

720 720 Federal Register / Vol. 61, No. 144 / Thursday, July 25, 1996 / Notices 1995 (44 U. S. C. Chapter 35) requires that the Office of Management and Budget (OMB) provide interested Federal agencies and the public an early opportunity to comment on information collection requests. OMB may amend or waive the requirement for public consultation to the extent that public participation in the approval process would defeat the purpose of the information collection, violate State or Federal law, or substantially interfere with any agency's ability to perform its statutory obligations. The Director of the Information Resources Group publishes this notice containing proposed information collection requests prior to submission of these requests to OMB. Each proposed information collection,

109

The EU Foreign Policy.  

E-Print Network [OSTI]

?? This dissertations aims to examine the EU Foreign Policy, and more precisely map the High Representative (HR) and his impact on the Common Foreign (more)

Petersson, Emmy

2007-01-01T23:59:59.000Z

110

The RERTR (Reduced Enrichment Research and Test Reactor) program: A progress report  

SciTech Connect (OSTI)

The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1985, the activities, results, and new developments which occurred in 1986 are reviewed. The second miniplate series, concentrating on U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al fuels, was expanded and its irradiation continued. Postirradiation examinations of several of these miniplates and of six previously irradiated U/sub 3/Si/sub 2/-Al full-size elements were completed with excellent results. The whole-core ORR demonstration with U/sub 3/Si/sub 2/-Al fuel at 4.8 g U/cm/sup 3/ is well under way and due for completion before the end of 1987. DOE removed an important barrier to conversions by announcing that the new LEU fuels will be accepted for reprocessing. New DOE prices for enrichment and reprocessing services were calculated to have minimal effect on HEU reactors, and to reduce by about 8 to 10% the total fuel cycle costs of LEU reactors. New program activities include preliminary feasibility studies of LEU use in DOE reactors, evaluation of the feasibility to use LEU targets for the production of fission-product /sup 99/Mo, and responsibility for coordinating safety evaluations related to LEU conversions of US university reactors, as required by NRC. Achievement of the final program goals is projected for 1990. This progress could not have been achieved without close international cooperation, whose continuation and intensification are essential to the achievement of the ultimate goals of the RERTR Program.

Travelli, A.

1986-11-01T23:59:59.000Z

111

2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting  

SciTech Connect (OSTI)

The Meeting papers discuss research and test reactor fuel performance, manufacturing and testing. Some of the main topics are: conversion from HEU to LEU in different reactors and corresponding problems and activities; flux performance and core lifetime analysis with HEU and LEU fuels; physics and safety characteristics; measurement of gamma field parameters in core with LEU fuel; nondestructive analysis of RERTR fuel; thermal hydraulic analysis; fuel interactions; transient analyses and thermal hydraulics for HEU and LEU cores; microstructure research reactor fuels; post irradiation analysis and performance; computer codes and other related problems.

NONE

2008-07-15T23:59:59.000Z

112

Research and Development Roadmaps for Nondestructive Evaluation of Cables, Concrete, Reactor Pressure Vessels, and Piping Fatique  

SciTech Connect (OSTI)

To address these research needs, the MAaD Pathway supported a series of workshops in the summer of 2012 for the purpose of developing R&D roadmaps for enhancing the use of Nondestructive Evaluation (NDE) technologies and methodologies for detecting aging and degradation of materials and predicting the remaining useful life. The workshops were conducted to assess requirements and technical gaps related to applications of NDE for cables, concrete, reactor pressure vessels (RPV), and piping fatigue for extended reactor life. An overview of the outcomes of the workshops is presented here. Details of the workshop outcomes and proposed R&D also are available in the R&D roadmap documents cited in the bibliography and are available on the LWRS Program website (http://www.inl.gov/lwrs).

Clayton, Dwight A [ORNL] [ORNL; Bakhtiari, Sasan [Argonne National Laboratory (ANL)] [Argonne National Laboratory (ANL); Smith, Cyrus M [ORNL] [ORNL; Simmons, Kevin [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Coble, Jamie [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Brenchley, David [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Meyer, Ryan [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL)

2013-01-01T23:59:59.000Z

113

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

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

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

114

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

SciTech Connect (OSTI)

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

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

115

International Atomic Energy Agency support of research reactor highly enriched uranium to low enriched uranium fuel conversion projects  

SciTech Connect (OSTI)

The IAEA has been involved for more than twenty years in supporting international nuclear non- proliferation efforts associated with reducing the amount of highly enriched uranium (HEU) in international commerce. IAEA projects and activities have directly supported the Reduced Enrichment for Research and Test Reactors (RERTR) programme, as well as directly assisted efforts to convert research reactors from HEU to LEU fuel. HEU to LEU fuel conversion projects differ significantly depending on several factors including the design of the reactor and fuel, technical needs of the member state, local nuclear infrastructure, and available resources. To support such diverse endeavours, the IAEA tailors each project to address the relevant constraints. This paper presents the different approaches taken by the IAEA to address the diverse challenges involved in research reactor HEU to LEU fuel conversion projects. Examples of conversion related projects in different Member States are fully detailed. (author)

Bradley, E.; Adelfang, P.; Goldman, I.N. [Research Reactors Unit, Division of Nuclear Fuel Cycle and Waste Technology, International Atomic Energy Agency, Wagramer Strasse 5, P.O. Box 100, A-1400 Vienna (Austria)

2008-07-15T23:59:59.000Z

116

Current status of the development of high density LEU fuel for Russian research reactors  

SciTech Connect (OSTI)

One of the main directions of the Russian RERTR program is to develop U-Mo fuel and fuel elements/FA with this fuel. The development is carried out both for existing reactors, and for new advanced designs of reactors. Many organizations in Russia, i.e. 'TVEL', RDIPE, RIAR, IRM, NPCC participate in the work. Two fuels are under development: dispersion and monolithic U-Mo fuel, as well two types of FA to use the dispersion U-Mo fuel: with tubular type fuel elements and with pin type fuel elements. The first stage of works was successfully completed. This stage included out-pile, in-pile and post irradiation examinations of U-Mo dispersion fuel in experimental tubular and pin fuel elements under parameters similar to operation conditions of Russian design pool-type research reactors. The results received both in Russia and abroad enabled to go on to the next stage of development which includes irradiation tests both of full-scale IRT pin-type and tube-type fuel assemblies with U-Mo dispersion fuel and of mini-fuel elements with modified U-Mo dispersion fuel and monolithic fuel. The paper gives a generalized review of the results of U-Mo fuel development accomplished by now. (author)

Vatulin, A.; Dobrikova, I.; Suprun, V.; Trifonov, Y. [Federal State Unitary Enterprise, A.A. Bochvar All-Russian Scientific Research Institute of Inorganic Materials (VNIINM), 123060 Rogov 5a, Moscow (Russian Federation); Kartashev, E.; Lukichev, V. [Federal State Unitary Enterprise RDIPE, 101000 P.O. Box 788, Moscow (Russian Federation)

2008-07-15T23:59:59.000Z

117

Performance characteristics of the annular core research reactor fuel motion detection system  

SciTech Connect (OSTI)

Recent proof tests have shown that the annular core research reactor (ACRR) fuel motion detection system has reached its design goals of providing high temporal and spatial resolution pictures of fuel distributions in the ACRR. The coded aperture imaging system (CAIS) images the fuel by monitoring the fission gamma rays from the fuel that pass through collimators in the reactor core. The gamma-ray beam is modulated by coded apertures before producing a visible light coded image in thin scintillators. Each coded image is then amplified and recorded by an opticalimage-intensifier/fast-framing-camera combination. The proximity to the core and the coded aperture technique provide a high data collection rate and high resolution. Experiments of CAIS at the ACRR conducted under steady-state operation have documented the beneficial effects of changes in the radiation shielding and imaging technique. The spatial resolutions are 1.7 mm perpendicular to the axis of a single liquid-metal fast breeder reactor fuel pin and 9 mm in the axial dimension. Changes in mass of 100 mg in each resolution element can be detected each frame period, which may be from 5 to 100 ms. This diagnostic instrument may help resolve important questions in fuel motion phenomenology.

Kelly, J.G.; Stalker, K.T.

1983-12-01T23:59:59.000Z

118

RAMI Analysis Program Design and Research for CFETR (Chinese Fusion Engineering Testing Reactor) Tokamak Machine  

Science Journals Connector (OSTI)

Chinese Fusion Engineering Testing Reactor (CFETR) is a test reactor which shall be constructed by National Integration Design Group for Magnetic Confinement Fusion Reactor of China with an ambitious scientific ...

Shijun Qin; Yuntao Song; Damao Yao; Yuanxi Wan; Songtao Wu

2014-10-01T23:59:59.000Z

119

Progress of the RERTR (Reduced Enrichment Research and Test Reactor) Program in 1989  

SciTech Connect (OSTI)

The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1988, the major events, findings, and activities of 1989 are reviewed. The scope of the RERTR Program activities was curtailed, in 1989, by an unexpected legislative restriction which limited the ability of the Arms Control and Disarmament Agency to adequately fund the program. Nevertheless, the thrust of the major planned program activities was maintained, and meaningful results were obtained in several areas of great significance for future work. 15 refs., 12 figs.

Travelli, A.

1989-01-01T23:59:59.000Z

120

Foreign Direct Investment  

Gasoline and Diesel Fuel Update (EIA)

Investment Investment Foreign Direct Investment Foreign Direct Investment Foreign Direct Investment in U.S. Energy in U.S. Energy in U.S. Energy in U.S. Energy in 1999 in 1999 in 1999 in 1999 June 2001 ii iii Contents Foreign Affiliates' Role in U.S. Energy Industry Operations ..............................................................................1 Foreign Direct Investment: The International Transactions Accounts ..............................................................8 U.S. Companies' Direct Investment Abroad in Energy ......................................................................................14 Conclusion...............................................................................................................................................................19

Note: This page contains sample records for the topic "foreign 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

E-Print Network 3.0 - advanced reactor research Sample Search...  

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

to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be built at Cadarache, near the...

122

E-Print Network 3.0 - advanced research reactor Sample Search...  

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

to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be built at Cadarache, near the...

123

E-Print Network 3.0 - austrian research reactor Sample Search...  

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

to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be built at Cadarache, near the...

124

E-Print Network 3.0 - anuclear research reactor Sample Search...  

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

to build the world's most advanced nuclear fusion reactor... ) International Thermonuclear Experimental Reactor (ITER), which will be built at Cadarache, near the...

125

Status of the RERTR (Reduced Enrichment Research and Test Reactor) Program  

SciTech Connect (OSTI)

The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1987, the major events, findings and activities of 1988 are reviewed. The US Nuclear Regulatory Commission issued a formal and generic approval of the use of U3Si2-Al dispersion fuel in research and test reactors, with densities up to 4.8 g U/cmT. New significant findings from postirradiation examinations, from ion-beam irradiations, and from analytical modeling, have raised serious doubts about the potential of LEU U3Si-Al dispersion fuel for applications requiring very high uranium densities and high burnups (>6 g U/cmT, >50% burnup). As a result of these findings, the fuel development efforts have been redirected towards three new initiatives: (1) a systematic application of ion-beam irradiations to screen new materials; (2) application of Hot Isostatic Pressing (HIP) procedures to produce U3Si2-Al plates with high uranium densities and thin uniform cladding; and (3) application of HIP procedures to produce plates with U3Si wires imbedded in an aluminum matrix, achieving stability, high uranium density, and thin uniform cladding. The new fuel concepts hold the promise of extraordinary performance potential and require approximately five years to develop.

Travelli, A.

1988-01-01T23:59:59.000Z

126

The RERTR (Reduced Enrichment Research and Test Reactor) Program: Progress and plans  

SciTech Connect (OSTI)

The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1986, the activities, results, and new developments which occurred in 1987 are reviewed. Irradiation of the second miniplate series, concentrating on U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al fuels, was completed and postirradiation examinations were performed on many of its miniplates. The whole-core ORR demonstration with U/sub 3/Si/sub 2/-Al fuel at 4.8 g U/cm/sup 3/ was completed at the end of March with excellent results and with 29 elements estimated to have reached at least 40% average burnup. Good progress was made in the area of LEU usage for the production of fission /sup 99/Mo, and in the coordination of safety evaluations related to LEU conversions of US university reactors. Planned activities include testing and demonstrating advanced fuels intended to allow use of reduced enrichment uranium in very-high-performance reactors. Two candidate fuels are U/sub 3/Si-Al with 19.75% enrichment and U/sub 3/Si/sub 2/-Al with 45% enrichment. Demonstration of these fuels will include irradiation of full-size elements and, possibly, a full-core demonstration. Achievement of the final program goals is still projected for 1990. This progress could not have been possible without the close international cooperation which has existed from the beginning, and which is essential to the ultimate success of the RERTR Program.

Travelli, A.

1987-01-01T23:59:59.000Z

127

LOSS-OF-COOLANT ACIDENT SIMULATIONS IN THE NATIONAL RESEARCH UNIVERSAL REACTOR  

SciTech Connect (OSTI)

Pressurized water reactor loss-of-coolant accident (LOCA) 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 among the reflood delay time of emergency coolant, the reflooding rate, and the resultant fuel rod cladding peak temperature. Subsequent experiments establish the fuel rod failure characteristics at selected peak cladding temperatures. Fuel rod cladding pressurization simulates high burnup fission gas pressure levels of modern PWRs. This document contains both an experiment overview of the LOCA simulation program and a review of the safety analyses performed by Pacific Northwest Laboratory (PNL) to define the expected operating conditions as well as to evaluate the worst case operating conditions. The primary intent of this document is to supply safety information required by the Chalk River Nuclear Laboratories (CRNL), to establish readiness to proceed from one test phase to the next and to establish the overall safety of the experiment. A hazards review summarizes safety issues, normal operation and three worst case accidents that have been addressed during the development of the experiment plan.

Bennett, W D; Goodman, R L; Heaberlin, S W; Hesson, G M; Nealley, C; Kirg, L L; Marshall, R K; McNair, G W; Meitzler, W D; Neally, G W; Parchen, L J; Pilger, J P; Rausch, W N; Russcher, G E; Schreiber, R E; Wildung, N J

1981-02-01T23:59:59.000Z

128

Foreign Deities in Egypt  

E-Print Network [OSTI]

fig. 211. ) Foreign Deities in Egypt, Zivie-Coche, UEE 2011god Hauron and his cult in Egypt. Gttinger Miszellen 107,2011, Foreign Deities in Egypt. UEE. Full Citation: Zivie-

Zivie-Coche, Christiane

2011-01-01T23:59:59.000Z

129

NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669  

SciTech Connect (OSTI)

The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

Not Available

1992-08-01T23:59:59.000Z

130

Foreign Tax Credit  

Science Journals Connector (OSTI)

Income taxes paid to a foreign country that can be claimed as a tax credit against a domestic tax liability.

2006-01-01T23:59:59.000Z

131

A computer model for the transient analysis of compact research reactors with plate type fuel  

SciTech Connect (OSTI)

A coupled neutronics and core thermal-hydraulic performance model has been developed for the analysis of plate type U-Al fueled high-flux research reactor transients. The model includes point neutron kinetics, one-dimensional, non-homogeneous, equilibrium two-phase flow and beat transfer with provision for subcooled boiling, and spatially averaged one-dimensional beat conduction. The feedback from core regions other than the fuel elements is included by employing a lumped parameter approach. Partial differential equations are discretized in space and the combined equation set representing the model is converted to an initial value problem. A variable-order, variable-time-step time advancement scheme is used to solve these ordinary differential equations. The model is verified through comparisons with two other computer code results and partially validated against SPERT-II tests. It is also used to analyze a series of HFIR reactivity transients.

Sofu, T. [Argonne National Lab., IL (United States); Dodds, H.L. [Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering

1994-03-01T23:59:59.000Z

132

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

SciTech Connect (OSTI)

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 licensees 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

133

THE EFFECT OF INCREASING TRANSPORTATION COST ON FOREIGN DIRECT INVESTMENT.  

E-Print Network [OSTI]

THE EFFECT OF INCREASING TRANSPORTATION COST ON FOREIGN DIRECT INVESTMENT Major: Maritime Administration April 2009 Submitted to the Office of Undergraduate Research Texas A&M University in partial fulfillment... of the requirements for the designation as UNDERGRADUATE RESEARCH SCHOLAR A Senior Scholars Thesis by KIMBERLY GRESSLER THE EFFECT OF INCREASING TRANSPORTATION COST ON FOREIGN DIRECT INVESTMENT Approved by: Research Advisor: Joan Mileski...

Gressler, Kimberly

2009-06-09T23:59:59.000Z

134

Methods of estimating the reliability of nuclear reactor installations  

Science Journals Connector (OSTI)

Domestic and foreign experience indicate that quantitative analysis of the reliability of reactor systems during their development is a rather effective means of increasing their reliability.

I. Ya. Emel'yanov; A. I. Klemin; E. F. Polyakov

1974-11-01T23:59:59.000Z

135

Hydro-mechanical analysis of low enriched uranium fuel plates for University of Missouri Research Reactor .  

E-Print Network [OSTI]

??As part of the Global Threat Reduction Initiative (GTRI) Reactor Conversion program, work is underway to analyze and validate a new fuel assembly for the (more)

Kennedy, John C.

2012-01-01T23:59:59.000Z

136

Development of a core design optimization tool and analysis in support of the planned LEU conversion of the MIT Research Reactor (MITR-II) ; Development of a core design optimization tool and analysis in support of the planned low enriched uranium 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 (more)

Connaway, Heather M. (Heather Moira)

2012-01-01T23:59:59.000Z

138

FOREIGN INVESTMENT: Barriers Remain  

Science Journals Connector (OSTI)

FOREIGN INVESTMENT: Barriers Remain ... The two-volume work, titled "Obstacles and Incentives to Private Foreign Investment 1967-68," shows that barriers to private foreign investment around the world haven't really changed much overall in recent years although there have been some dramatic changes in the investment climate of a few individual nations. ... Comparison with an earlier NICB study covering 1962 to 1964 shows that economic problems are now considered a barrier to foreign investment in a greater number of countries than in the earlier period. ...

1969-09-22T23:59:59.000Z

139

Official Foreign Travel  

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

The order establishes requirements and responsibilities governing official foreign travel by Federal and contractor employees. Cancels DOE O 551.1C.

2012-04-12T23:59:59.000Z

140

Status of the RERTR program: overview, progress and plans. [Reduced Enrighment Research and Test Reactor  

SciTech Connect (OSTI)

The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a summary of the accomplishments which the RERTR Program had achieved by the end of 1984 with its many international partners, emphasis is placed on the progress achieved during 1985 and on current plans and schedules. A new miniplate series, concentrating on U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al fuels, was fabricated and is well into irradiation. The whole-core ORR demonstration is scheduled to begin in November 1985, with U/sub 3/Si/sub 2/-Al fuel at 4.8 g U/cm/sup 3/. Altogether, 921 full-size test and prototype elements have been ordered for fabrication with reduced enrichment and the new technologies. Qualification of U/sub 3/Si-Al fuel with approx.7 g U/cm/sup 3/ is still projected for 1989. This progress could not have been achieved without the close international cooperation which has existed since the beginning, and whose continuation and intensification will be essential to the achievement of the long-term RERTR goals.

Travelli, A.

1985-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

Novel, Magnetically Fluidized-Bed Reactor Development for the Looping Process: Coal to Hydrogen Production Research and Development  

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

142

Research and Development of High Temperature Light Water Cooled Reactor Operating at Supercritical-Pressure in Japan  

SciTech Connect (OSTI)

This paper summarizes the status and future plans of research and development of the high temperature light water cooled reactor operating at supercritical-pressure in Japan. It includes; the concept development; material for the fuel cladding; water chemistry under supercritical pressure; thermal hydraulics of supercritical fluid; and the conceptual design of core and plant system. Elements of concept development of the once-through coolant cycle reactor are described, which consists of fuel, core, reactor and plant system, stability and safety. Material studies include corrosion tests with supercritical water loops and simulated irradiation tests using a high-energy transmission electron microscope. Possibilities of oxide dispersion strengthening steels for the cladding material are studied. The water chemistry research includes radiolysis and kinetics of supercritical pressure water, influence of radiolysis and radiation damage on corrosion and behavior on the interface between water and material. The thermal hydraulic research includes heat transfer tests of single tube, single rod and three-rod bundles with a supercritical Freon loop and numerical simulations. The conceptual designs include core design with a three-dimensional core simulator and sub-channel analysis, and balance of plant. (authors)

Yoshiaki Oka [Nuclear Engineering Research Laboratory, The University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, Tokyo, 112-0006 (Japan); Katsumi Yamada [Isogo Nuclear Engineering Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan)

2004-07-01T23:59:59.000Z

143

When Do Commercial Reactors Permanently Shut Down?  

Reports and Publications (EIA)

For those wishing to obtain current data, the following resources are available: U.S. reactors, go to the Energy Information Administration's nuclear reactor shutdown list. (Note: As of April 30, 2010, the last U.S. reactor to permanently shut down was Big Rock Point in 1997.) Foreign Reactors, go to the Power Reactor Information System (PRIS) on the International Atomic Energy Agency's website.

2011-01-01T23:59:59.000Z

144

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

145

Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program  

E-Print Network [OSTI]

Simulations for two series of anticipated transients phics. without scram (ATWS) events have been carried out for a small, hypothetical, research reactor based on the High Flux Australian Reador HIFAR using the RELAPS/MOD3.Z computer program...

Hari, Sridhar

1998-01-01T23:59:59.000Z

146

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

147

Status of axial heterogeneous liquid-metal fast breeder reactor core design studies and research and development  

SciTech Connect (OSTI)

The current status of axial heterogeneous core (AHC) design development in Japan, which consists of an AHC core design in a pool-type demonstration fast breeder reactor (DFBR) and research and development activities supporting AHC core design, is presented. The DFBR core design objectives developed by The Japan Atomic Power Company include (a) favorable core seismic response, (b) core compactness, (c) high availability, and (d) lower fuel cycle cost. The AHC concept was selected as a reference pool-type DFBR core because it met these objectives more suitably than the homogeneous core (HOC). The AHC core layouts were optimized emphasizing the reduction of the burnup reactivity swing, peak fast fluence, and power peaking. The key performance parameters resulting from the AHC, such as flat axial power/flux distribution, lower peak fast fluence, lower burnup reactivity swing, etc., were evaluated in comparison with the HOC. The critical experiments at the Japan Atomic Energy Research Institute's Fast Critical Assembly facility demonstrate the key AHC performance characteristics. The large AHC engineering benchmark experiments using the zero-power plutonium reactor and the AHC fuel pin irradiation test program using the JOYO reactor are also presented.

Nakagawa, H.; Inagaki, T.; Yoshimi, H.; Shirakata, K.; Watari, Y.; Suzuki, M.; Inoue, K.

1988-11-01T23:59:59.000Z

148

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

SciTech Connect (OSTI)

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

149

Official Foreign Travel  

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

To establish Department of Energy (DOE) and National Nuclear Security Administration (NNSA) requirements and responsibilities governing official foreign travel by Federal and contractor employees. Cancels DOE O 551.1A. Canceled by DOE O 551.1C.

2003-08-19T23:59:59.000Z

150

JAPAN LIBERALIZES FOREIGN INVESTMENT  

Science Journals Connector (OSTI)

JAPAN LIBERALIZES FOREIGN INVESTMENT ... The list adds 155 business categories to the 50 designated for freeing and partial freeing almost two years ago in Japan's first-round liberalization (C&EN, July 24, 1967, page 24). ...

1969-02-17T23:59:59.000Z

151

Light Water Reactors Technology Development - Nuclear Reactors  

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

Light Water Reactors Light Water Reactors 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 Argonne's Nuclear Science and Technology Legacy

152

DOE Drops Plan to Restart Reactor  

Science Journals Connector (OSTI)

...longer in flux. Hanford research reactor...decision to scrap the Hanford reactor, which...research. At public meetings, however...decision to scrap the Hanford reactor, which...research. At public meetings, however, FFTF...

Robert F. Service

2000-12-01T23:59:59.000Z

153

Examples of the use of PSA in the design process and to support modifications at two research reactors  

SciTech Connect (OSTI)

Many, if not most, of the world`s commercial nuclear power plants have been the subject of plant-specific probabilistic safety assessments (PSA). A growing number of other nuclear facilities as well as other types of industrial installations have been the focus of plant-specific PSAs. Such studies have provided valuable information concerning the nature of the risk of the individual facility and have been used to identify opportunities to manage that risk. This paper explores the risk management activities associated with two research reactors in the United States as a demonstration of the versatility of the use of PSA to support risk-related decision making.

Johnson, D.H.; Bley, D.C.; Lin, J.C. [PLG, Inc., Newport Beach, CA (United States); Ramsey, C.T.; Linn, M.A. [Oak Ridge National Lab., TN (United States)

1994-03-01T23:59:59.000Z

154

The Argonaut Reactor - Reactors designed/built by Argonne National  

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

Achievements > Achievements > Argonne Reactors > Training Reactors 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

155

Foreign Fishery Developments Abalone Culture in Japan  

E-Print Network [OSTI]

Foreign Fishery Developments Abalone Culture in Japan Adam G. C. Body Introduction Abalone, known as awabe in Japan, is a popular and traditional food maintain ing a good, consistent market value. Up transplanted from areas of high spatfall, aquaculture research centers were set up in each of Japan's 37

156

Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters  

SciTech Connect (OSTI)

Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies.

Konzek, G.J.

1983-07-01T23:59:59.000Z

157

Experimental evaluation of gamma fluence-rate predictions from Argon-41 releases to the atmosphere over a nuclear research reactor site  

Science Journals Connector (OSTI)

......radiation experimental dataset has been subsequently...reactor at the Belgium Nuclear Research Center...measurements. The dataset obtained may also...3, 4) used for nuclear emergency preparedness...radiation experimental dataset has been subsequently...RIMPUFF. | Belgian Nuclear Research Center......

Carlos Rojas-Palma; Helle Karina Aage; Poul Astrup; Kim Bargholz; Martin Drews; Hans E. Jrgensen; Uffe Korsbech; Bent Lauritzen; Torben Mikkelsen; Sren Thykier-Nielsen; Raf Van Ammel

2004-01-01T23:59:59.000Z

158

Report of the ANS Project Feasibility Workshop for a High Flux Isotope Reactor-Center for Neutron Research Facility  

SciTech Connect (OSTI)

The Advanced Neutron Source (ANS) Conceptual Design Report (CDR) and its subsequent updates provided definitive design, cost, and schedule estimates for the entire ANS Project. A recent update to this estimate of the total project cost for this facility was $2.9 billion, as specified in the FY 1996 Congressional data sheet, reflecting a line-item start in FY 1995. In December 1994, ANS management decided to prepare a significantly lower-cost option for a research facility based on ANS which could be considered during FY 1997 budget deliberations if DOE or Congressional planners wished. A cost reduction for ANS of about $1 billion was desired for this new option. It was decided that such a cost reduction could be achieved only by a significant reduction in the ANS research scope and by maximum, cost-effective use of existing High Flux Isotope Reactor (HFIR) and ORNL facilities to minimize the need for new buildings. However, two central missions of the ANS -- neutron scattering research and isotope production-were to be retained. The title selected for this new option was High Flux Isotope Reactor-Center for Neutron Research (HFIR-CNR) because of the project`s maximum use of existing HFIR facilities and retention of selected, central ANS missions. Assuming this shared-facility requirement would necessitate construction work near HFIR, it was specified that HFIR-CNR construction should not disrupt normal operation of HFIR. Additional objectives of the study were that it be highly credible and that any material that might be needed for US Department of Energy (DOE) and Congressional deliberations be produced quickly using minimum project resources. This requirement made it necessary to rely heavily on the ANS design, cost, and schedule baselines. A workshop methodology was selected because assessment of each cost and/or scope-reduction idea required nearly continuous communication among project personnel to ensure that all ramifications of propsed changes.

Peretz, F.J.; Booth, R.S. [comp.

