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1

U.S. Department Of Energy Naval Reactors Laboratory Field Office  

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

Of Energy Naval Reactors Laboratory Field Office Knolls Laboratory National Environmental Policy Act (NEPA) Categorical Exclusion (CX) Determination Summary Form BUILDING A10...

2

NAVAL RESEARCH LABORATORY Information Technology Solutions  

power (CHP) or emergency backup power Small, High Efficiency, Recuperated Ceramic Turboshaft Engine NAVAL RESEARCH LABORATORY TECHNOLOGY T RANSFER ...

3

Request for Naval Reactors Comment on Proposed Prometheus Space Flight Nuclear Reactor High Tier Reactor Safety Requirements and for Naval Reactors Approval to Transmit These Requirements to JPL  

SciTech Connect

The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophy on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory.

D. Kokkinos

2005-04-28T23:59:59.000Z

4

More About NNSA's Naval Reactors Office | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Naval Reactors Office The Naval Nuclear Propulsion Program provides militarily effective nuclear propulsion plants and ensures their safe, reliable and long-lived operation. This...

5

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

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

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

6

A Review of OLED Research at Naval Research Laboratory  

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

Division at Naval Research Laboratory. Her research is focused on organic light emitting diode (OLED) material and devices. She will discuss the research activities at Naval...

7

More About NNSA's Naval Reactors Office | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

to skip to the main content Facebook Flickr RSS Twitter YouTube More About NNSA's Naval Reactors Office | National Nuclear Security Administration Our Mission Managing the...

8

1996 environmental monitoring report for the Naval Reactors Facility  

Science Conference Proceedings (OSTI)

The results of the radiological and nonradiological environmental monitoring programs for 1996 at the Naval Reactors Facility (NRF) are presented in this report. The NRF is located on the Idaho National Engineering and Environmental Laboratory and contains three naval reactor prototypes and the Expended Core Facility, which examines developmental nuclear fuel material samples, spent naval fuel, and irradiated reactor plant components/materials. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with state and federal regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the Environmental Protection Agency (EPA) and the Department of Energy (DOE).

NONE

1996-12-31T23:59:59.000Z

9

Audit Report - Naval Reactors Information Technology System Development Efforts, IG-0879  

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

Naval Reactors Information Naval Reactors Information Technology System Development Efforts DOE/IG-0879 December 2012 U.S. Department of Energy Office of Inspector General Office of Audits & Inspections Department of Energy Washington, DC 20585 December 21, 2012 MEMORANDUM FOR THE ADMINISTRATOR, NATIONAL NUCLEAR SECURITY ADMINISTRATION FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on the "Naval Reactors Information Technology System Development Efforts" INTRODUCTION AND OBJECTIVE The Naval Reactors Program (Naval Reactors), an organization within the National Nuclear Security Administration, was established to provide the military with safe and reliable nuclear propulsion plants to power warships and submarines. Naval Reactors maintains responsibility

10

NAVAL REACTORS PHYSICS HANDBOOK. VOLUME I. SELECTED BASIC TECHNIQUES  

SciTech Connect

The purpose of this work is to present the most pertinent parts of the body of physics knowledge which has been built up in the course of the Naval and Shippingport (PWR) Reactor Programs, with the aim of providing a background of understanding for those interested in nuclear core design. Volume 1 of this handbook was planned to bring together topics in the basic theoretical and experimental material which are of especially wide interest, including those common to both thermal and intermediate neutron energy reactor types. The physics design of light water-moderated and -cooled reactors is covered in Volume 2 (classified), and that of intermediate neutron-energy power reactors in Volume 3. The emphasis in Volume 1 is thus on light water reactor systems, and as many recent advances in reactor physics of the Naval and Shippingport Reactor Programs as possible have been included.

Radkowsky, A. ed.

1964-01-01T23:59:59.000Z

11

Tag: Naval Reactors | Y-12 National Security Complex  

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

Naval Reactors Naval Reactors Tag: Naval Reactors Displaying 1 - 7 of 7... Category: Employees & Retirees "Cook"ing at Y-12 for 70 years We have an enduring mission. Y-12 plays a key role in it. And a nuclear deterrent remains the ultimate insurance policy for America. More... Category: News Y-12 Knows Uranium Y-12 produces many forms of uranium. More... Category: News A Rich Resource Requires Recovery Given the value and scarcity of enriched uranium, Y-12 recycles and reuses as much of it as possible. More... Category: News Seawolf Manufacturing Challenge For decades, attack submarines were either fast or quiet - but never both. The fast subs were so loud that an enemy could hear them long before they were within striking distance. More... Category: News Reliable fuel source

12

Statement on Defense Nuclear Nonproliferation and Naval Reactors Activities  

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

Defense Nuclear Nonproliferation and Naval Reactors Activities Defense Nuclear Nonproliferation and Naval Reactors Activities before the House Committee on Appropriations Subcommittee on Energy & Water Development | 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 > Congressional Testimony > Statement on Defense Nuclear

13

Statement on Defense Nuclear Nonproliferation and Naval Reactors Activities  

National Nuclear Security Administration (NNSA)

Defense Nuclear Nonproliferation and Naval Reactors Activities Defense Nuclear Nonproliferation and Naval Reactors Activities before the House Committee on Appropriations Subcommittee on Energy & Water Development | 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 > Congressional Testimony > Statement on Defense Nuclear

14

DOE - Office of Legacy Management -- Naval Research Laboratory - DC 02  

Office of Legacy Management (LM)

Research Laboratory - DC 02 Research Laboratory - DC 02 FUSRAP Considered Sites Site: NAVAL RESEARCH LABORATORY (DC.02 ) Eliminated from consideration under FUSRAP - Referred to DOD Designated Name: Not Designated Alternate Name: None Location: Washington , D.C. DC.02-4 Evaluation Year: 1987 DC.02-4 Site Operations: Research and development on thermal diffusion. DC.02-4 Site Disposition: Eliminated - No Authority - AEC licensed - Military facility DC.02-4 DC.02-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium, Thorium DC.02-2 DC.02-3 Radiological Survey(s): None Indicated Site Status: Eliminated from consideration under FUSRAP - Referred to DOD DC.02-4 Also see Documents Related to NAVAL RESEARCH LABORATORY DC.02-1 - AEC Memorandum and Source Material License No. C-3393;

15

Naval Reactors Facility environmental monitoring report, calendar year 2001  

Science Conference Proceedings (OSTI)

The results of the radiological and nonradiological environmental monitoring programs for 2001 at the Naval Reactors Facility are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U. S. Environmental Protection Agency and the U. S. Department of Energy.

NONE

2002-12-31T23:59:59.000Z

16

Naval Reactors Facility environmental monitoring report, calendar year 1999  

Science Conference Proceedings (OSTI)

The results of the radiological and nonradiological environmental monitoring programs for 1999 at the Naval Reactors Facility (NRF) are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE).

None

2000-12-01T23:59:59.000Z

17

Naval Reactors Facility environmental monitoring report, calendar year 2000  

Science Conference Proceedings (OSTI)

The results of the radiological and nonradiological environmental monitoring programs for 2000 at the Naval Reactors Facility (NRF) are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE).

None

2001-12-01T23:59:59.000Z

18

Naval Reactors Facility Environmental Monitoring Report, Calendar Year 2003  

Science Conference Proceedings (OSTI)

The results of the radiological and nonradiological environmental monitoring programs for 2003 at the Naval Reactors Facility are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U.S. Environmental Protection Agency and the U.S. Department of Energy.

None

2003-12-31T23:59:59.000Z

19

EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS  

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

89: Disposal of Decommissioned, Defueled Naval Reactor Plants 89: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington Summary This EA, prepared by the Department of the Navy, evaluates the environmental impacts of the disposal of decommissioned, defueled, naval reactor plants from the USS Enterprise at DOE's Hanford Site, Richland, Washington. DOE participated as a cooperating agency in the preparation of this EA. The Department of the Navy issued its FONSI on August 23, 2012. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download August 23, 2012

20

Development of A Mesoscale Ensemble Data Assimilation System at The Naval Research Laboratory  

Science Conference Proceedings (OSTI)

An ensemble Kalman filter (EnKF) has been adopted and implemented at the Naval Research Laboratory (NRL) for mesoscale and storm-scale data assimilation to study the impact of ensemble assimilation of high-resolution observations, including those ...

Qingyun Zhao; Fuqing Zhang; Teddy Holt; Craig H. Bishop; Qin Xu

Note: This page contains sample records for the topic "naval reactors laboratory" 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

September 10, 2003, Board Public Meeting - Naval Reactors Approach to Oversight  

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

4 4 25 22 As I previously mentioned this morning, we will receive testimony from experienced representatives from other organizations. First, I would like to welcome representatives from the U.S. Naval Sea Systems Command, Mr. Thomas Beckett and Mr. Storm Kauffman. If you would be kind enough to give your names and titles so the stenographer can identify you for the record. MR. BECKETT: Thank you, Mr. Chairman. Thomas H. Beckett. I ' m the Deputy Director for Naval Reactors, a joint Department of the Navy/Department of Energy Program. MR. KAUFFMAN: Storm Kauffman. I ' m the Director of Reactor Safety and Analysis for the Naval Reactors Program CHAIRMAN CONWAY: Mr. Beckett. MR. BECKETT: Thank you, Mr. Chairman, and let me thank you and the other Board Members f

22

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement. Volume 1, Appendix D: Part A, Naval Spent Nuclear Fuel Management  

SciTech Connect

Volume 1 to the Department of Energy`s Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site.

Not Available

1994-06-01T23:59:59.000Z

23

DOE - Office of Legacy Management -- Naval Ordnance Laboratory - MD 0-03  

Office of Legacy Management (LM)

Ordnance Laboratory - MD 0-03 Ordnance Laboratory - MD 0-03 FUSRAP Considered Sites Site: NAVAL ORDNANCE LABORATORY (MD.0-03 ) Eliminated from further consideration under FUSRAP - Referred to DOD Designated Name: Not Designated Alternate Name: Naval Ordnance Laboratory - White Oak Location: White Oak Area , Silver Spring , Maryland MD.0-03-1 MD.0-03-2 Evaluation Year: 1987 MD.0-03-2 Site Operations: Research and development - may have involved radioactive materials because the site was identified on a 1955 Accountability Station List. MD.0-03-1 Site Disposition: Eliminated - NRC licensed MD.0-03-2 Radioactive Materials Handled: None Specifically Identified Primary Radioactive Materials Handled: None specifically indicated Radiological Survey(s): None Indicated Site Status: Eliminated from further consideration under FUSRAP - Referred to DOD MD.0-03-2

24

Naval Nuclear Propulsion Program Directorate, Washington ...  

Science Conference Proceedings (OSTI)

Naval Nuclear Propulsion Program Directorate, Washington, DC. NVLAP Lab Code: 100565-10. Address and Contact Information: Naval Reactors ...

2013-07-26T23:59:59.000Z

25

Naval Research Laboratory Washington, DC 20375-5320  

E-Print Network (OSTI)

Laboratory, Washington, DC M. Wolford, Science Applications International, Corporation, McLean, VA F. Hegeler resolution along the laser axis to account for the change in gain from mirror to front window. The code) Pulsed Power System Amplifier Window BZ Laser Input Electron Beam Foil Support (Hibachi) Cathode Laser

26

Idaho National Laboratory Advanced Test Reactor Probabilistic...  

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

Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment September 19, 2012...

27

Accelerator Laboratory AGN-201M Nuclear Reactor Laboratory  

E-Print Network (OSTI)

Laboratory Nuclear Power Institute (NPI) Nuclear Science Center (1MW Triga Reactor) (NSC) Nuclear SecurityAccelerator Laboratory AGN-201M Nuclear Reactor Laboratory Center for Large-scale Scientific Simulations (CLASS) Fuel Cycle and Materials Laboratory (FCML) Institute for National Security, Education

28

Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories  

Office of Legacy Management (LM)

ADVANCED REACTORS DIVISION FUEL LABORATORIES CHESWICK, PENNSYLVANIA Department of Energy Office of Policy, Safety and Environment Office of Operational Safety Environmental...

29

Naval Research Laboratory Multiscale Targeting Guidance for T-PARC and TCS-08  

Science Conference Proceedings (OSTI)

As part of The Observing System Research and Predictability Experiment (THORPEX) Pacific Asian Regional Campaign (T-PARC) and the Office of Naval Research’s (ONR’s) Tropical Cyclone Structure-08 (TCS-08) experiments, a variety of real-time ...

Carolyn A. Reynolds; James D. Doyle; Richard M. Hodur; Hao Jin

2010-04-01T23:59:59.000Z

30

Naval Nuclear Propulsion Plants | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Naval Nuclear Propulsion Plants In naval nuclear propulsion plants, fissioning of uranium atoms in the reactor core produces heat. Because the fission process also produces...

31

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix D, Part B: Naval spent nuclear fuel management  

SciTech Connect

This volume contains the following attachments: transportation of Naval spent nuclear fuel; description of Naval spent nuclear receipt and handling at the Expended Core Facility at the Idaho National Engineering Laboratory; comparison of storage in new water pools versus dry container storage; description of storage of Naval spent nuclear fuel at servicing locations; description of receipt, handling, and examination of Naval spent nuclear fuel at alternate DOE facilities; analysis of normal operations and accident conditions; and comparison of the Naval spent nuclear fuel storage environmental assessment and this environmental impact statement.

1994-06-01T23:59:59.000Z

32

Sandia National Laboratories Medical Isotope Reactor concept.  

SciTech Connect

This report describes the Sandia National Laboratories Medical Isotope Reactor and hot cell facility concepts. The reactor proposed is designed to be capable of producing 100% of the U.S. demand for the medical isotope {sup 99}Mo. The concept is novel in that the fuel for the reactor and the targets for the {sup 99}Mo production are the same. There is no driver core required. The fuel pins that are in the reactor core are processed on a 7 to 21 day irradiation cycle. The fuel is low enriched uranium oxide enriched to less than 20% {sup 235}U. The fuel pins are approximately 1 cm in diameter and 30 to 40 cm in height, clad with Zircaloy (zirconium alloy). Approximately 90 to 150 fuel pins are arranged in the core in a water pool {approx}30 ft deep. The reactor power level is 1 to 2 MW. The reactor concept is a simple design that is passively safe and maintains negative reactivity coefficients. The total radionuclide inventory in the reactor core is minimized since the fuel/target pins are removed and processed after 7 to 21 days. The fuel fabrication, reactor design and operation, and {sup 99}Mo production processing use well-developed technologies that minimize the technological and licensing risks. There are no impediments that prevent this type of reactor, along with its collocated hot cell facility, from being designed, fabricated, and licensed today.

Coats, Richard Lee; Dahl, James J.; Parma, Edward J., Jr.