1995-07-01T23:59:59.000Z

159

Revision to the Record of Decision for the Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel (DOE/EIS-218) (7/19/00)  

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

767 767 Federal Register / Vol. 65, No. 139 / Wednesday, July 19, 2000 / Notices The office is located in the Pentagon which is guarded. RETENTION AND DISPOSAL: Records are kept until the person is deceased or the person seeks removal of information, whichever is sooner. SYSTEM MANAGER(S) AND ADDRESS: Chief of Naval Operations (N09BC), 2000 Navy Pentagon, Washington, DC 20350-2000. NOTIFICATION PROCEDURE: Individuals seeking to determine whether information about themselves is contained in this system should address written inquiries to the Chief of Naval Operations (N09BC), 2000 Navy Pentagon, Washington, DC 20350-2000. RECORD ACCESS PROCEDURES: Individuals seeking access to information about themselves contained in this system should address written inquiries to the Chief of Naval

160

Theoretical analysis of the subcritical experiments performed in the IPEN/MB-01 research reactor facility  

SciTech Connect (OSTI)

The theoretical analysis of the subcritical experiments performed at the IPEN/MB-01 reactor employing the coupled NJOY/AMPX-II/TORT systems was successfully accomplished. All the analysis was performed employing ENDF/B-VII.0. The theoretical approach follows all the steps of the subcritical model of Gandini and Salvatores. The theory/experiment comparison reveals that the calculated subcritical reactivity is in a very good agreement to the experimental values. The subcritical index ({xi}) shows some discrepancies although in this particular case some work still have to be made to model in a better way the neutron source present in the experiments. (authors)

Lee, S. M.; Dos Santos, A. [Inst. de Pesquisas Energeticas e Nucleares, Cidade Universitaria, Av. Lineu Prestes, 2242, 05508-000 Sao Paulo - SP (Brazil)

2012-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

Unclassified Foreign National Visits and Assignments at Oak Ridge National Laboratory  

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

Unclassified Foreign National Visits Unclassified Foreign National Visits and Assignments at Oak Ridge National Laboratory INS-O-13-05 September 2013 Department of Energy Washington, DC 20585 September 16, 2013 MEMORANDUM FOR THE MANAGER, OAK RIDGE NATIONAL LABORATORY SITE OFFICE FROM: Sandra D. Bruce Assistant Inspector General for Inspections Office of Inspector General SUBJECT: INFORMATION: Inspection Report on "Unclassified Foreign National Visits and Assignments at Oak Ridge National Laboratory" BACKGROUND In support of its research and development mission, the Department of Energy's national laboratories host thousands of foreign national visitors and assignees (foreign nationals) every year for research collaborations and access to scientific user facilities. During calendar year

162

US urged to keep labs open to foreigners  

Science Journals Connector (OSTI)

... that foreign companies that wanted to participate in a Co-operative Research and Development Agreement (CRADA) with the Department of Energy, or in the Commerce Department's Advanced Technology Program ...

Tony Reichhardt

1996-06-13T23:59:59.000Z

163

Calculational-experimental research models for a fast reactor with a heterogeneous core  

SciTech Connect (OSTI)

The physical characteristics of heterogeneous metallic oxide cores were experimentally studied by physical tests of the critical assemblies BFS-46 and BFS-46AZ, which simulate a reactor of the BN-1600 type, into the core of which a fuel assembly with metallic uranium is inserted. A calculational model for the critical assemblies being investigated, showing the zones and their dimensions, is presented. The critical assembly BFS-46AZ is a modification of the basic critical assembly BFS-46 which adds plutonium to the IBZ to simulate its accumulation during reactor operation. The BFS-46 and BFS-46AZ assemblies have identical dimensions for the IBZ and LEZ, and have different HEZ dimensions, necessary to ensure the criticality of each assembly. Plutonium with a /sup 240/Pu content equal to 3.8% is used in the LEZ. The critically parameters are calculated using one-dimensional and two-dimensional models in a 26-group diffusion approximation based on the BNAP-78 system of group constants.

Belov, S.P.; Bobrov, S.B.; Kazanskii, Yu.A.; Kuzin, E.N.; Matveev, V.I.; Novozhilov, A.I.; Chernyi, V.A.

1987-11-01T23:59:59.000Z

164

Irradiation research capabilities at HFIR (High Flux Isotope Reactor) and ANS (Advanced Neutron Source)  

SciTech Connect (OSTI)

A variety of materials irradiation facilities exist in the High Flux Isotope Reactor (HFIR) and are planned for the Advanced Neutron Source (ANS) reactor. In 1986 the HFIR Irradiation Facilities Improvement (HIFI) project began modifications to the HFIR which now permit the operation of two instrumented capsules in the target region and eight capsules of 46-mm OD in the RB region. Thus, it is now possible to perform instrumented irradiation experiments in the highest continuous flux of thermal neutrons available in the western world. The new RB facilities are now large enough to permit neutron spectral tailoring of experiments and the modified method of access to these facilities permit rotation of experiments thereby reducing fluence gradients in specimens. A summary of characteristics of irradiation facilities in HFIR is presented. The ANS is being designed to provide the highest thermal neutron flux for beam facilities in the world. Additional design goals include providing materials irradiation and transplutonium isotope production facilities as good, or better than, HFIR. The reference conceptual core design consists of two annular fuel elements positioned one above the other instead of concentrically as in the HFIR. A variety of materials irradiation facilities with unprecedented fluxes are being incorporated into the design of the ANS. These will include fast neutron irradiation facilities in the central hole of the upper fuel element, epithermal facilities surrounding the lower fuel element, and thermal facilities in the reflector tank. A summary of characteristics of irradiation facilities presently planned for the ANS is presented. 2 tabs.

Thoms, K.R.

1990-01-01T23:59:59.000Z

165

Greek research reactor performance characteristics after addition of beryllium reflector and LEU fuel  

SciTech Connect (OSTI)

The GRR-1 is a 5-MW pool-type, light-water-moderated and-cooled reactor fueled with MTR-type fuel elements. Recently received Be reflector blocks will soon be added to the core to add additional reactivity until fresh LEU fuel arrives. REBUS-3 xy fuel cycle analyses, using burnup dependent cross sections, were performed to assist in fuel management decisions for the water- and Be-reflected HEU nonequilibrium cores. Cross sections generated by EPRI-CELL have been benchmarked to identical VIM Monte Carlo models. The size of the Be-reflected LEU core has been reduced to 30 elements compared to 35 for the HEU water-reflected core, and an equilibrium cycle calculation has been performed.

Deen, J.R.; Snelgrove, J.L. [Argonne National Lab., IL (United States); Papastergiou, C. [National Center for Scientific Research, Athens (Greece)

1992-12-31T23:59:59.000Z

166

Greek research reactor performance characteristics after addition of beryllium reflector and LEU fuel  

SciTech Connect (OSTI)

The GRR-1 is a 5-MW pool-type, light-water-moderated and-cooled reactor fueled with MTR-type fuel elements. Recently received Be reflector blocks will soon be added to the core to add additional reactivity until fresh LEU fuel arrives. REBUS-3 xy fuel cycle analyses, using burnup dependent cross sections, were performed to assist in fuel management decisions for the water- and Be-reflected HEU nonequilibrium cores. Cross sections generated by EPRI-CELL have been benchmarked to identical VIM Monte Carlo models. The size of the Be-reflected LEU core has been reduced to 30 elements compared to 35 for the HEU water-reflected core, and an equilibrium cycle calculation has been performed.

Deen, J.R.; Snelgrove, J.L. (Argonne National Lab., IL (United States)); Papastergiou, C. (National Center for Scientific Research, Athens (Greece))

1992-01-01T23:59:59.000Z

167

Promoting the Reduction Reactivity of Ilmenite by Introducing Foreign Ions in Chemical Looping Combustion  

Science Journals Connector (OSTI)

Promoting the Reduction Reactivity of Ilmenite by Introducing Foreign Ions in Chemical Looping Combustion ... Industrial & Engineering Chemistry Research2014 53 (39), 15157-15166 ...

Jinhua Bao; Zhenshan Li; Ningsheng Cai

2013-04-15T23:59:59.000Z

168

Unclassified Foreign Visits and Assignments  

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

To define a program for unclassified foreign national access to Department of Energy sites, information, and technologies. This Order cancels DOE P 142.1, Unclassified Foreign Visits and Assignments, dated 7-14-99; DOE N 142.1, Unclassified Foreign Visits and Assignments, dated 7-14-99; Secretarial Memorandum Unclassified Foreign Visits and Assignments, dated 7-14-99; Memorandum from Francis S. Blake, Departmental Use of Foreign Access Central Tracking System, dated 11-05-01; Memorandum from Kyle E. McSlarrow, Interim Guidance for Implementation of the Department's Unclassified Foreign Visits and Assignments Program, dated 12-17-02; and Secretarial Memorandum, Policy Exclusion for Unclassified Foreign National's Access to Department of Energy Facilities in Urgent or Emergency Medical Situations, dated 4-10-01. Cancels: DOE P 142.1 and DOE N 142.1

2004-06-18T23:59:59.000Z

169

Foreign Direct Investment in U  

Gasoline and Diesel Fuel Update (EIA)

Foreign Direct Investment in U.S. Energy in 1998 Foreign Direct Investment in U.S. Energy in 1998 Foreign Direct Investment Foreign Direct Investment Foreign Direct Investment Foreign Direct Investment in U.S. Energy in U.S. Energy in U.S. Energy in U.S. Energy in 1998 in 1998 in 1998 in 1998 November 2000 Energy Information Administration/Foreign Direct Investment in U.S. Energy in 1998 Contacts This report was prepared in the Office of Energy Markets and End Use of the Energy Information Administration, U.S. Department of Energy, under the general direction of W. Calvin Kilgore. The project was directed by Mark E. Rodekohr, Director of the Energy Markets and Contingency Information Division (202) 586-1441, and Mary E. Northup, the Team Leader for Financial Analysis (202) 586-1383. Specific technical information concerning this

170

Groundwater Monitoring and Control Before Decommissioning of the Research Reactor VVR-S from Magurele-Bucharest  

SciTech Connect (OSTI)

The research reactor type VVR-S (tank type, water is cooler, moderator and reflector, thermal power- 2 MW, thermal energy- 9. 52 GW d) was put into service in July 1957 and, in December 1997 was shout down. In 2002, Romanian Government decided to put the research reactor in the permanent shut-down in order to start the decommissioning. This nuclear facility was used in nuclear research and radioisotope production for 40 years, without events, incidents or accidents. Within the same site, in the immediate vicinity of the research reactor, there are many other nuclear facilities: Radioactive Waste Treatment Plant, Tandem Van der Graaf heavy ions accelerator, Cyclotron, Industrial Irradiator, Radioisotope Production Center. The objectives of this work were dedicated on the water underground analyses described in the following context: - presentation of the approaches in planning the number of drillings, vertical soil profiles (characteristics, analyses, direction of the flow of underground water, uncertainties in measurements); - presentation of the instrumentation used in analyses of water, soil and vegetation samples - analyses and final conclusions on results of the measurements; - comparison of the results of measurements on underground water from drillings with the measurements results on samples from the town and the system of drinking water - supplied from the second level of underground water. According to the analysis, in general, no values higher than the Minimum Detectable Activity were detected in water samples (MDA) for Pb{sup 212}, Bi{sup 214}, Pb{sup 214}, Ac{sup 228}, but situated under values foreseen in drinking water. Distribution of Uranium As results of the Uranium determination, values higher than 0,004 mg/l (4 ppb) were detected, values that represent the average contents in the underground water. The higher values, 2-3 times higher than background, were detected in the water from the drillings F15, F12, F5, F13, drillings located between RWTP (Radioactive Waste Treatment Plant) - the 300 m{sup 3} tanks and the Spent Filters Storage (SFS). At south of this area, on the leaking direction of the underground water layer, in the drillings F1, F2, F3, F18 and at east, in F6, F7, the natural Uranium values are within the background for the underground-water. Distribution of Radon For the Radon determination with RAD 7 equipment, water samples were taken from the same piezo-metrical drilling, 2 or 4 times during of six months period, and then, the average contents were calculated, which varied between 0,35 - 2,1 Bq/l. The values higher than 1,1 -1,2 Bq/l were detected in the water taken from the drillings located in the northern part (F10, F11) and in the eastern part (F6, F8) of the Institute fences (around of the radioactive waste storage facilities). The concentrations of 0,3 - 0,5 Bq/l are in the underground-water layer 'intercepted' by the piezo-metrical drillings (F1, F2, F3) located near the Nuclear Reactor. Concentration of heavy metals: 0.04-0.08 mg/l Pb in F5, F14, F7, F8 exceeding MCA-Maximum Admissible Concentration (0.01 mg/l) for Pb, and for Zn in F5, F7, F8, F14 are 0.2-0.5 mg/l situated under MCA , and 0.18 mg/l in F18, in accordance with tendency of decreasing of concentration of contaminants. After 50 years of deploying nuclear activities on the site the underground water quality is in very good condition. Taking into consideration the direction of the underground water flow, it results that, only in the area of underground pipe, around of the research reactor and radioactive waste treatment plant, the quality of water is influenced, and remediation actions are not necessary. Based on measurements executed in F18, the water quality is the same with any other part of the region. During the decommissioning of the Research Reactor, the samples from 18 drillings will be analysed monthly, and the contents of the heavy metals, Pb and Zn, will be monitored carefully, together with all the factors: air, soil, vegetation, subsoil, water surface and underground water. A great attention will be paid t

Dragusin, Mitica [National Institute of Physics and Nuclear Engineering-Horia Hulubei - IFIN-HH, Bucharest-Magurele, Romania, POBox MG-6, 077125, Ilfov (Romania)

2008-01-15T23:59:59.000Z

171

Advanced Test Reactor Tour  

SciTech Connect (OSTI)

The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

Miley, Don

2011-01-01T23:59:59.000Z

172

Advanced Test Reactor Tour  

ScienceCinema (OSTI)

The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

Miley, Don

2013-05-28T23:59:59.000Z

173

Nuclear reactors built, being built, or planned 1992  

SciTech Connect (OSTI)

Nuclear Reactors Built, Being Built, or Planned contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1992. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE from the US Nuclear Regulatory Commission (NRC); from the US reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from US and foreign embassies; and from foreign governmental nuclear departments. Information is presented on five parts: Civilian, Production, Military, Export and Critical Assembly.

Not Available

1993-07-01T23:59:59.000Z

174

Benchmark calculations for a heavy water research reactor using the WIMS-D4M code and a ENDF/B-V based library  

SciTech Connect (OSTI)

The results of unit-cell and global diffusion and transport calculations performed for the Georgia Tech heavy water research reactor using the WIMS-D4m code and a new ENDF/B-V based library are presented in this paper. Key cross sections, eigenvalues, neutron fluxes and peak power densities obtained from global diffusion calculations are compared.

Mo, S.C.

1993-12-31T23:59:59.000Z

175

Functional reliability evaluation of an MTR-pool type research reactor core using the loadcapacity interference model  

Science Journals Connector (OSTI)

Abstract This paper presents the functional reliability evaluation of Tehran Research Reactor (TRR) core in normal operation. The concept of functional reliability, borrowed from reliability physics, uses the well-known resistancestress or loadcapacity interference model that is used in the structural reliability framework. To use the loadcapacity interference model, uncertainties of significant parameters in system performance are propagated into system dynamics modeled with RELAP5/Mod 3.2 using Latin Hypercube Sampling (LHS) method and exceedance probability (EP) model is used as quantification method. The proposed method in this paper solves a common problem in reliability analysis, i.e., lack of sufficient failure data in specific operating conditions. Although defining failure criteria in normal operation are difficult, this paper focuses on the application of multiple states criteria to determine the status of a system. The status of the reactor core in normal operation is considered multiple states regarding to a performance representative parameter that is temperature in this work. Outlet temperatures of fuel hot and average channels were selected to be performance indicators in normal operation. Consulting with TRR engineers and operators as well as safety analysis report, two failure states were considered exceeding 65.1C and 58.9C for the hot channel and 50.4C and 45.6C for the average channel as upper and lower limits respectively. The calculated reliability was 9.1e?01 with 95% of confidence interval, which is in good agreement with experimental results. Using sensitivity analysis in input parameters, it was concluded that the value of the heat transfer coefficient parameter in fuel has the most significant effect on the results.

Ramin Barati; Saeed Setayeshi

2013-01-01T23:59:59.000Z

176

Nuclear Reactor (atomic reactor)  

Science Journals Connector (OSTI)

A nuclear reactor splits Uranium or Plutonium nuclei, and the...235 is fissionable but more than 99% of the naturally occurring Uranium is U238 that makes enrichment mandatory. In some reactors U238 and Thorium23...

2008-01-01T23:59:59.000Z

177

Nuclear Fission Reactor Safety Research in FP7 and future perspectives  

E-Print Network [OSTI]

The European Union (?U) has defined in the Europe 2020 strategy and 2050 Energy Roadmap its long-term vision for establishing a secure, sustainable and competitive energy system and setting up legally binding targets by 2020 for reducing greenhouse emissions, by increasing energy efficiency and the share of renewable energy sources while including a significant share from nuclear fission. Nuclear energy can enable the further reduction in harmful emissions and can contribute to the EUs competitive energy system, security of supply and independence from fossil fuels. Nuclear fission is a valuable option for those 14 EU countries that promote its use as part of their national energy mix. The European Group on Ethics in Science and New Technologies (EGE) adopted its Opinion No.27 An ethical framework for assessing research, production and use of energy and proposed an integrated ethics approach for the research, production and use of energy in the EU, seeking equilibrium among four criteria access ...

Garbil, Roger

2014-01-01T23:59:59.000Z

178

Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor Materials Tests 1 and 2  

SciTech Connect (OSTI)

A loss of Coolant Accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects of LOCA conditions on pressurized water reactor test fuel bundles. This experiment operation plan for the second and third experiments of the program will provide peak fuel cladding temperatures of up to 1172K (1650{degree}F) and 1061K (1450{degree}) respectively. for a long enough time to cause test fuel cladding deformation and rupture in both. Reflood coolant delay times and the reflooding rates for the experiments were selected from thermal-hydraulic data measured in the National Research Universal (NRU) reactor facilities and test train assembly during the first experiment.

Russcher, G. E.; Wilson, C. L.; Marshall, R, K.; King, L. L.; Parchen, L. J.; Pilger, J. P.; Hesson, G. M.; Mohr, C. L.

1981-09-01T23:59:59.000Z

179

Reformulated Gasoline Foreign Refinery Rules  

Gasoline and Diesel Fuel Update (EIA)

Reformulated Gasoline Reformulated Gasoline Foreign Refinery Rules Contents * Introduction o Table 1. History of Foreign Refiner Regulations * Foreign Refinery Baseline * Monitoring Imported Conventional Gasoline * Endnotes Related EIA Short-Term Forecast Analysis Products * Areas Participating in the Reformulated Gasoline Program * Environmental Regulations and Changes in Petroleum Refining Operations * Oxygenate Supply/Demand Balances in the Short-Term Integrated Forecasting Model * Refiners Switch to Reformulated Gasoline Complex Model * Demand, Supply, and Price Outlook for Reformulated Motor Gasoline, 1995 Introduction On August 27, 1997, the EPA promulgated revised the rules that allow foreign refiners to establish and use individual baselines, but it would not be mandatory (the optional use of an

180

Developing fuel management capabilities based on coupled Monte Carlo depletion in support of the MIT Research Reactor (MITR) conversion .  

E-Print Network [OSTI]

??Pursuant to a 1986 NRC ruling, the MIT Reactor (MITR) is planning on converting from the use of highly enriched uranium (HEU) to low enriched (more)

Romano, Paul K. (Paul Kollath)

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

Radiological Survey of Contaminated Installations of Research Reactor before Dismantling in High Dose Conditions with Complex for Remote Measurements of Radioactivity - 12069  

SciTech Connect (OSTI)

Decontamination and decommissioning of the research reactors MR (Testing Reactor) and RFT (Reactor of Physics and Technology) has recently been initiated in the National Research Center (NRC) 'Kurchatov institute', Moscow. These research reactors have a long history and many installations - nine loop facilities for experiments with different kinds of fuel. When decommissioning nuclear facilities it is necessary to measure the distribution of radioactive contamination in the rooms and at the equipment at high levels of background radiation. At 'Kurchatov Institute' some special remote control measuring systems were developed and they are applied during dismantling of the reactors MR and RFT. For a survey of high-level objects a radiometric system mounted on the robotic Brokk vehicle is used. This system has two (4? and collimated) dose meters and a high resolution video camera. Maximum measured dose rate for this system is ?8.5 Sv/h. To determine the composition of contaminants, a portable spectrometric system is used. It is a remotely controlled, collimated detector for scanning the distribution of radioactive contamination. To obtain a detailed distribution of contamination a remote-controlled gamma camera is applied. For work at highly contaminated premises with non-uniform background radiation, another camera is equipped with rotating coded mask (coded aperture imaging). As a result, a new system of instruments for remote radioactivity measurements with wide range of sensitivity and angular resolution was developed. The experience and results of measurements in different areas of the reactor and at its loop installations, with emphasis on the radioactive survey of highly-contaminated samples, are presented. These activities are conducted under the Federal Program for Nuclear and Radiation Safety of Russia. Adaptation of complex remote measurements of radioactivity and survey of contaminated installations of research reactor before dismantling in high dose conditions has proven successful. The radioactivity measuring devices for operation at high, non-uniform dose background were tested in the field and a new data of measurement of contamination distribution in the premises and installations were obtained. (authors)

Danilovich, Alexey; Ivanov, Oleg; Lemus, Alexey; Smirnov, Sergey; Stepanov, Vyacheslav; Volkovich, Anatoly [National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)

2012-07-01T23:59:59.000Z

182

Chapter_6_Foreign_Interaction  

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

Foreign Interaction Foreign Interaction This chapter describes the security procedures adopted by DOE HQ to implement the requirements of the following Executive Order and DOE directives: * Executive Order 12344 (as prescribed by 42 U.S.C. 7158) * DOE Oder 142.3A, Unclassified Foreign Visits and Assignments Program * DOE Order 470.4B, Safeguards and Security Program, Appendix B, Section 4 * DOE Order 475.1, Counterintelligence Program * DOE Order 551.1C, Official Foreign Travel * DOE Manual 552.1-1A, U.S. Department of Energy Travel Manual * DOE Order 552.1A, Change 1, Travel Policy and Procedures The directives have two objectives: the first objective is to protect DOE sensitive and classified information from being disclosed to foreign nationals, except when authorized by international

183

Unclassified Foreign National Visits & Assignments Questionnaire |  

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

Services » Calibration Facilities » Unclassified Foreign National Services » Calibration Facilities » Unclassified Foreign National Visits & Assignments Questionnaire Unclassified Foreign National Visits & Assignments Questionnaire Visitors who are foreign nationals must complete and submit the Unclassified Foreign National Visits & Assignments Questionnaire 30 days before accessing facilities. Unclassified Foreign National Visits.doc Description Unclassified Foreign National Visits & Assignments Questionnaire More Documents & Publications NEUP Foreign Travel Request Form FAQS Qualification Card - Safeguards and Security General Technical Base FAQS Qualification Card - Safeguards and Security Calibration Facilities Ecosystem Management Team Environmental Justice Environmental Management System Long-Term Surveillance - Operations and Maintenance

184

Regulation of Foreign Banks in Russia.  

E-Print Network [OSTI]

??In this paper, the issues of foreign investment in Russian banking sector are addressed. The study aims to shed light on foreign banks challenges in (more)

Trofimov, Kirill

2010-01-01T23:59:59.000Z

185

Isotope correlations for determining the isotopic composition of plutonium produced in research and power reactors using the experimental data obtained by alpha and mass spectrometry  

Science Journals Connector (OSTI)

Correlations have been developed for obtaining the isotopic composition of Pu produced in Indian research (CIRUS, DHRUVA) and power (PHWR) reactors. The experimental data obtained on 238Pu/(239Pu + 240Pu) alpha activity ratio using alpha spectrometry and on 240Pu/239Pu, 241Pu/239Pu, 242Pu/239Pu atom ratios by thermal ionisation mass spectrometry were used for developing isotope correlations.

S.K. Aggarwal; D. Alamelu

2005-01-01T23:59:59.000Z

186

Developing fuel management capabilities based on coupled Monte Carlo depletion in support of the MIT Research Reactor (MITR) conversion  

E-Print Network [OSTI]

Pursuant to a 1986 NRC ruling, the MIT Reactor (MITR) is planning on converting from the use of highly enriched uranium (HEU) to low enriched uranium (LEU) for fuel. Prior studies have shown that the MITR will be able to ...

Romano, Paul K. (Paul Kollath)

2009-01-01T23:59:59.000Z

187

FOREIGN INVESTMENT: Commerce Cracks Down  

Science Journals Connector (OSTI)

FOREIGN INVESTMENT: Commerce Cracks Down ... U.S. companies "will have to learn to live with" some form of mandatory federal controls on direct overseas investments "for at least a few years." ...

1968-09-02T23:59:59.000Z

188

RERTR program activities related to the development and application of new LEU fuels. [Reduced Enrichment Research and Test Reactor; low-enriched uranium  

SciTech Connect (OSTI)

The statue of the U.S. Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and schedules project the uranium density of qualified RERTR fuels for plate-type reactors to grow by approximately 1 g U/cm/sup 3/ each year, from the current 1.7 g U/cm/sup 3/ to the 7.0 g U/cm/sup 3/ which will be reached in late 1988. The technical needs of research and test reactors for HEU exports are also forecasted to undergo a gradual but dramatic decline in the coming years.

Travelli, A.

1983-01-01T23:59:59.000Z

189

2012 UMAR: 1994-2012 Foreign Puchases, Foreign Sales, and Inventories  

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

5 5 2012 Uranium Marketing Annual Report Release Date: May 16, 2013 Next Release Date: May 2014 Delivery Year 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Foreign Purchases by U.S. Suppliers 21.1 20.2 21.7 20.4 22.6 21.0 17.4 18.7 22.7 18.2 30.2 27.0 26.1 21.6 24.1 26.7 25.0 19.3 20.2 Foreign Purchases by Owners and Operators of U.S. Civilian Nuclear Power Reactors 15.5 21.1 23.7 22.5 21.1 26.6 27.5 28.0 30.0 34.9 35.9 38.5 38.7 32.5 32.9 32.2 30.4 35.1 36.0 Total Foreign Purchases 36.6 41.3 45.4 43.0 43.7 47.6 44.9 46.7 52.7 53.0 66.1 65.5 64.8 54.1 57.1 58.9 55.3 54.4 56.2 U.S. Broker and Trader Purchases from Foreign Suppliers 22.3 18.3 17.8 15.7 21.7 19.2 15.8 18.3 18.6 15.8 26.4 24.0 24.0 18.9 21.3 26.8 24.7 19.6 20.2 Foreign Sales 17.7 9.8 11.5 17.0 15.1 8.5 13.6 11.7 15.4 13.2 13.2 20.5 18.7 14.8 17.2 23.5

190

Recovery and Blend-Down Uranium for Beneficial use in Commercial Reactors - 13373  

SciTech Connect (OSTI)

In April 2001 the Department of Energy (DOE) and the Tennessee Valley Authority (TVA) signed an Interagency Agreement to transfer approximately 33 MT of off-specification (off-spec) highly enriched uranium (HEU) from DOE to TVA for conversion to commercial reactor fuel. Since that time additional surplus off-spec HEU material has been added to the program, making the total approximately 46 MT off-spec HEU. The disposition path for approximately half (23 MT) of this 46 MT of surplus HEU material, was down blending through the H-canyon facility at the Savannah River Site (SRS). The HEU is purified through the H-canyon processes, and then blended with natural uranium (NU) to form low enriched uranium (LEU) solution with a 4.95% U-235 isotopic content. This material was then transported to a TVA subcontractor who converted the solution to uranium oxide and then fabricated into commercial light water reactor (LWR) fuel. This fuel is now powering TVA reactors and supplying electricity to approximately 1 million households in the TVA region. There is still in excess of approximately 10 to 14 MT of off-spec HEU throughout the DOE complex or future foreign and domestic research reactor returns that could be recovered and down blended for use in either currently designed light water reactors, ?5% enriched LEU, or be made available for use in subsequent advanced 'fast' reactor fuel designs, ?19% LEU. (authors)

Magoulas, Virginia [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

191

Generation -IV Reactor Concepts  

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

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

192

2014 Headquarters Facilities Master Security Plan- Chapter 6, Foreign Interaction  

Broader source: Energy.gov [DOE]

2014 Headquarters Facilities Master Security Plan - Chapter 6, Foreign Interaction Describes DOE Headquarters procedures for approving foreign national visitors and assignees and travel to foreign countries.

193

Essays on Foreign Investment, Agglomeration Economies, and Industrial Policy  

E-Print Network [OSTI]

from Foreign Direct Investment in Services Industries?from Direct Foreign Investment? Evidence from Venezuela. Thefrom Foreign Direct Investment through Technology Transfer

Du, Luosha

2012-01-01T23:59:59.000Z

194

E-Print Network 3.0 - advanced fission reactors Sample Search...  

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

fission reactors, which release energy by splitting atoms... ) International Thermonuclear Experimental Reactor (ITER), which will be ... Source: Fusiongnition Research...

195

PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE BROOKHAVEN GRAPHITE RESEARCH REACTOR ENGINEERED CAP, BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK DCN 5098-SR-07-0  

SciTech Connect (OSTI)

The Oak Ridge Institute for Science and Education (ORISE) has reviewed the project documentation and data for the Brookhaven Graphite Research Reactor (BGRR) Engineered Cap at Brookhaven National Laboratory (BNL) in Upton, New York. The Brookhaven Science Associates (BSA) have completed removal of affected soils and performed as-left surveys by BSA associated with the BGRR Engineered Cap. Sample results have been submitted, as required, to demonstrate that remediation efforts comply with the cleanup goal of {approx}15 mrem/yr above background to a resident in 50 years (BNL 2011a).