2010-04-01T23:59:59.000Z

33

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

34

Zero Power Reactor simulation | Argonne National Laboratory  

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

Zero Power Reactor simulation Share Description Ever wanted to see a nuclear reactor core in action? Here's a detailed simulation of the Zero Power Reactor experiment, run by...

35

CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor |  

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

Reactor Reactor CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. RADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor

36

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Maintenance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor

37

Reactor Tree of Argonne National Laboratory  

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

Argonne Reactors > The Argonne Reactor Tree About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne...

38

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Engineering - Oak Ridge National Laboratory High Flux Isotope Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Engineering Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

39

Overview of Sandia National Laboratories pulse nuclear reactors  

SciTech Connect

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

40

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Maintenance Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Idaho National Laboratory Advanced Test Reactor Probabilistic Risk  

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

Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment September 19, 2012 Presenter: Bentley Harwood, Advanced Test Reactor Nuclear Safety Engineer Battelle Energy Alliance Idaho National Laboratory Topics covered: PRA studies began in the late 1980s 1989, ATR PRA published as a summary report 1991, ATR PRA full report 1994 and 2004 various model changes 2011, Consolidation, update and improvement of previous PRA work 2012/2013, PRA risk monitor implementation Idaho National Laboratory Advanced Test Reactor Probabilistic Risk Assessment More Documents & Publications DOE's Approach to Nuclear Facility Safety Analysis and Management Nuclear Regulatory Commission Handling of Beyond Design Basis Events for

42

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor |  

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

Management- Oak Ridge National Laboratory High Flux Isotope Management- Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope

43

Tag: Naval Reactors  

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

9/all en "Cook"ing at Y-12 for 70 9/all en "Cook"ing at Y-12 for 70 years http://www.y12.doe.gov/employees-retirees/y-12-times/cooking-y-12-70-years

We have an enduring mission. Y-12 plays a key role in it. And a nuclear deterrent remains the ultimate insurance policy for America.

CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux

45

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Oak Ridge National Laboratory High Flux Isotope Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Engineering Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications

46

CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Oak Ridge National Laboratory High Flux Isotope Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications

47

Reactor Decommissioning Projects | Brookhaven National Laboratory  

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

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

48

U.S. Department of Energy Naval Reactors Laboratory Field Office  

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

use soil cleanup objectives. The ICM will be conducted by a DOE-EM SPRU contractor (URS). URS work will entail the preparation of an excavation plan in accordance with the ICM...

49

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

Science Conference Proceedings (OSTI)

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

Rosenthal, Murray Wilford [ORNL

2009-08-01T23:59:59.000Z

50

Risk management at the Oak Ridge National Laboratory research reactors  

SciTech Connect

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

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

1994-12-31T23:59:59.000Z

51

Current Reactor Physics Benchmark Activities at the Idaho National Laboratory  

SciTech Connect

The International Reactor Physics Experiment Evaluation Project (IRPhEP) [1] and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) [2] were established to preserve integral reactor physics and criticality experiment data for present and future research. These valuable assets provide the basis for recording, developing, and validating our integral nuclear data, and experimental and computational methods. These projects are managed through the Idaho National Laboratory (INL) and the Organisation for Economic Co-operation and Development Nuclear Energy Agency (OECD-NEA). Staff and students at the Department of Energy - Idaho (DOE-ID) and INL are engaged in the development of benchmarks to support ongoing research activities. These benchmarks include reactors or assemblies that support Next Generation Nuclear Plant (NGNP) research, space nuclear Fission Surface Power System (FSPS) design validation, and currently operational facilities in Southeastern Idaho.

John D. Bess; Margaret A. Marshall; Mackenzie L. Gorham; Joseph Christensen; James C. Turnbull; Kim Clark

2011-11-01T23:59:59.000Z

52

Multiple Irradiation Capsule Experiment (MICE)-3B Irradiation Test of Space Fuel Specimens in the Advanced Test Reactor (ATR) - Close Out Documentation for Naval Reactors (NR) Information  

SciTech Connect

Few data exist for UO{sub 2} or UN within the notional design space for the Prometheus-1 reactor (low fission rate, high temperature, long duration). As such, basic testing is required to validate predictions (and in some cases determine) performance aspects of these fuels. Therefore, the MICE-3B test of UO{sub 2} pellets was designed to provide data on gas release, unrestrained swelling, and restrained swelling at the upper range of fission rates expected for a space reactor. These data would be compared with model predictions and used to determine adequacy of a space reactor design basis relative to fission gas release and swelling of UO{sub 2} fuel and to assess potential pellet-clad interactions. A primary goal of an irradiation test for UN fuel was to assess performance issues currently associated with this fuel type such as gas release, swelling and transient performance. Information learned from this effort may have enabled use of UN fuel for future applications.

M. Chen; CM Regan; D. Noe

2006-01-09T23:59:59.000Z

53

SUPPLEMENT ANALYSIS OF FOREIGN RESEARCH REACTOR srENT NUCLEAR FUEL  

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

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

54

Naval applications study areas  

SciTech Connect

This memorandum discusses study areas and items that will require attention for the naval studies of the utilization of nuclear propulsion in a submarine-based missile system.

Hadley, J. W.

1962-06-20T23:59:59.000Z

55

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

SciTech Connect

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

1962-09-14T23:59:59.000Z

56

Early Exploration - Reactors designed/built by Argonne National Laboratory  

NLE Websites -- All DOE Office Websites (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

57

Sandia National Laboratories: Research: Facilities: Sandia Pulsed Reactor  

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

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

58

The High Flux Isotope Reactor at Oak Ridge National Laboratory  

NLE Websites -- All DOE Office Websites

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

59

Idaho National Engineering Laboratory waste area groups 1--7 and 10 Technology Logic Diagram. Volume 1  

SciTech Connect

The Technology Logic Diagram was developed to provide technical alternatives for environmental restoration projects at the Idaho National Engineering Laboratory. The diagram (three volumes) documents suggested solutions to the characterization, retrieval, and treatment phases of cleanup activities at contaminated sites within 8 of the laboratory`s 10 waste area groups. Contaminated sites at the laboratory`s Naval Reactor Facility and Argonne National Laboratory-West are not included in this diagram.

O`Brien, M.C.; Meservey, R.H.; Little, M.; Ferguson, J.S.; Gilmore, M.C.

1993-09-01T23:59:59.000Z

60

Vertical Pretreatment Reactor System (Poster), NREL (National Renewable Energy Laboratory)  

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

Vertical Pretreatment Reactor System Vertical Pretreatment Reactor System Two-vessel system for primary and secondary pretreatment at diff erent temperatures * Biomass is heated by steam injection to temperatures of 120°C to 210°C in the pressurized mixing tube * Preheated, premixed biomass is retained for specified residence time in vertical holding vessel; material continuously moves by gravity from top to bottom of reactor in plug-fl ow fashion * Residence time is adjusted by changing amount of material held in vertical vessel relative to continuous fl ow of material entering and exiting vessel * Optional additional reactor vessel allows for secondary pretreatment at lower temperatures-120°C to 180°C-with potential to add other chemical catalysts * First vessel can operate at residence

Note: This page contains sample records for the topic "naval reactors laboratory" 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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61

Horizontal Pretreatment Reactor System (Poster), NREL (National Renewable Energy Laboratory)  

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

Diff Diff erent pretreatment chemistry/ residence time combinations are possible using these multiple horizontal-tube reactors * Each tube is indirectly and directly steam heated to temperatures of 150 0 C to 210 0 C * Residence time is varied by changing the speed of the auger that moves the biomass through each tube reactor * Tubes are used individually or in combination to achieve diff erent pretreatment residence times * Smaller tubes made from Hastelloy, an acid-resistant material, are used with more corrosive chemicals and residence times from 3 to 20 minutes * Larger tubes made from 316 stainless steel are used for residence times from 20 to 120 minutes Horizontal Pretreatment Reactor System Versatile pretreatment system for a wide range of pretreatment chemistries

62

Los Alamos National Laboratory Omega West Reactor restart  

Science Conference Proceedings (OSTI)

This report is a critical evaluation of the effort for the restart of the Omega West reactor. It is divided into the following areas: progress made; difficulties in restart effort; current needs; and suggested detailed steps for improvement. A brief discussion is given for each area of study.

NONE

1993-08-27T23:59:59.000Z

63

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

SciTech Connect

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

Nick A. Altic

2011-11-11T23:59:59.000Z

64

An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory  

SciTech Connect

Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs.

Boing, L.E.; Henley, D.R. (Argonne National Lab., IL (USA)); Manion, W.J.; Gordon, J.W. (Nuclear Energy Services, Inc., Danbury, CT (USA))

1989-12-01T23:59:59.000Z

65

EIS-0259 Final Environmental Impact Statement On The Disposal Of Decommissioned, Defueled Cruiser, Ohio Class, And Los Angeles Class Naval Reactor Plants  

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

-. -. 1. PURPOSE AND NEED U.S. Navy nuclear ships are decommissioned and defieled at the end of their usefi Metime, when the cost of continued operation is not justified by their fitary capabfity, or when the ship is no longer needed. The Navy needs to disposition the reactor compartments born defieled and decommissioned ctisers, and OHIO Class and LOS ANGELES Class submarines. The number of reactor compartments under consideration by this Environmental Impact Statement is about 100. These reactor compartments are in addition to the pre-LOS ANGELES Class submarines tieady being disposed of under the Na&s 1984 Find Environmental hpact Statement (USN, 1984a). Newer types of U.S. Navy nuclear-powered stips that are not expected to be decommissioned in the next 20 years (e.g., aircraft carriers, SEAWOLF Class submarines) are not included in this fid Enviromentd Impact Statement.

66

EIS-0259 Final Environmental Impact Statement On The Disposal Of Decommissioned, Defueled Cruiser, Ohio Class, And Los Angeles Class Naval Reactor Plants  

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

... -. FEASIBILITY STUDY FOR LEAD REMOVAL FROM AND STRUCTURAL RESTORATION OF CRUISER, OHIO, AND LOS ANGELES CLASS REACTOR COMPARTMENT DISPOSAL PACWGES Appendix A A-i . Table of Contents E~CUT~ S~Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..A.3 1. ~TRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .." . . . . . . . . . . . . . . . ..A.3 2. DESCR~TION OF S~ELD~G LEAD CONTmD ~ REACTOR commmm PAcmGEs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..A.4 2.1 PermanentSMeldingLead . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..A-4 2.2 MisceUaneousLead . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..A-5 2.3 Considerations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................"A-5 2.4 Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .................A-5 3. SHIELD~G LEAD REMOVQ

67

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

SciTech Connect

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

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

1990-01-01T23:59:59.000Z

68

INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK  

SciTech Connect

5098-SR-03-0 FINAL REPORT- INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS, BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-12-15T23:59:59.000Z

69

Modern Status of Neutrino Experiments at the Underground Neutrino Laboratory of Kurchatov Institute Near Krasnoyarsk Nuclear Reactor  

E-Print Network (OSTI)

The investigation of antineutrino-deuteron interaction at Krasnoyarsk reactor are discussed. The characteristics of the installation ''Deuteron'', present results and perspectives of Krasnoyarsk neutrino laboratory are presented.

Yu. V. Kozlov; S. V. Khalturtsev; I. N. Machulin; A. V. Martemyanov; V. P. Martemyanov; A. A. Sabelnikov; S. V. Sukhotin; V. G. Tarasenkov; E. V. Turbin; V. N. Vyrodov

1998-11-11T23:59:59.000Z

70

Dynamic Impregnator Reactor System (Poster), NREL (National Renewable Energy Laboratory)  

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

Several unit operations are combined into Several unit operations are combined into one robust system, off ering fl exible and staged process confi gurations in one vessel. Spraying, soaking, low-severity pretreat- ment, enzymatic hydrolysis, fermentation, concentration/evaporation, and distillation are amongst its many capabilities. * 1,900 L Horizontal Paddle Blender Vessel with Sidewall Liquid Drains * 6-60 rpm / 50 HP Tri-Directional Agitator * 3.4 bar & Vacuum ASME Design, 316L Stainless Steel * Heating/Cooling Jacket using Water or Steam * 150 L Chemical Mix Tank & Pump with Spray Injectors * Vent Condenser with Collection Tank and Vacuum Pump Dynamic Impregnator Reactor System Multifaceted system designed for complex feedstock impregnation and processing Integrated Biorefi nery Research Facility | NREL * Golden, Colorado | December 15, 2011 | NREL/PO-5100-56156

71

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

SciTech Connect

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

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

1984-09-01T23:59:59.000Z

72

Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report  

Science Conference Proceedings (OSTI)

The decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East (ANL-E) was completed in October 1997. Descriptions and evaluations of the activities performed and analyses of the results obtained during the JANUS D and D Project are provided in this Final Report. The following information is included: objective of the JANUS D and D Project; history of the JANUS Reactor facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed; description of the project planning and engineering; description of the D and D operations; summary of the final status of the JANUS Reactor facility based upon the final survey results; description of the health and safety aspects of the project, including personnel exposure and OSHA reporting; summary of the waste minimization techniques utilized and total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project.

Fellhauer, C.R.; Clark, F.R. [Argonne National Lab., IL (United States). Technology Development Div.; Garlock, G.A. [MOTA Corp., Cayce, SC (United States)

1997-10-01T23:59:59.000Z

73

DOE - Office of Legacy Management -- Bettis Atomic Power Laboratories - PA  

Office of Legacy Management (LM)

Bettis Atomic Power Laboratories - Bettis Atomic Power Laboratories - PA 44 FUSRAP Considered Sites Site: Bettis Atomic Power Laboratories (PA.44 ) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Allegheny County , West Mifflin , Pennsylvania PA.44-1 Evaluation Year: Circa 1987 PA.44-2 Site Operations: Conducted activities directed toward the design, development, testing, and operational follow of nuclear reactor propulsion plants for Naval surface and submarine vessels. PA.44-1 Site Disposition: Eliminated - Active DOE facility PA.44-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Radioactive Materials Associated with Reactor Operation PA.44-3 Radiological Survey(s): None Indicated

74

FY 2012 Budget Hearing Testimony on Nuclear Nonproliferation and Naval  

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

on Nuclear Nonproliferation and Naval on Nuclear Nonproliferation and Naval Reactor Programs before the House Appropriations Committee, Energy and Water Development Subcommittee | 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 > Congressional Testimony > FY 2012 Budget Hearing Testimony on Nuclear ...

75

FY 2012 Budget Hearing Testimony on Nuclear Nonproliferation and Naval  

National Nuclear Security Administration (NNSA)

on Nuclear Nonproliferation and Naval on Nuclear Nonproliferation and Naval Reactor Programs before the House Appropriations Committee, Energy and Water Development Subcommittee | 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 > Congressional Testimony > FY 2012 Budget Hearing Testimony on Nuclear ...

76

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

Science Conference Proceedings (OSTI)

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

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

2002-11-01T23:59:59.000Z

77

NAVAL POSTGRADUATE SCHOOL MONTEREY, CALIFORNIA  

E-Print Network (OSTI)

), Stockholm Intl Peace Research Inst, Oxford University Oress 337 p., 1997. Arkin, WM and J Handler, Naval Geochemistry (eds. AC Sigleo and A Hattori), Lewis Publishers, Inc., Chelsea, MI, 97-119, 1985. Brungot, AL

78

Fracture of aluminum naval structures  

E-Print Network (OSTI)

Structural catastrophic failure of naval vessels due to extreme loads such as underwater or air explosion, high velocity impact (torpedoes), or hydrodynamic loads (high speed vessels) is primarily caused by fracture. ...

Galanis, Konstantinos, 1970-

2007-01-01T23:59:59.000Z

79

Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor  

SciTech Connect

In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs.

Boing, L.E.

1989-12-01T23:59:59.000Z

80

Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes  

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

Independent Oversight Review of the Independent Oversight Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 2

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes  

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

Independent Oversight Review of the Independent Oversight Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 2

82

Naval Spent Fuel Rail Shipment Accident Exercise Objectives ...  

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

Naval Spent Fuel Rail Shipment Accident Exercise Objectives Naval Spent Fuel Rail Shipment Accident Exercise Objectives Naval Spent Fuel Rail Shipment Accident Exercise Objectives...

83

2013 Annual Planning Summary for the Naval Nuclear Propulsion...  

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

Naval Nuclear Propulsion Program 2013 Annual Planning Summary for the Naval Nuclear Propulsion Program 2013 Annual Planning Summary for the Naval Nuclear Propulsion Program The...

84

Naval Research Laboratory Technologies Available for Licensing ...  

Energy Innovation Portal Technologies. ... Solar Thermal; Startup America; ... equipment, systems and ocean, atmospheric, and space sciences and related technologies.

85

NAVAL RESEARCH LABORATORY Information Technology Solutions  

in energy-storage devices that are: Low Cost Safe to Operate Environmentally Benign Relevant energy ... a time scale of relevance for hybrid electric ...

86

Naval Research Laboratory Technology Marketing Summaries ...  

Biomass and Biofuels; Building Energy Efficiency; Electricity Transmission; Energy Analysis; Energy Storage; ... target imprinted, porous, organosilicate sorbents.

87

Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory Â… East Argonne, Illinois  

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

DOE/EA-1483 DOE/EA-1483 Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois March 2004 U.S. Department of Energy Chicago Operations Office Argonne Area Office Argonne, Illinois Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois Table of Contents Acronyms....................................................................................................................................... iii 1.0 Background ..........................................................................................................................1 1.1 Facility History ........................................................................................................1

88

Naval Petroleum Reserves | Department of Energy  

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

Naval Petroleum Reserves For much of the 20th century, the Naval Petroleum and Oil Shale Reserves served as a contingency source of fuel for the Nation's military. All that...

89

Naval Nuclear Propulsion Program Directorate, Washington ...  

Science Conference Proceedings (OSTI)

Naval Nuclear Propulsion Program Directorate, Washington, DC. NVLAP Lab Code: 100565-0. Address and Contact Information: ...

2013-08-23T23:59:59.000Z

90

Naval Nuclear Propulsion Program Directorate, Washington ...  

Science Conference Proceedings (OSTI)

Naval Nuclear Propulsion Program Directorate, Washington, DC. NVLAP Lab Code: 100565-2. Address and Contact Information: Point Loma, Bldg. ...

2013-08-23T23:59:59.000Z

91

Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project  

SciTech Connect

The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned.

Hartnett, S.; Seguin, N. [Benchmark Environmental Corp., Albuquerque, NM (United States); Burns, M. [Los Alamos National Lab., NM (United States)

1995-12-31T23:59:59.000Z

92

PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 3 TRENCH 5, BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK  

Science Conference Proceedings (OSTI)

5098-SR-04-0 PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 3 TRENCH 5, BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-11-03T23:59:59.000Z

93

PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 3 TRENCH 1, BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK  

SciTech Connect

5098-SR-05-0 PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 3 TRENCH 1 BROOKHAVEN NATIONAL LABORATORY

E.M. Harpenau

2010-12-15T23:59:59.000Z

94

Containment performance analyses for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

This paper discusses salient aspects of methodology, assumptions, and modeling of various features related to estimation of source terms from two conservatively scoped severe accident scenarios in the Advanced Neutron Source (ANS) reactor at the Oak Ridge National Laboratory. Various containment configurations are considered for steaming-pool-type accidents and an accident involving molten core-concrete interaction. Several design features (such as rupture disks) are examined to study containment response during postulated severe accidents. Also, thermal-hydraulic response of the containment and radionuclide transport and retention in the containment are studied. The results are described as transient variations of source terms for each scenario, which are to be used for studying off-site radiological consequences and health effects for these postulated severe accidents. Also highlighted will be a comparison of source terms estimated by two different versions of the MELCOR code.

Kim, S.H.; Taleyarkhan, R.P.; Georgevich, V.

1992-10-01T23:59:59.000Z

95

Pulsed Power Technology at Sandia National Laboratories  

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

are some specific sites on Pulsed Power MAGPIE Pulsed Power Facility, Imperial College NIF Naval Research Laboratory, Plasma Physics Division Reviews of U.S. Fusion Policy UKAEA...

96

Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory Â… East Argonne, Illinois  

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

Finding of No Significant Impact Finding of No Significant Impact Proposed Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois AGENCY: U. S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has prepared an Environmental Assessment (EA), DOE/EA-1483, evaluating the decontamination and decommissioning of the Juggernaut Reactor at Argonne National Laboratory-East (ANL-E), in Argonne, Illinois. The decontamination and decommissioning of the reactor is needed to ensure the protection of the health and safety of the public, DOE and contractor employees, and the environment, consistent with DOE Order 5400.5, Radiation Protection of the Public and the Environment. Based on the analysis in the EA, DOE has determined that the proposed action does not

97

Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect

The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory’s recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy’s ability to meet obligations with the State of Idaho.

Lisa Harvego

2009-06-01T23:59:59.000Z

98

Geothermal energy at Long Beach Naval Shipyard and Naval Station and at Seal Beach Naval Weapons Station, California. Final report  

DOE Green Energy (OSTI)

The purpose of this project was to determine and evaluate sources of geothermal energy at two military bases in southern California, the Long Beach Naval Shipyard and Naval Station and the Seal Beach Naval Weapons Station. One part of the project focused on the natural geothermal characteristics beneath the naval bases. Another part focused on the geothermal energy produced by oilfield operations on and adjacent to each base. Results of the study are presented here for the US Department of the Navy to use in its program to reduce its reliance on petrolem by the development of different sources of energy. The study was accomplished under a cooperative agreement between the US Department of Energy's San Francisco Operations Office and the Department of the Navy's Naval Weapons Center, China Lake, California, for joint research and development of geothermal energy at military installations.

Higgins, C.T.; Chapman, R.H.

1984-01-01T23:59:59.000Z

99

EA-1008: Continued Development of Naval Petroleum Reserve No...  

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

8: Continued Development of Naval Petroleum Reserve No. 3 (Sitewide), Natrona County, Wyoming EA-1008: Continued Development of Naval Petroleum Reserve No. 3 (Sitewide), Natrona...

100

EA-1236: Preparation for Transfer of Ownership of Naval Petroleum...  

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

236: Preparation for Transfer of Ownership of Naval Petroleum Reserve No. 3, Natrona County, WY EA-1236: Preparation for Transfer of Ownership of Naval Petroleum Reserve No. 3,...

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Distributed energy resources at naval base ventura county building 1512  

E-Print Network (OSTI)

Naval Base Ventura County Standby Generator OptimizationC&H Engineering performed a standby generator optimizationOn Naval Base Ventura County Standby Generator Optimization

Bailey, Owen C.; Marnay, Chris

2004-01-01T23:59:59.000Z

102

2013 Federal Energy and Water Management Award Winner Naval Sea...  

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

Naval Sea Systems Command 2013 Federal Energy and Water Management Award Winner Naval Sea Systems Command fewm13nswcphiladelphiahighres.pdf fewm13nswcphiladelphia.pdf More...

103

Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory  

SciTech Connect

The Final Report for the Decontamination and Decommissioning (D&D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D&D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D&D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D&D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a {open_quotes}Radiologically Controlled Area,{close_quotes} noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion).

Fellhauer, C.R.; Boing, L.E. [Argonne National Lab., IL (United States); Aldana, J. [NES, Inc., Danbury, CT (United States)

1997-03-01T23:59:59.000Z

104

Scientific Upgrades at the Oak Ridge National Laboratory High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

The United States Department of Energy is sponsoring a number of projects that will provide scientific upgrades to the neutron science facilities associated with the High Flux Isotope Reactor (HFIR) located at Oak Ridge National Laboratory. Funding for the first upgrade project was initiated in 1996 and all presently identified upgrade projects are expected to be completed by the end of 2003. The upgrade projects include: (1) larger beam tubes, (2) a new monochromator drum for the HB-1 beam line, (3) a new HB-2 beam line system that includes one thermal guide and a new monochromator drum, (4) new instruments for the HB-2 beamline, (5) a new monochromator drum for the HB-3 beam line, (6) a supercritical hydrogen cold source system to be retrofitted into the HB-4 beam tube, (7) a 3.5 kW refrigeration system at 20 K to support the cold source and a new building to house it, (8) a new HB-4 beam line system composed of four cold neutron guides with various mirror coatings and associated shielding, (9) a number of new instruments for the cold beams including two new SANS instruments, and (10) construction of support buildings. This paper provides a short summary of these projects including their present status and schedule.

Selby, Douglas L [ORNL; Jones, Amy [ORNL; Crow, Lowell [ORNL

2012-01-01T23:59:59.000Z

105

Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois  

Science Conference Proceedings (OSTI)

Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratory’s Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007).

W. C. Adams

2007-05-25T23:59:59.000Z

106

TEMPERATURE MONITORING OPTIONS AVAILABLE AT THE IDAHO NATIONAL LABORATORY ADVANCED TEST REACTOR  

SciTech Connect

As part of the Advanced Test Reactor National Scientific User Facility (ATR NSUF) program, the Idaho National Laboratory (INL) has developed in-house capabilities to fabricate, test, and qualify new and enhanced sensors for irradiation testing. To meet recent customer requests, an array of temperature monitoring options is now available to ATR users. The method selected is determined by test requirements and budget. Melt wires are the simplest and least expensive option for monitoring temperature. INL has recently verified the melting temperature of a collection of materials with melt temperatures ranging from 100 to 1000 C with a differential scanning calorimeter installed at INL’s High Temperature Test Laboratory (HTTL). INL encapsulates these melt wires in quartz or metal tubes. In the case of quartz tubes, multiple wires can be encapsulated in a single 1.6 mm diameter tube. The second option available to ATR users is a silicon carbide temperature monitor. The benefit of this option is that a single small monitor (typically 1 mm x 1 mm x 10 mm or 1 mm diameter x 10 mm length) can be used to detect peak irradiation temperatures ranging from 200 to 800 C. Equipment has been installed at INL’s HTTL to complete post-irradiation resistivity measurements on SiC monitors, a technique that has been found to yield the most accurate temperatures from these monitors. For instrumented tests, thermocouples may be used. In addition to Type-K and Type-N thermocouples, a High Temperature Irradiation Resistant ThermoCouple (HTIR-TC) was developed at the HTTL that contains commercially-available doped molybdenum paired with a niobium alloy thermoelements. Long duration high temperature tests, in furnaces and in the ATR and other MTRs, demonstrate that the HTIR-TC is accurate up to 1800 C and insensitive to thermal neutron interactions. Thus, degradation observed at temperatures above 1100 C with Type K and N thermocouples and decalibration due to transmutation with tungsten-rhenium and platinum rhodium thermocouples can be avoided. INL is also developing an Ultrasonic Thermometry (UT) capability. In addition to small size, UT’s offer several potential advantages over other temperature sensors. Measurements may be made near the melting point of the sensor material, potentially allowing monitoring of temperatures up to 3000 C. In addition, because no electrical insulation is required, shunting effects are avoided. Most attractive, however, is the ability to introduce acoustic discontinuities to the sensor, as this enables temperature measurements at several points along the sensor length. As discussed in this paper, the suite of temperature monitors offered by INL is not only available to ATR users, but also to users at other MTRs.

J.E. Daw; J.L. Rempe; D.L. Knudson; T. Unruh; B.M. Chase; K.L Davis

2012-03-01T23:59:59.000Z

107

Comparative naval architecture analysis of diesel submarines  

E-Print Network (OSTI)

Many comparative naval architecture analyses of surface ships have been performed, but few published comparative analyses of submarines exist. Of the several design concept papers, reports and studies that have been written ...

Torkelson, Kai Oscar

2005-01-01T23:59:59.000Z

108

The dynamics of naval resource allocation  

Science Conference Proceedings (OSTI)

Naval policy planning requires viewing the entire spectrum of annual resource allocation, over a long period. Emerging research into the trade offs between force asset levels and fund flows to support those assets is described. The method underlying ...

Rolf Clark

1981-01-01T23:59:59.000Z

109

Sandia National Laboratories results for the 2010 criticality accident dosimetry exercise, at the CALIBAN reactor, CEA Valduc France.  

Science Conference Proceedings (OSTI)

This document describes the personal nuclear accident dosimeter (PNAD) used by Sandia National Laboratories (SNL) and presents PNAD dosimetry results obtained during the Nuclear Accident Dosimeter Intercomparison Study held 20-23 September, 2010, at CEA Valduc, France. SNL PNADs were exposed in two separate irradiations from the CALIBAN reactor. Biases for reported neutron doses ranged from -15% to +0.4% with an average bias of -7.7%. PNADs were also exposed on the back side of phantoms to assess orientation effects.

Ward, Dann C.

2011-09-01T23:59:59.000Z

110

HWMA/RCRA CLOSURE PLAN FOR THE MATERIALS TEST REACTOR WING (TRA-604) LABORATORY COMPONENTS VOLUNTARY CONSENT ORDER ACTION PLAN VCO-5.8 D REVISION2  

SciTech Connect

This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the laboratory components of the Test Reactor Area Catch Tank System (TRA-630) that are located in the Materials Test Reactor Wing (TRA-604) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan VCO-5.8.d. The TRA-604 laboratory components addressed in this closure plan were deferred from the TRA-630 Catch Tank System closure plan due to ongoing laboratory operations in the areas requiring closure actions. The TRA-604 laboratory components include the TRA-604 laboratory warm wastewater drain piping, undersink drains, subheaders, and the east TRA-604 laboratory drain header. Potentially contaminated surfaces located beneath the TRA-604 laboratory warm wastewater drain piping and beneath the island sinks located in Laboratories 126 and 128 (located in TRA-661) are also addressed in this closure plan. The TRA-604 laboratory components will be closed in accordance with the interim status requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265, Subparts G and J. This closure plan presents the closure performance standards and the methods for achieving those standards.