Evan Harpenau

2011-07-15T23:59:59.000Z

196

Analytical support for the ORR (Oak Ridge Research Reactor) whole-core LEU U/sub 3/Si/sub 2/-Al fuel demonstration  

SciTech Connect (OSTI)

Analytical methods used to analyze neutronic data from the whole-core LEU fuel demonstration in the Oak Ridge Research Reactor are briefly discussed. Calculated eigenvalues corresponding to measured critical control rod positions are presented for each core used in the gradual transition from an all HEU to an all LEU configuration. Some calculated and measured results, including ..beta../sub eff//l/sub p/, are compared for HEU and LEU fresh fuel criticals. Finally, the perturbing influences of the six voided beam tubes on certain core parameters are examined. For reasons yet to be determined, differential shim rod worths are not well-calculated in partially burned cores.

Bretscher, M.M.

1986-01-01T23:59:59.000Z

197

Advanced Reactor Technologies | Department of Energy  

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

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

198

Web-based, speech-enabled games for vocabulary acquisition in a foreign language  

E-Print Network [OSTI]

In this thesis, I present two novel ways in which speech recognition technology might aid students with vocabulary acquisition in a foreign language. While research in the applied linguistics field of second language ...

McGraw, Ian C. (Ian Carmichael)

2008-01-01T23:59:59.000Z

199

FOREIGN INVESTMENT: Controls Coming Off  

Science Journals Connector (OSTI)

Chances are good that one of President Nixon's first tasks when he returns from Europe will be to see what he can do to dismantle the direct controls on foreign investment by U.S. firms instituted in January 1968.Speaking at the just-concluded midwinter ...

1969-03-03T23:59:59.000Z

200

FOREIGN INVESTMENT: Private Capital Welcome  

Science Journals Connector (OSTI)

FOREIGN INVESTMENT: Private Capital Welcome ... The recent proposal by a business advisory council for a federally chartered corporation to spur private capital investment in developing countries " . . . ... The proposed corporation, urged in a report to the Agency for International Development, would take over and expand the investment guaranty and financing programs administered by AID's Office of Private Resources. ...

1969-01-06T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

The IAEA Coordinated Research Program on HTGR Reactor Physics, Thermal-hydraulics and Depletion Uncertainty Analysis: Description of the Benchmark Test Cases and Phases  

SciTech Connect (OSTI)

The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of design and safety features with reliable high fidelity physics models and robust, efficient, and accurate codes. The uncertainties in the HTR analysis tools are today typically assessed with sensitivity analysis and then a few important input uncertainties (typically based on a PIRT process) are varied in the analysis to find a spread in the parameter of importance. However, one wish to apply a more fundamental approach to determine the predictive capability and accuracies of coupled neutronics/thermal-hydraulics and depletion simulations used for reactor design and safety assessment. Today there is a broader acceptance of the use of uncertainty analysis even in safety studies and it has been accepted by regulators in some cases to replace the traditional conservative analysis. Finally, there is also a renewed focus in supplying reliable covariance data (nuclear data uncertainties) that can then be used in uncertainty methods. Uncertainty and sensitivity studies are therefore becoming an essential component of any significant effort in data and simulation improvement. In order to address uncertainty in analysis and methods in the HTGR community the IAEA launched a Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling early in 2012. The project is built on the experience of the OECD/NEA Light Water Reactor (LWR) Uncertainty Analysis in Best-Estimate Modelling (UAM) benchmark activity, but focuses specifically on the peculiarities of HTGR designs and its simulation requirements. Two benchmark problems were defined with the prismatic type design represented by the MHTGR-350 design from General Atomics (GA) while a 250 MW modular pebble bed design, similar to the INET (China) and indirect-cycle PBMR (South Africa) designs are also included. In the paper more detail on the benchmark cases, the different specific phases and tasks and the latest status and plans are presented.

Frederik Reitsma; Gerhard Strydom; Bismark Tyobeka; Kostadin Ivanov

2012-10-01T23:59:59.000Z

202

Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor Materials Test 2  

SciTech Connect (OSTI)

A loss-of-coolant accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects on pressurized water reactor (PWR) test fuel bundles. This Experiment Operation Plan (EOP) Addendum 2, together with the referenced EOP, describes the desired operating conditions and additional hazards review associated with the four-part MT-2 experiment. The primary portions of the experiment, MT-2.2 and MT-2.3, will evaluate the following: 1) the mechanical deformation of pressurized fuel rods subjected to a slow LOCA, using reflood water for temperature control, that is designed to produce cladding temperatures in the range from 1033 to 1089K (1400 to 1500F) for an extended time, and 2) the effects of the deformed and possibly failed cladding on the thermal-hydraulic performance of the test assembly during simulated LOCA heating and reflooding. The secondary portions of the experiment, MT-2.1 and MT-2.4, are intended to provide thermal-hydraulic calibration information during two-stage reflood conditions for 1) relatively low cladding temperatures, <839K (1050F), on nondeformed rods, and 2) moderately high cladding temperatures, <1089K (1500F), on deformed rods.

Russcher, G. E.; Barner, J. O.; Hesson, G. M.; Wilson, C. L.; Parchen, L. J.; Cunningham, M. E.; Marshall, R. K.; Mohr, C. L.

1981-09-01T23:59:59.000Z

203

Unclassified Foreign Visits and Assignments Program  

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

The order defines a program for unclassified foreign national access to Department of Energy sites, information, and technologies. The page change streamlines the HQs Management Panel review process to include reviews by HSS, IN, and a representative of the cognizant under secretary for access requests involving foreign nationals. Cancels Secretarial Memorandum, Unclassified Foreign Visits and Assignments, dated 7-14-99; Memorandum from Francis S. Blake, Departmental Use of Foreign Access Central Tracking System, dated 11-05-01; Memorandum from Kyle E. McSlarrow, Interim Guidance for Implementation of the Department's Unclassified Foreign Visits and Assignments Program, dated 12-17-02; and Secretarial Memorandum, Policy Exclusion for Unclassified Foreign National's Access to Department of Energy Facilities in Urgent or Emergency Medical Situations, dated 4-10-01. Cancels: DOE P 142.1 and DOE N 142.1

2004-06-18T23:59:59.000Z

204

Management and Control of Foreign Intelligence  

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

The order provides for the management of and assign responsibilities for foreign intelligence activities of DOE. Cancels DOE 5670.1.

1992-01-15T23:59:59.000Z

205

Development of foreign direct investment in Finland.  

E-Print Network [OSTI]

??During 1990 to 2009, Foreign Direct Investment (FDI henceforth) in Finland has fluctuated greatly. This paper focused on analyzing the overall development and basic characteristics (more)

Yanyan, Yan

2011-01-01T23:59:59.000Z

206

Foreign Visits & Assignments Guidelines | The Ames Laboratory  

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

Visits and Assignments Request Form, as well as the Ames Laboratory Specific Security Plan Form. Form 473 Foreign Visits and Assignments Request Form Specific Security Plan...

207

Unclassified Foreign Visits and Assignments Program  

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

The order defines a program for unclassified foreign national access to DOE sites, information, technologies, and equipment. Cancels DOE O 142.3.

2010-10-14T23:59:59.000Z

208

Foreign Obligations Implementation Status Presentation  

National Nuclear Security Administration (NNSA)

January 13, 2004 Crowne Plaza Ravinia Atlanta, January 13, 2004 Crowne Plaza Ravinia Atlanta, January 13, 2004 Crowne Plaza Ravinia Atlanta, Georgia Georgia Obligations Accounting Implementation Workshop Obligations Accounting Implementation Workshop Foreign Obligations Implementation Status Brian G. Horn U.S. Nuclear Regulatory Commission January 13, 2004 Obligations Accounting Implementation Workshop January 13, 2 Obligations Accounting Implementation Workshop January 13, 2004 Crowne Plaza Ravinia Atlanta, GA 004 Crowne Plaza Ravinia Atlanta, GA Overview of Meeting Overview of Meeting * Review how the Obligation Tracking System is working * Presentations: - Review of Government notification procedures - Establishment of the beginning Obligation Balances for sites

209

NUCLEAR REACTORS.  

E-Print Network [OSTI]

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

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

210

Reactors: Modern-Day Alchemy - Argonne's Nuclear Science and Technology  

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

Achievements > Achievements > Legacy > Reactors: Modern-Day Alchemy 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

211

Achievements: Nuclear Reactors designed/built by Argonne National  

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

Achievements > Achievements > Argonne National Laboratory Reactors 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

212

Use of phenomena identification and ranking (PIRT) process in research related to design certification of the AP600 advanced passive light water reactor (LWR)  

SciTech Connect (OSTI)

The AP600 LWR is a new advanced passive design that has been submitted to the USNRC for design certification. Within the certification process the USNRC will perform selected system thermal hydraulic response audit studies to help confirm parts of the vendor`s safety analysis submittal. Because of certain innovative design features of the safety systems, new experimental data and related advances in the system thermal hydraulic analysis computer code are being developed by the USNRC. The PIRT process is being used to focus the experimental and analytical work to obtain a sufficient and cost effective research effort. The objective of this paper is to describe the application and most significant results of the PIRT process, including several innovative features needed in the application to accommodate the short design certification schedule. The short design certification schedule has required that many aspects of the USNRC experimental and analytical research be performed in parallel, rather than in series as was normal for currently operating LWRS. This has required development and use of management techniques that focus and integrate the various diverse parts of the research. The original PIRTs were based on inexact knowledge of an evolving reactor design, and concentrated on the new passive features of the design. Subsequently, the PIRTs have evolved in two more stages as the design became more firm and experimental and analytical data became available. A fourth and final stage is planned and in progress to complete the PIRT development. The PIRTs existing at the end of each development stage have been used to guide the experimental program, scaling analyses and code development supporting the audit studies.

Wilson, G.E.; Fletcher, C.D. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Eltawila, F. [Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research

1996-07-01T23:59:59.000Z

213

STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S DOMESTIC AND FOREIGN PATENT  

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

DOMESTIC AND FOREIGN PATENT DOMESTIC AND FOREIGN PATENT RIGHTS IN INVENTIONS MADE IN THE PERFORMANCE OF RESEARCH IN THE INORGANIC MEMBRANE TECHNOLOGY LABORATORY OPERATED BY BECHTEL JACOBS COMPANY UNDER ITS MANAGEMENT AND INTEGRATION CONTRACT DE-AC05-980R22700; WAIVER ORO-674, W(C)-98-004 The Department of Energy (DOE) previously approved a class waiver [W(C)-96-006] of domestic and foreign patent rights in inventions made in the performance of Cooperative Research and Development Agreements (CRADAs) relating to inorganic membrane technology, which were entered into by Lockheed Martin Energy Systems, Inc. under prime contract DE-AC05-840R21400 and by Lockheed Martin Energy Research Corporation under prime contract DE-AC05-960R22464. Those contractors performed cooperative research involving inorganic membrane

214

U.S./Belarus/Ukraine joint research on the biomedical effects of the Chernobyl Reactor Accident. Final report  

SciTech Connect (OSTI)

The National Cancer Institute has negotiated with the governments of Belarus and Ukraine (Ministers/Ministries of Health, institutions and scientists) to develop scientific research protocols to study the effects of radioactive iodine released by the Chernobyl accident upon thyroid anatomy and function in defined cohorts of persons under the age of 19 years at the time of the accident. These studies include prospective long term medical follow-up of the cohort and the reconstruction of the radiation dose to each cohort subject's thyroid. The protocol for the study in Belarus was signed by the US and Belorussian governments in May 1994 and the protocol for the study in Ukraine was signed by the US and Ukraine in May 1995. A second scientific research protocol also was negotiated with Ukraine to study the feasibility of a long term study to follow the development of leukemia and lymphoma among Ukrainian cleanup workers; this protocol was signed by the US and Ukraine in October 1996.

Bruce Wachholz

2000-06-20T23:59:59.000Z

215

Using reactor operating experience to improve the design of a new Broad Application Test Reactor  

SciTech Connect (OSTI)

Increasing regulatory demands and effects of plant aging are limiting the operation of existing test reactors. Additionally, these reactors have limited capacities and capabilities for supporting future testing missions. A multidisciplinary team of experts developed sets of preliminary safety requirements, facility user needs, and reactor design concepts for a new Broad Application Test Reactor (BATR). Anticipated missions for the new reactor include fuels and materials irradiation testing, isotope production, space testing, medical research, fusion testing, intense positron research, and transmutation doping. The early BATR design decisions have benefited from operating experiences with existing reactors. This paper discusses these experiences and highlights their significance for the design of a new BATR.

Fletcher, C.D.; Ryskamp, J.M.; Drexler, R.L.; Leyse, C.F.

1993-07-01T23:59:59.000Z

216

Council on Foreign Relations | Department of Energy  

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

Council on Foreign Relations Council on Foreign Relations Council on Foreign Relations January 13, 2005 - 9:47am Addthis Remarks Prepared for Energy Secretary Abraham Thank you. It's an honor to be here with you today. For over 80 years the Council has played a leading role in guiding American foreign policy. As Leslie Gelb once said, "If the Council as a body has stood for anything ... it has been for American internationalism based on American interests." This body has not just stood for American internationalism and American interests, it has helped guarantee them. Scholars and historians have dubbed the last 100 years "the American Century," and there can be little doubt the Council on Foreign Relations helped make it so. As my tenure in the Bush Administration comes to a close, I wanted to

217

Use of synthetic DNA in expression of foreign proteins  

Science Journals Connector (OSTI)

Synthetic \\{DNAs\\} and oligonucleotides, which can be prepared conveniently by combining chemical synthesis and enzymatic methods, have been used extensively in recombinant DNA research. Examples include total gene synthesis, probes for the isolation of specific genes from cDNA or genomic libraries, linkers containing specific restriction sites for cloning, primers for DNA and RNA sequencing, and primers for the construction of specific mutations (either deletion, insertion or point mutations) by oligonucleotide-directed site-specific mutagenesis. This article reviews recent advances in the chemical and enzymatic synthesis of oligo- and polynucleotides and the application of synthetic DNA to the expression of foreign proteins. The synthesis of genes, including structural genes and regulatory genes are reviewed. Oligonucleotide-directed site-specific mutagenesis and use of synthetic DNA to optimize foreign protein expression are also discussed.

Hansen M. Hsiung

1986-01-01T23:59:59.000Z

218

Credibility and flexibility : political institutions and foreign direct investment  

E-Print Network [OSTI]

Meyer. 2004. Foreign investment location and institutionaleconomics of foreign direct investment incentives. WorkingBidding for Mobile Investment: Economic Consequences and

Zheng, Yu

2007-01-01T23:59:59.000Z

219

Before the House Foreign Affairs Subcommittee on Asia, the Pacific...  

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

Foreign Affairs Subcommittee on Asia, the Pacific and the Global Environment Before the House Foreign Affairs Subcommittee on Asia, the Pacific and the Global Environment Before...

220

Bush Administration Establishes Program to Reduce Foreign Oil...  

Office of Environmental Management (EM)

Establishes Program to Reduce Foreign Oil Dependency, Greenhouse Gases Bush Administration Establishes Program to Reduce Foreign Oil Dependency, Greenhouse Gases April 10, 2007 -...

Note: This page contains sample records for the topic "foreign 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

Reactor and Nuclear Systems Division (RNSD)  

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

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

222

The Integral Fast Reactor (IFR) - Reactors designed/built by Argonne  

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

Integral Fast Reactor Integral Fast Reactor 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 Argonne's Nuclear Science and Technology Legacy

223

Percutaneous Retrieval of Chronic Intravascular Foreign Bodies  

SciTech Connect (OSTI)

To evaluate the feasibility of intravascular retrieval of chronic foreign bodies, we retrospectively reviewed an 8 year experience (1993-2001) of percutaneous retrieval of chronically retained intravascular foreign bodies (n = 6). In 6 of 6 cases (4 catheter fragments, 2 guidewires), 5-90 days elapsed before retrieval via the femoral or internal jugular vein. Under fluoroscopy, we determined the foreign body's course, position and size. A guidewire was advanced through a multipurpose catheter to the foreign body. The multipurpose catheter was replaced with a gooseneck snare catheter and the snare advanced to grasp and remove the foreign body. Percutaneous retrieval was successful in all 6 cases. One patient experienced mild hemoptysis, which resolved within 24 hr of observation. No patient experienced long-term sequelae. Given the potential life-threatening complications from intravascular foreign bodies and the low complication rate from percutaneous retrieval, we recommend extraction of the foreign body even if it is asymptomatic in the chronic setting (> 24 hr)

Savage, Clare [University of Texas Medical Branch, Galveston, Texas, Department of Surgery (United States); Ozkan, Orhan S.; Walser, Eric M. [University of Texas Medical Branch, Galveston, Texas, Department of Radiology (United States); Wang Dongfang; Zwischenberger, Joseph B. [University of Texas Medical Branch, Galveston, Texas, Department of Surgery (United States)], E-mail: jzwische@utmb.edu

2003-09-15T23:59:59.000Z

224

Foreign Ownership, Control, or Influence Program  

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

To establish the policies, responsibilities, and authorities for implementing the Department of Energy (DOE) Foreign Ownership, Control, or Influence (FOCI) program, which is designed to obtain information that indicates whether DOE offerors/bidders or contractors/subcontractors are owned, controlled, or influenced by foreign individuals, governments, or organizations, and whether that foreign involvement may pose an undue risk to the common defense and security. This directive does not cancel another directive. Canceled by DOE O 470.1 of 9-28-1995.

1993-06-14T23:59:59.000Z

225

naval reactors  

National Nuclear Security Administration (NNSA)

After operating for 34 years and training over 14,000 sailors, the Department of Energy S1C Prototype Reactor Site in Windsor, Connecticut, was returned to "green field"...

226

Thermonuclear Reflect AB-Reactor  

E-Print Network [OSTI]

The author offers a new kind of thermonuclear reflect reactor. The remarkable feature of this new reactor is a three net AB reflector, which confines the high temperature plasma. The plasma loses part of its energy when it contacts with the net but this loss can be compensated by an additional permanent plasma heating. When the plasma is rarefied (has a small density), the heat flow to the AB reflector is not large and the temperature in the triple reflector net is lower than 2000 - 3000 K. This offered AB-reactor has significantly less power then the currently contemplated power reactors with magnetic or inertial confinement (hundreds-thousands of kW, not millions of kW). But it is enough for many vehicles and ships and particularly valuable for tunnelers, subs and space apparatus, where air to burn chemical fuel is at a premium or simply not available. The author has made a number of innovations in this reactor, researched its theory, developed methods of computation, made a sample computation of typical project. The main point of preference for the offered reactor is its likely cheapness as a power source. Key words: Micro-thermonuclear reactor, Multi-reflex AB-thermonuclear reactor, Self-magnetic AB-thermonuclear reactor, aerospace thermonuclear engine.

Alexander Bolonkin

2008-03-26T23:59:59.000Z

227

Early Exploration - Reactors designed/built by Argonne National Laboratory  

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

Early Exploration Early Exploration 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 Argonne's Nuclear Science and Technology Legacy

228

Foreign Tax Credit and the Current Account  

Science Journals Connector (OSTI)

This paper provides a general equilibrium analysis of the effects of a foreign tax credit (FTC) provision on current account dynamics ... a change in the home country capital income tax rate causes different resp...

Yasushi Iwamoto; Akihisa Shibata

1999-05-01T23:59:59.000Z

229

Foreign Fishery Developments Japan's Use of Processed  

E-Print Network [OSTI]

Foreign Fishery Developments Japan's Use of Processed Fish Products Declines Total 7,691.9 7 expenses were Y2,890,household household expenses from net income (fisherman income minus sev- eral taxes), the disposable income was Y1

230

Techniques for Intravascular Foreign Body Retrieval  

SciTech Connect (OSTI)

As endovascular therapies increase in frequency, the incidence of lost or embolized foreign bodies is increasing. The presence of an intravascular foreign body (IFB) is well recognized to have the potential to cause serious complications. IFB can embolize and impact critical sites such as the heart, with subsequent significant morbidity or mortality. Intravascular foreign bodies most commonly result from embolized central line fragments, but they can originate from many sources, both iatrogenic and noniatrogenic. The percutaneous approach in removing an IFB is widely perceived as the best way to retrieve endovascular foreign bodies. This minimally invasive approach has a high success rate with a low associated morbidity, and it avoids the complications related to open surgical approaches. We examined the characteristics, causes, and incidence of endovascular embolizations and reviewed the various described techniques that have been used to facilitate subsequent explantation of such materials.

Woodhouse, Joe B.; Uberoi, Raman, E-mail: raman.uberoi@orh.nhs.uk [Oxford University Hospitals (United Kingdom)

2013-08-01T23:59:59.000Z

231

Adaptive systems for foreign exchange trading  

E-Print Network [OSTI]

, Cambridge, and Dr Mark Austin and Dr Stacy Williams, both of HSBC Global Markets, outline the results- niques in foreign exchange markets for a number of years. Over 18 months a joint project with HSBC Global

Fernandez, Thomas

232

HQFMSP Chapter 6, Foreign Interaction | Department of Energy  

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

6, Foreign Interaction 6, Foreign Interaction HQFMSP Chapter 6, Foreign Interaction October 2013 2013 Headquarters Facilities Master Security Plan - Chapter 6, Foreign Interaction DOE has adopted significant controls over the interaction of its employees and contractors with foreign nationals. When authorized by a treaty or international agreement, some DOE classified information can be shared with foreign government representatives. Unclassified information can be shared with foreign nationals only after a senior DOE official has approved that exchange. No foreign national can be admitted to a HQ facility without the approval of a senior HQ official and then only when required information is placed in the Foreign Access Central Tracking System (FACTS). There are also controls over some foreign travel performed by

233

Political risk, institutions and foreign direct investment  

Science Journals Connector (OSTI)

The paper explores the linkages among political risk, institutions, and foreign direct investment inflows. For a data sample of 83 developing countries covering 1984 to 2003, we identify indicators that matter most for the activities of multinational corporations. The results show that government stability, internal and external conflict, corruption and ethnic tensions, law and order, democratic accountability of government, and quality of bureaucracy are highly significant determinants of foreign investment inflows.

Matthias Busse; Carsten Hefeker

2007-01-01T23:59:59.000Z

234

Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels -- Final Report under the International Nuclear Energy Research Initiative (I-NERI)  

SciTech Connect (OSTI)

The objective of this INERI project was to develop improved fuel behavior models for gas reactor coated-particle fuels and to explore improved coated-particle fuel designs that could be used reliably at very high burnups and potentially in gas-cooled fast reactors. Project participants included the Idaho National Engineering Laboratory (INEEL), Centre tude Atomique (CEA), and the Massachusetts Institute of Technology (MIT). To accomplish the project objectives, work was organized into five tasks.

David Petti; Philippe Martin; Mayeul Phlip; Ronald Ballinger; Petti does not have NT account

2004-12-01T23:59:59.000Z

235

DOE - Office of Legacy Management -- Ames Laboratory Research...  

Office of Legacy Management (LM)

Ames Laboratory Research Reactor Facility - IA 03 FUSRAP Considered Sites Site: Ames Laboratory Research Reactor Facility (IA.03) Designated Name: Alternate Name: Location:...

236

Light Water Reactor Sustainability  

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

4 Light Water Reactor Sustainability ACCOMPLISHMENTS REPORT 2014 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

237

University Reactor Conversion Lessons Learned Workshop for Purdue University Reactor  

SciTech Connect (OSTI)

The Department of Energys Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at Purdue University Reactor. With this work completed and in anticipation of other impending conversion projects, the INL convened and engaged the project participants in a structured discussion to capture the lessons learned. The lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project teams experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.

Eric C. Woolstenhulme; Dana M. Hewit

2008-09-01T23:59:59.000Z

238

Catalytic reactor  

DOE Patents [OSTI]

A catalytic reactor is provided with one or more reaction zones each formed of set(s) of reaction tubes containing a catalyst to promote chemical reaction within a feed stream. The reaction tubes are of helical configuration and are arranged in a substantially coaxial relationship to form a coil-like structure. Heat exchangers and steam generators can be formed by similar tube arrangements. In such manner, the reaction zone(s) and hence, the reactor is compact and the pressure drop through components is minimized. The resultant compact form has improved heat transfer characteristics and is far easier to thermally insulate than prior art compact reactor designs. Various chemical reactions are contemplated within such coil-like structures such that as steam methane reforming followed by water-gas shift. The coil-like structures can be housed within annular chambers of a cylindrical housing that also provide flow paths for various heat exchange fluids to heat and cool components.

Aaron, Timothy Mark (East Amherst, NY); Shah, Minish Mahendra (East Amherst, NY); Jibb, Richard John (Amherst, NY)

2009-03-10T23:59:59.000Z

239

Light Water Reactor Sustainability Technical Documents | Department of  

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

Reactor Technologies » Light Water Reactor Reactor Technologies » Light Water Reactor Sustainability Program » Light Water Reactor Sustainability Technical Documents Light Water Reactor Sustainability Technical Documents April 30, 2013 LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs: DOE-NE's Light Water Reactor Sustainability (LWRS) Program and EPRI's Long-Term Operations (LTO) Program. April 30, 2013 Light Water Reactor Sustainability Program - Integrated Program Plan The Light Water Reactor Sustainability (LWRS) Program is a research and

240

ANALYSIS OF SEPCTRUM CHOICES FOR SMALL MODULAR REACTORS-PERFORMANCE AND DEVELOPMENT  

E-Print Network [OSTI]

. The research mainly focused on producing a small modular reactor (Pebble Bed Modular Reactor) design to analyze the fuel depletion and plutonium and minor actinide accumulation with varying power densities. The reactors running at low power densities were found...

Kafle, Nischal

2011-04-26T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

Foreign offshore worker injuries in foreign waters: why a United States forum  

SciTech Connect (OSTI)

When foreigners are injured or killed in offshore oil operations in foreign jurisdictional waters, US laws do not always apply as they would if the plaintiffs are American or resident aliens. The courts must first consider whether the Jones Act, Death on the High Seas Act, general maritime law, or a combination of laws applies and whether the court should assume jurisdiction or use the doctrine of forum non conveniens. Cases involving foreign offshore workers are used to illustrate the factors involved in each application and to consider the foreign-policy implication when foreign nationals assume that American laws and morality accompany multinational business. Congress has yet to resolve the issues, although a bill was proposed in 1980. 75 references. (DCK)

Sutterfield, J.R.

1981-07-01T23:59:59.000Z

242

Foreign Direct Investment Acquisitions and Divestitures for the Year 2002  

Gasoline and Diesel Fuel Update (EIA)

Investment Acquisitions and Divestitures for the Year 2002 Investment Acquisitions and Divestitures for the Year 2002 Home > Energy Finance > Foreign Investment in U.S. Energy > Foreign Direct Investment Acquisitions and Divestitures, 2002 Acquisitions of U.S. Energy Assets by Foreign Investors in 2002 Remain High Foreign direct acquisitions are purchases, directly or indirectly, by the original foreign investor resulting in the ownership of 10 percent or more of the voting securities of an incorporated U.S. business enterprise or the equivalent interest in an unincorporated U.S. business. The purchases may include foreign assets owned by the U.S. business that is being acquired. Purchases of a U.S. business or asset by one foreign owner from another foreign owner are not included in the foreign

243

WA_00_018_PRAXAIR_Waive_of_Domestic_and_Foreign_Invention_Ri...  

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

18PRAXAIRWaiveofDomesticandForeignInventionRi.pdf WA00018PRAXAIRWaiveofDomesticandForeignInventionRi.pdf WA00018PRAXAIRWaiveofDomesticandForeignInvention...

244

WA_03_024_PRAXAIR_Waiver_of_Domestic_and_Foreign_Invention_R...  

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

24PRAXAIRWaiverofDomesticandForeignInventionR.pdf WA03024PRAXAIRWaiverofDomesticandForeignInventionR.pdf WA03024PRAXAIRWaiverofDomesticandForeignInventio...

245

WA_01_039_PRAXAIR_INC_Waiver_of_Domestic_and_Foreign_Patent_...  

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

1039PRAXAIRINCWaiverofDomesticandForeignPatent.pdf WA01039PRAXAIRINCWaiverofDomesticandForeignPatent.pdf WA01039PRAXAIRINCWaiverofDomesticandForeignP...

246

WA_02_055_PRAXAIR_Waiver_of_Domestic_and_Foreign_Patent_Righ...  

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

2055PRAXAIRWaiverofDomesticandForeignPatentRigh.pdf WA02055PRAXAIRWaiverofDomesticandForeignPatentRigh.pdf WA02055PRAXAIRWaiverofDomesticandForeignPaten...

247

WA_00_001_PRAXAIR_INC_Waiver_of_Domestic_and_Foreign_Inventi...  

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

01PRAXAIRINCWaiverofDomesticandForeignInventi.pdf WA00001PRAXAIRINCWaiverofDomesticandForeignInventi.pdf WA00001PRAXAIRINCWaiverofDomesticandForeignInve...

248

WA_02_022_HONEYWELL_INC_Waiver_of_Domestic_and_Foreign_Inven...  

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

22HONEYWELLINCWaiverofDomesticandForeignInven.pdf WA02022HONEYWELLINCWaiverofDomesticandForeignInven.pdf WA02022HONEYWELLINCWaiverofDomesticandForeignIn...

249

WC_1990_008_CLASS_WAIVER_for_the_Governments_US_and_Foreign_...  

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

8CLASSWAIVERfortheGovernmentsUSandForeign.pdf WC1990008CLASSWAIVERfortheGovernmentsUSandForeign.pdf WC1990008CLASSWAIVERfortheGovernmentsUSandForeign...

250

WC_1996_005_CLASS_WAIVER_Of_the_Governments_US_and_Foreign_.pdf...  

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

6005CLASSWAIVEROftheGovernmentsUSandForeign.pdf WC1996005CLASSWAIVEROftheGovernmentsUSandForeign.pdf WC1996005CLASSWAIVEROftheGovernmentsUSandForeign...

251

WC_1993_003_CLASS_WAIVER__of_the_Government_US_and_Foreign_P...  

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

3CLASSWAIVERoftheGovernmentUSandForeignP.pdf WC1993003CLASSWAIVERoftheGovernmentUSandForeignP.pdf WC1993003CLASSWAIVERoftheGovernmentUSandForeignP...

252

WC_1991_004CLASS_WAIVER_of_GOVERNMENT_US_and_Foreign_Paten.pdf...  

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

WC1991004CLASSWAIVERofGOVERNMENTUSandForeignPaten.pdf WC1991004CLASSWAIVERofGOVERNMENTUSandForeignPaten.pdf WC1991004CLASSWAIVERofGOVERNMENTUSandForeignP...

253

WC_1990_003__CLASS_WAIVER_of_the_Government_US_and_Foreign_P...  

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

03CLASSWAIVERoftheGovernmentUSandForeignP.pdf WC1990003CLASSWAIVERoftheGovernmentUSandForeignP.pdf WC1990003CLASSWAIVERoftheGovernmentUSandForeign...

254

WC_1990_014_CLASS_ADVANCE_WAIVER_of_US_and_Foreign_Rights_fo...  

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

4CLASSADVANCEWAIVERofUSandForeignRightsfo.pdf WC1990014CLASSADVANCEWAIVERofUSandForeignRightsfo.pdf WC1990014CLASSADVANCEWAIVERofUSandForeignRightsfo...

255

WC_1993_014_CLASS_WAIVER_of_the_Governments_US_and_Foreign_P...  

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

14CLASSWAIVERoftheGovernmentsUSandForeignP.pdf WC1993014CLASSWAIVERoftheGovernmentsUSandForeignP.pdf WC1993014CLASSWAIVERoftheGovernmentsUSandForeign...

256

WC_1993_005__CLASS_WAIVER_of_the_Goernment_US_and_Foreign_Pa...  

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

5CLASSWAIVERoftheGoernmentUSandForeignPa.pdf WC1993005CLASSWAIVERoftheGoernmentUSandForeignPa.pdf WC1993005CLASSWAIVERoftheGoernmentUSandForeignPa...

257

WC_1990_015_CLASS_WAIVER_OF_Domestic_and_Foreign_Patent_Righ...  

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

0015CLASSWAIVEROFDomesticandForeignPatentRigh.pdf WC1990015CLASSWAIVEROFDomesticandForeignPatentRigh.pdf WC1990015CLASSWAIVEROFDomesticandForeignPatent...

258

FOREIGN RELATIONS U.S., China pledge to cooperate on greenhouse gas mitigation  

Science Journals Connector (OSTI)

FOREIGN RELATIONS U.S., China pledge to cooperate on greenhouse gas mitigation ... President Barack Obama and Chinese President Hu Jintao have pledged to work together to mitigate greenhouse gas emissions. ... They will also conduct collaborative research to encourage clean-coal technologies, electric vehicles, renewable energy, shale-gas exploration, and new energy-efficiency technologies. ...

JEFF JOHNSON

2009-11-23T23:59:59.000Z

259

Recovery Act Workers Clear Reactor Shields from Brookhaven Lab | Department  

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

Workers Clear Reactor Shields from Brookhaven Lab Workers Clear Reactor Shields from Brookhaven Lab Recovery Act Workers Clear Reactor Shields from Brookhaven Lab American Recovery and Reinvestment Act workers are in the final stage of decommissioning a nuclear reactor after they recently removed thick steel shields once used to absorb neutrons produced for research. The Brookhaven National Laboratory is using $39 million from the Recovery Act to decommission the Brookhaven Graphite Research Reactor, the world's first reactor built solely for peaceful research purposes. Recovery Act Workers Clear Reactor Shields from Brookhaven Lab More Documents & Publications Brookhaven Graphite Research Reactor Workshop 2011 ARRA Newsletters Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell

260

REQUEST BY PRAXAIR, INC.(PRAXAIR) FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN PATENT RIGHTS TO INVENTIONS MADE UNDER  

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

PRAXAIR, INC.(PRAXAIR) FOR AN ADVANCE WAIVER OF PRAXAIR, INC.(PRAXAIR) FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN PATENT RIGHTS TO INVENTIONS MADE UNDER CONTRACT NO. DE-FC26-00NT41027 ENTITLED "NOVEL REACTOR FOR THE PRODUCTION OF SYNTHESIS GAS"; W(A)-01-005, CH1058. Praxair has requested an advance waiver of domestic and foreign patent rights to inventions its employees may conceive or first actually reduce to practice in the performance of Contract No. DE-FC26-00NT41027. As brought out in the attached waiver petition, the work will focus on development of an advanced technology for producing synthesis gas from a reaction of natural gas with pure methane. This process combines the use of a short-reaction time catalyst with Praxair's gas mixing technology to provide a novel reactor system. The total cost of this work under the

Note: This page contains sample records for the topic "foreign 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

Foreign-Language Units of Kansas  

E-Print Network [OSTI]

" dennedSpecial terms denned (for-ling, f~lang, stock at home, for-ling population, critical year)Standards of the Importance Label Part I: General Population Statistics 3 Preliminary Explanations Foreign-born in Kansas 1860 by Counties and by Regions..., and Bohemia 10 Mexico - 11 For-ling Population of Kansas in 1895 1 The State by Regions 2 The Regions by Counties 14 Foreign-born Population 1850-1950 of the States Providing the Principal Sources and Outlets of the Population of Kansas: Colorado...

Carman, J. Neale

1962-01-01T23:59:59.000Z

262

Foreign Direct Investment in U.S. Energy  

Gasoline and Diesel Fuel Update (EIA)

in in 2000 This report presents an analysis of foreign direct investment in U.S. energy resources and companies in 2000. Foreign direct investment (FDI) is the ownership or control of 10 percent, or more, of a U.S. business (or asset) by a foreign entity. In this report a U.S. business with at least 10 percent foreign ownership is a "foreign- affiliated company" (FDI affiliate) and the foreign owner holding at least 10 percent ownership is the "parent." The report describes the role of foreign ownership in U.S. energy enterprises with respect to net investment (including net loans), energy operations, capital investment, and financial performance. Additionally, since energy investments are made in a global context, this report examines patterns of direct investment in foreign

263

Ban On Foreign Scientists' Visits To Weapon Labs Lifted  

Science Journals Connector (OSTI)

Ban On Foreign Scientists' Visits To Weapon Labs Lifted ... Once again, foreign scientists from "sensitive" countries may be able to work with U.S. scientists at Department of Energy nuclear weapons laboratories. ...

JEFF JOHNSON

2000-09-04T23:59:59.000Z

264

Income tax treaties, tax havens, and the foreign tax credit  

Science Journals Connector (OSTI)

Income tax treaties (also called income tax Conventions) are a crucial consideration for many foreign investors in the United States. They are an important consideration for all foreign investors.

Paul Brundage; Adam Starchild

1983-01-01T23:59:59.000Z

265

Japan lifts bars slightly on foreign capital investment  

Science Journals Connector (OSTI)

Japan lifts bars slightly on foreign capital investment ... Last week, after months (actually years) of debate, Japan took its first tentative steps toward liberalizing the rules that govern foreign capital investment when the cabinet approved the government's decontrol plan. ...

1967-06-12T23:59:59.000Z

266

Considerations CLASS WANER OF THE U.S. GOVERNMENT'S U.S ..AND FOREIGN PATENT  

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

U.S. GOVERNMENT'S U.S ..AND FOREIGN PATENT U.S. GOVERNMENT'S U.S ..AND FOREIGN PATENT RIGHTS IN INVENTIONS MADE AND TO BE MADE BY SUCCESSFUL A W ARDEES, AND SUBA W ARDEES AND TEAM MEMBERS, IN THE COURSE OF WORK UNDER FUNDING OPPORTUNITY ANNOUNCEMENT DE-FOA- 0000324, FOR A U.S.- CHINA CLEAN ENERGY RESEARCH CENTER (CERC). W(C) 2010-007 On March 29, 2010, the U.S. Department of Energy (DOE) issued a Funding Opportunity Announcement (FOA) intended to develop a U.S.-China Clean Energy Research Center (CERC). This Center would facilitate joint research and development on clean energy by teams of scientists and engineers from the U.S. and China, as well as serve as a clearinghouse to help researchers in each country. Priority topics to be addressed through CERC are: 1. Building energy efficiency

267

Early Argonne reactor lit the way for worldwide nuclear industry -  

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

Early Argonne reactor lit the way for worldwide Early Argonne reactor lit the way for worldwide nuclear industry 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

268

Foreign Fishery Developments Soviet Union and Japan  

E-Print Network [OSTI]

Foreign Fishery Developments Soviet Union and Japan Agree on 1978 Quotas The Soviet Union and Japan year in Moscow. Japan's total 1978 allocation in the Soviet zone was set at 850,000 metric tons (t ex- trapolation of the 1977 quotas, which were 700,000 t for Japan during March-December and 335

269

WA_-01_001_PHILLIPS_PETROLEUM_Waiver_of_Domestic_and_Foreign...  

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

-01001PHILLIPSPETROLEUMWaiverofDomesticandForeign.pdf WA-01001PHILLIPSPETROLEUMWaiverofDomesticandForeign.pdf WA-01001PHILLIPSPETROLEUMWaiverofDomesticand...

270

WA_99_015_FORD_MOTOR_COMPANY_Waiver_of_Domestic_and_Foreign_...  

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

COMPANYWaiverofDomesticandForeign.pdf More Documents & Publications WA97038FORDMOTORCOMPANYWaiverofDomesticandForeign.pdf WA98008GENERALELECTRICCOMPANYWaive...

271

Research News November 2014  

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

They also toured several of NETL's laboratories, including the Fuel Cells Lab, Chemical Looping Reactor, and the Supercomputer and Visualization Center. There, NETL's researchers...

272

Reactor Project Presses Ahead Despite Protests  

Science Journals Connector (OSTI)

...existing research reactors-in Berlin, Braunschweig, Jiilich, Geesthacht, and Munich were built in the 1950s and '60s and, even...the United States and 15 reactors abroad (including one in Geesthacht, Germany) have so far been converted to low-enriched uranium...

Robert Koenig

1995-08-04T23:59:59.000Z

273

Photocatalytic reactor  

DOE Patents [OSTI]

A photocatalytic reactor is described for processing selected reactants from a fluid medium comprising at least one permeable photocatalytic membrane having a photocatalytic material. The material forms an area of chemically active sites when illuminated by light at selected wavelengths. When the fluid medium is passed through the illuminated membrane, the reactants are processed at these sites separating the processed fluid from the unprocessed fluid. A light source is provided and a light transmitting means, including an optical fiber, for transmitting light from the light source to the membrane. 4 figs.

Bischoff, B.L.; Fain, D.E.; Stockdale, J.A.D.

1999-01-19T23:59:59.000Z

274

Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database  

SciTech Connect (OSTI)

Materials behaviors caused by neutron irradiation under fission and/or fusion environments can be little understood without practical examination. Easily accessible material information system with large material database using effective computers is necessary for design of nuclear materials and analyses or simulations of the phenomena. The developed Embrittlement Data Base (EDB) at ORNL is this comprehensive collection of data. EDB database contains power reactor pressure vessel surveillance data, the material test reactor data, foreign reactor data (through bilateral agreements authorized by NRC), and the fracture toughness data. The lessons learned from building EDB program and the associated database management activity regarding Material Database Design Methodology, Architecture and the Embedded QA Protocol are described in this report. The development of IAEA International Database on Reactor Pressure Vessel Materials (IDRPVM) and the comparison of EDB database and IAEA IDRPVM database are provided in the report. The recommended database QA protocol and database infrastructure are also stated in the report.

Wang, Jy-An John [ORNL

2010-08-01T23:59:59.000Z

275

STATEMENT OF CONSIDERATION CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN  

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

CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN INVENTIONS MADE BY PARTICIPANTS IN THE PERFORMANCE OF COOPERATIVE RESEARCH AND DEVELOPMENT AGREEMENTS ENTERED INTO BY SOUTHERN UNIVERSITY RESEARCH ASSOCIATION, INC., UNDER ITS MANAGEMENT AND OPERATING CONTRACT NO. DE-AC05-84ER40150 - [W(C)-93-002; ORO-550] The Department of Energy (DOE) considers its Government-owned, Contractor- operated (GOCOs) laboratories, such as Southern University Research Association, Inc. (SURA), national resources capable of providing significant contribution to the development of new products and processes, creation of jobs, enhancement of the skill level of the U.S. labor force, and in improved U.S. competitiveness. Congress, recognizing this unique aspect of GOCO laboratories, enacted the

276

STATEMENT OF CONSIDERATIONS ADVANCE WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT  

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

AND FOREIGN PATENT AND FOREIGN PATENT RIGHTS TO INVENTIONS MADE BY BECHTEL NEVADA CORPORATION OR FCI ENVIRONMENTAL INC. IN THE PERFORMANCE OF COOPERATIVE AGREEMENT NO. DE-FC08-95-NV11863 BETWEEN THE DEPARTMENT OF ENERGY AND FCI ENVIRONMENTAL INC. FOR THE DEVELOPMENT OF A SENSOR PLATFORM FOR A VERSATILE SENSOR PROBE SYSTEM, W(A)-95-033, SAN 666. Background Bechtel Nevada Corporation (Bechtel) operates the research and production facilities for the Department of Energy under DOE M&O Contract DE-ACO8-96NV11718. Before Bechtel's M&O Contract became effective on January 1, 1996, EG&G Energy Measurements Division (EG&G/EM) of EG&G Inc. managed and operated the research facility for the Department of Energy under DOE M&O Contract DE-ACO3-93NV11265. In the course of its research activities for DOE, Bechtel and its predecessor EG&G/EM

277

CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN  

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

GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN CERTAIN IDENTIFIED INVENTIONS TO SUCCESSFUL A W ARDEES MADE AND TO BE MADE IN THE COURSE OF OR THROUGH ARP A-E NONCOMPETITIVE AWARDS AND FUNDING OPPORTUNITY ANNOUNCEMENT NOS. DE-FOA-0000675, DE-FOA- 0000674, DE-FOA-0000672, DE-FOA-0000670, DE-FOA-0000474, DE-FOA-0000473 , DE- FOA-0000472, DE-FOA-0000471, DE-FOA-0000470. W(C) 2012-001 ARP A-E was established and charged with the following objectives: 1. To bring a freshness, excitement, and sense of mission to energy research that will attract many of the U.S.'s best and brightest minds-those of experienced scientists and engineers, and, especially, those of students and young researchers, including persons in the entrepreneurial world; 2. To focus on creative "out-of-the-box" transformational energy research that

278

STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENTS U.S. AND FOREIGN PATENT RIGHTS  

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

U.S. AND FOREIGN PATENT RIGHTS U.S. AND FOREIGN PATENT RIGHTS IN INVENTIONS MADE IN THE PERFORMANCE OF COOPERATIVE RESEARCH AND DEVELOPMENT AGREEMENTS ENTERED INTO BY BDM OKLAHOMA, INC. UNDER ITS MANAGEMENT AND OPERATING CONTRACT NO. DE-AC22-94PC91008; W(C)-94-007, CH-0833 The Department of Energy (DOE) considers its Government-owned, Contractor-operated (GOCOs) laboratories, such as the Bartlesville Research Facility at the National Institute for Petroleum and Energy Research (NIPER), operated for DOE by BDM Oklahoma, Inc., as national resources capable of providing significant contributions to the development of new products and processes, creation ofjobs, enhancement of the skill level of the U.S. labor force, and improved U.S. competitiveness. Congress, recognizing this unique aspect of GOCO laboratories, enacted the National

279

Hybrid adsorptive membrane reactor  

DOE Patents [OSTI]

A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

Tsotsis, Theodore T. (Huntington Beach, CA); Sahimi, Muhammad (Altadena, CA); Fayyaz-Najafi, Babak (Richmond, CA); Harale, Aadesh (Los Angeles, CA); Park, Byoung-Gi (Yeosu, KR); Liu, Paul K. T. (Lafayette Hill, PA)

2011-03-01T23:59:59.000Z

280

Advance Reactor Concepts Technical Review Panel Public Report  

Broader source: Energy.gov [DOE]

The Office of Nuclear Energy supports research and development for advanced reactor technologies. This report documents the results of the 2014 Technical Review Panel (TRP) review of seven advanced reactor concepts. The intent of the process was to identify R&D needs for advanced reactor concepts in order to inform Department of Energy (DOE) Office of Nuclear Energy R&D investment decisions.

Note: This page contains sample records for the topic "foreign 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

Overview of Sandia National Laboratories pulse nuclear reactors  

SciTech Connect (OSTI)

Sandia National Laboratories has designed, constructed and operated bare metal Godiva-type and pool-type pulse reactors since 1961. The reactor facilities were designed to support a wide spectrum of research, development, and testing activities associated with weapon and reactor systems.

Schmidt, T.R. [Sandia National Labs., Albuquerque, NM (United States); Reuscher, J.A. [Texas A& M Univ., College Station, TX (United States)

1994-10-01T23:59:59.000Z

282

Management of Naval Reactors' Cyber Security Program, OIG-0884  

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

Naval Reactors' Naval Reactors' Cyber Security Program DOE/IG-0884 April 2013 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 April 12, 2013 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "Management of Naval Reactors' Cyber Security Program" INTRODUCTION AND OBJECTIVE The Naval Reactors Program (Naval Reactors), an organization within the National Nuclear Security Administration, provides the military with safe and reliable nuclear propulsion plants to power warships and submarines. Naval Reactors maintains responsibility for activities supporting the United States Naval fleet nuclear propulsion systems, including research and

283

GEN-IV Reactors  

Science Journals Connector (OSTI)

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

Taek K. Kim

2013-01-01T23:59:59.000Z

284

The Netherlands Reactor Centre  

Science Journals Connector (OSTI)

... Two illustrated brochures in English have recently J. been issued by the Netherlands Reactor Centre ( ... Centre (Reactor Centrum Nederland). The first* gives a general survey of the ...

S. WEINTROUB

1964-04-04T23:59:59.000Z

285

Concept development of rotating bed chemical looping combustion reactor:.  

E-Print Network [OSTI]

??In this research a new rotary chemical looping combustion (CLC) reactor was developed which is suitable for larger scales and solves some of the issues (more)

Hermans, C.W.M.

2013-01-01T23:59:59.000Z

286

Unclassified Foreign National Visits & Assignments Questionnaire  

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

Unclassified Foreign National Visits & Assignments Questionnaire Unclassified Foreign National Visits & Assignments Questionnaire |Welcome to U.S. Department of Energy Office of Legacy Management! We are looking forward to your visit or assignment with us. In order to comply with our security requirements and ensure that your time with the Department of Energy goes smoothly we need to obtain some information from you prior to your arrival. Please take a few minutes to provide the information requested below for each member of your party that is not a U.S. citizen and then return the form(s) to your host. Please be sure to comply with the deadlines your host has communicated to you for returning this form.| |Part 1: Completed by Visitor Please complete all questions below, as applicable. | |1.|Given (first) name (exactly as it appears on passport)| |

287

Subject: DOE PERSONAL PROPERTY FOREIGN TRANSACTIONS  

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

DOE PERSONAL PROPERTY FOREIGN TRANSACTIONS DOE PERSONAL PROPERTY FOREIGN TRANSACTIONS (Title Transfer, Loan, and Abandonment) References: Atomic Energy Act Sections 161g and 161j., Title 42 of the United States Code (U.S.C.) sections 2201g, and 22201j 42 U.S.C 16312 (Public Law 109-58, title IX, section 972, Aug. 8, 2005, 119 Stat. 899), 41 Code of Federal Regulations (CFR) 102-36.380-395, Federal Management Regulation (FMR) DOE Order 580.1, Department of Energy Personal Property Program 4.c(3) DOE Guide 580.1-1, Department of Energy Personal Property Management Guide Chapter 11.8 When is this Acquisition Letter (AL) Effective? This AL is effective immediately upon issuance. When Does This AL Expire? This AL remains in effect until superseded, or canceled. Guidance in this Acquisition Letter shall

288

Research departments Materials Research Department  

E-Print Network [OSTI]

research reactor and X- radiation from the synchrotron facilities in Hamburg and Grenoble. In this con-parameter experiments in RERAF. Systems Analysis Department The objective of the research is to de- velop and apply are systems reliability, organisation, toxi- cology, informatics, simulation methods, work studies, economics

289

Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting: Volume 1, Plenary session, Severe accident sequence analysis, Risk analysis/PRA applications, Reference plant risk analysis - NUREG-1150, Innovative concepts for increased safety of advanced power reactors  

SciTech Connect (OSTI)

This six-volume report contains 156 papers out of the 175 that were presented at the Fourteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 27-31, 1986. 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 thirty-four different papers presented by researchers from Canada, Czechoslovakia, Finland, Germany, Italy, Japan, Mexico, Spain, Sweden, Switzerland and the 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.

Weiss, A.J. (comp.)

1987-02-01T23:59:59.000Z

290

SRS Small Modular Reactors  

SciTech Connect (OSTI)

The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

None

2012-04-27T23:59:59.000Z

291

SRS Small Modular Reactors  

ScienceCinema (OSTI)

The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

None

2014-05-21T23:59:59.000Z

292

REQUEST BY THE GENERAL ELECTRIC COMPANY FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN  

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

ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN SUBJECT INVENTIONS MADE IN THE COURSE OF OR UNDER LOCKHEED MARTIN ENERGY RESEARCH CORPORATION SUBCONTRACT NO. 85X-SZ581C UNDER PRIME CONTRACT NO. DE- AC05-960R22464; DOE WAIVER DOCKET W(A)-98-008 [ORO-740] The General Electric Company (GE) has made a timely request for an advance waiver to worldwide rights in Subject Inventions made in the course of or under Lockheed Martin Energy Research (LMER) Subcontract No. 85X-SZ581C under LMER Prime Contract No. DE-AC05-960R22464. In addition, GE wishes to acquire a nonexclusive, paid-up irrevocable, worldwide license to make, have made, and use certain subcontractors' inventions and discoveries made under this subcontract when the subcontractor has agreed to such license. The scope of the work is to achieve a cost

293

A gluttonous plant reveals how its cellular power plant devours foreign DNA  

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

December 20, 2013 December 20, 2013 A gluttonous plant reveals how its cellular power plant devours foreign DNA Amborella trichopoda, a sprawling shrub that grows on just a single island in the remote South Pacific, is the only plant in its family and genus. It is also one of the oldest flowering plants, having branched off from others about 200 million years ago. Now, researchers from Indiana University, with the U.S. Department of Energy Joint Genome Institute (DOE JGI), Penn State University, and the Institute of Research for Development in New Caledonia, have determined a remarkable expansion of the genome of the plant's critical energy-generating structures. Its mitochondria, the plant's energy-producing organelles, in an epic demonstration of horizontal gene transfer, have acquired six genome equivalents of foreign DNA -- one from a

294

Reducing Foreign Lithium Dependence through Co-Production of Lithium from Geothermal Brine  

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

Foreign Lithium Dependence through Co-Production of Lithium from Foreign Lithium Dependence through Co-Production of Lithium from Geothermal Brine Kerry Klein 1 , Linda Gaines 2 1 New West Technologies LLC, Washington, DC, USA 2 Center for Transportation Research, Argonne National Laboratory, Argonne, IL, USA KEYWORDS Mineral extraction, zinc, silica, strategic metals, Imperial Valley, lithium ion batteries, electric- drive vehicles, battery recycling ABSTRACT Following a 2009 investment of $32.9 billion in renewable energy and energy efficiency research through the American Recovery and Reinvestment Act, President Obama in his January 2011 State of the Union address promised deployment of one million electric vehicles by 2015 and 80% clean energy by 2035. The United States seems poised to usher in its bright energy future,

295

State Administration for Foreign Exchange | Open Energy Information  

Open Energy Info (EERE)

State Administration for Foreign Exchange State Administration for Foreign Exchange Jump to: navigation, search TODO: More information needed This article is a stub. You can help OpenEI by expanding it. China's State Administration For Foreign Exchange (SAFE) is also responsible for NGOs http://en.wikipedia.org/wiki/State_Administration_of_Foreign_Exchange http://www.csmonitor.com/World/Asia-Pacific/2010/0520/Law-chokes-Chinese-NGOs-foreign-funding Retrieved from "http://en.openei.org/w/index.php?title=State_Administration_for_Foreign_Exchange&oldid=306631" Categories: Articles with outstanding TODO tasks Stubs What links here Related changes Special pages Printable version Permanent link Browse properties 429 Throttled (bot load) Error 429 Throttled (bot load) Throttled (bot load) Guru Meditation:

296

Foreign Direct Investment in U.S. Energy 2001  

Gasoline and Diesel Fuel Update (EIA)

Foreign Direct Investment in U.S. Energy 2002 Foreign Direct Investment in U.S. Energy 2002 December 2004 Foreign Direct Investment in U.S. Energy 2002 The purpose of this foreign direct investment report is to provide an assessment of the extent of foreign ownership of energy assets in the United States. Section 657, Subpart 8 of the U.S. Department of Energy Organization Act (Public Law 95-91) requires an annual report to Congress which presents: "a summary of activities in the United States by companies which are foreign owned or controlled and which own or control United States energy sources and supplies ...." EIA intends the information in this report for use by the U.S. Congress, Government agencies, industry analysts, and the general public. Introduction

297

Nuclear reactor  

DOE Patents [OSTI]

A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

Thomson, Wallace B. (Severna Park, MD)

2004-03-16T23:59:59.000Z

298

The High Flux Isotope Reactor at Oak Ridge National Laboratory  

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

The High Flux Isotope Reactor at ORNL The High Flux Isotope Reactor at ORNL Aerial of the High Flux Isotope Reactor Site The High Flux Isotope Reactor site is located on the south side of the ORNL campus and is about a three-minute drive from her sister neutron facility, the Spallation Neutron Source. Operating at 85 MW, HFIR is the highest flux reactor-based source of neutrons for research in the United States, and it provides one of the highest steady-state neutron fluxes of any research reactor in the world. The thermal and cold neutrons produced by HFIR are used to study physics, chemistry, materials science, engineering, and biology. The intense neutron flux, constant power density, and constant-length fuel cycles are used by more than 500 researchers each year for neutron scattering research into

299

THREE ESSAYS ON FOREIGN DIRECT INVESTMENT AND BILATERAL INVESTMENT TREATIES.  

E-Print Network [OSTI]

??In the past several decades, a significant, worldwide expansion in bilateral investment treaties (BITs) occurred and aimed to improve protection for foreign investors rights and (more)

Vashchilko, Tatiana

2011-01-01T23:59:59.000Z

300

PIA - Foreign Travel Management System (FTMS) | Department of...  

Office of Environmental Management (EM)

(FTMS) PIA - Foreign Travel Management System (FTMS) More Documents & Publications PIA - INL PeopleSoft - Human Resource System PIA - INL SECURITY INFORMATION MANAGEMENT SYSTEM...

Note: This page contains sample records for the topic "foreign 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

PIA - Foreign Access Central Tracking System (FACTS) | Department...  

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

PIA - Foreign Access Central Tracking System (FACTS) More Documents & Publications PIA - INL SECURITY INFORMATION MANAGEMENT SYSTEM BUSINESS ENCLAVE PIA - INL PeopleSoft - Human...

302

ORISE: Securing the Golden State from threats foreign and domestic  

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

Securing the Golden State from threats foreign and domestic ORISE helps California emergency planners with innovative training on state and local levels To protect the state of...

303

Assessing political risk for foreign investments  

SciTech Connect (OSTI)

Political risk assessment provides a prediction of the likelihood that future foreign government actions will deteriorate the return on a planned foreign investment. Such political risk predictions are commonly provided with great assurance by political experts. Political risk assessments are frequently quantified to two or three significant figures, so that comparisons can be made between various countries, at various times in the future. It is my contention that most of such quantifications and predictions are nonsense; that the political future is not being accurately predicted. It is useful to describe some general axioms on predicting the future: (1) Future events can be predicted in a rigorous manner only if they represent expected outcomes of physical laws; (2) Future events can be predicted with some statistical confidence if they represent a modest extrapolation of consistent history into the future; (3) The farther into the future one predicts, the less reliable history-based predictions should be: (4) Predictions become less certain as more parameters influence the event; (5) Predictions must be less certain as more precision is required; and (6) Predictions of singular future complex political events are merely guesses, no matter how they may be swaddled in statistical mumbo-jumbo. For proper analysis of political risk it is important to create multiple scenarios of the future, to be well acquainted with foreign politics, and to understand the economic fundamentals of the country where you are considering investments. Such approaches allow management to look for possible flexibilities in investments, to consider insurance, hedging, and other risk abatement techniques against some of the most likely negative political/economic outcomes.