KIRK WINTERHOLLER

2008-02-25T23:59:59.000Z

111

Tiger Team assessment of the Idaho National Engineering Laboratory  

SciTech Connect

This report documents the Tiger Team Assessment of the Idaho National Engineering Laboratory (INEL) located in Idaho Falls, Idaho. INEL is a multiprogram, laboratory site of the US Department of Energy (DOE). Overall site management is provided by the DOE Field Office, Idaho; however, the DOE Field Office, Chicago has responsibility for the Argonne National Laboratory-West facilities and operations through the Argonne Area Office. In addition, the Idaho Branch Office of the Pittsburgh Naval Reactors Office has responsibility for the Naval Reactor Facility (NRF) at the INEL. The assessment included all DOE elements having ongoing program activities at the site except for the NRF. In addition, the Safety and Health Subteam did not review the Westinghouse Idaho Nuclear Company, Inc. facilities and operations. The Tiger Team Assessment was conducted from June 17 to August 2, 1991, under the auspices of the Office of Special Projects, Office of the Assistant Secretary for Environment, Safety and Health, Headquarters, DOE. The assessment was comprehensive, encompassing environmental, safety, and health (ES H) disciplines; management; and contractor and DOE self-assessments. Compliance with applicable federal, state, and local regulations; applicable DOE Orders; best management practices; and internal INEL site requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of the DOE and the site contractors management of ES H/quality assurance programs was conducted.

Not Available

1991-08-01T23:59:59.000Z

112

Department of Reactor Technology Ris#-H-2101 Ris National Laboratory SRE-7-78  

E-Print Network (OSTI)

. April 1978 Denmark NUCLEAR DISTRICT HEATING PLANT PRELIMINARY DESIGN CONCEPT by Kurt Hansen * Hans Erik-M-fnoi I Title and authors) NUCLEAR DISTRICT HEATING PLANT PRELIMINARY DESIGN CONCEPT by Kurt Hansen ft-7-78 16 0 tabtes + 2 fflvstrMnas Abstract A nuclear reactor for district heating is proposed

113

EA-0531: Proposed Natural Gas Protection Program for Naval Oil...  

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

1: Proposed Natural Gas Protection Program for Naval Oil Shale Reserves Nos. 1 and 3, Garfield County, Colorado EA-0531: Proposed Natural Gas Protection Program for Naval Oil Shale...

114

The Naval Petroleum and Oil Shale Reserves | Department of Energy  

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

The Naval Petroleum and Oil Shale Reserves The Naval Petroleum and Oil Shale Reserves To ensure sufficient fuel for the fleet, the Government began withdrawing probable oil-bearing...

115

REACTOR  

DOE Patents (OSTI)

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

Roman, W.G.

1961-06-27T23:59:59.000Z

116

Fuel Summary Report: Shippingport Light Water Breeder Reactor  

SciTech Connect

The Shippingport Light Water Breeder Reactor (LWBR) was a small water cooled, U-233/Th-232 cycle breeder reactor developed by the Pittsburgh Naval Reactors to improve utilization of the nation's nuclear fuel resources in light water reactors. The LWBR was operated at Shippingport Atomic Power Station (APS), which was a Department of Energy (DOE) (formerly Atomic Energy Commission)-owned reactor plant. Shippingport APS was the first large-scale, central-station nuclear power plant in the United States and the first plant of such size in the world operated solely to produce electric power. The Shippingport LWBR was operated successfully from 1977 to 1982 at the APS. During the five years of operation, the LWBR generated more than 29,000 effective full power hours (EFPH) of energy. After final shutdown, the 39 core modules of the LWBR were shipped to the Expended Core Facility (ECF) at Naval Reactors Facility at the Idaho National Engineering and Environmental Laboratory (INEEL). At ECF, 12 of the 39 modules were dismantled and about 1000 of more than 17,000 rods were removed from the modules of proof-of-breeding and fuel performance testing. Some of the removed rods were kept at ECF, some were sent to Argonne National Laboratory-West (ANL-W) in Idaho and some to ANL-East in Chicago for a variety of physical, chemical and radiological examinations. All rods and rod sections remaining after the experiments were shipped back to ECF, where modules and loose rods were repackaged in liners for dry storage. In a series of shipments, the liners were transported from ECF to Idaho Nuclear Technology Engineering Center (INTEC), formerly the Idaho Chemical Processing Plant (ICPP). The 47 liners containing the fully-rodded and partially-derodded core modules, the loose rods, and the rod scraps, are now stored in underground dry wells at CPP-749.

Illum, D.B.; Olson, G.L.; McCardell, R.K.

1999-01-01T23:59:59.000Z

117

Title 10, Chapter 641 Pertaining to Naval Petroleum Reserves in U.S.C. |  

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

Title 10, Chapter 641 Pertaining to Naval Petroleum Reserves in Title 10, Chapter 641 Pertaining to Naval Petroleum Reserves in U.S.C. Title 10, Chapter 641 Pertaining to Naval Petroleum Reserves in U.S.C. CITE: 10USC7420 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7421 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7422 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7423 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7424 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7425 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7427 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7428 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7429 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7430 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7431 CHAPTER 641--NAVAL PETROLEUM RESERVES CITE: 10USC7432 CHAPTER 641--NAVAL PETROLEUM RESERVES

118

Yangtze Patrol: American Naval Forces in China  

E-Print Network (OSTI)

Yangtze Patrol: American Naval Forces in China A Selected, Partially-Annotated Bibliography literature of the United States Navy in China. mvh #12;"Like Chimneys in Summer" The thousands of men who served on the China Station before World War II have been all but forgotten, except in the mythology

119

Reactor pressure vessel integrity research at the Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

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

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

1995-12-31T23:59:59.000Z

120

Implementation plan for operating alternatives for the Naval Computer and Telecommunications Station cogeneration facility at Naval Air Station North Island, San Diego, California  

SciTech Connect

The goal of the US Department of Energy (DOE) Federal Energy Management Program (FEMP) is to facilitate energy efficiency improvements at federal facilities. This is accomplished by a balanced program of technology development, facility assessment, and use of cost-sharing procurement mechanisms. Technology development focuses upon the tools, software, and procedures used to identify and evaluate energy efficiency technologies and improvements. For facility assessment, FEMP provides metering equipment and trained analysts to federal agencies exhibiting a commitment to improve energy use efficiency. To assist in procurement of energy efficiency measures, FEMP helps federal agencies devise and implement performance contracting and utility demand-side management strategies. Pacific Northwest Laboratory (PNL) supports the FEMP mission of energy systems modernization. Under this charter, the Laboratory and its contractors work with federal facility energy managers to assess and implement energy efficiency improvements at federal facilities nationwide. The SouthWestern Division of the Naval Facilities Engineering Command, in cooperation with FEMP, has tasked PNL with developing a plan for implementing recommended modifications to the Naval Computer and Telecommunications Station (NCTS) cogeneration plant at the Naval Air Station North Island (NASNI) in San Diego. That plan is detailed in this report.

Carroll, D.M.; Parker, S.A.; Stucky, D.J.

1994-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Laboratory Measurement of Water Nucleation Using a Laminar Flow Tube Reactor  

SciTech Connect

A Laminar Flow Tube Reactor (LFTR) was used to study the nucleation of water vapor. Computational analysis was carried out to define the operating conditions of the LFTR suitable for water nucleation measurements. An interface between the LFTR and a mass spectrometer was developed to analyze the chemical content of the freshly nucleated water particles. Presence of contaminants was detected in the initial configuration of the LFTR. As a result, improvements were made to the LFTR to achieve ultra-high purity conditions in the system. The nucleation rate of water vapor as a function of supersaturation was measured over the temperature range 210-250 K. The first measurement of the nucleation rate of water at a temperature of 210 K was obtained. Reasonable agreement with the classical theory predictions is observed for temperatures in the range 230-250 K. However, below 220 K, classical theory begins to overestimate nucleation rates compared to experimental data and the disagreement grows with decreasing temperature. The experimental data obtained provide an excellent benchmark for further nucleation studies of binary, ternary and more complex systems.

Mikheev, Vladimir B. (InnovaTek, Inc); Irving, Patricia M. (InnovaTek); Laulainen, Nels S. (BATTELLE (PACIFIC NW LAB)); Barlow, Stephan E. (BATTELLE (PACIFIC NW LAB)); Pervukhin, Viktor V. (Institute of Inorganic Chemistry of SB RAS, Novosibirsk, Russia)

2002-06-22T23:59:59.000Z

122

Fuel Cell Power Plant Experience Naval Applications  

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

clean clean Fuel Cell Power Plant Experience Naval Applications US Department of Energy/ Office of Naval Research Shipboard Fuel Cell Workshop Washington, DC March 29, 2011 FuelCell Energy, the FuelCell Energy logo, Direct FuelCell and "DFC" are all registered trademarks (®) of FuelCell Energy, Inc. *FuelCell Energy, Inc. *Renewable and Liquid Fuels Experience *HTPEM Fuel Cell Stack for Shipboard APU *Solid Oxide Experience and Applications DOE-ONR Workshop FuelCell Energy, the FuelCell Energy logo, Direct FuelCell and "DFC" are all registered trademarks (®) of FuelCell Energy, Inc. FuelCell Energy, Inc. * Premier developer of fuel cell technology - founded in 1969 * Over 50 power installations in North America, Europe, and Asia * Industrial, commercial, utility

123

Impact of Magnetic Diversion on Laser IFE Reactor Design and Performance  

E-Print Network (OSTI)

; 3Consultant to Naval Research Laboratory, Washington, DC, USA; 4ATK Mission Research, Albuquerque, NM, USA; 5Naval Research Laboratory, Washington, DC, USA; 6Oak Ridge National Laboratory, PO Box 2008 windows for the HAPL laser IFE study," to appear in the Journal of Nucl. Mat. (2005). [3] A. E. Robson

Raffray, A. René

124

MEASUREMENT OF THE NEUTRON SPECTRUM OF THE HB-4 COLD SOURCE AT THE HIGH FLUX ISOTOPE REACTOR AT OAK RIDGE NATIONAL LABORATORY  

DOE Green Energy (OSTI)

Measurements of the cold neutron spectrum from the super critical hydrogen cold source at the High Flux Isotope Reactor at Oak Ridge National Laboratory were made using time-of-flight spectroscopy. Data were collected at reactor power levels of 8.5MW, 42.5MW and 85MW. The moderator temperature was also varied. Data were collected at 17K and 25K while the reactor power was at 8.5MW, 17K and 25K while at 42.5MW and 18K and 22K while at 85MW. The purpose of these measurements was to characterize the brightness of the cold source and to better understand the relationship between reactor power, moderator temperature, and cold neutron production. The authors will discuss the details of the measurement, the changes observed in the neutron spectrum, and the process for determining the source brightness from the measured neutron intensity.

Robertson, Lee [ORNL; Iverson, Erik B [ORNL

2009-01-01T23:59:59.000Z

125

The Naval Research Laboratory's Air-Sea Interaction Blimp Experiment  

Science Conference Proceedings (OSTI)

The rationale is given for a unique experiment in which microwave scatterometer and surface flux measurements are to be made from a blimp to develop an improved scatterometer model function. A principal goal of the effort is to obtain a more ...

Theodore V. Blanc; William J. Plant; William C. Keller

1989-04-01T23:59:59.000Z

126

The Naval Research Laboratory: 75 Years of Materials Innovation  

Science Conference Proceedings (OSTI)

... to which have been added recent explorations within the fields of virtual reality, ... It also contributed to U.S. seapower by improving the production of the ...

127

Engineering Evaluation of Proposed Alternative Salt Transfer Method for the Molten Salt Reactor Experiement for the Oak Ridge National Laboratory  

SciTech Connect

This evaluation was performed by Pro2Serve in accordance with the Technical Specification for an Engineering Evaluation of the Proposed Alternative Salt Transfer Method for the Molten Salt Reactor Experiment at the Oak Ridge National Laboratory (BJC 2009b). The evaluators reviewed the Engineering Evaluation Work Plan for Molten Salt Reactor Experiment Residual Salt Removal, Oak Ridge National Laboratory, Oak Ridge, Tennessee (DOE 2008). The Work Plan (DOE 2008) involves installing a salt transfer probe and new drain line into the Fuel Drain Tanks and Fuel Flush Tank and connecting them to the new salt transfer line at the drain tank cell shield. The probe is to be inserted through the tank ball valve and the molten salt to the bottom of the tank. The tank would then be pressurized through the Reactive Gas Removal System to force the salt into the salt canisters. The Evaluation Team reviewed the work plan, interviewed site personnel, reviewed numerous documents on the Molten Salt Reactor (Sects. 7 and 8), and inspected the probes planned to be used for the transfer. Based on several concerns identified during this review, the team recommends not proceeding with the salt transfer via the proposed alternate salt transfer method. The major concerns identified during this evaluation are: (1) Structural integrity of the tanks - The main concern is with the corrosion that occurred during the fluorination phase of the uranium removal process. This may also apply to the salt transfer line for the Fuel Flush Tank. Corrosion Associated with Fluorination in the Oak Ridge National Laboratory Fluoride Volatility Process (Litman 1961) shows that this problem is significant. (2) Continued generation of Fluorine - Although the generation of Fluorine will be at a lower rate than experienced before the uranium removal, it will continue to be generated. This needs to be taken into consideration regardless of what actions are taken with the salt. (3) More than one phase of material - There are likely multiple phases of material in the salt (metal or compound), either suspended through the salt matrix, layered in the bottom of the tank, or both. These phases may contribute to plugging during any planned transfer. There is not enough data to know for sure. (4) Probe heat trace - The alternate transfer method does not include heat tracing of the bottom of the probe. There is a concern that this may cool the salt and other phases of materials present enough to block the flow of salt. (5) Stress-corrosion cracking - Additionally, there is a concern regarding moisture that may have been introduced into the tanks. Due to time constraints, this concern was not validated. However, if moisture was introduced into the tanks and not removed during heating the tanks before HF and F2 sparging, there would be an additional concern regarding the potential for stress-corrosion cracking of the tank walls.

Carlberg, Jon A.; Roberts, Kenneth T.; Kollie, Thomas G.; Little, Leslie E.; Brady, Sherman D.