Downey, M.W.

1995-12-31T23:59:59.000Z

304

Evaluation of Alternate Materials for Coated Particle Fuels for the Gas-Cooled Fast Reactor. Laboratory Directed Research and Development Program FY 2006 Final Report  

SciTech Connect (OSTI)

Candidate ceramic materials were studied to determine their suitability as Gas-Cooled Fast Reactor particle fuel coatings. The ceramics examined in this work were: TiC, TiN, ZrC, ZrN, AlN, and SiC. The studies focused on (i) chemical reactivity of the ceramics with fission products palladium and rhodium, (ii) the thermomechanical stresses that develop in the fuel coatings from a variety of causes during burnup, and (iii) the radiation resiliency of the materials. The chemical reactivity of TiC, TiN, ZrC, and ZrN with Pd and Rh were all found to be much lower than that of SiC. A number of important chemical behaviors were observed at the ceramic-metal interfaces, including the formation of specific intermetallic phases and a variation in reaction rates for the different ceramics investigated. Based on the data collected in this work, the nitride ceramics (TiN and ZrN) exhibit chemical behavior that is characterized by lower reaction rates with Pd and Rh than the carbides TiC and ZrC. The thermomechanical stresses in spherical fuel particle ceramic coatings were modeled using finite element analysis, and included contributions from differential thermal expansion, fission gas pressure, fuel kernel swelling, and thermal creep. In general the tangential stresses in the coatings during full reactor operation are tensile, with ZrC showing the lowest values among TiC, ZrC, and SiC (TiN and ZrN were excluded from the comprehensive calculations due to a lack of available materials data). The work has highlighted the fact that thermal creep plays a critical role in the development of the stress state of the coatings by relaxing many of the stresses at high temperatures. To perform ion irradiations of sample materials, an irradiation beamline and high-temperature sample irradiation stage was constructed at the University of Wisconsins 1.7MV Tandem Accelerator Facility. This facility is now capable of irradiating of materials to high dose while controlling sample temperature up to 800C.

Paul A. Demkowicz; Karen Wright; Jian Gan; David Petti; Todd Allen; Jake Blanchard

2006-09-01T23:59:59.000Z

305

STATEMENT OF CONSIDERATIONS REQUEST BY CHEMICAL RESEARCH AND LICENSING COMPANY FOR AN  

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

4 12:09 FR IPL DOE CH 630 252 2??9 TO RGCP-HO P. 02/03 4 12:09 FR IPL DOE CH 630 252 2??9 TO RGCP-HO P. 02/03 * * STATEMENT OF CONSIDERATIONS REQUEST BY CHEMICAL RESEARCH AND LICENSING COMPANY FOR AN ADVANCE WAIVER OF PATENT RIGHTS UNDER DOE COOPERATIVE AGREEMENT NO- DE-FC36-04G014152; ENTITLED "ADVANCES IN PROCESS INTENSIFICATION THROUGH MULTI-FUNCTIONAL REACTOR ENGINEERING"; W(A)-04-057;CH-1227 As set out in the attached waiver petition and in subsequent discussions with DOE Patent Counsel, Chemical Research and Licensing Company (CR&L) has requested an advance waiver of domestic and foreign patent rights for all subject inventions made under the above-identified cooperative agreement by its employees and its subcontractors' employees, regardless of tier, except inventions made by subcontractors eligible to retain title to inventions

306

Why Nuclear Energy? - Reactors designed/built by Argonne National  

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

Nuclear Energy: Nuclear Energy: Why Nuclear Energy? 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 Argonne's Nuclear Science and Technology Legacy

307

Development of a system model for advanced small modular reactors.  

SciTech Connect (OSTI)

This report describes a system model that can be used to analyze three advance small modular reactor (SMR) designs through their lifetime. Neutronics of these reactor designs were evaluated using Monte Carlo N-Particle eXtended (MCNPX/6). The system models were developed in Matlab and Simulink. A major thrust of this research was the initial scoping analysis of Sandia's concept of a long-life fast reactor (LLFR). The inherent characteristic of this conceptual design is to minimize the change in reactivity over the lifetime of the reactor. This allows the reactor to operate substantially longer at full power than traditional light water reactors (LWRs) or other SMR designs (e.g. high temperature gas reactor (HTGR)). The system model has subroutines for lifetime reactor feedback and operation calculations, thermal hydraulic effects, load demand changes and a simplified SCO2 Brayton cycle for power conversion.

Lewis, Tom Goslee,; Holschuh, Thomas Vernon,

2014-01-01T23:59:59.000Z

308

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.

309

Features of a subcritical nuclear reactor  

Science Journals Connector (OSTI)

Abstract A subcritical nuclear reactor is a device where the nuclear-fission chain reaction is initiated and maintained using an external neutron source. It is a valuable educational and research tool where in a safe way many reactor parameters can be measured. Here, we have used the six-factor formula to calculate the effective multiplication factor of a subcritical nuclear reactor Nuclear Chicago model 9000. Using the MCNP5 code, a three-dimensional model of the subcritical reactor was developed to estimate the effective multiplication factor, the neutron spectra, and the total and thermal neutron fluences along the radial and axial axis. The MCNP5 results of the effective multiplication factor were compared with those obtained from the six-factor formula. The effective dose and the Ambient dose equivalent, at three sites outside the reactor, were estimated; the Ambient dose equivalent was also measured and compared with the calculated values.

Hector Rene Vega-Carrillo; Isvi Ruben Esparza-Garcia; Alvaro Sanchez

2015-01-01T23:59:59.000Z

310

Small Modular Nuclear Reactors | Department of Energy  

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

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

311

Controlled Fusion and Reactors of the Tokamak Type  

Science Journals Connector (OSTI)

Research on fusion reactor problems has increased dramatically as the plasma physics of magnetic confinement continues to make substantial progress. As part of this research several studies (16) have been comple...

Robert W. Conn

1977-01-01T23:59:59.000Z

312

UCLA program in reactor studies: The ARIES tokamak reactor study  

SciTech Connect (OSTI)

The ARIES research program is a multi-institutional effort to develop several visions of tokamak reactors with enhanced economic, safety, and environmental features. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Four ARIES visions are currently planned for the ARIES program. The ARIES-1 design is a DT-burning reactor based on modest'' extrapolations from the present tokamak physics database and relies on either existing technology or technology for which trends are already in place, often in programs outside fusion. ARIES-2 and ARIES-4 are DT-burning reactors which will employ potential advances in physics. The ARIES-2 and ARIES-4 designs employ the same plasma core but have two distinct fusion power core designs; ARIES-2 utilize the lithium as the coolant and breeder and vanadium alloys as the structural material while ARIES-4 utilizes helium is the coolant, solid tritium breeders, and SiC composite as the structural material. Lastly, the ARIES-3 is a conceptual D-{sup 3}He reactor. During the period Dec. 1, 1990 to Nov. 31, 1991, most of the ARIES activity has been directed toward completing the technical work for the ARIES-3 design and documenting the results and findings. We have also completed the documentation for the ARIES-1 design and presented the results in various meetings and conferences. During the last quarter, we have initiated the scoping phase for ARIES-2 and ARIES-4 designs.

Not Available

1991-01-01T23:59:59.000Z

313

High Flux Beam Reactor | Environmental Restoration Projects | BNL  

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

Environmental Protection Division Environmental Protection Division Home Reactor Projects Celebrating DOE's Cleanup Accomplishments (PDF) Brookhaven Graphite Research Reactor(BGRR) BGRR Overview BGRR Complex Description Decommissioning Decision BGRR Complex Cleanup Actions BGRR Documents BGRR Science & Accomplishments High Flux Beam Reactor (HFBR) HFBR Overview HFBR Complex Description Decommissioning Decision HFBR Complex Cleanup Actions HFBR Documents HFBR Science & Accomplishments Groundwater Protection Group Environmental Protection Division Contact > See also: HFBR Science & Accomplishments High Flux Beam Reactor Under the U.S. Department of Energy (DOE), the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL) underwent stabilization and partial decommissioning to prepare the HFBR confinement for long-term safe

314

Light Water Reactor Sustainability (LWRS) Program | Department of Energy  

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

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

315

Advanced Test Reactor National Scientific User Facility  

SciTech Connect (OSTI)

The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is a large test reactor for providing the capability for studying the effects of intense neutron and gamma radiation on reactor materials and fuels. The ATR is a pressurized, light-water, high flux test reactor with a maximum operating power of 250 MWth. The INL also has several hot cells and other laboratories in which irradiated material can be examined to study material irradiation effects. In 2007 the US Department of Energy (DOE) designated the ATR as a National Scientific User Facility (NSUF) to facilitate greater access to the ATR and the associated INL laboratories for material testing research by a broader user community. This paper highlights the ATR NSUF research program and the associated educational initiatives.

Frances M. Marshall; Jeff Benson; Mary Catherine Thelen

2011-08-01T23:59:59.000Z

316

Nuclear Energy Research Brookhaven National  

E-Print Network [OSTI]

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

Ohta, Shigemi

317

Profiles of foreign direct investment in US energy, 1992  

SciTech Connect (OSTI)

The report reviews the patterns of foreign ownership interest in US energy enterprises, exclusive of portfolio investment (<10% ownership of a US enterprise). It profiles the involvement of foreign-affiliated US companies in the following areas: domestic petroleum production (including natural gas), reserve holdings, refining and marketing activities, coal production, and uranium exploration and development.

Not Available

1994-05-16T23:59:59.000Z

318

Attrition reactor system  

DOE Patents [OSTI]

A reactor vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the reactor vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur. 2 figures.

Scott, C.D.; Davison, B.H.

1993-09-28T23:59:59.000Z

319

Elementary Reactor Physics  

Science Journals Connector (OSTI)

... THERE are few subjects which have developed at the rate at which reactor physics and ... physics and reactor theory have done. This, of course, is largely due to the circumstances in ...

J. F. HILL

1962-02-10T23:59:59.000Z

320

Colliding Beam Fusion Reactors  

Science Journals Connector (OSTI)

The recirculating power for virtually all types of fusion reactors has previously been calculated [1] with the FokkerPlanck equation. The reactors involve non-Maxwellian plasmas. The calculations are ... the rec...

Norman Rostoker; Artan Qerushi; Michl Binderbauer

2003-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

Our Dependence on Foreign Oil Is Declining | Department of Energy  

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

Dependence on Foreign Oil Is Declining Dependence on Foreign Oil Is Declining Our Dependence on Foreign Oil Is Declining March 1, 2012 - 11:02am Addthis Image courtesy of whitehouse.gov Image courtesy of whitehouse.gov Megan Slack Deputy Director of Digital Content, White House Office of Digital Strategy What are the key facts? America's dependence on foreign oil has decreased every year since President Obama took office. We need an all-out, all-of-the-above strategy to protect Americans from high energy prices in the long run. Editor's Note: This post originally appeared on the White House Blog. America's dependence on foreign oil has gone down every single year since President Obama took office. In 2010, we imported less than 50 percent of the oil our nation consumed-the first time that's happened in 13

322

Our Dependence on Foreign Oil Is Declining | Department of Energy  

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

Our Dependence on Foreign Oil Is Declining Our Dependence on Foreign Oil Is Declining Our Dependence on Foreign Oil Is Declining March 1, 2012 - 11:02am Addthis Image courtesy of whitehouse.gov Image courtesy of whitehouse.gov Megan Slack Deputy Director of Digital Content, White House Office of Digital Strategy What are the key facts? America's dependence on foreign oil has decreased every year since President Obama took office. We need an all-out, all-of-the-above strategy to protect Americans from high energy prices in the long run. Editor's Note: This post originally appeared on the White House Blog. America's dependence on foreign oil has gone down every single year since President Obama took office. In 2010, we imported less than 50 percent of the oil our nation consumed-the first time that's happened in 13

323

EA-1255: Project Partnership Transportation of Foreign-Owned Enriched  

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

5: Project Partnership Transportation of Foreign-Owned 5: Project Partnership Transportation of Foreign-Owned Enriched Uranium from the Republic of Georgia EA-1255: Project Partnership Transportation of Foreign-Owned Enriched Uranium from the Republic of Georgia SUMMARY This EA evaluates the environmental impacts for the proposal to transport 5.26 kilograms of enriched uranium-23 5 in the form of nuclear fuel, from the Republic of Georgia to the United Kingdom. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 30, 1998 EA-1255: Finding of No Significant Impact Project Partnership Transportation of Foreign-Owned Enriched Uranium from the Republic of Georgia April 30, 1998 EA- 1255: Finding of No Significant Impact Project Partnership Transportation of Foreign-Owned Enriched Uranium from

324

STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENTS' U.S. AND FOREIGN PATENT RIGHTS  

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

GOVERNMENTS' U.S. AND FOREIGN PATENT RIGHTS GOVERNMENTS' U.S. AND FOREIGN PATENT RIGHTS IN CERTAIN IDENTIFIED INVENTIONS MADE IN THE COURSE OF OR UNDER MANAGEMENT AND OPERATING CONTRACT NO. DE-AC06-87RL10930 BETWEEN THE DEPARTMENT OF ENERGY AND WESTINGHOUSE HANFORD COMPANY The Department of Energy (DOE), unlike most other Government agencies, employs contractors, both for-profit and nonprofit organizations, to manage and operate certain of its major research, production and weapons facilities, and its National Laboratories. Westinghouse Hanford Company (WHC), a large business, for-profit corporation, under Prime Contract DE-ACO6-87RL10930 with DOE, manages and operates certain of the Government-owned facilities at the Hanford Site near Richland, Washington. These Government-owned, Contractor-operated facilities have for some

325

STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN  

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

U.S. AND FOREIGN PATENT RIGHTS IN U.S. AND FOREIGN PATENT RIGHTS IN INVENTIONS ARISING OUT OF THE RESEARCH AND DEVELOPMENT ACTIVITIES CONDUCTED UNDER THE UNIVERSITY OF CHICAGO'S MISSION SUPPORT COMMITMENT FOR STRATEGIC COLLABORATIVE INITIATIVES SET FORTH IN APPENDIX D OF MANAGEMENT AND OPERATING CONTRACT NO. DE-AC02- 06CH11357 BETWEEN THE DEPARTMENT OF ENERGY (DOE) AND UCHICAGO ARGONNE , LLC, AS OPERATOR OF ARGONNE NATIONAL LABORATORY (ANL); W(C) 08-008, CH-1454 The University of Chicago (University) is a nonprofit educational organization , which is the sole member of UChicago Argonne , LLC (the Contractor), which manages and operates the Government owned facilities of the Department of Energy's Argonne National Laboratory (Laboratory) in Argonne , Illinois under Prime Contract DE-AC02-

326

STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U. S. AND FOREIGN PATENT  

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

FOREIGN PATENT FOREIGN PATENT RIGHTS IN INVENTIONS MADE IN THE PERFORMANCE OF COOPERATIVE RESEARCH AND DEVELOPMENT AGREEMENTS ENTERED INTO BY WESTINGHOUSE SAVANNAH RIVER COMPANY (WSRC), UNDER ITS MANAGEMENT AND OPERATING CONTRACT NO. DE-AC09-89SR18035 W(C)-93-009 The Department of Energy (DOE) considers its Government-owned, Contractor-operated (GOCOs) laboratories, such as WSRC, national resources capable of providing significant contribution to the development of new products and processes, creation of jobs, enhancement of the skill level of the U. S. labor force, and in improved U. S. competitiveness. Congress, recognizing this unique aspect of GOCO laboratories, enacted the National Competitiveness Technology Transfer Act of 1989, hereinafter "Act", (Public Law 101-189).

327

STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN  

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

CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN INVENTIONS MADE IN THE PERFORMANCE OF COOPERATIVE RESEARCH AND DEVELOPMENT AGREEMENTS ENTERED INTO BY THE REGENTS OF THE UNIVERSITY OF CALIFORNIA UNDER MANAGEMENT AND OPERATING CONTRACT NO. DE-ACO3-76SF00098 BETWEEN THE DEPARTMENT OF ENERGY AND THE REGENTS OF THE UNIVERSITY OF CALIFORNIA [W(C) -91-ol; SAN 581 1 Background Lawrence Berkeley Laboratory (LBL) is owned by the U.S. Government and operated by the Regents of the University of California (hereinafter Regents) under contract with the Department of Energy (DOE). DOE considers its Government-Owned, Contractor-Operated (GOCO) laboratories, such as LBL, national resources capable of providing significant contribution to the development of new products and processes, creation of jobs,

328

STATEMENT OF CONSIDERATIONS REQUEST BY PRAXAIR, INC. FOR WAIVER OF DOMESTIC AND FOREIGN  

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

PRAXAIR, INC. FOR WAIVER OF DOMESTIC AND FOREIGN PRAXAIR, INC. FOR WAIVER OF DOMESTIC AND FOREIGN PATENT RIGHTS IN AN IDENTIFIED INVENTION, DOE DOCKET NO. S- 115,861 MADE UNDER DOE COOPERATIVE AGREEMENT NO. DE-FC26- 05NT42469, SUBCONTRACT QZ001, W(I)-08-011, CH1428 This waiver request by Praxair, Inc., is for an identified invention developed under Praxair's subcontract with Eltron Research. Eltron was awarded a cooperative agreement for work entitled, "Scale-Up Hydrogen Transport Membranes for IGCC and FutureGen Coal to Hydrogen Production Plants". Eltron is a small business whose patent rights under this cooperative agreement are governed by the terms of 48 CFR 952.227-11. The terms of 48 CFR 952.227-13, Acquisition by the Government, were then flowed down by Eltron in the subcontract

329

Basic Engineering Research for D&D of R. Reactor Storage Pond Sludge: Electrokinetics, Carbon Dioxide Extraction, and Supercritical Water Oxidation  

SciTech Connect (OSTI)

Collaborating researchers at the University of South Carolina (USC), Clemson University (CU), and the Savannah River Site (SRS) are investigating the fundamentals of a combined extraction and destruction process for the decontamination and decommissioning (D&D) of PCB-contaminated materials as found at DOE sites. Currently, the volume of PCBs and PCB contaminated wastes at DOE sites nationwide is approximately 19,000 m3. While there are a number of existing and proposed processes for the recovery and/or destruction of these persistent 4 pollutants, none has emerged as the preferred choice. Therefore, this research focuses on combining novel processes to solve the problem. The research objectives are to investigate benign dense-fluid extraction with either carbon dioxide (USC) or hot water (CU), followed by destruction of the extracted PCBs via either electrochemical (USC) or hydrothermal (CU) oxidation. Based on the results of these investigations, a combined extraction and destruction process that incorporates the most successful elements of the various processes will be recommended for application to contaminated DOE sites.

Hamilton, Edward A.; Bruce, David A.; Oji, Lawrence; White, Ralph E.; Matthews, Michael A.; Thies, Mark C.

1999-06-01T23:59:59.000Z

330

WC_1997_003_CLASS_WAIVER_of_the_Governmens_ULS_and_Foreign.pdf...  

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

1997003CLASSWAIVERoftheGovernmensULSandForeign.pdf WC1997003CLASSWAIVERoftheGovernmensULSandForeign.pdf WC1997003CLASSWAIVERoftheGovernmensULSandForeig...

331

WC_1991_003_CLASS_WAIVER_of_the_Government_US_and_Foreign_Pa...  

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

1003CLASSWAIVERoftheGovernmentUSandForeignPa.pdf WC1991003CLASSWAIVERoftheGovernmentUSandForeignPa.pdf WC1991003CLASSWAIVERoftheGovernmentUSandForeig...

332

WC_1993_006_CLASS_WAIVER_of_the_Governments_Us_and_Foreign_P...  

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

3006CLASSWAIVERoftheGovernmentsUsandForeignP.pdf WC1993006CLASSWAIVERoftheGovernmentsUsandForeignP.pdf WC1993006CLASSWAIVERoftheGovernmentsUsandForei...

333

WC_1991_002_CLASS_WAIVER_OF_the_Government_US_and_Foreign_Pa...  

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

WC1991002CLASSWAIVEROFtheGovernmentUSandForeignPa.pdf WC1991002CLASSWAIVEROFtheGovernmentUSandForeignPa.pdf WC1991002CLASSWAIVEROFtheGovernmentUSand...

334

WC_1992_002_CLASS_WAIVER_of_the_Government_US_and_Foreign_Pa...  

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

2002CLASSWAIVERoftheGovernmentUSandForeignPa.pdf WC1992002CLASSWAIVERoftheGovernmentUSandForeignPa.pdf WC1992002CLASSWAIVERoftheGovernmentUSandForeig...

335

WC_1993_013_CLASS_WAIVER_of_the_Governments_US_and_Foreign_P...  

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

3013CLASSWAIVERoftheGovernmentsUSandForeignP.pdf WC1993013CLASSWAIVERoftheGovernmentsUSandForeignP.pdf WC1993013CLASSWAIVERoftheGovernmentsUSandForei...

336

Prospects for spheromak fusion reactors  

Science Journals Connector (OSTI)

The reactor study of Hagenson and Krakowski demonstrated the attractiveness of the spheromak as a compact fusion reactor, based on...

T. K. Fowler; D. D. Hua

1995-06-01T23:59:59.000Z

337

Light Water Reactor Sustainability Nondestructive Evaluation for Concrete  

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

Nondestructive Evaluation for Nondestructive Evaluation for Concrete Research and Development Roadmap Light Water Reactor Sustainability Nondestructive Evaluation for Concrete Research and Development Roadmap Materials issues are a key concern for the existing nuclear reactor fleet as material degradation can lead to increased maintenance, increased downtown, and increased risk. Extending reactor life to 60 years and beyond will likely increase susceptibility and severity of known forms of degradation. Additionally, new mechanisms of materials degradation are also possible. The purpose of the US Department of Energy Office of Nuclear Energy's Light Water Reactor Sustainability (LWRS) Program is to develop technologies and other solutions that can improve the reliability, sustain the safety, and extend

338

Improved vortex reactor system  

DOE Patents [OSTI]

An improved vortex reactor system for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor.

Diebold, James P. (Lakewood, CO); Scahill, John W. (Evergreen, CO)

1995-01-01T23:59:59.000Z

339

BASIC ENGINEERING RESEARCH FOR D&D OF R REACTOR STORAGE POND SLUDGE: ELECTROKINETICS, CARBON DIOXIDE EXTRACTION, AND SUPERCRITICAL WATER OXIDATION  

SciTech Connect (OSTI)

Large quantities of mixed low level waste (MLLW) that fall under the Toxic Substances Control Act (TSCA) exist and will continue to be generated during D&D operations at DOE sites across the country. Currently, the volume of these wastes is approximately 23,500 m3, and the majority of these wastes (i.e., almost 19,000 m3) consist of PCBs and PCB-contaminated materials. Further, additional PCB-contaminated waste will be generated during D&D operations in the future. The standard process for destruction of this waste is incineration, which generates secondary waste that must be disposed, and the TSCA incinerator at Oak Ridge has an uncertain future. Beyond incineration, no proposed process for the recovery and/or destruction of these persistent pollutants has emerged as the preferred choice for DOE cleanup. The main objective of the project was to investigate and develop a deeper understanding of the thermodynamic and kinetic reactions involved in the extraction and destruction of polychlorinated biphenyls (PCBs) from low-level mixed waste solid matrices in order to provide data that would permit the design of a combined-cycle extraction/destruction process. The specific research objectives were to investigate benign dense-fluid extraction with either carbon dioxide (USC) or hot water (CU), followed by destruction of the extracted PCBs via either electrochemical (USC) or hydrothermal (CU) oxidation. Two key advantages of the process are that it isolates and concentrates the PCBs from the solid matrices (thereby reducing waste volume greatly and removing the remaining low-level mixed waste from TSCA control), and little, if any, secondary solvent or solid wastes are generated. This project was a collaborative effort involving the University of South Carolina (USC), Clemson University (CU), and Westinghouse Savannah River Company (WSRC) (including the Savannah River Technology Center, Facilities Decommissioning Division and Regulatory Compliance). T he project was directed and coordinated by the South Carolina Universities Research and Education Foundation (SCUREF), a consortium of the four public research universities in South Carolina. The original plan was to investigate two PCB extraction processes (supercritical carbon dioxide and hot, pressurized water) and two PCB destruction processes (electrochemical oxidation and hydrothermal oxidation). However, at approximately the mid-point of the three year project, it was decided to focus on the more promising extraction process (supercritical carbon dioxide) and the more promising destruction process (supercritical water oxidation). This decision was taken because the investigation of two processes simultaneously by each university was stretching resources too thin, and because the electrochemical oxidation process needed more concentrated research before it would be ready for application to PCB destruction. The solid matrix chosen for experimental work was Toxi-dry, a commonly used adsorbent made from plant material that is used in cleanup of spills and/or liquid solvents. The Toxi-dry was supplied by the research team member from the Facilities Decommissioning Division, WSRC. This adsorbent is a major component of job control waste.

Matthews, Michael A.; Bruce,David; Davis,Thomas; Thies, Mark; Weidner, John; White, Ralph

2001-12-31T23:59:59.000Z

340

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel  

SciTech Connect (OSTI)

This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integrity of the dry-stored spent fuel from actual foreign experience. Countries covered in this survey are: Argentina, Canada, Federal Republic of Germany (before reunification with the former East Germany), former German Democratic Republic (former East Germany), France, India, Italy, Japan, South Korea, Spain, Switzerland, United Kingdom, and the former USSR (most of these former Republics are now in the Commonwealth of Independent States [CIS]). Industrial dry storage of Magnox fuels started in 1972 in the United Kingdom; Canada began industrial dry storage of CANDU fuels in 1980. The technology for safe storage is generally considered to be developed for time periods of 30 to 100 years for LWR fuel in inert gas and for some fuels in oxidizing gases at low temperatures. Because it will probably be decades before countries will have a repository for spent fuels and high-level wastes, the plans for expanded use of dry storage have increased significantly in recent years and are expected to continue to increase in the near future.

Schneider, K.J.; Mitchell, S.J.

1992-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel  

SciTech Connect (OSTI)

This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integrity of the dry-stored spent fuel from actual foreign experience. Countries covered in this survey are: Argentina, Canada, Federal Republic of Germany (before reunification with the former East Germany), former German Democratic Republic (former East Germany), France, India, Italy, Japan, South Korea, Spain, Switzerland, United Kingdom, and the former USSR (most of these former Republics are now in the Commonwealth of Independent States (CIS)). Industrial dry storage of Magnox fuels started in 1972 in the United Kingdom; Canada began industrial dry storage of CANDU fuels in 1980. The technology for safe storage is generally considered to be developed for time periods of 30 to 100 years for LWR fuel in inert gas and for some fuels in oxidizing gases at low temperatures. Because it will probably be decades before countries will have a repository for spent fuels and high-level wastes, the plans for expanded use of dry storage have increased significantly in recent years and are expected to continue to increase in the near future.

Schneider, K.J.; Mitchell, S.J.

1992-04-01T23:59:59.000Z

342

Reactor vessel support system  

DOE Patents [OSTI]

A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

Golden, Martin P. (Trafford, PA); Holley, John C. (McKeesport, PA)

1982-01-01T23:59:59.000Z

343

Device Scale Model Development for Transport Reactor  

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

Gary J. stiegel Gary J. stiegel Gasification Technology Manager National Energy Technology Laboratory 626 Cochrans Mill Road P.O. Box 10940 Pittsburgh, PA 15236 412-386-4499 gary.stiegel@netl.doe.gov Chris Guenther Computational Science Division National Energy Technology Laboratory 3610 Collins Ferry Road P. O. Box 880 Morgantown, WV 26507 304-285-4483 chris.guenther@netl.doe.gov 8/2006 Gasification Technologies Device Scale MoDel DevelopMent for tranSport reactor Background Coal gasification is an efficient and environmentally acceptable technology that can utilize the vast coal reserves in the United States to produce clean affordable power and reduce dependence on foreign oil. Coal and other carbon containing materials can be gasified to produce a synthesis gas. This syngas can be fed to a

344

Reactor water cleanup system  

DOE Patents [OSTI]

A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling.

Gluntz, Douglas M. (San Jose, CA); Taft, William E. (Los Gatos, CA)

1994-01-01T23:59:59.000Z

345

Reactor water cleanup system  

DOE Patents [OSTI]

A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling. 1 figure.

Gluntz, D.M.; Taft, W.E.

1994-12-20T23:59:59.000Z

346

The Department of Energy's Management of Foreign Travel, IG-0872  

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

The Department of Energy's Management of Foreign Travel DOE/IG-0872 October 2012 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 October 16, 2012 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Management Alert: "The Department of Energy's Management of Foreign Travel" INTRODUCTION The Department of Energy and its workforce of 116,000 Federal and contractor personnel have numerous international exchanges and interactions at different levels and for a variety of important programmatic and other purposes. The Office of Inspector General is currently reviewing the Department's management of international offices and foreign assignments. As

347

Russia's Foreign Policy Toward Iran: A Critical Geopolitics Perspective  

E-Print Network [OSTI]

document contains the authors accepted manuscript. For the publishers version, see the link in the header of this document.] Russias Foreign Policy Toward Iran: A Critical Geopolitics Perspective Mariya Y. Omelicheva Paper citation: Omelicheva..., Mariya Y. Russias Foreign Policy Toward Iran: A Critical Geopolitics Perspective, forthcoming in Journal of Balkan and Near Eastern Studies, 14(3): 331-344, 2012. Abstract: Russias foreign policy stance on nuclear Iran has been a subject of debate...

Omelicheva, Mariya Y.

2012-01-01T23:59:59.000Z

348

CLASS WAIVER OF THE U.S. GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN INVENTIONS  

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

U.S. GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN INVENTIONS U.S. GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN INVENTIONS MADE AND TO BE MADE BY SUCCESSFUL AWARDEE$, AND SUBAWARDEES AND TEAM MEMBERS, IN THE COURSE OF WORK UNDER AWARDS PURSUANT TO FUNDING OPPORTUNITY ANNOUNCEMENT DE-FOA-0000506, FOR A U.S.-INDIA JOINT CLEAN ENERGY RESEARCH AND DEVELOPMENT CENTER (CENTER). W(C) 2012-005 On May 16, 2011, the U.S. Department of Energy (DOE) issued a Funding Opportunity Announcement (FOA) intended to develop a U.S.-India Joint Clean Energy Research and Development Center (Center). This Center would facilitate joint research and development on clean energy by teams of scien t ists and engineers from the U.S. and India and related joint activities, needed to deploy clean energy technologies rapidly with the greatest impact. Priority

349

Heterogeneous Recycling in Fast Reactors  

SciTech Connect (OSTI)

Current sodium fast reactor (SFR) designs have avoided the use of depleted uranium blankets over concerns of creating weapons grade plutonium. While reducing proliferation risks, this restrains the reactor design space considerably. This project will analyze various blanket and transmutation target configurations that could broaden the design space while still addressing the non-proliferation issues. The blanket designs will be assessed based on the transmutation efficiency of key minor actinide (MA) isotopes and also on mitigation of associated proliferation risks. This study will also evaluate SFR core performance under different scenarios in which depleted uranium blankets are modified to include minor actinides with or without moderators (e.g. BeO, MgO, B4C, and hydrides). This will be done in an effort to increase the sustainability of the reactor and increase its power density while still offering a proliferation resistant design with the capability of burning MA waste produced from light water reactors (LWRs). Researchers will also analyze the use of recycled (as opposed to depleted) uranium in the blankets. The various designs will compare MA transmutation efficiency, plutonium breeding characteristics, proliferation risk, shutdown margins and reactivity coefficients with a current reference sodium fast reactor design employing homogeneous recycling. The team will also evaluate the out-of-core accumulation and/or burn-down rates of MAs and plutonium isotopes on a cycle-by-cycle basis. This cycle-by-cycle information will be produced in a format readily usable by the fuel cycle systems analysis code, VISION, for assessment of the sustainability of the deployment scenarios.

Dr. Benoit Forget; Michael Pope; Piet, Steven J.; Michael Driscoll

2012-07-30T23:59:59.000Z

350

Micro -Thermonuclear AB-Reactors for Aerospace  

E-Print Network [OSTI]

The author offers several innovations that he first suggested publicly early in 1983 for the AB multi-reflex engine, space propulsion, getting energy from plasma, etc. (see: A. Bolonkin, Non-Rocket Space Launch and Flight, Elsevier, London, 2006, Chapters 12, 3A). It is the micro-thermonuclear AB-Reactors. That is new micro-thermonuclear reactor with very small fuel pellet that uses plasma confinement generated by multi-reflection of laser beam or its own magnetic field. The Lawson criterion increases by hundreds of times. The author also suggests a new method of heating the power-making fuel pellet by outer electric current as well as new direct method of transformation of ion kinetic energy into harvestable electricity. These offered innovations dramatically decrease the size, weight and cost of thermonuclear reactor, installation, propulsion system and electric generator. Non-industrial countries can produce these researches and constructions. Currently, the author is researching the efficiency of these innovations for two types of the micro-thermonuclear reactors: multi-reflection reactor (ICF) and self-magnetic reactor (MCF).

Alexander Bolonkin

2007-01-08T23:59:59.000Z

351

Modeling for Anaerobic Fixed-Bed Biofilm Reactors  

SciTech Connect (OSTI)

The specific objectives of this research were: 1. to develop an equilibrium model for chemical aspects of anaerobic reactors; 2. to modify the equilibrium model for non-equilibrium conditions; 3. to incorporate the existing biofilm models into the models above to study the biological and chemical behavior of the fixed-film anaerobic reactors; 4. to experimentally verify the validity of these models; 5. to investigate the biomass-holding ability of difference packing materials for establishing reactor design criteria.

Liu, B. Y. M.; Pfeffer, J. T.

1989-06-01T23:59:59.000Z

352

Basic Engineering Research for D and D of R Reactor Storage Pond Sludge: Electrokinetics, Carbon Dioxide Extraction, and Supercritical Water Oxidation  

SciTech Connect (OSTI)

Large quantities of mixed low level waste (MLLW) that fall under the Toxic Substances Control Act (TSCA) exist and will continue to be generated during D and D operations at DOE sites across the country. The standard process for destruction of MLLW is incineration, which has an uncertain future. The extraction and destruction of PCBs from MLLW was the subject of this research Supercritical Fluid Extraction (SFE) with carbon dioxide with 5% ethanol as cosolvent and Supercritical Waster Oxidation (SCWO) were the processes studied in depth. The solid matrix for experimental extraction studies was Toxi-dry, a commonly used absorbent made from plant material. PCB surrogates were 1.2,4-trichlorobenzene (TCB) and 2-chlorobiphenyl (2CBP). Extraction pressures of 2,000 and 4,000 psi and temperatures of 40 and 80 C were studied. Higher extraction efficiencies were observed with cosolvent and at high temperature, but pressure little effect. SCWO treatment of the treatment of the PCB surrogates resulted in their destruction below detection limits.

Michael A. Matthews; David A. Bruce,; Thomas A. Davis; Mark C. Thies; John W. Weidner; Ralph E. White

2002-04-01T23:59:59.000Z

353

SHARP: Reactor Performance and Safety Simulation Suite  

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

SHARP SHARP Argonne National Laboratory's Reactor Performance and Safety Simulation Suite SHARP could save millions in nuclear reactor design and development... The Simulation-based High-efficiency Advanced Reactor Prototyping (SHARP) suite of codes enables virtual design and engineering of nuclear plant behavior that would be impractical from a traditional experimental approach. ...by leveraging the computational power of one of the world's most powerful supercomputers. Exploiting the power of Argonne Leadership Computing Facility's near-petascale computers, researchers have developed a set of simulation tools that provide a highly detailed description of the reactor core and the nuclear plant behavior. This enables the efficient and precise design of tomorrow's safe and clean nuclear energy sources.

354

Role of Political Violence in Foreign Direct Investment Decisions  

Science Journals Connector (OSTI)

Most developing countries are trying to attract foreign direct investment (FDI) because the traditional sources of ... . FDI has other advantages in terms of risk sharing and technology transfers. The role of political

H. Singh

2000-01-01T23:59:59.000Z

355

GCC Inward and Outward Foreign Direct Investment and Capital Flows  

Science Journals Connector (OSTI)

Real economic growth is measured by GDP growth and is often reflected in a high ranking of a countrys economic and financial risk (Calderon et al. 2003). However, ... in 2008. These countries attracted Foreign D...

Mohamed A. Ramady

2014-01-01T23:59:59.000Z

356

Hybridizing BPNN and Exponential Smoothing for Foreign Exchange Rate Prediction  

Science Journals Connector (OSTI)

A challenging task in financial market such as stock market and foreign exchange market is to predict the movement direction of financial markets so as to provide valuable decision information for investors (Lai ...

2007-01-01T23:59:59.000Z

357

Drunk On Oil: Russian Foreign Policy 2000-2007  

E-Print Network [OSTI]

R. and Peter Rutland. "Putin and Russian Foreign Policy."Putin's Russia: Past Imperfect, Future Uncertain. Ed. DaleInc. , 2005. 259-292. Vladimir Putin and Military Reform in

Brugato, Thomas

2008-01-01T23:59:59.000Z

358

When governments break contracts : foreign firms in emerging economies  

E-Print Network [OSTI]

Emerging economy governments commit to protect the property rights of foreign firms through a variety of contracts, from treaties to direct agreements. In an era of liberalized capital flows, these contracts are thought ...

Wellhausen, Rachel L. (Rachel Louise)

2012-01-01T23:59:59.000Z

359

Effective foreign investment in China : utilizing Taiwanese resources  

E-Print Network [OSTI]

It is no doubt that China is expanding its market potential because of its high economic growth and its entry into the World Trade Organizations. This Chinese expansion owes a great deal to foreign direct investment from ...

Takeuchi, Isao, M.B.A. Massachusetts Institute of Technology

2006-01-01T23:59:59.000Z

360

Opportunities and obstacles for foreign investors in Turkish real estate  

E-Print Network [OSTI]

This paper examines the Turkish real estate market from the viewpoint of foreign investors contemplating entering into that market. Since 2002, the government of Turkey has been implementing an aggressive economic reform ...

Halkali, Hasan

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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.


361

The Heroic Framing of US Foreign Policy  

E-Print Network [OSTI]

research and development program to begin to achieve our ultimate goal of eliminating the threat posed by strategic nuclear

Shaw, Emily D.

2010-01-01T23:59:59.000Z

362

Communist China's foreign trade and its implication for Japan  

E-Print Network [OSTI]

COMMUNIST CHINA'S FOREIGN TRADE AND ITS IMPLICATION FOR JAPAN A Thesis by LEH-AN HSIEH Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE August lg72... Major Subject: Economics COMMUNIST CHINA'S FOREIGI'J TRADE AND ITS IMPLICATION FOR JAPAN A Thesis LEH-AN HSIEH Approved as to style and content by: Head of Department Member / Member Member (Member) ABSTRACT Communist China's Foreign Trade...

Hsieh, Leh-An

2012-06-07T23:59:59.000Z

363

Power Reactor Progress  

Science Journals Connector (OSTI)

Argonne kicks off EBWR; Allis-Chalmers plans power reactor using both nuclear and conventional fuels ... NUCLEAR POWER took two giant steps last week. ... Just as the first nuclear power system in the U. S. designed and built solely for the generation of electric power went into full operation at Argonne, Allis-Chalmers came up with a new twist in power reactorsa controlled recirculation boiling reactor (CRBR) using both nuclear and conventional fuels (C&EN, Feb. 18, page 7). ...

1957-02-25T23:59:59.000Z

364

Improved vortex reactor system  

DOE Patents [OSTI]

An improved vortex reactor system is described for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor. 12 figs.

Diebold, J.P.; Scahill, J.W.

1995-05-09T23:59:59.000Z

365

AEC Pushes Fusion Reactors  

Science Journals Connector (OSTI)

AEC Pushes Fusion Reactors ... Project Sherwood, as the study program is called, began in 1951-52 soon after the first successful thermonuclear explosion in the Pacific. ...

1955-10-10T23:59:59.000Z

366

Tokamak reactor first wall  

DOE Patents [OSTI]

This invention relates to an improved first wall construction for a tokamak fusion reactor vessel, or other vessels subjected to similar pressure and thermal stresses.

Creedon, R.L.; Levine, H.E.; Wong, C.; Battaglia, J.

1984-11-20T23:59:59.000Z

367

2012_AdvReactor_Factsheet.indd  

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

nuclear.gov nuclear.gov February 15, 2011 A ADVANCED REACTOR CONCEPTS DVANCED REACTOR CONCEPTS The U.S. Department of Energy's Offi ce of Nuclear Energy T he Advanced Reactor Concepts (ARC) program, an expanded version of the Generation IV research, development and demonstration (RD&D) program, sponsors research, development and deployment activities leading to further safety, technical, economical, and environmental advancements of innovative 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 nuclear industry and international partners. These activities will focus on advancing

368

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor...  

Office of Scientific and Technical Information (OSTI)

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor Design and Feasibility Problem Re-direct Destination: Temp Data Fields Rosen, M. A.; Coburn, D. B.; Flynn, T....

369

The ARIES tokamak reactor study  

SciTech Connect (OSTI)

The ARIES study is a community effort to develop several visions of tokamaks as fusion power reactors. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Three ARIES visions are planned, each having a different degree of extrapolation from the present data base in physics and technology. The ARIES-I design assumes a minimum extrapolation from current tokamak physics (e.g., 1st stability) and incorporates technological advances that can be available in the next 20 to 30 years. ARIES-II is a DT-burning tokamak which would operate at a higher beta in the 2nd MHD stability regime. It employs both potential advances in the physics and expected advances in technology and engineering. ARIES-II will examine the potential of the tokamak and the D{sup 3}He fuel cycle. This report is a collection of 14 papers on the results of the ARIES study which were presented at the IEEE 13th Symposium on Fusion Engineering (October 2-6, 1989, Knoxville, TN). This collection describes the ARIES research effort, with emphasis on the ARIES-I design, summarizing the major results, the key technical issues, and the central conclusions.

Not Available

1989-10-01T23:59:59.000Z

370

Portfolio for fast reactor collaboration  

SciTech Connect (OSTI)

The development of the LMFBR type reactor in the United Kingdom is reviewed. Design characteristics of a commercial demonstration fast reactor are presented and compared with the Super Phenix reactor.

Rippon, S.

1981-12-01T23:59:59.000Z

371

Handbook of Reactor Physics  

Science Journals Connector (OSTI)

... THIS handbook is one volume in a series sponsored by the United States Atomic Energy Commission with ... data and reference information in the field of reactors. The volume is devoted to reactor physics and radiation shielding, the latter subject occupying approximately a quarter of the book.

PETER W. MUMMERY

1956-08-25T23:59:59.000Z

372

Fast reactor safety  

Science Journals Connector (OSTI)

... SIR, - In his article on fast reactor safety (26 July, page 270) Norman Dombey claims to introduce to non-specialists ... , page 270) Norman Dombey claims to introduce to non-specialists some features of fast reactors that are not available outside the technical literature. The non-specialist would do well ...

R.D. SMITH

1979-08-23T23:59:59.000Z

373

Instrumentation of Nuclear Reactors  

Science Journals Connector (OSTI)

... s Lecture Theatre on January 8, a symposium of papers on the instrumentation of nuclear reactors was organized, at which about five hundred members and visitors attended, including guests from ... the Institution, took the chair and introduced Sir John Cockcroft, whose lecture on "Nuclear Reactors and their Applications" provided a general background for the three specialized papers which followed. ...

1953-03-07T23:59:59.000Z

374

High Flux Beam Reactor | Environmental Restoration Projects | BNL  

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

Why is the High Flux Beam Reactor Being Decommissioned? Why is the High Flux Beam Reactor Being Decommissioned? HFBR The High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL) is being decommissioned because the Department of Energy (DOE) decided in 1999 that it would be permanently closed. The reactor was shut down in 1997 after tritium from a leak in the spent-fuel pool was found in the groundwater. The HFBR, which had operated from 1965 to 1996, was used solely for scientific research, providing neutrons for materials science, chemistry, biology, and physics experiments. The reactor was shut down for routine maintenance in November of 1996. In January 1997, tritium, a radioactive form of hydrogen and a by-product of reactor operations, was found in groundwater monitoring wells immediately south of the HFBR. The tritium

375

Reactor Physics and Fuel Cycle Analysis - Nuclear Engineering Division  

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

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

376

Simulation of a marine nuclear reactor  

SciTech Connect (OSTI)

A Nuclear-powered ship Engineering Simulation SYstem (NESSY) has been developed by the Japan Atomic Energy Research Institute as an advanced design tool for research and development of future marine reactors. A marine reactor must respond to changing loads and to the ship`s motions because of the ship`s maneuvering and its presence in a marine environment. The NESSY has combined programs for the reactor plant behavior calculations and the ship`s motion calculations. Thus, it can simulate reactor power fluctuations caused by changing loads and the ship`s motions. It can also simulate the behavior of water in the pressurizer and steam generators. This water sloshes in response to the ship`s motions. The performance of NESSY has been verified by comparing the simulation calculations with the measured data obtained by experiments performed using the nuclear ship Mutsu. The effects of changing loads and the ship`s motions on the reactor behavior can be accurately simulated by NESSY.

Kusunoki, Tsuyoshi; Kyouya, Masahiko; Kobayashi, Hideo; Ochiai, Masaaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Office of Nuclear Ship Research and Development

1995-02-01T23:59:59.000Z

377

STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS  

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

IN INVENTIONS MADE IN THE PERFORMANCE OF COOPERATIVE RESEARCH IN INVENTIONS MADE IN THE PERFORMANCE OF COOPERATIVE RESEARCH AND DEVELOPMENT AGREEMENTS (CRADAS) RELATING TO INORGANIC MEMBRANE TECHNOLOGY ENTERED INTO BY LOCKHEED MARTIN ENERGY SYSTEMS, INC. UNDER ITS MANAGEMENT AND OPERATING CONTRACT DE-AC05-840R21400 AND BY LOCKHEED MARTIN ENERGY RESEARCH CORP. UNDER ITS MANAGEMENT AND OPERATING CONTRACT DE-AC05-960R22464; WAIVER ORO-632, W(C)-96-006 The Department of Energy (DOE) previously approved a class waiver [W(C)-90-001] of domestic and foreign patent rights to Martin Marietta Energy Systems, Inc. (Energy Systems) in inventions made by Energy System's employees in the performance of work under a CRADA and to participants in inventions made by their employees under the class of CRADAs entered into by participants with Energy Systems under its

378

Reactor & Nuclear Systems Publications | ORNL  

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

Nuclear Science Home | Science & Discovery | Nuclear Science | Publications and Reports | Reactor and Nuclear Systems Publications SHARE Reactor and Nuclear Systems Publications...

379

E-Print Network 3.0 - argonaut bilbao reactor Sample Search Results  

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

reprocessing and transmutation... with industry, national laboratories, and universities; upgrading and sharing of research reactors Source: Laughlin, Robert B. - Department of...

380

The development of a remote monitoring system for the Nuclear Science Center reactor.  

E-Print Network [OSTI]

??With funding provided by Nuclear Energy Research Initiative (NERI), design of Secure, Transportable, Autonomous Reactors (STAR) to aid countries with insufficient energy supplies is underway. (more)

Jiltchenkov, Dmitri Victorovich

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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

E-Print Network 3.0 - advanced reactor study Sample Search Results  

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

Hotel bargains... to iron out their differences over the site of the International Thermonuclear Experimental Reactor Source: Fusiongnition Research Experiment (FIRE) Collection:...

382

Radiochemical characteristics of tritium to be considered in fusion reactor facility design  

Science Journals Connector (OSTI)

The results of research and development related to radiochemical characteristics of tritium to be considered in a fusion reactor facility design are summarized. Reactions induced by...

S. Ohira; T. Hayashi; W. Shu; T. Yamanishi

2007-06-01T23:59:59.000Z

383

RESEARCH AND DEVELOPMENT ACTIVITIES AT SAVANNAH RIVER SITE'S H CANYON FACILITY  

SciTech Connect (OSTI)

The Savannah River Site's (SRS) H Canyon Facility is the only large scale, heavily shielded, nuclear chemical separations plant still in operation in the U.S. The facility's operations historically recovered uranium-235 (U-235) and neptunium-237 (Np-237) from aluminum-clad, enriched-uranium fuel tubes from Site nuclear reactors and other domestic and foreign research reactors. Today the facility, in conjunction with HB Line, is working to provide the initial feed material to the Mixed Oxide Facility also located on SRS. Many additional campaigns are also in the planning process. Furthermore, the facility has started to integrate collaborative research and development (R&D) projects into its schedule. H Canyon can serve as the appropriate testing location for many technologies focused on monitoring the back end of the fuel cycle, due to the nature of the facility and continued operation. H Canyon, in collaboration with the Savannah River National Laboratory (SRNL), has been working with several groups in the DOE complex to conduct testing demonstrations of novel technologies at the facility. The purpose of conducting these demonstrations at H Canyon will be to demonstrate the capabilities of the emerging technologies in an operational environment. This paper will summarize R&D testing activities currently taking place in H Canyon and discuss the possibilities for future collaborations.

Sexton, L.; Fuller, Kenneth

2013-07-09T23:59:59.000Z

384

An autonomous long-term fast reactor system and the principal design limitations of the concept  

E-Print Network [OSTI]

Actinides MOX Mixed OXide MSR Molten-Salt Reactors NERI Nuclear Energy Research Initiative vii PWR Pressurized Water Reactor RGPu Reactor-Grade Plutonium SCNES Self-Consistent Nuclear Energy System STAR Secure Transportable Autonomous Reactor... of LWR?s, the drastic increase of Am and Cm inventories are observed after uranium fuel irradiation and the second recycling of MOX fuel.1 Therefore, partitioning and transmutation of the recovered MA?s could significantly reduce the long...

Tsvetkova, Galina Valeryevna

2004-09-30T23:59:59.000Z

385

International Power Engineering Research Collaborations  

E-Print Network [OSTI]

- disciplinary projects. Index Terms Collaborative Research and Educa- tion, Renewable Energy, Market Mechanisms range from market mechanisms to renewable en- ergy integration and from specific power topics to inter with foreign institutions in Spain, Brazil, China and Ma- laysia. The presentation discusses the objectives

Gross, George

386

Strengthening the nuclear-reactor fuel cycle against proliferation  

SciTech Connect (OSTI)

Argonne National Laboratory (ANL) conducts several research programs that serve to reduce the risks of fissile-material diversion from the nuclear-reactor fuel cycle. The objectives are to provide economical and efficient neutron or power generation with the minimum of inherent risks, and to further minimize risks by utilizing sophisticated techniques to detect attempts at material diversion. This paper will discuss the Reduced Enrichment Research and Test Reactor (RERTR) Program, the Isotope Correlation Technique (ICT), and Proliferation-Resistant Closed-Cycle Reactors. The first two are sponsored by the DOE Office of Arms Control and Nonproliferation.

Travelli, A.; Snelgrove, J.; Persiani, P. [Argonne National Lab., IL (United States). Arms Control and Nonproliferation Program

1992-12-31T23:59:59.000Z

387

Nuclear reactor control column  

DOE Patents [OSTI]

The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest cross-sectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

Bachovchin, Dennis M. (Plum Borough, PA)

1982-01-01T23:59:59.000Z

388

Laboratory Directed Research and Development (LDRD)  

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

concepts - including advanced reactor modeling, nuclear waste reduction and fuel recycling - to develop DOE-NE's needs. INL's LDRD research stimulates exploration at the...

389

Nuclear reactor reflector  

DOE Patents [OSTI]

A nuclear reactor reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for reactor fuel rods. Water flows between the reflector and the reactor barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled.

Hopkins, Ronald J. (Pensacola, FL); Land, John T. (Pensacola, FL); Misvel, Michael C. (Pensacola, FL)

1994-01-01T23:59:59.000Z

390

Spherical torus fusion reactor  

DOE Patents [OSTI]

The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.

Martin Peng, Y.K.M.

1985-10-03T23:59:59.000Z

391

PNNL Breakthrough Leads to Less Foreign Oil, More American Jobs |  

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

PNNL Breakthrough Leads to Less Foreign Oil, More American Jobs PNNL Breakthrough Leads to Less Foreign Oil, More American Jobs PNNL Breakthrough Leads to Less Foreign Oil, More American Jobs October 17, 2011 - 2:50pm Addthis A highly efficient catalyst to convert renewable crops into the product propylene glycol was discovered by scientists at the Pacific Northwest National Laboratory (PNNL) and commercialized by the Archer Daniels Midland Company. | Image courtesy of PNNL. A highly efficient catalyst to convert renewable crops into the product propylene glycol was discovered by scientists at the Pacific Northwest National Laboratory (PNNL) and commercialized by the Archer Daniels Midland Company. | Image courtesy of PNNL. Ginny Simmons Ginny Simmons Former Managing Editor for Energy.gov, Office of Public Affairs

392

Bush Administration Establishes Program to Reduce Foreign Oil Dependency,  

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

Bush Administration Establishes Program to Reduce Foreign Oil Bush Administration Establishes Program to Reduce Foreign Oil Dependency, Greenhouse Gases Bush Administration Establishes Program to Reduce Foreign Oil Dependency, Greenhouse Gases April 10, 2007 - 12:34pm Addthis WASHINGTON, DC - In step with the Bush Administration's call to increase the supply of alternative and renewable fuels nationwide, the U.S. Environmental Protection Agency today established the nation's first comprehensive Renewable Fuel Standard (RFS) program. At a press conference today, EPA Administrator Johnson, joined by Energy Secretary Samuel Bodman and National Highway Traffic Safety Administrator Nicole Nason, discussed the RFS program, increasing the use of alternative fuels and modernizing CAFÉ standards for cars. "The Renewable Fuel Standard offers the American people a hat trick - it

393

Bush Administration Establishes Program to Reduce Foreign Oil Dependency,  

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

Establishes Program to Reduce Foreign Oil Establishes Program to Reduce Foreign Oil Dependency, Greenhouse Gases Bush Administration Establishes Program to Reduce Foreign Oil Dependency, Greenhouse Gases April 10, 2007 - 12:34pm Addthis WASHINGTON, DC - In step with the Bush Administration's call to increase the supply of alternative and renewable fuels nationwide, the U.S. Environmental Protection Agency today established the nation's first comprehensive Renewable Fuel Standard (RFS) program. At a press conference today, EPA Administrator Johnson, joined by Energy Secretary Samuel Bodman and National Highway Traffic Safety Administrator Nicole Nason, discussed the RFS program, increasing the use of alternative fuels and modernizing CAFÉ standards for cars. "The Renewable Fuel Standard offers the American people a hat trick - it

394

Hosting foreign educators | Y-12 National Security Complex  

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

Partnerships / Y-12/UT Collaboration / Hosting foreign educators Partnerships / Y-12/UT Collaboration / Hosting foreign educators Hosting foreign educators Posted: November 27, 2013 - 11:16am Six Indonesian educators (seated) met with Y-12, UT’s Institute for Nuclear Security, and ORNL experts to learn about Y-12’s role in U.S. nuclear security. Y-12, in support of the University of Tennessee's Institute for Nuclear Security, recently welcomed a group of professors from Indonesia's Universitas Gadjah Mada, the only university in Indonesia that offers a nuclear engineering program. As part of a U.S. Department of State Nuclear Security Educator Study Tour, the professors are on a month-long tour of U.S. universities and nuclear sites, where they'll learn strategies and best practices to help them develop new nuclear security courses to implement in Indonesia.

395

Foreign Travel Health & Wellness Information | Department of Energy  

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

Wellness Programs » Foreign Travel Health Wellness Programs » Foreign Travel Health & Wellness Information Foreign Travel Health & Wellness Information All travelers should take the following precautions, no matter the destination: Wash hands often with soap and water. Because motor vehicle crashes are a leading cause of injury among travelers, walk and drive defensively; avoid travel at night if possible and always use seat belts. Don't eat or drink dairy products unless you know they have been pasteurized. Never eat undercooked ground beef and poultry, raw eggs, and unpasteurized dairy products; raw shellfish is particularly dangerous to persons who have liver disease or compromised immune systems. Don't eat food purchased from street vendors; do not drink beverages with ice. Don't handle animals, including dogs and cats, to avoid bites and

396

PNNL Breakthrough Leads to Less Foreign Oil, More American Jobs |  

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

Breakthrough Leads to Less Foreign Oil, More American Jobs Breakthrough Leads to Less Foreign Oil, More American Jobs PNNL Breakthrough Leads to Less Foreign Oil, More American Jobs October 17, 2011 - 2:50pm Addthis A highly efficient catalyst to convert renewable crops into the product propylene glycol was discovered by scientists at the Pacific Northwest National Laboratory (PNNL) and commercialized by the Archer Daniels Midland Company. | Image courtesy of PNNL. A highly efficient catalyst to convert renewable crops into the product propylene glycol was discovered by scientists at the Pacific Northwest National Laboratory (PNNL) and commercialized by the Archer Daniels Midland Company. | Image courtesy of PNNL. Ginny Simmons Ginny Simmons Former Managing Editor for Energy.gov, Office of Public Affairs "Not only can we reduce our use of petroleum, but we can make better use

397

Foreign direct investment and governance quality in Russia  

Science Journals Connector (OSTI)

Abstract This paper studies the effect of poor governance quality on foreign direct investment in Russia. Using a survey of businesses across forty administrative districts, we find that higher frequency of using illegal payments and higher pressure from regulatory agencies, enforcement authorities, and criminals, negatively affect foreign direct investment. Our identification strategy builds on the exogenous cross-regional variation in worker strikes during 18951914, the period before the October Revolution. We find that moving from the average to the top governance quality across Russian regions more than doubles the FDI stock.

Olga Kuzmina; Natalya Volchkova; Tatiana Zueva

2014-01-01T23:59:59.000Z

398

Foreign ownership, technological capabilities and clothing exports in Sri Lanka  

Science Journals Connector (OSTI)

Drawing on recent developments in applied international trade and innovation and learning in developing countries, this paper examines the links between firm-level export performance, foreign ownership and the acquisition of technological capabilities in a sample of 205 clothing enterprises in Sri Lanka. Econometric analysis indicates that foreign ownership, firm size, human capital, technological capabilities and geographical location are all positively associated with export shares. Furthermore, higher levels of technological capability are associated with larger firm size, university-level manpower and in-house technological effort. Micro-level investigations are a complementary input to developing policies for promoting private sector competitiveness in outward-oriented developing countries.