2009-09-30T23:59:59.000Z

128

Pacific Northwest Laboratory report on controlled thermonuclear reactor technology, January 1975 - September 1975  

SciTech Connect

The PNL staff has been studying fusion technology in areas such as economics, fusion-fission hybrid concepts, materials, neutronics, environment and safety. These studies have been scoped to make efficient use of ERDA resources, and to complement and support efforts at other laboratories. The effect the plasma and associated radiation and emission will have upon the surfaces of the first wall are being studied. Neutron sputtering experiments were made on niobium and gold and the results were evaluated for absolute neutron yields. Molybdenum and vanadium were studied for effects of ion bombardment under various conditions of helium injection. Graphite cloth is being irradiated for examination of radiation effects because it is suggested for use in several CTR concepts as a shield between the plasma and the first wall. Helium effects are being studied to characterize degradation of structural metal properties. Work is progressing on absolute measurement of the electrical resistivity of insulators and the demonstration of the feasibility of producing insulating coatings by sputter deposition. (auth)

1975-10-01T23:59:59.000Z

129

Principles of Reactor Physics  

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

Nuclear Reactor Physics M A Smith Argonne National Laboratory Nuclear Engineering Division Phone: 630-252-9747, Email: masmith@anl.gov Abstract: Nuclear reactor physics deals with...

130

Naval Station Newport Wind Resource Assessment. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites, and The Naval Facilities Engineering Service Center  

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

Naval Station Newport Naval Station Newport Wind Resource Assessment A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites, and The Naval Facilities Engineering Service Center Robi Robichaud, Jason Fields, and Joseph Owen Roberts Technical Report NREL/TP-6A20-52801 February 2012 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No. DE-AC36-08GO28308 Naval Station Newport

131

Analysis of operating alternatives for the Naval Computer and Telecommunications Station Cogeneration Facility at Naval Air Station North Island, San Diego, California  

SciTech Connect

The Naval Facilities Engineering Command Southwestern Division commissioned Pacific Northwest Laboratory (PNL), in support of the US Department of Energy (DOE) Federal Energy Management Program (FEMP), to determine the most cost-effective approach to the operation of the cogeneration facility in the Naval Computer and Telecommunications Station (NCTS) at the Naval Air Station North Island (NASNI). Nineteen alternative scenarios were analyzed by PNL on a life-cycle cost basis to determine whether to continue operating the cogeneration facility or convert the plant to emergency-generator status. This report provides the results of the analysis performed by PNL for the 19 alternative scenarios. A narrative description of each scenario is provided, including information on the prime mover, electrical generating efficiency, thermal recovery efficiency, operational labor, and backup energy strategy. Descriptions of the energy and energy cost analysis, operations and maintenance (O&M) costs, emissions and related costs, and implementation costs are also provided for each alternative. A summary table presents the operational cost of each scenario and presents the result of the life-cycle cost analysis.

Parker, S.A.; Carroll, D.M.; McMordie, K.L.; Brown, D.R.; Daellenbach, K.K.; Shankle, S.A.; Stucky, D.J.

1993-12-01T23:59:59.000Z

132

Distributed energy resources at naval base ventura county building 1512  

E-Print Network (OSTI)

up by a DER system. Distributed Energy Resources at NavalFebruary 2003. “Distributed Energy Resources in Practice: ARyan. January 2004. “Distributed Energy Resources Customer

Bailey, Owen C.; Marnay, Chris

2004-01-01T23:59:59.000Z

133

DOE - Office of Legacy Management -- Naval Oil Shale Reserves...  

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

Oil Shale Reserves Site - 013 FUSRAP Considered Sites Site: Naval Oil Shale Reserves Site (013 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site...

134

13.400 Introduction to Naval Architecture, Fall 2004  

E-Print Network (OSTI)

Introduction to principles of naval architecture, ship geometry, hydrostatics, calculation and drawing of curves of form, intact and damaged stability, hull structure strength calculations and ship resistance. Projects ...

Herbein, David

135

2012 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2011 through October 31, 2012. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance issues Discussion of the facility’s environmental impacts During the 2012 permit year, approximately 183 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

Mike Lewis

2013-02-01T23:59:59.000Z

136

2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance and other issues Discussion of the facility's environmental impacts During the 2011 permit year, approximately 166 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

Mike Lewis

2012-02-01T23:59:59.000Z

137

Naval Reserve Force : cost and benefit analysis of reducing the number of Naval Surface Reserve Force operating budget holders ; .  

E-Print Network (OSTI)

??The Quadrennial Defense Review 1997 recommended reductions of civilian and military personnel associated with infrastructure. The Naval Reserve Force is aggressively pursuing options to reduce… (more)

Young, Eric Coy

1997-01-01T23:59:59.000Z

138

Geothermal energy at Long Beach Naval Shipyard and Naval Station and at Seal Beach Naval Weapons Station, California. Final Report 1  

DOE Green Energy (OSTI)

The purpose of this project was to determine and evaluate sources of geothermal energy at two military bases in southern California, the Long Beach Naval Shipyard and Naval Station and the Seal Beach Naval Weapons Station. One part of the project focused on the natural geothermal characteristics beneath the naval bases. Another part focused on the geothermal energy produced by oilfield operations on and adjacent to each base. Results of the study are presented here for the US Department of the Navy to use in its program to reduce its reliance on petroleum by the development of different sources of energy. The project required research of various reports and data, both published and unpublished, particularly those of the California Department of Conservation, Division of Oil and Gas and of oil companies with leases on or adjacent to the naval bases. Important field investigations included the measurement of well-head temperatures of fluids produced from selected oil wells at each naval base and a detailed gravity survey of the Seal Beach naval base and vicinity. The well-head temperatures were needed to evaluate individual wells as sources of geothermal energy, while the gravity survey attempted to discover subsurface geologic structures that might contain geothermal fluids of temperatures higher than those predicted by the regional geothermal conditions.

Higgins, C.T.; Chapman, R.H.

1984-01-01T23:59:59.000Z

139

Success Story: Naval Medical Center San Diego Co-Generation Project...  

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

Success Story: Naval Medical Center San Diego Co-Generation Project Success Story: Naval Medical Center San Diego Co-Generation Project Presentation covers the FUPWG Fall Meeting,...

140

A Tabu Search Heuristic for Resource Management in Naval Warfare  

Science Conference Proceedings (OSTI)

Effective utilization of scarce resources, in particular weapon resources, is a prominent issue in naval anti-air warfare. In this paper, defence plans are constructed to guide the allocation and scheduling of different types of defence weapons against ... Keywords: defence plan, naval warfare, resource management, tabu search, weapon

Dale E. Blodgett; Michel Gendreau; François Guertin; Jean-Yves Potvin; René Séguin

2003-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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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141

Naval Spent Fuel Rail Shipment Accident Exercise Objectives  

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

NAVAL SPENT FUEL RAIL SHIPMENT NAVAL SPENT FUEL RAIL SHIPMENT ACCIDENT EXERCISE OBJECTIVES * Familiarize stakeholders with the Naval spent fuel ACCIDENT EXERCISE OBJECTIVES Familiarize stakeholders with the Naval spent fuel shipping container characteristics and shipping practices * Gain understanding of how the NNPP escorts who accompany the spent fuel shipments will interact with civilian emergency services representatives g y p * Allow civilian emergency services agencies the opportunity to evaluate their response to a pp y p simulated accident * Gain understanding of how the communications links that would be activated in an accident involving a Naval spent fuel shipment would work 1 NTSF May 11 ACCIDENT EXERCISE TYPICAL TIMELINE * Conceptual/Organizational Meeting - April 6 E R T i d it t t d TYPICAL TIMELINE

142

Integrated Surface Geophysical Methods for Characterization of the Naval  

Open Energy Info (EERE)

Integrated Surface Geophysical Methods for Characterization of the Naval Integrated Surface Geophysical Methods for Characterization of the Naval Air Warfare Center, New Jersey Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Integrated Surface Geophysical Methods for Characterization of the Naval Air Warfare Center, New Jersey Author USGS Published Publisher Not Provided, 2013 DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for Integrated Surface Geophysical Methods for Characterization of the Naval Air Warfare Center, New Jersey Citation USGS. Integrated Surface Geophysical Methods for Characterization of the Naval Air Warfare Center, New Jersey [Internet]. 2013. [updated 2013/01/03;cited 2013/11/22]. Available from: http://water.usgs.gov/ogw/bgas/toxics/NAWC-surface.html

143

Preliminary Feasibility, Design, and Hazard Analysis of a Boiling Water Test Loop Within the Idaho National Laboratory Advanced Test Reactor National Scientific User Facility  

Science Conference Proceedings (OSTI)

The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The ATR and its support facilities are located at the Idaho National Laboratory (INL). A Boiling Water Test Loop (BWTL) is being designed for one of the irradiation test positions within the. The objective of the new loop will be to simulate boiling water reactor (BWR) conditions to support clad corrosion and related reactor material testing. Further it will accommodate power ramping tests of candidate high burn-up fuels and fuel pins/rods for the commercial BWR utilities. The BWTL will be much like the pressurized water loops already in service in 5 of the 9 “flux traps” (region of enhanced neutron flux) in the ATR. The loop coolant will be isolated from the primary coolant system so that the loop’s temperature, pressure, flow rate, and water chemistry can be independently controlled. This paper presents the proposed general design of the in-core and auxiliary BWTL systems; the preliminary results of the neutronics and thermal hydraulics analyses; and the preliminary hazard analysis for safe normal and transient BWTL and ATR operation.

Douglas M. Gerstner

2009-05-01T23:59:59.000Z

144

Groundwater Protection Group, Brookhaven National Laboratory...  

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

Reactor Long Term Surveillance & Maintenance High Flux Beam Reactor Long Term Surveillance & Maintenance The High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory (BNL)...

145

INFORMATION MEETING ON GAS-COOLED POWER REACTORS, OAK RIDGE NATIONAL LABORATORY, OCTOBER 21-22, 1958  

SciTech Connect

This meeting is one of a series of Civilian Power Reactor Conferences and was held colncident with an AEC invitation to industry to bid on the construction of a gas-cooled facility. Papers are presented on design studles, hazards, components, costs, materials, and design concepts for specific reactors. (W.D.M.)

1959-10-31T23:59:59.000Z

146

CRAD, Configuration Management - Oak Ridge National Laboratory...  

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

Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor February...

147

SUMMARY AND RESULTS LETTER REPORT – INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PROJECT, PHASE 3: TRENCHES 2, 3, AND 4 BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK  

SciTech Connect

5098-LR-02-0 SUMMARY AND RESULTS LETTER REPORT – INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PROJECT, PHASE 3 TRENCHES 2, 3, AND 4 BROOKHAVEN NATIONAL LABORATORY

E.M. Harpenau

2010-11-15T23:59:59.000Z

148

Decontamination and decommissioning of the Argonne Thermal Source Reactor at Argonne National Laboratory - East project final report.  

SciTech Connect

The ATSR D&D Project was directed toward the following goals: (1) Removal of radioactive and hazardous materials associated with the ATSR Reactor facility; (2) Decontamination of the ATSR Reactor facility to unrestricted use levels; and (3)Documentation of all project activities affecting quality (i.e., waste packaging, instrument calibration, audit results, and personnel exposure). These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the ATSR Reactor facility and to allow, upon completion of the project, unescorted and unmonitored access to the area. The reactor aluminum, reactor lead, graphite piles in room E-111, and the contaminated concrete in room E-102 were the primary areas of concern. NES, Incorporated (Danbury, CT) characterized the ATSR Reactor facility from January to March 1998. The characterization identified a total of thirteen radionuclides, with a total activity of 64.84 mCi (2.4 GBq). The primary radionuclides of concern were Co{sup 60}, Eu{sup 152}, Cs{sup 137}, and U{sup 238}. No additional radionuclides were identified during the D&D of the facility. The highest dose rates observed during the project were associated with the reactor tank and shield tank. Contact radiation levels of 30 mrem/hr (0.3 mSv/hr) were measured on reactor internals during dismantlement of the reactor. A level of 3 mrem/hr (0.03 mSv/hr) was observed in a small area (hot spot) in room E-102. DOE Order 5480.2A establishes the maximum whole body exposure for occupational workers at 5 rem/yr (50 mSv/yr); the administrative limit at ANL-E is 1 rem/yr (10 mSv/yr).

Fellhauer, C.; Garlock, G.; Mathiesen, J.

1998-12-02T23:59:59.000Z

149

Renewable Energy Optimization Report for Naval Station Newport  

DOE Green Energy (OSTI)

In 2008, the U.S. Environmental Protection Agency (EPA) launched the RE-Powering America's Land initiative to encourage the development of renewable energy (RE) on potentially contaminated land and mine sites. As part of this effort, EPA is collaborating with the U.S. Department of Energy's (DOE's) National Renewable Energy Laboratory (NREL) to evaluate RE options at Naval Station (NAVSTA) Newport in Newport, Rhode Island. NREL's Renewable Energy Optimization (REO) tool was utilized to identify RE technologies that present the best opportunity for life-cycle cost-effective implementation while also serving to reduce energy-related carbon dioxide emissions and increase the percentage of RE used at NAVSTA Newport. The technologies included in REO are daylighting, wind, solar ventilation preheating (SVP), solar water heating, photovoltaics (PV), solar thermal (heating and electric), and biomass (gasification and cogeneration). The optimal mix of RE technologies depends on several factors including RE resources; technology cost and performance; state, utility, and federal incentives; and economic parameters (discount and inflation rates). Each of these factors was considered in this analysis. Technologies not included in REO that were investigated separately per NAVSTA Newport request include biofuels from algae, tidal power, and ground source heat pumps (GSHP).

Robichaud, R.; Mosey, G.; Olis, D.

2012-02-01T23:59:59.000Z

150

Naval Undersea Warfare Center Division Newport utilities metering, Phase 1  

SciTech Connect

Pacific Northwest Laboratory developed this report for the US Navy`s Naval Undersea Warfare Center Division Newport, Rhode Island (NUWC). The purpose of the report was to review options for metering electricity and steam used in the NUWC compound, and to make recommendations to NUWC for implementation under a follow-on project. An additional NUWC concern is a proposed rate change by the servicing utility, Newport Electric, which would make a significant shift from consumption to demand billing, and what effect that rate change would have on the NUWC utility budget. Automated, remote reading meters are available which would allow NUWC to monitor its actual utility consumption and demand for both the entire NUWC compound and by end-use in individual buildings. Technology is available to perform the meter reads and manipulate the data using a personal computer with minimal staff requirement. This is not meant to mislead the reader into assuming that there is no requirement for routine preventive maintenance. All equipment requires routine maintenance to maintain its accuracy. While PNL reviewed the data collected during the site visit, however, it became obvious that significant opportunities exist for reducing the utility costs other than accounting for actual consumption and demand. Unit costs for both steam and electricity are unnecessarily high, and options are presented in this report for reducing them. Additionally, NUWC has an opportunity to undertake a comprehensive energy resource management program to significantly reduce its energy demand, consumption, and costs.

Carroll, D.M.