Ganeshan Wignaraja

2008-01-01T23:59:59.000Z

399

Recovery Act Workers Clear Reactor Shields from Brookhaven Lab  

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

UPTON, N.Y. - American Recovery and Reinvestment Act UPTON, N.Y. - American Recovery and Reinvestment Act workers are in the final stage of decommissioning a nuclear reactor after they recently removed thick steel shields once used to absorb neutrons produced for research. The Brookhaven National Laboratory is using $39 million from the Recovery Act to decommission the Brookhaven Graphite Research Reactor, the world's first reactor built solely for peaceful research purposes. The decommissioning is slated for completion later this year and will end Office of Environmental Management legacy cleanup activities at the Lab. The neutron shields were located on the north and south sides of a 700-ton graphite pile. The three-inch-thick shields absorbed neutrons that escaped from the graphite pile. The shields also limited movement of the pile when the reactor was in opera-

400

Reactor Thermal-Hydraulics  

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

Thermal-Hydraulics Thermal-Hydraulics Dr. Tanju Sofu, Argonne National Laboratory In a power reactor, the energy produced in fission reaction manifests itself as heat to be removed by a coolant and utilized in a thermodynamic energy conversion cycle to produce electricity. A simplified schematic of a typical nuclear power plant is shown in the diagram below. Primary coolant loop Steam Reactor Heat exchanger Primary pump Secondary pump Condenser Turbine Water Although this process is essentially the same as in any other steam plant configuration, the power density in a nuclear reactor core is typically four orders of magnitude higher than a fossil fueled plant and therefore it poses significant heat transfer challenges. Maximum power that can be obtained from a nuclear reactor is often limited by the

Note: This page contains sample records for the topic "foreign 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

Reactor hot spot analysis  

SciTech Connect (OSTI)

The principle methods for performing reactor hot spot analysis are reviewed and examined for potential use in the Applied Physics Division. The semistatistical horizontal method is recommended for future work and is now available as an option in the SE2-ANL core thermal hydraulic code. The semistatistical horizontal method is applied to a small LMR to illustrate the calculation of cladding midwall and fuel centerline hot spot temperatures. The example includes a listing of uncertainties, estimates for their magnitudes, computation of hot spot subfactor values and calculation of two sigma temperatures. A review of the uncertainties that affect liquid metal fast reactors is also presented. It was found that hot spot subfactor magnitudes are strongly dependent on the reactor design and therefore reactor specific details must be carefully studied. 13 refs., 1 fig., 5 tabs.

Vilim, R.B.

1985-08-01T23:59:59.000Z

402

Gas Reactor Technology R&D  

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

U.S. Department of Energy to Invest U.S. Department of Energy to Invest up to $7.3 Million for "Deep-Burn" Gas-Reactor Technology R&D Artist's rendering of Nuclear Plant An artist's rendering of the Next Generation Nuclear Plant concept. The U.S. Department of Energy today announced a Funding Opportunity Announcement (FOA) valued at $7.3 million for universities, commercial entities, National Laboratories with expertise in the concept of nuclear fuel "Deep-Burn" in which plutonium and higher transuranics recycled from spent nuclear fuel are destroyed. The funding opportunity seeks to establish the technological foundations that will support the role of the very-high-temperature, gas-cooled reactor (VHTR) in the nuclear fuel cycle -- which is one of the prototype reactors being researched/developed under

403

Molten metal reactors  

DOE Patents [OSTI]

A molten metal reactor for converting a carbon material and steam into a gas comprising hydrogen, carbon monoxide, and carbon dioxide is disclosed. The reactor includes an interior crucible having a portion contained within an exterior crucible. The interior crucible includes an inlet and an outlet; the outlet leads to the exterior crucible and may comprise a diffuser. The exterior crucible may contain a molten alkaline metal compound. Contained between the exterior crucible and the interior crucible is at least one baffle.

Bingham, Dennis N; Klingler, Kerry M; Turner, Terry D; Wilding, Bruce M

2013-11-05T23:59:59.000Z

404

F Reactor Inspection  

ScienceCinema (OSTI)

Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-11-24T23:59:59.000Z

405

F Reactor Inspection  

SciTech Connect (OSTI)

Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-10-29T23:59:59.000Z

406

Nuclear Power Contracts and International Cooperation: Analyzing Innovation and Social Distribution in Russian Foreign Policy  

Science Journals Connector (OSTI)

What is the role of nuclear contracts in Russian foreign policy? This chapter analyzes the political economy of nuclear power regulation in Russia and its implications for Russian foreign policy when it comes to ...

Theocharis N. Grigoriadis

2012-01-01T23:59:59.000Z

407

American Foreign Policy: A Time for a Shift in Priorities and Instruments  

E-Print Network [OSTI]

In the post 9/11 world of American Foreign Policy, where interdependence and globalization are variables that influence every aspect of world affairs, what should the priorities of the United States be and what instruments of foreign policy...

Issa, Patrick 1989-

2011-05-05T23:59:59.000Z

408

STATEMENT OF CONSIDERATIONS ADVANCE WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN  

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

IN INVENTIONS MADE -BY THE SARNOFF IN INVENTIONS MADE -BY THE SARNOFF CORPORATION IN THE PERFORMANCE OF LLNL'S SUBCONTRACT NO. B513201 UNDER DOE'S NONPROLIFERATION RESEARCH AND ENGINEERING PROGRAM DOE WAIVER No. W(A)-01-015, (SAN 687) The Petitioner, the Saroff Corporation, a subsidiary of SRI International, has submitted a petition for an advance waiver of the Government's domestic and foreign rights to inventions made during performance of the above cited Subcontract. Background: DOE's Nonproliferation Research and Engineering Program (NN-20) has provided the University of California (UC), Management and Operator of the Lawrence Livermore National Laboratory (LLNL) under Contract No. W-7405-ENG-48, approximately $770,000 in FY 2001 funding for accomplishment of the Sonoma Project. This particular Project is involved with remote based sensor work for the purpose of nuclear

409

Risk Management for Sodium Fast Reactors.  

SciTech Connect (OSTI)

Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of self - correcting, or inherently safe, reactor designs the focus has shifted from management by operators to allowing the syste m's design to manage the accident. While inherently and passively safe designs are laudable, extreme boundary conditions can interfere with the design attributes which facilitate inherent safety , thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast reactor experiencing a beyond design basis seismic event with the intend of exploring two issues : (1) can human intervention either improve or worsen the potential end states and (2) can a Bayes ian Network be constructed to infer the state of the reactor to inform (1). ACKNOWLEDGEMENTS The author s would like to acknowledge the U.S. Department of E nergy's Office of Nuclear Energy for funding this research through Work Package SR - 14SN100303 under the Advanced Reactor Concepts program. The authors also acknowledge the PRA teams at A rgonne N ational L aborator y , O ak R idge N ational L aborator y , and I daho N ational L aborator y for their continue d contributions to the advanced reactor PRA mission area.

Denman, Matthew R; Groth, Katrina; Cardoni, Jeffrey N; Wheeler, Timothy A.

2015-01-01T23:59:59.000Z

410

The physics of magnetic fusion reactors  

Science Journals Connector (OSTI)

During the past two decades there have been substantial advances in magnetic fusion research. On the experimental front, progress has been led by the mainline tokamaks, which have achieved reactor-level values of temperature and plasma pressure. Comparable progress, when allowance is made for their smaller programs, has been made in complementary configurations such as the stellarator, reversed-field pinch and field-reversed configuration. In this paper, the status of understanding of the physics of toroidal plasmas is reviewed. It is shown how the physics performance, constrained by technological and economic realities, determines the form of reference toroidal reactors. A comparative study of example reactors is not made, because the level of confidence in projections of their performance varies widely, reflecting the vastly different levels of support which each has received. Success with the tokamak has led to the initiation of the International Thermonuclear Experimental Reactor project. It is designed to produce 1500 MW of fusion power from a deuterium-tritium plasma for pulses of 1000 s or longer and to demonstrate the integration of the plasma and nuclear technologies needed for a demonstration reactor.

John Sheffield

1994-07-01T23:59:59.000Z

411

WA_01_005__PRAXAIR_INC_Waiver_of_Domestic_and_Foreign_patent...  

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

1005PRAXAIRINCWaiverofDomesticandForeignpatent.pdf WA01005PRAXAIRINCWaiverofDomesticandForeignpatent.pdf WA01005PRAXAIRINCWaiverofDomesticandForeign...

412

WA_02_021_H2GEN_INNOVATIONS_Waiver_of_Domestic_and_Foreign_P...  

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

WA02046QUESTAAIRTECHNOLOGIESWaiverofDomesticandFor.pdf WA02055PRAXAIRWaiverofDomesticandForeignPatentRigh.pdf WA04034NUVERAFUELCELLSINCWaiver...

413

Capital and chaos : fragile states, political risk and foreign direct investment  

E-Print Network [OSTI]

Direct Investment . . . . . . . . . . . . . . . . . . . .71of! diaspora! direct! investment! than! flows! from!increasing! foreign! investment! and! integrating! Georgia!

Graham, Benjamin A. T.

2012-01-01T23:59:59.000Z

414

Inside the Castle Gates: How Foreign Corporations Nagivate Japan's Policymaking Processes  

E-Print Network [OSTI]

rapidly. Aiming at Japans massive household assets, whichhouseholds Paprzycki and Fukao, Foreign Direct Investment in Japan :

Kushida, Kenji Erik

2010-01-01T23:59:59.000Z

415

APPLICATION FOR THE RECOGNITION/ VALIDATION OF FOREIGN CERTIFICATES  

E-Print Network [OSTI]

Eingang APPLICATION FOR THE RECOGNITION/ VALIDATION OF FOREIGN CERTIFICATES to study ____________________________________ Other Subject 2. PERSONAL DETAILS (exactly as in passport) Surname Forename(s) Date of birth Gender OF PREVIOUS EDUCATION All certificates must be presented with official accreditation and officially certified

Kaus, Boris

416

1988 saw major efforts to spur foreign interest  

SciTech Connect (OSTI)

This article discusses how Africa's large producers are offering incentives to attract exploration. Egypt is pushing new gas development, while Nigeria announced reduced taxes to lure foreign operators. Gabon has rejuvenated its production with discovery of a large new oil field. Libya is offering liberal concession terms, though the status of U.S. firms is uncertain.

Bell, G.D. (Gustavson Associates, Inc., Boulder, CO (USA))

1989-08-01T23:59:59.000Z

417

Foreign Fishery Developments Mediterranean Bluefin Tuna Airlifted to Japan  

E-Print Network [OSTI]

Foreign Fishery Developments Mediterranean Bluefin Tuna Airlifted to Japan Japan-Soviet Fishery dealt a seri- ous blow by the various new restric- tions introduced in the S-year Japan- Soviet in Japan has revived a once-abandoned airlift of fresh bluefin tuna from the Mediterranean. Two earlier

418

Coal Science: Basic Research Opportunities  

Science Journals Connector (OSTI)

...super-critical fluids or molten bath reactors might be other approaches...residence time, pressure, reactor design, and gas-phase composi-tion...additional re-search include improved technology for removing impurities...140 (1974). 2. P. Sabatier and J. B. Senderens, Ann...

Martin L. Gorbaty; Franklin J. Wright; Richard K. Lyon; Robert B. Long; Richard H. Schlosberg; Zeinab Baset; Ronald Liotta; Bernard G. Silbernagel; Dan R. Neskora

1979-11-30T23:59:59.000Z

419

REACTOR GROUT THERMAL PROPERTIES  

SciTech Connect (OSTI)

Savannah River Site has five dormant nuclear production reactors. Long term disposition will require filling some reactor buildings with grout up to ground level. Portland cement based grout will be used to fill the buildings with the exception of some reactor tanks. Some reactor tanks contain significant quantities of aluminum which could react with Portland cement based grout to form hydrogen. Hydrogen production is a safety concern and gas generation could also compromise the structural integrity of the grout pour. Therefore, it was necessary to develop a non-Portland cement grout to fill reactors that contain significant quantities of aluminum. Grouts generate heat when they set, so the potential exists for large temperature increases in a large pour, which could compromise the integrity of the pour. The primary purpose of the testing reported here was to measure heat of hydration, specific heat, thermal conductivity and density of various reactor grouts under consideration so that these properties could be used to model transient heat transfer for different pouring strategies. A secondary purpose was to make qualitative judgments of grout pourability and hardened strength. Some reactor grout formulations were unacceptable because they generated too much heat, or started setting too fast, or required too long to harden or were too weak. The formulation called 102H had the best combination of characteristics. It is a Calcium Alumino-Sulfate grout that contains Ciment Fondu (calcium aluminate cement), Plaster of Paris (calcium sulfate hemihydrate), sand, Class F fly ash, boric acid and small quantities of additives. This composition afforded about ten hours of working time. Heat release began at 12 hours and was complete by 24 hours. The adiabatic temperature rise was 54 C which was within specification. The final product was hard and displayed no visible segregation. The density and maximum particle size were within specification.

Steimke, J.; Qureshi, Z.; Restivo, M.; Guerrero, H.

2011-01-28T23:59:59.000Z

420

Reactor Safety Planning for Prometheus Project, for Naval Reactors Information  

SciTech Connect (OSTI)

The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

P. Delmolino

2005-05-06T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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.


421

Modeling and Simulation for Nuclear Reactors Hub | Department of Energy  

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

Modeling and Simulation for Nuclear Reactors Hub Modeling and Simulation for Nuclear Reactors Hub Modeling and Simulation for Nuclear Reactors Hub August 1, 2010 - 4:20pm Addthis Scientists and engineers are working to help the nuclear industry make reactors more efficient through computer modeling and simulation. Scientists and engineers are working to help the nuclear industry make reactors more efficient through computer modeling and simulation. The Department's Energy Innovation Hubs are helping to advance promising areas of energy science and engineering from the earliest stages of research to the point of commercialization where technologies can move to the private sector by bringing together leadings scientists to collaborate on critical energy challenges. The Energy Innovation Hubs aim to develop innovation through a unique

422

Small Modular Reactors Presentation to Secretary of Energy Advisory Board -  

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

Small Modular Reactors Presentation to Secretary of Energy Advisory Small Modular Reactors Presentation to Secretary of Energy Advisory Board - Deputy Assistant Secretary John Kelly Small Modular Reactors Presentation to Secretary of Energy Advisory Board - Deputy Assistant Secretary John Kelly DOE Small Modular Reactor Program (SMR) Research, Development & Deployment (RD&D) to enable the deployment of a fleet of SMRs in the United States SMR Program is a new program for FY 2011 Structured to address the need to enable the deployment of mature, near-term SMR designs based on known LWR technology Conduct needed R&D activities to advance the understanding and demonstration of innovative reactor technologies and concepts John_Kelly-SEAB_SMRBriefing_July20_2011_final.pdf More Documents & Publications Meeting Materials: June 12, 2012

423

High Flux Isotope Reactor (HFIR) | Nuclear Science | ORNL  

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

High Flux Isotope Reactor High Flux Isotope Reactor May 30, 2013 The High Flux Isotope Reactor (HFIR) first achieved criticality on August 25, 1965, and achieved full power in August 1966. It is a versatile 85-MW isotope production, research, and test reactor with the capability and facilities for performing a wide variety of irradiation experiments and a world-class neutron scattering science program. HFIR is a beryllium-reflected, light water-cooled and moderated flux-trap type swimming pool reactor that uses highly enriched uranium-235 as fuel. HFIR typically operates seven 23-to-27 day cycles per year. Irradiation facility capabilities include Flux trap positions: Peak thermal flux of 2.5X1015 n/cm2/s with similar epithermal and fast fluxes (Highest thermal flux available in the

424

B Reactor | Department of Energy  

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

Operational Management » History » Manhattan Project » Signature Operational Management » History » Manhattan Project » Signature Facilities » B Reactor B Reactor B Reactor Completed in September 1944, the B Reactor was the world's first large-scale plutonium production reactor. As at Oak Ridge, the need for labor turned Hanford into an atomic boomtown, with the population reaching 50,000 by summer 1944. Similar to the X-10 Graphite Reactor at Oak Ridge in terms of loading and unloading fuel, the B Reactor was built on a much larger scale and used water rather than air as a coolant. Whereas the X-10 had an initial design output of 1,000 kilowatts, the B Reactor was designed to operate at 250,000 kilowatts. Consisting of a 28- by 36-foot, 1,200-ton graphite cylinder lying on its side, the reactor was penetrated through its

425

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR licenses are now being extended from 40y to 60y by the U.S. Nuclear Regulatory Commission (NRC) with intentions to extend licenses to 80y and beyond. The RPV materials exhibit varying degrees of sensitivity to irradiation-induced embrittlement (decreased toughness) , as shown in Fig. 1.1, and extending operation from

426

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment The reactor pressure vessel (RPV) in a light-water reactor (LWR) represents the first line of defense against a release of radiation in case of an accident. Thus, regulations, which govern the operation of commercial nuclear power plants, require conservative margins of fracture toughness, both during normal operation and under accident scenarios. In the unirradiated condition, the RPV has sufficient fracture toughness such that failure is implausible under any postulated condition, including

427

Reactor for exothermic reactions  

DOE Patents [OSTI]

A liquid phase process is described for oligomerization of C[sub 4] and C[sub 5] isoolefins or the etherification thereof with C[sub 1] to C[sub 6] alcohols wherein the reactants are contacted in a reactor with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120 to 300 F. Wherein the improvement is the operation of the reactor at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the reactor is controlled.

Smith, L.A. Jr.; Hearn, D.; Jones, E.M. Jr.

1993-03-02T23:59:59.000Z

428

Thermionic Reactor Design Studies  

SciTech Connect (OSTI)

Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their (thermionic reactor) performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling.

Schock, Alfred

1994-08-01T23:59:59.000Z

429

Solar Thermal Reactor Materials Characterization  

SciTech Connect (OSTI)

Current research into hydrogen production through high temperature metal oxide water splitting cycles has created a need for robust high temperature materials. Such cycles are further enhanced by the use of concentrated solar energy as a power source. However, samples subjected to concentrated solar radiation exhibited lifetimes much shorter than expected. Characterization of the power and flux distributions representative of the High Flux Solar Furnace(HFSF) at the National Renewable Energy Laboratory(NREL) were compared to ray trace modeling of the facility. In addition, samples of candidate reactor materials were thermally cycled at the HFSF and tensile failure testing was performed to quantify material degradation. Thermal cycling tests have been completed on super alloy Haynes 214 samples and results indicate that maximum temperature plays a significant role in reduction of strength. The number of cycles was too small to establish long term failure trends for this material due to the high ductility of the material.

Lichty, P. R.; Scott, A. M.; Perkins, C. M.; Bingham, C.; Weimer, A. W.

2008-03-01T23:59:59.000Z

430

Diagnostics for hybrid reactors  

SciTech Connect (OSTI)

The Hybrid Reactor(HR) can be considered an attractive actinide-burner or a fusion assisted transmutation for destruction of transuranic(TRU) nuclear waste. The hybrid reactor has two important subsystems: the tokamak neutron source and the blanket which includes a fuel zone where the TRU are placed and a tritium breeding zone. The diagnostic system for a HR must be as simple and robust as possible to monitor and control the plasma scenario, guarantee the protection of the machine and monitor the transmutation.

Orsitto, Francesco Paolo [ENEA Unita' Tecnica Fusione , Associazione ENEA-EURATOM sulla Fusione C R Frascati v E Fermi 45 00044 Frascati (Italy)

2012-06-19T23:59:59.000Z

431

STATEMENT OF CONSIDERATIONS REQUEST BY URS GROUP (URS) FOR THE WAIVER OF U.S. AND FOREIGN  

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

URS GROUP (URS) FOR THE WAIVER OF U.S. AND FOREIGN URS GROUP (URS) FOR THE WAIVER OF U.S. AND FOREIGN RIGHTS IN AN IDENTIFIED INVENTION DOE DOCKET NUMBER S-116,616, MADE UNDER DOE CONTRACT NO. DE-FC2604NT42314, W(I)-2009-004, CH-1507 This waiver request is for domestic and foreign rights in the above identified invention pertaining to a wet flue gas desulfurization system additive for control of mercury re-ernissions and enhanced removal of elemental mercury. The dollar amount of the contract is $518,997 of which $381,145 is the Government's share. URS provided an additional $16,190 to its share of$137,852 to develop the invention. URS will incur all the costs of patenting the invention. URS will partner with the Electric Power Research Institute (EPRI) to further develop and commercialize the invention. EPRI has funded URS $34,900 at DCAA audited

432

Summary of Research Instruction Research Instruction  

E-Print Network [OSTI]

generator, Separator) is carried out with numerical simulations and tests. Through these thermal and information in nuclear power plants. In addition, research on structural changes induced by high-energy ion subjects. W02 W52 Thermal-Hydraulics of Nuclear Reactors Optimization of thermal-hydraulic performance

Kaji, Hajime

433

Structural materials for fusion reactors  

Science Journals Connector (OSTI)

Fusion Reactors will require specially engineered structural materials, which ... on safety considerations. The fundamental differences between fusion and other nuclear reactors arise due to the 14MeV neutronics ...

P. M. Raole; S. P. Deshpande

2009-04-01T23:59:59.000Z

434

Reactor Materials | Department of Energy  

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

Benefits Crosscutting Technology Development Reactor Materials Advanced Sensors and Instrumentation Proliferation and Terrorism Risk Assessment Advanced Methods for Manufacturing...

435

Reactor operation safety information document  

SciTech Connect (OSTI)

The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

Not Available

1990-01-01T23:59:59.000Z

436

Fossil fuel furnace reactor  

DOE Patents [OSTI]

A fossil fuel furnace reactor is provided for simulating a continuous processing plant with a batch reactor. An internal reaction vessel contains a batch of shale oil, with the vessel having a relatively thin wall thickness for a heat transfer rate effective to simulate a process temperature history in the selected continuous processing plant. A heater jacket is disposed about the reactor vessel and defines a number of independent controllable temperature zones axially spaced along the reaction vessel. Each temperature zone can be energized to simulate a time-temperature history of process material through the continuous plant. A pressure vessel contains both the heater jacket and the reaction vessel at an operating pressure functionally selected to simulate the continuous processing plant. The process yield from the oil shale may be used as feedback information to software simulating operation of the continuous plant to provide operating parameters, i.e., temperature profiles, ambient atmosphere, operating pressure, material feed rates, etc., for simulation in the batch reactor.

Parkinson, William J. (Los Alamos, NM)

1987-01-01T23:59:59.000Z

437

Transport reactor development status  

SciTech Connect (OSTI)

This project is part of METC`s Power Systems Development Facility (PSDF) located at Wilsonville, Alabama. The primary objective of the Advanced Gasifier module is to produce vitiated gases for intermediate-term testing of Particulate Control Devices (PCDs). The Transport reactor potentially allows particle size distribution, solids loading, and particulate characteristics in the off-gas stream to be varied in a number of ways. Particulates in the hot gases from the Transport reactor will be removed in the PCDs. Two PCDs will be initially installed in the module; one a ceramic candle filter, the other a granular bed filter. After testing of the initial PCDs they will be removed and replaced with PCDs supplied by other vendors. A secondary objective is to verify the performance of a Transport reactor for use in advanced Integrated Gasification Combined Cycle (IGCC), Integrated Gasification Fuel Cell (IG-FC), and Pressurized Combustion Combined Cycle (PCCC) power generation units. This paper discusses the development of the Transport reactor design from bench-scale testing through pilot-scale testing to design of the Process Development Unit (PDU-scale) facility at Wilsonville.

Rush, R.E.; Fankhanel, M.O.; Campbell, W.M.

1994-10-01T23:59:59.000Z

438

Thermal Reactor Safety  

SciTech Connect (OSTI)

Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

Not Available

1980-06-01T23:59:59.000Z

439

NETL - Chemical Looping Reactor  

ScienceCinema (OSTI)

NETL's Chemical Looping Reactor unit is a high-temperature integrated CLC process with extensive instrumentation to improve computational simulations. A non-reacting test unit is also used to study solids flow at ambient temperature. The CLR unit circulates approximately 1,000 pounds per hour at temperatures around 1,800 degrees Fahrenheit.

None

2014-06-26T23:59:59.000Z

440

Research helps safeguard nuclear workers worldwide - Argonne's Historical  

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

Research helps safeguard nuclear workers Research helps safeguard nuclear workers worldwide 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 Argonne's Nuclear Science and Technology Legacy

Note: This page contains sample records for the topic "foreign 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

PROFILES OF FOREIGN DIRECT INVESTMENT IN U.S. ENERGY  

Gasoline and Diesel Fuel Update (EIA)

3OE/EIA-O466O3) 3OE/EIA-O466O3) PROFILES OF FOREIGN DIRECT INVESTMENT IN U.S. ENERGY MAY 1995 1993 Elk This publication and other Energy Information Administration (EIA) publications may be purchased from the Superintendent of Documents, U.S. Government Printing Office. Telephone orders may be directed to: Superintendent of Documents U.S. Government Printing Office Main Order Desk (202) 512-1800 FAX: (202)512-2250 8 a.m. to 4:30 p.m., eastern time, M-F All mail orders should be directed to: U.S. Government Printing Office P.O. Box 371954 Pittsburgh, PA 15250-7954 Complimentary subscriptions and single issues are available to certain groups of subscribers, such as public and academic libraries, Federal, State, local and foreign governments, EIA survey respondents, and the media. For further information and for answers to questions on energy statistics, please contact EIA's

442

Foreign National Tax Frequently Asked Questions 11/5/2013  

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

5/2013 5/2013 Foreign National Tax Frequently Asked Questions (FAQs) What is the difference between a resident alien and a nonresident alien for tax purposes? The Internal Revenue Service (IRS) classifies all foreign nationals as either resident aliens or nonresident aliens. Resident aliens are, for the most part, taxed in the same manner as U.S. citizens. The Internal Revenue Code (IRC), however, imposes an entirely different tax system on nonresident aliens. There are many differences between the two tax regimes, but perhaps the most significant is that resident aliens, like U.S. citizens, are taxed on their worldwide income, while nonresident aliens are taxed only on their U.S. source income. In addition, different income tax withholding and reporting requirements are imposed on payments made to nonresident

443

STATEMENTOF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S.AND FOREIGN PATENT RIGHTS IN  

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

STATEMENTOF CONSIDERATIONS STATEMENTOF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S.AND FOREIGN PATENT RIGHTS IN CERTAIN IDENTIF IED IN VENTIONS TO JEFFERSON SCIENCE ASSOCIATES, LLC (JSA), MADE AND TO BE MADE IN THE COURSE OF OR UNDER CONTRACT DE- AC05-060R23177WITlf THE DEPARTMENT OF ENERGY (DOE) FOR THE MANAGEMENT ANDOr ERATION OF THE THOMASJEFFERSONNATlONAL ACCELERATOR FACILITY, INCLUDING A CLASS ADVANCE WAIVER OF TITLE TO INVENTIONS MADE IN T H E PERFORMANCE OF COOPERATIVE RESEARCH AND DEVELOPMENT AGREEMENTS (CRADAS) ENTERED INTO BY JSA, PURSUANT TO CONTRACT DE-AC05-060R23177WITH DOE . W(C)-20 11-00 l[OR0-550] Background The Department of Energy (DOE) awarded Prime Contract No. DE-AC05-060R23177 (Prime Contract) to Jefferson Science Associates, LLC (JSA) for management and

444

REQUEST BY SIEMENS WESTINGHOUSE POWER CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN  

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

POWER CORPORATION FOR POWER CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN SUBJECT INVENTIONS MADE UNDER SUBCONTRACT NO. C-93-0016532 UNDER DEPARTMENT OF ENERGY COOPERATIVE AGREEMENT NO. DE-FC21-90MC25140; DOE WAIVER DOCKET W(A) 03-012 [CH1139] The Petitioner, Siemens Westinghouse Power Corporation (SWPC), is a subcontractor to Southern Company Services, Inc. (SCS) under the subject cost shared cooperative agreement titled "Research and Development of the Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion." The overall scope of the Department of Energy (DOE) cooperative agreement with SCS calls for the design, construction, and operation of a facility to provide long- term hot gas cleanup and process testing for gasification systems and pressurized fluidized bed

445

REQUEST BY SIEMENS WESTINGHOUSE POWER CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN  

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

SIEMENS WESTINGHOUSE POWER CORPORATION SIEMENS WESTINGHOUSE POWER CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN SUBJECT INVENTIONS MADE IN THE COURSE OF OR UNDER LOCKHEED MARTIN SUBCONTRACT NO. 4500004925 UNDER DOE CONTRACT NO. DE-AC05-960R22464; AND FOR CERTAIN LARGE BUSINESS SUBCONTRACTS THEREUNDER; DOE WAIVER DOCKET W(A)99-011 [ORO-744] Siemens Westinghouse Power Corporation (Siemens Westinghouse) has made a timely request for an advance waiver to worldwide rights in Subject Inventions conceived or made in the course of or under Lockheed Martin Energy Research Subcontract No. 4500004925 under DOE Contract No. DE-AC05-960R22464 and under certain subcontracts entered thereunder with parties who do not qualify for treatment under Public Law 96-517. The primary program goal of this work, entitled,