1992-11-01T23:59:59.000Z

151

Naval Undersea Warfare Center Division Newport utilities metering, Phase 1  

SciTech Connect

Pacific Northwest Laboratory developed this report for the US Navy's Naval Undersea Warfare Center Division Newport, Rhode Island (NUWC). The purpose of the report was to review options for metering electricity and steam used in the NUWC compound, and to make recommendations to NUWC for implementation under a follow-on project. An additional NUWC concern is a proposed rate change by the servicing utility, Newport Electric, which would make a significant shift from consumption to demand billing, and what effect that rate change would have on the NUWC utility budget. Automated, remote reading meters are available which would allow NUWC to monitor its actual utility consumption and demand for both the entire NUWC compound and by end-use in individual buildings. Technology is available to perform the meter reads and manipulate the data using a personal computer with minimal staff requirement. This is not meant to mislead the reader into assuming that there is no requirement for routine preventive maintenance. All equipment requires routine maintenance to maintain its accuracy. While PNL reviewed the data collected during the site visit, however, it became obvious that significant opportunities exist for reducing the utility costs other than accounting for actual consumption and demand. Unit costs for both steam and electricity are unnecessarily high, and options are presented in this report for reducing them. Additionally, NUWC has an opportunity to undertake a comprehensive energy resource management program to significantly reduce its energy demand, consumption, and costs.

Carroll, D.M.

1992-11-01T23:59:59.000Z

152

Closed-loop biomass co-firing in a laboratory reactor and in a full-scale boiler.  

DOE Green Energy (OSTI)

Co-firing tests were conducted in a pilot-scale reactor at Sandia National Laboratories and in a boiler at the Hawaiian Commercial & Sugar factory at Puunene, Hawaii. Combustion tests were performed in the Sandia Multi-Fuel Combustor using Australian coal, whole fiber cane including tops and leaves processed at three different levels (milled only, milled and leached, and milled followed by leaching and subsequent milling), and fiber cane stripped of its tops and leaves and heavily processed through subsequent milling, leaching, and milling cycles. Testing was performed for pure fuels and for biomass co-firing with the coal at levels of 30% and 70% by mass. The laboratory tests revealed the following information: (1) The biomass fuels convert their native nitrogen into NO more efficiently than coal because of higher volatile content and more reactive nitrogen complexes. (2) Adding coal to whole fiber cane to reduce its tendency to form deposits should not adversely affect NO emissions. ( 3 ) Stripped cane does not offer a NO advantage over whole cane when co-fired with coal. During the field test, Sandia measured 0 2 , C02, CO, SO2, and NO concentrations in the stack and gas velocities near the superheater. Gas concentrations and velocities fluctuated more during biomass co-firing than during coal combustion. The mean 0 2 concentration was lower and the mean C02 concentration was higher during biomass co-firing than during coal combustion. When normalized to a constant exhaust 0 2 concentration, mean CO concentration was higher and mean NO concentration was lower for biomass co-firing than for coal. The SO2 concentration tracked the use of Bunker C fuel oil. When normalized by the amount of boiler energy input, the amounts of NO and SO2 formed were lower during biomass co-firing than during coal combustion. The difference between NOx trends in the lab and in the field are most likely a result of less effective heat and mass transfer in the boiler. Particles were sampled near the superheater tube using an impaction probe and were analyzed using scanning electron microscopy. Particle loading appeared higher for biomass co-firing than for coal combustion, especially for the smaller particle diameters. Laser-induced breakdown spectroscopy (LIBS) was used to detect silicon, aluminum, titanium, iron, calcium, magnesium, sodium, and potassium concentrations near the superheater. LIBS provided an abundant amount of real-time information. The major constituents of the fuel ash (silicon and aluminum) were also the major measured inorganic constituents of the combustion products. The combustion products were enriched in sodium relative to the fuel ash during all tests, and they were enriched in potassium for the biomass co-firing tests. Alkali metals are enriched because compounds containing these elements are more readily releasable into the combustion products than refractory components that remain in large particles such as silicon, aluminum, and titanium. Relative to the measured deposit chemistry, the combustion flows were enriched in iron, sodium, and potassium, constituents that are known to form fumes laden with fine particles and/or vapors. The LIBS results yield insight into the deposition mechanism: Impaction of larger particles dominates over fume deposition. The present application of LIBS reveals its potential to provide real-time field information on the deposition propensity of different fuels and the effects of different fuels and boiler operating conditions.

Jenkins, Bryan M. (University of California, Davis, CA); Williams, Robert B. (University of California, Davis, CA); Turn, Scott Q. (Hawaii Natural Energy Institute.); Jakeway, Lee A. (Hawaiian Commercial & Sugar Company); Blevins, Linda Gail

2004-05-01T23:59:59.000Z

153

INDEPENDENT CONFIRMATORY SURVEY REPORT FOR THE REACTOR BUILDING, HOT LABORATORY, PRIMARY PUMP HOUSE, AND LAND AREAS AT THE PLUM BROOK REACTOR FACILITY, SANDUSKY, OHIO  

Science Conference Proceedings (OSTI)

In 1941, the War Department acquired approximately 9,000 acres of land near Sandusky, Ohio and constructed a munitions plant. The Plum Brook Ordnance Works Plant produced munitions, such as TNT, until the end of World War II. Following the war, the land remained idle until the National Advisory Committee for Aeronautics later called the National Aeronautics and Space Administration (NASA) obtained 500 acres to construct a nuclear research reactor designed to study the effects of radiation on materials used in space flight. The research reactor was put into operation in 1961 and was the first of fifteen test facilities eventually built by NASA at the Plum Brook Station. By 1963, NASA had acquired the remaining land at Plum Brook for these additional test facilities

Erika N. Bailey

2011-10-10T23:59:59.000Z

154

Naval Petroleum Reserve No. 3 Disposition Decision Analysis and Timeline  

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

This Report to Congress provides a summary of the analysis supporting DOE's determination to dispose of the Naval Petroleum Reserve No. 3 through sale of all right, title, interest on the open market.

155

Distributed energy resources at naval base ventura county building 1512  

E-Print Network (OSTI)

the affects of energy prices and tariff structures on energythe default SCE tariff, total energy bills for Building 1512$0.1097. This tariff Distributed Energy Resources at Naval

Bailey, Owen C.; Marnay, Chris

2004-01-01T23:59:59.000Z

156

Distributed energy resources at naval base ventura county building 1512  

E-Print Network (OSTI)

the prices of electricity and gas, that might make PV costprices increase by 10% Distributed Energy Resources at Naval Base Ventura Country Building 1512 over current Public Works levels, then PV

Bailey, Owen C.; Marnay, Chris

2004-01-01T23:59:59.000Z

157

Identification and evaluation of alternatives for the disposition of fluoride fuel and flush salts from the molten salt reactor experiment at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

This document presents an initial identification and evaluation of the alternatives for disposition of the fluoride fuel and flush salts stored in the drain tanks at the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory (ORNL). It will serve as a resource for the U.S. Department of Energy contractor preparing the feasibility study for this activity under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA). This document will also facilitate further discussion on the range of credible alternatives, and the relative merits of alternatives, throughout the time that a final alternative is selected under the CERCLA process.

NONE

1996-08-15T23:59:59.000Z

158

Idaho National Laboratory (INL) Site Greenhouse Gas (GHG) Monitoring Plan - 40 CFR 98  

SciTech Connect

The purpose of this Greenhouse Gas (GHG) Monitoring Plan is to meet the monitoring plan requirements of Title 40 of the Code of Federal Regulations Part 98.3(g)(5). This GHG Monitoring Plan identifies procedures and methodologies used at the Idaho National Laboratory Site (INL Site) to collect data used for GHG emissions calculations and reporting requirements from stationary combustion and other regulated sources in accordance with 40 CFR 98, Subparts A and other applicable subparts. INL Site Contractors determined subpart applicability through the use of a checklist (Appendix A). Each facility/contractor reviews operations to determine which subparts are applicable and the results are compiled to determine which subparts are applicable to the INL Site. This plan is applicable to the 40 CFR 98-regulated activities managed by the INL Site contractors: Idaho National Laboratory (INL), Idaho Cleanup Project (ICP), Advanced Mixed Waste Treatment Project (AMWTP), and Naval Reactors Facilities (NRF).

Deborah L. Layton; Kimberly Frerichs

2010-07-01T23:59:59.000Z

159

Idaho National Laboratory (INL) Site Greenhouse Gas (GHG) Monitoring Plan - 40 CFR 98  

SciTech Connect

The purpose of this Greenhouse Gas (GHG) Monitoring Plan is to meet the monitoring plan requirements of Title 40 of the Code of Federal Regulations Part 98.3(g)(5). This GHG Monitoring Plan identifies procedures and methodologies used at the Idaho National Laboratory Site (INL Site) to collect data used for GHG emissions calculations and reporting requirements from stationary combustion and other regulated sources in accordance with 40 CFR 98, Subparts A and other applicable subparts. INL Site Contractors determined subpart applicability through the use of a checklist (Appendix A). Each facility/contractor reviews operations to determine which subparts are applicable and the results are compiled to determine which subparts are applicable to the INL Site. This plan is applicable to the 40 CFR 98-regulated activities managed by the INL Site contractors: Idaho National Laboratory (INL), Idaho Cleanup Project (ICP), Advanced Mixed Waste Treatment Project (AMWTP), and Naval Reactors Facilities (NRF).

Deborah L. Layton; Kimberly Frerichs

2011-12-01T23:59:59.000Z

160

Naval Spent Nuclear Fuel disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Naval Spent Nuclear Fuel Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers/waste packages are loaded and sealed in the surface waste handling facilities, transferred underground through the access drifts using a rail mounted transporter, and emplaced in emplacement drifts. The Naval Spent Nuclear Fuel Disposal Container System provides long term confinement of the naval spent nuclear fuel (SNF) placed within the disposal containers, and withstands the loading, transfer, emplacement, and retrieval operations. The Naval Spent Nuclear Fuel Disposal Container System provides containment of waste for a designated period of time and limits radionuclide release thereafter. The waste package maintains the waste in a designated configuration, withstands maximum credible handling and rockfall loads, limits the waste form temperature after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Each naval SNF disposal container will hold a single naval SNF canister. There will be approximately 300 naval SNF canisters, composed of long and short canisters. The disposal container will include outer and inner cylinder walls and lids. An exterior label will provide a means by which to identify a disposal container and its contents. Different materials will be selected for the waste package inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and the natural barrier will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel while the outer cylinder and outer cylinder lids will be made of high-nickel alloy.

N. E. Pettit

2001-07-13T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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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161

Proceedings of the Oak Ridge National Laboratory/Brookhaven National Laboratory workshop on neutron scattering instrumentation at high-flux reactors  

SciTech Connect

For the first three decades following World War II, the US, which pioneered the field of neutron scattering research, enjoyed uncontested leadership in the field. By the mid-1970's, other countries, most notably through the West European consortium at Institut Laue-Langevin (ILL) in Grenoble, France, had begun funding neutron scattering on a scale unmatched in this country. By the early 1980's, observers charged with defining US scientific priorities began to stress the need for upgrading and expansion of US research reactor facilities. The conceptual design of the ANS facility is now well under way, and line-item funding for more advanced design is being sought for FY 1992. This should lead to a construction request in FY 1994 and start-up in FY 1999, assuming an optimal funding profile. While it may be too early to finalize designs for instruments whose construction is nearly a decade removed, it is imperative that we begin to develop the necessary concepts to ensure state-of-the-art instrumentation for the ANS. It is in this context that this Instrumentation Workshop was planned. The workshop touched upon many ideas that must be considered for the ANS, and as anticipated, several of the discussions and findings were relevant to the planning of the HFBR Upgrade. In addition, this report recognizes numerous opportunities for further breakthroughs on neutron instrumentation in areas such as improved detection schemes (including better tailored scintillation materials and image plates, and increased speed in both detection and data handling), in-beam monitors, transmission white beam polarizers, multilayers and supermirrors, and more. Each individual report has been cataloged separately.

McBee, M.R. (ed.); Axe, J.D.; Hayter, J.B.

1990-07-01T23:59:59.000Z

162

DOE - Office of Legacy Management -- Norfolk Naval Station - VA 05  

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

Norfolk Naval Station - VA 05 Norfolk Naval Station - VA 05 FUSRAP Considered Sites Site: NORFOLK NAVAL STATION (VA.05) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Norfolk , Virginia VA.05-1 Evaluation Year: 1993 VA.05-1 Site Operations: Demonstration of extinguishing a uranium fire at the Fire Fighters School for AEC contractors. VA.05-3 VA.05-2 Site Disposition: Eliminated - Potential for contamination considered remote based on the limited quantity of materials handled VA.05-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium VA.05-2 Radiological Survey(s): Yes - Health and Safety Monitoring during operations only VA.05-2 Site Status: Eliminated from consideration under FUSRAP

163

NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG 7 JUNE 2013 Quick Facts..............................................................................................................................................................4  

E-Print Network (OSTI)

NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG ­ 7 JUNE 2013 1 CONTENTS Quick Facts......................................................................................................................................................26 #12;NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG ­ 7 JUNE 2013 2 Curriculum Listing...............................................................................................................................................428 Energy Core Group

164

NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG 3 JAN 2013 Quick Facts..............................................................................................................................................................4  

E-Print Network (OSTI)

NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG ­ 3 JAN 2013 1 CONTENTS Quick Facts......................................................................................................................................................26 #12;NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG ­ 3 JAN 2013 2 Curriculum Listing ................................................................................................427 Energy Core Group

165

NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG 8 MARCH 2013 Quick Facts..............................................................................................................................................................4  

E-Print Network (OSTI)

NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG ­ 8 MARCH 2013 1 CONTENTS Quick Facts......................................................................................................................................................26 #12;NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG ­ 8 MARCH 2013 2 Curriculum Listing ................................................................................................428 Energy Core Group

166

Naval petroleum and oil shale reserves: Annual report of operations, FY 1987  

SciTech Connect

Production and reserves, development and exploration, revenues and expenditures, sales, environment and safety, and litigation are discussed for naval petroleum reserves numbers one through three and for naval oil shale reserves. 28 figs., 21 tabs. (ACT)

Not Available

1987-01-01T23:59:59.000Z

167

NPS-SCAT electrical power system ; Naval Postgraduate School Solar Cell Array Tester .  

E-Print Network (OSTI)

??The Naval Postgraduate School Solar Cell Array Tester (NPS-SCAT) seeks to expand the CubeSat knowledge base and provide learning possibilities at the Naval Postgraduate School.… (more)

Dorn, Lawrence Tyrone.

2009-01-01T23:59:59.000Z

168

Monitoring Uranium Transformations Determined by the Evolution of Biogeochemical Processes: Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory  

SciTech Connect

With funds provided by the US DOE, Argonne National Laboratory subcontracted the design of batch and column studies to a Stanford University team with field experience at the ORNL IFRC, Oak Ridge, TN. The contribution of the Stanford group ended in 2011 due to budget reduction in ANL. Over the funded research period, the Stanford research team characterized ORNL IFRC groundwater and sediments and set up microcosm reactors and columns at ANL to ensure that experiments were relevant to field conditions at Oak Ridge. The results of microcosm testing demonstrated that U(VI) in sediments was reduced to U(IV) with the addition of ethanol. The reduced products were not uraninite but were instead U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. The Stanford team communicated with the ANL team members through email and conference calls and face to face at the annual ERSP PI meeting and national meetings.

Criddle, Craig S.; Wu, Weimin

2013-04-17T23:59:59.000Z

169

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:...

170

CRAD, Emergency Management - Oak Ridge National Laboratory High...  

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

Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A...

171

CRAD, Emergency Management - Oak Ridge National Laboratory High...  

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

Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor...

172

Program management plan for the Molten Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect

The primary mission of the Molten Salt Reactor Experiment (MSRE) Remediation Project is to effectively implement the risk-reduction strategies and technical plans to stabilize and prevent further migration of uranium within the MSRE facility, remove the uranium and fuel salts from the system, and dispose of the fuel and flush salts by storage in appropriate depositories to bring the facility to a surveillance and maintenance condition before decontamination and decommissioning. This Project Management Plan (PMP) for the MSRE Remediation Project details project purpose; technical objectives, milestones, and cost objectives; work plan; work breakdown structure (WBS); schedule; management organization and responsibilities; project management performance measurement planning, and control; conduct of operations; configuration management; environmental, safety, and health compliance; quality assurance; operational readiness reviews; and training.

NONE

1996-09-01T23:59:59.000Z

173

Distributed Energy Resources at Naval Base Ventura County Building 1512  

E-Print Network (OSTI)

LBNL-55340 Distributed Energy Resources at Naval Base Ventura County Building 1512 Prepared, of the U.S. Department of Energy under Contract No. DE-AC03-76SF00098. #12;Distributed Energy Resources and the Distributed Energy Program of DOE also provided prior funding to develop and validate the DER-CAM model

174

Estimating the Economic Benefits of Forward-Engaged Naval Forces  

Science Conference Proceedings (OSTI)

In preparing for the 1997 quadrennial defense review, US Navy leaders asked us if we could quantify the economic benefits of forward-engaged naval forces and communicate them to policy makers. Until this point, the only evidence of such benefits was ... Keywords: INDUSTRIES--PETROLEUM-NATURAL GAS, MILITARY--COST EFFECTIVENESS

Robert E. Looney; David A. Schrady; Ronald L. Brown

2001-07-01T23:59:59.000Z

175

Approved for public release; distribution is unlimited. NAVAL POSTGRADUATE SCHOOL  

E-Print Network (OSTI)

1995 Thesis Advisor: Michael J. Zyda Thesis Co-Advisor: John S. Falby #12;Public reporting burden-18 REPORT DOCUMENTATION PAGE Form Approved OMB No. 0704-0188 1. AGENCY USE ONLY (Leave Blank) 2. REPORT DATEApproved for public release; distribution is unlimited. THESIS NAVAL POSTGRADUATE SCHOOL Monterey

Zyda, Michael

176

Technical Information on the Carbonation of the EBR-II Reactor, Summary Report Part 1: Laboratory Experiments and Application to EBR-II Secondary Sodium System  

DOE Green Energy (OSTI)

Residual sodium is defined as sodium metal that remains behind in pipes, vessels, and tanks after the bulk sodium metal has been melted and drained from such components. The residual sodium has the same chemical properties as bulk sodium, and differs from bulk sodium only in the thickness of the sodium deposit. Typically, sodium is considered residual when the thickness of the deposit is less than 5-6 cm. This residual sodium must be removed or deactivated when a pipe, vessel, system, or entire reactor is permanently taken out of service, in order to make the component or system safer and/or to comply with decommissioning regulations. As an alternative to the established residual sodium deactivation techniques (steam-and-nitrogen, wet vapor nitrogen, etc.), a technique involving the use of moisture and carbon dioxide has been developed. With this technique, sodium metal is converted into sodium bicarbonate by reacting it with humid carbon dioxide. Hydrogen is emitted as a by-product. This technique was first developed in the laboratory by exposing sodium samples to humidified carbon dioxide under controlled conditions, and then demonstrated on a larger scale by treating residual sodium within the Experimental Breeder Reactor II (EBR-II) secondary cooling system, followed by the primary cooling system, respectively. The EBR-II facility is located at the Idaho National Laboratory (INL) in southeastern Idaho, U.S.A. This report is Part 1 of a two-part report. It is divided into three sections. The first section describes the chemistry of carbon dioxide-water-sodium reactions. The second section covers the laboratory experiments that were conducted in order to develop the residual sodium deactivation process. The third section discusses the application of the deactivation process to the treatment of residual sodium within the EBR-II secondary sodium cooling system. Part 2 of the report, under separate cover, describes the application of the technique to residual sodium treatment within the EBR-II primary sodium cooling system and related systems.

Steven R. Sherman

2005-04-01T23:59:59.000Z

177

Study on severe accident fuel dispersion behavior in the Advanced Neutron Source reactor at Oak Ridge National Laboratory  

SciTech Connect

Core flow blockage events are a leading contributor to core damage initiation risk in the Advanced Neutron Source (ANS) reactor. During such an accident, insufficient cooling of the fuel could result in core heatup and melting under full coolant flow condition. Coolant inertia forces acting on the melt surface would likely break up the melt into small particles. Under thermal-hydraulic conditions of ANS coolant channel, micro-fine melt particles are expected. Heat transfer between melt particle and coolant, which affects particle breakup, was studied. The study indicates that the thermal effect on melt fragmentation seems to be negligible because the time corresponding to the breakup due to hydrodynamic forces is much shorter than the time for the melt surface to solidify. The study included modeling and analyses to predict transient behavior and transport of debris particles throughout the coolant system. The transient model accounts for the surface forces acting on the particle that results from the pressure variation on the surface, inertia, virtual mass, viscous force due to relative motion of particle in the coolant, gravitation, and resistance due to inhomogenous coolant velocity radially across piping due to possible turbulent coolant motions. Results indicate that debris particles would reside longest in heat exchangers because of lower coolant velocity there. Also core debris tends to move together upon melting and entrainment.

Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V. [Oak Ridge National Lab., TN (United States); Xiang, J.Y. [Wabash Coll., Crawfordsville, IN (United States)

1995-12-31T23:59:59.000Z

178

Study on severe accident fuel dispersion behavior in the Advanced Neutron Source reactor at Oak Ridge National Laboratory  

SciTech Connect

Core flow blockage events have been identified as a leading contributor to core damage initiation risk in the Advanced Neutron Source (ANS) reactor. During such an accident, insufficient cooling of the fuel in a few adjacent blocked coolant channels out of several hundred channels, could also result in core heatup and melting under full coolant flow condition in other coolant channels. Coolant inertia forces acting on the melt surface would likely break up the melt into small particles. Under thermal-hydraulic conditions of ANS coolant channel, micro-fine melt particles are expected. Heat transfer between melt particle and coolant, which affects the particle breakup characteristics, was studied. The study indicates that the thermal effect on melt fragmentation seems to be negligible because the time corresponding to the breakup due to hydrodynamic forces is much shorter than the time for the melt surface to solidify. The study included modeling and analyses to predict transient behavior and transport of debris particles throughout the coolant system. The transient model accounts for the surface forces acting on the particle that result from the pressure variation on the surface, inertia, virtual mass, viscous force due to the relative motion of the particle in the coolant, gravitation, and resistance due to inhomogeneous coolant velocity radially across piping due to expected turbulent coolant motions. The results indicate that debris particles would reside longest in the heat exchangers because of lower coolant velocity there. Also they are entrained and move together in a cloud.

Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V.

1995-09-01T23:59:59.000Z

179

Environmental Survey preliminary report, Naval Petroleum and Oil Shale Reserves in Colorado, Utah, and Wyoming, Casper, Wyoming  

Science Conference Proceedings (OSTI)

This report presents the preliminary environmental findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Naval Petroleum and Oil Shale Reserves in Colorado, Utah, and Wyoming (NPOSR-CUW) conducted June 6 through 17, 1988. NPOSR consists of the Naval Petroleum Reserve No. 3 (NPR-3) in Wyoming, the Naval Oil Shale Reserves No. 1 and 3 (NOSR-1 and NOSR-3) in Colorado and the Naval Oil Shale Reserve No. 2 (NOSR-2) in Utah. NOSR-2 was not included in the Survey because it had not been actively exploited at the time of the on-site Survey. The Survey is being conducted by an interdisciplinary team of environmental specialists, lead and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team specialists are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with NPOSR. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at NPOSR and interviews with site personnel. The Survey team has developed a Sampling and Analysis Plan to assist in further assessing specific environmental problems identified at NOSR-3 during the on-site Survey. There were no findings associated with either NPR-3 or NOSR-1 that required Survey-related sampling and Analysis. The Sampling and Analysis Plan will be executed by Idaho National Engineering Laboratory. When completed, the results will be incorporated into the Environmental Survey Summary report. The Summary Report will reflect the final determinations of the NPOSR-CUW Survey and the other DOE site-specific Surveys. 110 refs., 38 figs., 24 tabs.

Not Available

1989-02-01T23:59:59.000Z

180

Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, January-March 1980  

DOE Green Energy (OSTI)

The Johns Hopkins University Applied Physics Laboratory, under contracts with several agencies of the federal government and an agency of the State of Maryland, is engaged in developing energy resources, utilization concepts, and monitoring and storage methods. This Quarterly Report summarizes the work on the various tasks as of 31 March 1980. The Energy Quarterly Report is divided into four sections. The first, Geothermal Energy Development Planning and Technical Assistance, supported by the Department of Energy/Division of Geothermal Energy (DOE/DGE), contains reports on the progress of geothermal-related tasks on which effort was concentrated during the quarter. The second section, Operational Research, Hydroelectric Power Development, supported by the Department of Energy/Resource Applications (DOE/DGE), contains reports on small-scale hydroelectric investigations in the southeastern states. The third section, Seismotectonic Investigation, supported by the Reactor Safety Research Division of the Nuclear Regulatory Commission, reports on a neotectonic investigation in Connecticut. The fourth section, Energy Conversion and Storage Techniques, contains two articles, the first on OTEC core unit testing supported by the Department of Energy/Division of Central Solar Technology (DOE/CST), and the second on an analysis of the Community Annual Storage Energy System at the U.S. Naval Air Station, Norfolk, Va. This work is supported by the Department of Energy and the Department of Defense, Naval Facilities Engineering Command/Atlantic Division.

Entingh, Daniel J.

1980-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

In Situ Grouting of Liquid Waste Disposal Trenches and Experimental Reactor Fuel Disposal Wells at Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

In the early to mid-1960's, liquid low-level wastes (LLLW) generated at Oak Ridge National Laboratory were disposed of in specially-constructed, gravel-filled trenches within the Melton Valley watershed at the lab. The initial selected remedy for Trenches 5 and 7 was in situ vitrification; however, an amendment to the record of decision changed the remedy to in situ grouting of the trenches. The work was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout. At the HRE fuel wells, a 1-m ring of soil surrounding the fuel wells was grouted with acrylamide. The results of the hydraulic conductivity tests ranged from 4.74 x 10{sup -6} to 3.60 x 10{sup -7} cm/sec, values that were well below the 1 x 10{sup -5} cm/sec design criterion. In summary: The ISG Project was conducted to decrease hydraulic conductivity and thereby decrease water flow and contaminate migration from the area of the trenches. The initial remedy for Trenches 5 and 7 in the Melton Valley ROD was for in situ vitrification of the trench matrix. The remedy was changed to in situ grouting of the trenches and HRE fuel wells through an amendment to the ROD after moisture was found in the trenches. The grouting of the trenches was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout to further reduce water infiltration. Soil backfill above each of the seven HRE fuel wells was removed to a depth of approximately 1 m by augering, and the soils were replaced with a cement plug to prevent water infiltration from migrating down the original borehole. Soil surrounding the fuel wells was then grouted with acrylamide to ensure water infiltration through the HRE fuel wells is prevented. A summary of the quantities used is shown. After completion of grouting, in-situ hydraulic conductivities of the grouted materials were measured to verify attainment of the design objective. The areas were then covered with multi-layer caps as part of the MV hydrologic isolation project. (authors)

Johnson, Ch.; Cange, J.; Lambert, R. [Bechtel Jacobs Company, LLC, Oak Ridge, TN (United States); Trujillo, E. [BWXT Pantex, LLC, Amarillo, TX (United States); Julius, J. [U.S. DOE, Oak Ridge Operations Office, Oak Ridge, TN (United States)

2008-07-01T23:59:59.000Z

182

Naval Construction Battalion Center Gulfport - Mississippi Power Partnership Success Story  

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

Construction Battalion Center Construction Battalion Center Gulfport - Mississippi Power Partnership Success Story Utilities Hardening Project Joe Bosco May 5, 2009 May 5, 2009 * Naval Construction Battalion Center * Established 1942 - Gulfport * Home of Atlantic Fleet Seabees Home of Atlantic Fleet Seabees * Mission: Prepare for & support all facets of the mobilization of construction forces * Naval Construction Battalion Center * 1,100 Acres * 9+ MVA; $3M/yr in Electricity 9+ MVA; $3M/yr in Electricity * One of two Battalion Centers in U.S. * Economic Impact - $500M Mississippi Power Company * Headquartered - Gulfport * Subsidiary y of Southern Comp pany y * Serves 23 counties Southeast Mississippi * 192,000 retail customers * * Generating capacity: 3 166 192 kW Generating capacity: 3,166,192 kW

183

A Transient Numerical Simulation of Perched Ground-Water Flow at the Test Reactor Area, Idaho National Engineering and Environmental Laboratory, Idaho, 1952-94  

SciTech Connect

Studies of flow through the unsaturated zone and perched ground-water zones above the Snake River Plain aquifer are part of the overall assessment of ground-water flow and determination of the fate and transport of contaminants in the subsurface at the Idaho National Engineering and Environmental Laboratory (INEEL). These studies include definition of the hydrologic controls on the formation of perched ground-water zones and description of the transport and fate of wastewater constituents as they moved through the unsaturated zone. The definition of hydrologic controls requires stratigraphic correlation of basalt flows and sedimentary interbeds within the saturated zone, analysis of hydraulic properties of unsaturated-zone rocks, numerical modeling of the formation of perched ground-water zones, and batch and column experiments to determine rock-water geochemical processes. This report describes the development of a transient numerical simulation that was used to evaluate a conceptual model of flow through perched ground-water zones beneath wastewater infiltration ponds at the Test Reactor Area (TRA).