446

CLASS WAIVER OF THE GOVERNMENTS U.S. AND FOREIGN PATENT RIGHTS IN  

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

08/0.J04 15:49 FAX 08/0.J04 15:49 FAX _ 005 Statement of Consideratlons CLASS WAIVER OF THE GOVERNMENTS U.S. AND FOREIGN PATENT RIGHTS IN CERTAIN IDENTIFIED INVENTIONS AND COPYRIGHTS MADE OR AUTHORED BY PERFORMING ENTITY SUBCONT = ACTORS DURING THE COURSE OF OR UNDER SUBCONTRACTS AND CRADAs UNDER MANAGEMENT AND OPERATING CONTRACT DE-AC09-96SR186500 BETWEEN THE DEPARTMENT OF ENERGY (DOE) AND WESTINGHOUSE SAVANNAH RIVER COMPANY (WSRC) W(C)-2004- 003 [ORO-788) The purpose of this class waiver is to waive subject inventions and copyrights made or authored by employees of Performing Entity Subcontractors in Ihe course of or under subcontracts and Cooperative Research and Development Agreements (CRADAs) under Contract No. DE-AC09- 96SR18500 (hereinafter the 18500 Contract) to WSRC. This class waiver is In addition to two

447

STATEMENT OF CONSIDERATIONS ADVANCE WAIVER OF TIE GOVERNMENT'S U.S. AND FOREIGN  

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

MAY. -19' 15(THIJ) 15:55 OFFICE C( F COUNSE TEL:05 8 6913 P, 112 MAY. -19' 15(THIJ) 15:55 OFFICE C( F COUNSE TEL:05 8 6913 P, 112 STATEMENT OF CONSIDERATIONS ADVANCE WAIVER OF TIE GOVERNMENT'S U.S. AND FOREIGN PATENT RIG-ITS AND ADVANCE APPROVAL TO ASSERT COPYRIGHT RIGHTS UNDER SUBCONTACT B548850 ISSUED BY LAWRENCE LIVERMORE NATIONAL LABORATORY TO INTERNATIONAL BUSINESS MACHINES CORPORATION FOR THE BLUEGENE/P DESIGN ARCHITECTURE, PHASE II -DESIGN AND FABRICATION; DOE WAIVER NO. W(A)-05-014 The Petitioner, International Business Machines Corporation (IBM), has requested an Advance Waiver of the Government's Intellectual Property Rights in the above-cited research and development subcontract for the BlueGene/P Design Architecture, Phase IT (Design and Fabrication) (hereinafter BlueGene/P Phase TI). In its request, IBM has agreed to accept the same

448

REQUEST BY BALLARD POWER SYSTEMS CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN  

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

BALLARD POWER SYSTEMS CORPORATION FOR AN BALLARD POWER SYSTEMS CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS IN SUBJECT INVENTIONS MADE IN THE COURSE OF OR UNDER UT- BATTELLE, LLC SUBCONTRACT NO. 4000029752 UNDER PRIME CONTRACT NO. DE-AC05-00OR22725; DOE WAIVER DOCKET W(A)- 04-055 [ORO-790] Ballard Power Systems Corporation (Ballard) has made a timely request for an advance waiver of worldwide rights in Subject Inventions made in the course of or under UT- Battelle, LLC Subcontract No. 4000029752, entitled, "Research and Development of Fuel Cell & Advanced Vehicle Power Electronics and Machinery Applications" under UT-Battelle Prime Contract No. DE-AC05-00OR22725. The scope of work involves designing, developing, testing and delivering 4 prototype high voltage to 14V dc-to-dc

449

CLASS WAIVER OF THE GOVERNMENTS U.S. AND FOREIGN PATENT RIGHTS IN  

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

u5a/*i/04 FRI 07:03 FAX 8039528542 OCC u5a/*i/04 FRI 07:03 FAX 8039528542 OCC 002 -08/0104 15:49 FAX o 0 0 2 ._ _- - _ 00 5 Statement of Considerations CLASS WAIVER OF THE GOVERNMENTS U.S. AND FOREIGN PATENT RIGHTS IN CERTAIN IDENTIFIED INVENTIONS AND COPYRIGHTS MADE OR AUTHORED BY PERFORMING ENTrTY SUBCONTRACTORS DURING THE COURSE OF OR UNDER SUBCONTRACTS AND CRADAs UNDER MANAGEMENT AND OPERATING CONTRACT DE-AC09-96SR18500 BETWEEN THE DEPARTMENT OF ENERGY (DOE) AND WESTINGHOUSE SAVANNAH RIVER COMPANY (WSRC) W(C)-2004- 00s [ORO-788] The purpose of this class waiver is to waive subject inventions end copyrights.made or authored by employees of Performing Entity Subcontractors in the course of or under subcontracts and Cooperative Research and Development Agreements (CRADAs) under Contract No. DE-AC09-

450

STATEMENTOF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S.AND FOREIGN PATENT RIGHTS IN  

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

STATEMENTOF CONSIDERATIONS STATEMENTOF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S.AND FOREIGN PATENT RIGHTS IN CERTAIN IDENTIF IED IN VENTIONS TO JEFFERSON SCIENCE ASSOCIATES, LLC (JSA), MADE AND TO BE MADE IN THE COURSE OF OR UNDER CONTRACT DE- AC05-060R23177WITlf THE DEPARTMENT OF ENERGY (DOE) FOR THE MANAGEMENT ANDOr ERATION OF THE THOMASJEFFERSONNATlONAL ACCELERATOR FACILITY, INCLUDING A CLASS ADVANCE WAIVER OF TITLE TO INVENTIONS MADE IN T H E PERFORMANCE OF COOPERATIVE RESEARCH AND DEVELOPMENT AGREEMENTS (CRADAS) ENTERED INTO BY JSA, PURSUANT TO CONTRACT DE-AC05-060R23177WITH DOE . W(C)-20 11-00 l[OR0-550] Background The Department of Energy (DOE) awarded Prime Contract No. DE-AC05-060R23177 (Prime Contract) to Jefferson Science Associates, LLC (JSA) for management and

451

STATEMENT OF CONSIDERATIONS ADVANCE WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN  

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

S-21' 04 (MON) 14:45 OFFICE G EF GOUNSE TEL:505 6913 P. 002 S-21' 04 (MON) 14:45 OFFICE G EF GOUNSE TEL:505 6913 P. 002 STATEMENT OF CONSIDERATIONS ADVANCE WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS AND ADVANCE APPROVAL TO ASSERT COPYRIGHT RIGHTS UNDER SUBCONTACT B542702 ISSUED BY LAWRENCE LTVERMORE NATIONAL LABORATORY TO INTERNATIONAL BUSINESS MACHINES CORPORATION FOR THE BLUEGENE/P ASIC FEASIBILIY STUDY; DOE WAIVER NO W(A)-04-053 The Petitioner, International Business Machines Corporation (IBM), has requested an Advance Waiver of the Government's Intellectual Property Rights in the above-cited research and development subcontract for the BlueGene/P ASIC Feasibility Study. In its request, IBM has agreed to accept the same terms and conditions that were negotiated for previous LLNL Subcontract B517552 with IBM for the BlueGene /L Program and which were authorized under

452

Exposure conditions of reactor internals of Rovno VVER-440 NPP units 1 and 2  

SciTech Connect (OSTI)

Results of determination of irradiation conditions for vessel internals of VVER-440 reactor No. 1 and 2 at Rovno Nuclear Power Plant, obtained by specialists at Inst. for Nuclear Research Kyiv (Ukraine)), and Nuclear Research Inst. Rez (Czech Republic)), are presented. To calculate neutron transport, detailed calculation models of these reactors were prepared. Distribution of neutron flux functionals on the surface of reactor VVER-440 baffle and core barrel for different core loads was studied. Agreement between results obtained by specialists at Inst. for Nuclear Research and at Nuclear Research Inst. is shown. (authors)

Grytsenko, O.V.; Pugach, S.M.; Diemokhin, V.L.; Bukanov, V.N. [Inst. for Nuclear Research, Kyiv, 03680 (Ukraine); Marek, M.; Vandlik, S. [Nuclear Research Inst. Rez Plc., Rez, 25068 (Czech Republic)

2011-07-01T23:59:59.000Z

453

Reactor vessel support system. [LMFBR  

DOE Patents [OSTI]

A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

Golden, M.P.; Holley, J.C.

1980-05-09T23:59:59.000Z

454

Fusion reactor systems  

Science Journals Connector (OSTI)

In this review we consider deuterium-tritium (D-T) fusion reactors based on four different plasma-confinement and heating approaches: the tokamak, the theta-pinch, the magnetic-mirror, and the laser-pellet system. We begin with a discussion of the dynamics of reacting plasmas and basic considerations of reactor power balance. The essential plasma physical aspects of each system are summarized, and the main characteristics of the corresponding conceptual power plants are described. In tokamak reactors the plasma densities are about 1020 m-3, and the ? values (ratio of plasma pressure to confining magnetic pressure) are approximately 5%. Plasma burning times are of the order of 100-1000 sec. Large superconducting dc magnets furnish the toroidal magnetic field, and 2-m thick blankets and shields prevent heat deposition in the superconductor. Radially diffusing plasma is diverted away from the first wall by means of null singularities in the poloidal (or transverse) component of the confining magnetic field. The toroidal theta-pinch reactor has a much smaller minor diameter and a much larger major diameter, and operates on a 10-sec cycle with 0.1-sec burning pulses. It utilizes shock heating from high-voltage sources and adabatic-compression heating powered by low-voltage, pulsed cryogenic magnetic or inertial energy stores, outside the reactor core. The plasma has a density of about 1022 m-3 and ? values of nearly unity. In the power balance of the reactor, direct-conversion energy obtained by expansion of the burning high-? plasma against the containing magnetic field is an important factor. No divertor is necessary since neutral-gas flow cools and replaces the "spent" plasma between pulses. The open-ended mirror reactor uses both thermal conversion of neutron energy and direct conversion of end-loss plasma energy to dc electrical power. A fraction of this direct-convertor power is then fed back to the ioninjection system to sustain the reaction and maintain the plasma. The average ion energy is 600 keV, plasma diameter 6 m, and the plasma beta 85%. The power levels of the three magnetic-confinement devices are in the 500-2000 MWe range, with the exception of the mirror reactor, for which the output is approximately 200 MWe. In Laser-Pellet reactors, frozen D-T pellets are ignited in a cavity which absorbs the electromagnetic, charged particle, and neutron energy from the fusion reaction. The confinement is "inertial," since the fusion reaction occurs during the disassembly of the heated pellet. A pellet-cavity unit would produce about 200 MWt in pulses with a repetition rate of the order of 10 sec-1. Such units could be clustered to give power plants with outputs in the range of 1000 MWe.

F. L. Ribe

1975-01-01T23:59:59.000Z

455

Development of advanced strain diagnostic techniques for reactor environments.  

SciTech Connect (OSTI)

The following research is operated as a Laboratory Directed Research and Development (LDRD) initiative at Sandia National Laboratories. The long-term goals of the program include sophisticated diagnostics of advanced fuels testing for nuclear reactors for the Department of Energy (DOE) Gen IV program, with the future capability to provide real-time measurement of strain in fuel rod cladding during operation in situ at any research or power reactor in the United States. By quantifying the stress and strain in fuel rods, it is possible to significantly improve fuel rod design, and consequently, to improve the performance and lifetime of the cladding. During the past year of this program, two sets of experiments were performed: small-scale tests to ensure reliability of the gages, and reactor pulse experiments involving the most viable samples in the Annulated Core Research Reactor (ACRR), located onsite at Sandia. Strain measurement techniques that can provide useful data in the extreme environment of a nuclear reactor core are needed to characterize nuclear fuel rods. This report documents the progression of solutions to this issue that were explored for feasibility in FY12 at Sandia National Laboratories, Albuquerque, NM.

Fleming, Darryn D.; Holschuh, Thomas Vernon,; Miller, Timothy J.; Hall, Aaron Christopher; Urrea, David Anthony,; Parma, Edward J.,

2013-02-01T23:59:59.000Z

456

Nuclear reactor construction with bottom supported reactor vessel  

DOE Patents [OSTI]

An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core within the pool. The reactor vessel has an open top end, a closed flat bottom end wall and a continuous cylindrical closed side wall interconnecting the top end and bottom end wall. The reactor also has a generally cylindrical concrete containment structure surrounding the reactor vessel and being formed by a cylindrical side wall spaced outwardly from the reactor vessel side wall and a flat base mat spaced below the reactor vessel bottom end wall. A central support pedestal is anchored to the containment structure base mat and extends upwardly therefrom to the reactor vessel and upwardly therefrom to the reactor core so as to support the bottom end wall of the reactor vessel and the lower end of the reactor core in spaced apart relationship above the containment structure base mat. Also, an annular reinforced support structure is disposed in the reactor vessel on the bottom end wall thereof and extends about the lower end of the core so as to support the periphery thereof. In addition, an annular support ring having a plurality of inward radially extending linear members is disposed between the containment structure base mat and the bottom end of the reactor vessel wall and is connected to and supports the reactor vessel at its bottom end on the containment structure base mat so as to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event. The reactor construction also includes a bed of insulating material in sand-like granular form, preferably being high density magnesium oxide particles, disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall on the containment structure base mat so as to insulate the reactor vessel bottom end wall from the containment structure base mat and allow the reactor vessel bottom end wall to freely expand as it heats up while providing continuous support thereof. Further, a deck is supported upon the side wall of the containment structure above the top open end of the reactor vessel, and a plurality of serially connected extendible and retractable annular bellows extend between the deck and the top open end of the reactor vessel and flexibly and sealably interconnect the reactor vessel at its top end to the deck. An annular guide ring is disposed on the containment structure and extends between its side wall and the top open end of the reactor vessel for providing lateral support of the reactor vessel top open end by limiting imposition of lateral loads on the annular bellows by the occurrence of a lateral seismic event.

Sharbaugh, John E. (Bullskin Township, Fayette County, PA)

1987-01-01T23:59:59.000Z

457

Research Highlights | Nuclear Science | ORNL  

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

News and Awards News and Awards Nuclear Science Home | Science & Discovery | Nuclear Science | Research Highlights SHARE Research Highlights 1-3 of 3 Results Neutron scattering continues as a vital tool in superconductivity studies January 01, 2011 - In 2008, the totally unexpected discovery of a New class of superconductors, the iron pnictides, set off A Feverish international effort to understand them. Fabrication and Characterization of Uranium-based High Temperature Reactor Fuel June 01, 2013 - The Uranium Fuel Development Laboratory is a modern R&D scale lab for the fabrication and characterization of uranium-based high temperature reactor fuel. Light Water Reactor Fuel Cladding Research June 01, 2013 - ORNL is the focus point for Light Water Reactor (LWR)

458

Spherical torus fusion reactor  

DOE Patents [OSTI]

A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.

Peng, Yueng-Kay M. (Oak Ridge, TN)

1989-01-01T23:59:59.000Z

459

Nuclear divisional reactor  

SciTech Connect (OSTI)

A nuclear divisional reactor including a reactor core having side and top walls, a heat exchanger substantially surrounding the core, the heat exchanger including a plurality of separate fluid holding and circulating chambers each in contact with a portion of the core, control rod means associated with the core and external of the heat exchanger including control rods and means for moving said control rods, each of the chambers having separate means for delivering and removing fluid therefrom, separate means associated with each of the delivering and removing means for producing useable energy external of the chambers, each of the means for producing useable energy having separate variable capacity energy outputs thereby making available a plurality of individual sources of useable energy of varying degrees.

Administratrix, A.P.; Rugh, J.L.

1982-11-02T23:59:59.000Z

460

Fusion reactor pumped laser  

DOE Patents [OSTI]

A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam. 10 figs.

Jassby, D.L.

1987-09-04T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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.


461

WHAT DO WE KNOW ABOUT INTERNATIONAL STUDENTS? 1. Learn what the existing research tells us  

E-Print Network [OSTI]

·Recruitment ·Degree completion ·Retention ·International education ·Curriculum Themes of Research Mental Citation Index · Search word: "International Students" or "Foreign Students" · Language: English · Document

Amin, S. Massoud

462

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

SciTech Connect (OSTI)

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

463

Nuclear Data Measurements for 21st Century Reactor Physics Applications  

SciTech Connect (OSTI)

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

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

2003-03-01T23:59:59.000Z

464

demokritos national center for scientific research institute of  

E-Print Network [OSTI]

RESEARCH REACTOR CENTER N. Catsaros Dynamic reliability of Complex System & decision Analysis I. Papazoglou protection 2004 annual report #12;cover page: cherenkoff radiation from the core of the institute's reactor-Domis RADIATION PROTECTION & HEALTH PHYSICS OF THE REACTOR I. Stamatelatos Exposure of the Population to Ionizing

465

The BGU/CERN solar hydrothermal reactor  

E-Print Network [OSTI]

We describe a novel solar hydrothermal reactor (SHR) under development by Ben Gurion University (BGU) and the European Organization for Nuclear Research CERN. We describe in broad terms the several novel aspects of the device and, by extension, of the niche it occupies: in particular, enabling direct off-grid conversion of a range of organic feedstocks to sterile useable (solid, liquid) fuels, nutrients, products using only solar energy and water. We then provide a brief description of the high temperature high efficiency panels that provide process heat to the hydrothermal reactor, and review the basics of hydrothermal processes and conversion taking place in this. We conclude with a description of a simulation of the pilot system that will begin operation later this year.

Bertolucci, Sergio; Caspers, Fritz; Garb, Yaakov; Gross, Amit; Pauletta, Stefano

2014-01-01T23:59:59.000Z

466

US, Russian Federation Sign Joint Statement on Reactor Conversion |  

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

US, Russian Federation Sign Joint Statement on Reactor Conversion US, Russian Federation Sign Joint Statement on Reactor Conversion US, Russian Federation Sign Joint Statement on Reactor Conversion June 26, 2012 - 12:00pm Addthis News Media Contact (202) 586-4940 This release is cross-posted from NNSA.energy.gov. MOSCOW - The U.S. and Russian Federation jointly announced today that the first stage of work defined in the Implementing Agreement between the Russian State Corporation for Atomic Energy (Rosatom) and the Department of Energy (DOE) Regarding Cooperation in Concluding Feasibility Studies of the Conversion of Russian Research Reactors of Dec. 7, 2010, has been completed. The announcement comes at the close of the most recent session of the Working Group on Nuclear Energy and Nuclear Security under the U.S.-Russia bilateral Presidential Commission, co-chaired by Daniel

467

Light Water Reactor Sustainability Program - Integrated Program Plan |  

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

Light Water Reactor Sustainability Program - Integrated Program Light Water Reactor Sustainability Program - Integrated Program Plan Light Water Reactor Sustainability Program - Integrated Program Plan The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U. S. Department of Energy (DOE), performed in close collaboration and cooperation with related industry R&D programs. The LWRS Program provides technical foundations for licensing and managing the long-term, safe, and economical operation of current nuclear power plants, utilizing the unique capabilities of the national laboratory system. Sustainability is defined as the ability to maintain safe and economic operation of the existing fleet of nuclear power plants for a longer than-initially-licensed lifetime. It has two facets

468

US, Russian Federation Sign Joint Statement on Reactor Conversion |  

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

US, Russian Federation Sign Joint Statement on Reactor Conversion US, Russian Federation Sign Joint Statement on Reactor Conversion US, Russian Federation Sign Joint Statement on Reactor Conversion June 26, 2012 - 12:00pm Addthis News Media Contact (202) 586-4940 This release is cross-posted from NNSA.energy.gov. MOSCOW - The U.S. and Russian Federation jointly announced today that the first stage of work defined in the Implementing Agreement between the Russian State Corporation for Atomic Energy (Rosatom) and the Department of Energy (DOE) Regarding Cooperation in Concluding Feasibility Studies of the Conversion of Russian Research Reactors of Dec. 7, 2010, has been completed. The announcement comes at the close of the most recent session of the Working Group on Nuclear Energy and Nuclear Security under the U.S.-Russia bilateral Presidential Commission, co-chaired by Daniel

469

Advanced Neutron Source Reactor thermal analysis of fuel plate defects  

SciTech Connect (OSTI)

The Advanced Neutron Source Reactor (ANSR) is a research reactor designed to provide the highest continuous neutron beam intensity of any reactor in the world. The present technology for determining safe operations were developed for the High Flux Isotope Reactor (HFIR). These techniques are conservative and provide confidence in the safe operation of HFIR. However, the more intense requirements of ANSR necessitate the development of more accurate, but still conservative, techniques. This report details the development of a Local Analysis Technique (LAT) that provides an appropriate approach. Application of the LAT to two ANSR core designs are presented. New theories of the thermal and nuclear behavior of the U{sub 3}Si{sub 2} fuel are utilized. The implications of lower fuel enrichment and of modifying the inspection procedures are also discussed. Development of the computer codes that enable the automate execution of the LAT is included.

Giles, G.E.

1995-08-01T23:59:59.000Z

470

On-power refueling for the CANDU reactor  

SciTech Connect (OSTI)

Atomic Energy of Canada Limited (AECL) CANDU, along with its affiliates, has designed and developed a specialized robotic system capable of refueling a Canada deuterium uranium (CANDU) reactor at full power under full load. Additionally, this is a production system; such on-power refueling is a routine daily occurrence on a CANDU reactor. On-power refueling was first successfully implemented on NRU, an AECL research reactor located at the Chalk River Nuclear Laboratories. Since then, it has been refined into the sophisticated automated robotic systems in daily use at 20 CANDU reactor units around the world. Although its development was necessary for the CANDU natural uranium fuel cycle, the technology has spin-off benefits that may be useful elsewhere.

Granz, R.P. (Atomic Energy of Canada Ltd., Mississauga, Ontario (Canada))

1992-01-01T23:59:59.000Z

471

Regulatory Oversight of Foreign Clinical Trials: An Examination of the Industry's Influence on FDA Pharmaceutical Regulation and the Implications for Enforcement Activity Both Domestic and Abroad  

E-Print Network [OSTI]

Regulatory Oversight of Foreign Clinical Trials: An Examination of the Industry's Influence on FDA Pharmaceutical Regulation and the Implications for Enforcement Activity Both Domestic and Abroad Beeta Kashani (FacultyAdvisor: Gary Reich... of the pharmaceutical industry on research regulation, and the factors that contribute to the FDA's regulatory and supervisory failures. The first part of this thesis will briefly outline the nature and ramifications of unethical clinical trials in the developing...

Kashani, Beeta

2012-04-01T23:59:59.000Z

472

W(C)-90-006 STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT  

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

06 06 STATEMENT OF CONSIDERATIONS CLASS WAIVER OF THE GOVERNMENT'S U.S. AND FOREIGN PATENT RIGHTS IN INVENTIONS MADE BY PARTICIPANTS IN THE PERFORMANCE OF COOPERATIVE RESEARCH AND DEVELOPMENT AGREEMENTS ENTERED INTO BY MIDWEST RESEARCH INSTITUTE (MRI) UNDER ITS MANAGEMENT AND OPERATING CONTRACT NO. DE-AC02-83CH10093 The Department of Energy (DOE) considers its Government-owned, Contractor-operated (GOCOs) laboratories, such as Solar Energy Research Institute (SERI) national resources capable of providing significant contribution to the development of new products and processes, creation of jobs, enhancement of the skill level of the U.S. labor force, and improved U.S. competitiveness. Congress, recognizing this unique aspect of GOCO laboratories, enacted the National Competitiveness Technology Transfer Act of 1989,

473

Thermionic Reactor Design Studies  

SciTech Connect (OSTI)

During the 1960's and early 70's the author performed extensive design studies, analyses, and tests aimed at thermionic reactor concepts that differed significantly from those pursued by other investigators. Those studies, like most others under Atomic Energy Commission (AEC and DOE) and the National Aeronautics and Space Administration (NASA) sponsorship, were terminated in the early 1970's. Some of this work was previously published, but much of it was never made available in the open literature. U.S. interest in thermionic reactors resumed in the early 80's, and was greatly intensified by reports about Soviet ground and flight tests in the late 80's. This recent interest resulted in renewed U.S. thermionic reactor development programs, primarily under Department of Defense (DOD) and Department of Energy (DOE) sponsorship. Since most current investigators have not had an opportunity to study all of the author's previous work, a review of the highlights of that work may be of value to them. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling. Where the author's concepts differed from the later Topaz-2 design was in the relative location of the emitter and the collector. Placing the fueled emitter on the outside of the cylindrical diodes permits much higher axial conductances to reduce ohmic losses in the electrodes of full-core-height diodes. Moreover, placing the fuel on the outside of the diode makes possible reactors with much higher fuel volume fractions, which enable power-flattened fast reactors scalable to very low power levels without the need for life-limiting hydride moderators or the use of efficiency-limiting driver fuel. In addition, with the fuel on the outside its swelling does not increase the emitter diameter or reduce the interelectrode gap. This should permit long lifetimes even with closer spacings, which can significantly improve the system efficiences. This was confirmed by coupled neutronic, thermal, thermionic, and electrical system analyses - some of which are presented in this paper - and by subsequent experiments. A companion paper presented next describes the fabrication and testing of full-scale converter elements, both fueled and unfueled, and summarizes the test results obtained. There is a duplicate copy in the file.

Schock, Alfred

1994-06-01T23:59:59.000Z

474

9 - Microporous silica membranes: fundamentals and applications in membrane reactors for hydrogen separation  

Science Journals Connector (OSTI)

Abstract: This chapter discusses the research and development of membrane reactors, incorporating microporous silica-based membranes, specifically for hydrogen production. Microporous silica membranes are first introduced alongside a discussion of relevant gas transport mechanisms, membrane performance parameters, membrane reactor designs and membrane reactor performance metrics. This is followed by an in-depth analysis of the various research investigations where silica membrane reactors have been used to produce hydrogen and/or syngas from hydrocarbon reforming reactions. Of particular importance here is the hydrothermal instability of silica-based membranes at the required operating temperatures and so the chapter closes by presenting the future research trends and industrial design challenges and considerations of silica-based membrane reactors.

S. Smart; J. Beltramini; J.C. Diniz da Costa; S.P. Katikaneni; T. Pham

2013-01-01T23:59:59.000Z

475

Locally Employed Staff (LES)/Foreign Service National (FSN) of the Year Award  

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

Locally Employed Staff (LES)/Foreign Service National (FSN) Locally Employed Staff (LES)/Foreign Service National (FSN) of the Year Award The Locally Employed Staff (LES)/Foreign Service National (FSN) of the Year Award is designed to recognize special contributions made by the Department's LES/FSN's in achieving the U.S. Department of Energy's (DOE) and United States Government's (USG) foreign policy goals and objectives. The LES/FSN of the Year Award is the Department's most prestigious award for non- Federal locally employed staff serving the Department overseas, and recognizes their outstanding achievements for the period of 1 October through 30 September each year. This

476

FOREIGN ASSISTANCE FOR HANDLING SPENT NUCLEAR NAVAL FUEL IN RUSSIA: SETTING PRIORITIESi  

Science Journals Connector (OSTI)

For Russia's foreign partners, prioritizing tasks related to spent fuel management first involves identifying urgent needs, potential bottlenecks or gaps in assistance programs, safety and security issues, and...

C. CHUEN

2006-01-01T23:59:59.000Z

477

WA_02_045_KENNAMETAL_INC_Waiver_of_Domestic_and_Foreign_Righ...  

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

LINCWaiverofDomesticandForeignRigh.pdf More Documents & Publications WA00011HONEYWELLINTERNATIONALWaiverofDomesticandFor.pdf WA01034INGERSOLL-RANDENERGYSYSTEMS...

478

Diplomacy & deception : King James VI of Scotland's foreign relations with Europe (c.1584-1603) .  

E-Print Network [OSTI]

??This thesis is the first attempt to provide an assessment of Scottish-Jacobean foreign relations within a European context in the years before 1603. Moreover, it (more)

Fry, Cynthia Ann

2014-01-01T23:59:59.000Z

479

E-Print Network 3.0 - american foreign policy Sample Search Results  

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

foreign policy interests from a nonpartisan perspective within the framework... of political realism. American ... Source: Grant, James D.E. - Fakultt fr Mathematik,...

480

Understanding the information literacy experiences of EFL (English as a Foreign Language) students.  

E-Print Network [OSTI]

??This thesis investigated the information literacy experiences of EFL (English as a Foreign Language) students in a higher education institution in the United Arab Emirates (more)

Johnston, Nicole R.

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "foreign 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.


481

Property rights, negotiating power and foreign investment: An international and comparative law study on Africa.  

E-Print Network [OSTI]

??Property rights are crucial in shaping foreign investment and its socio?economic outcomes. Their allocation, protection and regulation influence the way the risks, costs and benefits (more)

Cotula, Lorenzo

2009-01-01T23:59:59.000Z