B. R. Orr (USGS)

1999-11-01T23:59:59.000Z

184

2010 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond  

Science Conference Proceedings (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2009 through October 31, 2010. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of compliance activities • Discussion of the facility’s environmental impacts During the 2010 permit year, approximately 164 million gallons of wastewater were discharged to the Cold Waste Pond. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

mike lewis

2011-02-01T23:59:59.000Z

185

United States Naval Surface Warfare Center | Open Energy Information  

Open Energy Info (EERE)

Naval Surface Warfare Center Naval Surface Warfare Center Jump to: navigation, search Hydro | Hydrodynamic Testing Facilities Name United States Naval Surface Warfare Center Address Carderock, 9500 MacArthur Boulevard West Place Bethesda, Maryland Zip 20817 Sector Hydro Phone number (301) 227-1574 Website http://www.dt.navy.mil/hyd/fac Coordinates 38.9782231°, -77.1973878° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":38.9782231,"lon":-77.1973878,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

186

CRAD, Configuration Management - Oak Ridge National Laboratory...  

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

Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope...

187

Naval Petroleum and Oil Shale Reserves annual report of operations for fiscal year 1996  

SciTech Connect

During fiscal year 1996, the Department of Energy continued to operate Naval Petroleum Reserve No. 1 in California and Naval Petroleum Reserve No. 3 in Wyoming through its contractors. In addition, natural gas operations were conducted at Naval Petroleum Reserve No. 3. All productive acreage owned by the Government at Naval Petroleum Reserve No. 2 in California was produced under lease to private companies. The locations of all six Naval Petroleum and Oil Shale Reserves are shown in a figure. Under the Naval Petroleum Reserves Production Act of 1976, production was originally authorized for six years, and based on findings of national interest, the President was authorized to extend production in three-year increments. President Reagan exercised this authority three times (in 1981, 1984, and 1987) and President Bush authorized extended production once (in 1990). President Clinton exercised this authority in 1993 and again in October 1996; production is presently authorized through April 5, 2000. 4 figs. 30 tabs.

1996-12-31T23:59:59.000Z

188

Reactor Operations informal monthly report December 1994  

Science Conference Proceedings (OSTI)

Reactor operations at the MRR and HFBR reactors at Brookhaven National Laboratory are presented for December 1994. Reactor run-time and power levels, instrumentation, mechanical maintenance, occurrence reports, and safety information are included.

NONE

1994-12-01T23:59:59.000Z

189

NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG 7 JUNE 2013 Quick Facts..............................................................................................................................................................4  

E-Print Network (OSTI)

NAVAL POSTGRADUATE SCHOOL ACADEMIC CATALOG ­ 7 JUNE 2013 1 CONTENTS Quick Facts...............................................................................................................................................435 Energy Core Group .............................................................................................................................................438 Certificate in Defense Energy - Curriculum 234

190

Distributed Energy Resources at Naval Base Ventura County Building 1512: A Sensitivity Analysis  

E-Print Network (OSTI)

Naval Base Ventura County Standby Generator Optimization20 Figure 7: Standby Charge Sensitivity – Separate24 Figure 11: Standby Charge Sensitivity Analysis –

Bailey, Owen C.; Marnay, Chris

2005-01-01T23:59:59.000Z

191

Idaho National Laboratory - Enforcement Documents  

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

associated with Replacement of Exhaust Ventilation Filters at the Test Reactor Area Hot Cell Facility at the Idaho National Engineering and Environmental Laboratory, May 19,...

192

IDAHO NATIONAL LABORATORY  

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

History of the Idaho National Laboratory (INL) History of the Idaho National Laboratory (INL) You are here: DOE-ID Home > Inside ID > Brief History Site History The Idaho National Laboratory (INL), an 890-square-mile section of desert in southeast Idaho, was established in 1949 as the National Reactor Testing Station. Initially, the missions at the INL were the development of civilian and defense nuclear reactor technologies and management of spent nuclear fuel. Fifty-two reactors—most of them first-of-a-kind—were built, including the Navy’s first prototype nuclear propulsion plant. Of the 52 reactors, three remain in operation at the site. In 1951, the INL achieved one of the most significant scientific accomplishments of the century—the first use of nuclear fission to produce a usable quantity of electricity at the Experimental Breeder Reactor No.

193

Naval Petroleum and Oil Shale Reserves. Annual report of operations, Fiscal year 1992  

SciTech Connect

During fiscal year 1992, the reserves generated $473 million in revenues, a $181 million decrease from the fiscal year 1991 revenues, primarily due to significant decreases in oil and natural gas prices. Total costs were $200 million, resulting in net cash flow of $273 million, compared with $454 million in fiscal year 1991. From 1976 through fiscal year 1992, the Naval Petroleum and Oil Shale Reserves generated more than $15 billion in revenues and a net operating income after costs of $12.5 billion. In fiscal year 1992, production at the Naval Petroleum Reserves at maximum efficient rates yielded 26 million barrels of crude oil, 119 billion cubic feet of natural gas, and 164 million gallons of natural gas liquids. From April to November 1992, senior managers from the Naval Petroleum and Oil Shale Reserves held a series of three workshops in Boulder, Colorado, in order to build a comprehensive Strategic Plan as required by Secretary of Energy Notice 25A-91. Other highlights are presented for the following: Naval Petroleum Reserve No. 1--production achievements, crude oil shipments to the strategic petroleum reserve, horizontal drilling, shallow oil zone gas injection project, environment and safety, and vanpool program; Naval Petroleum Reserve No. 2--new management and operating contractor and exploration drilling; Naval Petroleum Reserve No. 3--steamflood; Naval Oil Shale Reserves--protection program; and Tiger Team environmental assessment of the Naval Petroleum and Oil Shale Reserves in Colorado, Utah, and Wyoming.

1992-12-31T23:59:59.000Z

194

Fallon Naval Air Station Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Page Page Edit with form History Facebook icon Twitter icon » Fallon Naval Air Station Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Fallon Naval Air Station Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Exploration History 5 Well Field Description 6 Geology of the Area 7 Geofluid Geochemistry 8 NEPA-Related Analyses (0) 9 Exploration Activities (0) 10 References Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"TERRAIN","zoom":6,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"300px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":39.38,"lon":-118.65,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

195

EA-0531: Proposed Natural Gas Protection Program for Naval Oil Shale  

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

31: Proposed Natural Gas Protection Program for Naval Oil 31: Proposed Natural Gas Protection Program for Naval Oil Shale Reserves Nos. 1 and 3, Garfield County, Colorado EA-0531: Proposed Natural Gas Protection Program for Naval Oil Shale Reserves Nos. 1 and 3, Garfield County, Colorado SUMMARY This EA evaluates the environmental impacts of a proposal for a Natural Gas Protection Program for Naval Oil Shale Reserves Nos. 1 and 3 which would be implemented over a five-year period that would encompass a total of 200 wells in Garfield County, Colorado. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 9, 1991 EA-0531: Final Environmental Assessment Proposed Natural Gas Protection Program for Naval Oil Shale Reserves Nos. 1 and 3 August 9, 1991 EA-0531: Finding of No Significant Impact

196

CRAD, Conduct of Operations - Oak Ridge National Laboratory High...  

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

High Flux Isotope Reactor Contractor ORR CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C...

197

The Integral Fast Reactor  

SciTech Connect

Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 5 refs., 3 figs.

Till, C.E.; Chang, Y.I. (Argonne National Lab., IL (USA)); Lineberry, M.J. (Argonne National Lab., Idaho Falls, ID (USA))

1990-01-01T23:59:59.000Z

198

Commander, Naval Base ATTN: Ms. Cheryl Barnett Building N-26  

Office of Legacy Management (LM)

.J>?j 1.2 1990 .J>?j 1.2 1990 Commander, Naval Base ATTN: Ms. Cheryl Barnett Building N-26 Code N 9 E Norfolk, Virginia 23511-6002 Dear Ms. Barnett: I enjoyed speaking with you on the phone. The Department of Energy (DOE) has established its Formerly Utilized Sites Remedial Action Program (FUSRAP) to identify sites formerly utilized by its predecessor agencies in the early days of the nation's atomic energy program and to determine the potential for these sites to contain radiological contamination, related to DOE's past activities, which may require remedial action. When necessary, radiological surveys of individual sites are performed to provide the data necessary to make this necessary determination. As we discussed, in July 1956, the Atomic Energy Commission (a DOE

199

Energy Secretary to Visit Georgia Nuclear Reactor Site and Tennessee...  

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

Nuclear Reactor Site and Tennessee Laboratory to Highlight Administration Support for Nuclear Energy Energy Secretary to Visit Georgia Nuclear Reactor Site and Tennessee...

200

A laboratory and pilot plant scaled continuous stirred reactor separator for the production of ethanol from sugars, corn grits/starch or biomass streams  

DOE Green Energy (OSTI)

An improved bio-reactor has been developed to allow the high speed, continues, low energy conversion of various substrates to ethanol. The Continuous Stirred Reactor Separator (CSRS) incorporates gas stripping of the ethanol using a recalculating gas stream between cascading stirred reactors in series. We have operated a 4 liter lab scale unit, and built and operated a 24,000 liter pilot scale version of the bioreactor. High rates of fermentation are maintained in the reactor stages using a highly flocculent yeast strain. Ethanol is recovered from the stripping gas using a hydrophobic solvent absorber (isothermal), after which the gas is returned to the bioreactor. Ethanol can then be removed from the solvent to recover a highly concentrated ethanol product. We have applied the lab scale CSRS to sugars (glucose/sucrose), molasses, and raw starch with simultaneous saccharification and fermentation of the starch granules (SSF). The pilot scale CSRS has been operated as a cascade reactor using dextrins as a feed. Operating data from both the lab and pilot scale CSRS are presented. Details of how the system might be applied to cellulosics, with some preliminary data are also given.

Dale, M.C.; Lei, Shuiwang; Zhou, Chongde

1995-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Thomas Wallner | Argonne National Laboratory  

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

Argonne National Laboratory's Omnivorous Engine Argonne National Laboratory's Omnivorous Engine Argonne National Laboratory's Omnivorous Engine Argonne National Laboratory's Omnivorous Engine Browse by Topic Energy Energy efficiency Vehicles Alternative fuels Automotive engineering Biofuels Diesel Fuel economy Fuel injection Heavy-duty vehicles Hybrid & electric vehicles Hydrogen & fuel cells Internal combustion Powertrain research Vehicle testing Building design Manufacturing Energy sources Renewable energy Bioenergy Solar energy Wind energy Fossil fuels Oil Nuclear energy Nuclear energy modeling & simulation Nuclear fuel cycle Geology & disposal Reactors Nuclear reactor safety Nuclear reactor materials Energy usage Energy life-cycle analysis Energy storage Batteries Lithium-ion batteries Lithium-air batteries Smart Grid

202

PROCEEDINGS OF THE US/UK MEETING ON THE COMPATIBILITY PROBLEMS OF GAS- COOLED REACTORS HELD AT OAK RIDGE NATIONAL LABORATORY, FEBRUARY 24-26, 1960  

SciTech Connect

Forty papers presented at the US/UK Meeting on the Compatibility Problems of Gas Cooled Reactors are given. Thirty-two of the papers are covered by separate abstracts. Eight papers were previously abstracted for NSA. (M.C.G.)

1961-03-01T23:59:59.000Z

203

Draft Environmental Impact Statement for a Container System for the Management of Naval Spent Nuclear Fuel EIS-0251  

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

Document ID 51 Document ID 51 Commenter: Daniel Nix - Western Interstate Energy Board, Colorado Response to Comment: A. The Navy extended the comment period from 45 to 60 days (ending July 18, 1996) in response to requests from the state of Nevada. A further extension could not be provided because of the need to complete the EIS to support actions required under a court agreement among the Department of Energy, Navy, and State of Idaho covering spent fuel management at the Idaho National Engineering Laboratory. B.&D. The Board's comment is correct that the EIS is limited to naval spent nuclear fuel and Navy- generated special case waste. The Board's comment is incorrect in the implication that transportation to Yucca Mountain is supported by the EIS. The proposed action of this EIS

204

EA-1236: Preparation for Transfer of Ownership of Naval Petroleum Reserve  

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

236: Preparation for Transfer of Ownership of Naval Petroleum 236: Preparation for Transfer of Ownership of Naval Petroleum Reserve No. 3, Natrona County, WY EA-1236: Preparation for Transfer of Ownership of Naval Petroleum Reserve No. 3, Natrona County, WY SUMMARY This EA evaluates activities that DOE would conduct in anticipation of possible transfer of Naval Petroleum Reserve No. 3 (NPR-3) out of Federal operation. Proposed activities would include accelerated plugging and abandoning of uneconomic wells, complete reclamation and restoration of abandoned sites including dismantling surface facilities, batteries, roads, test satellites, electrical distribution systems and associated power poles, when they are no longer needed for production, and the development of the Rocky Mountain Oilfield Testing Center (RMOTC).

205

Development Wells At Fallon Naval Air Station Area (Sabin, Et Al., 2010) |  

Open Energy Info (EERE)

Naval Air Station Area (Sabin, Et Al., 2010) Naval Air Station Area (Sabin, Et Al., 2010) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Development Wells At Fallon Naval Air Station Area (Sabin, Et Al., 2010) Exploration Activity Details Location Fallon Naval Air Station Area Exploration Technique Development Wells Activity Date Usefulness not indicated DOE-funding Unknown Notes As was mentioned previously, the Navy signed a development contract with Ormat in 2005 to produce power from a potential resource on the SE corner of the main side portion of NAS Fallon. Additionally the GPO began additional exploration activities on the Bombing Range 16 in collaboration with the Great Basin Center for Geothermal Energy. The introduction of $9.1M of Recovery Act funds in early 2009 led to a broadening as well as an

206

Sale of the Elk Hills Naval Petroleum Reserve | Department of Energy  

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

Services » Petroleum Reserves » Naval Reserves » Sale of the Elk Services » Petroleum Reserves » Naval Reserves » Sale of the Elk Hills Naval Petroleum Reserve Sale of the Elk Hills Naval Petroleum Reserve Energy Secretary Federico Pena (left) and Occidental Petroleum's David Hentschel sign the historic transfer agreement with Patricia Godley, DOE's Assistant Secretary for Fossil Energy, who orchestrated the sale, looking on. Energy Secretary Federico Pena (left) and Occidental Petroleum's David Hentschel sign the historic transfer agreement with Patricia Godley, DOE's Assistant Secretary for Fossil Energy, who orchestrated the sale, looking on. On February 5, 1998, the Department of Energy and Occidental Petroleum Corporation concluded the largest divestiture of federal property in the history of the U.S. government.

207

Design and analysis of a permanent magnet generator for naval applications  

E-Print Network (OSTI)

This paper discusses the electrical and magnetic design and analysis of a permanent magnet generation module for naval applications. Numerous design issues are addressed and several issues are raised about the potential ...

Rucker, Jonathan E. (Jonathan Estill)

2005-01-01T23:59:59.000Z

208

Modular machinery arrangement and its impact in early-stage naval electric ship design  

E-Print Network (OSTI)

Electrical power demands for naval surface combatants are projected to rise with the development of increasingly complex and power intensive combat systems. This trend also coincides with the need of achieving maximum fuel ...

Jurkiewicz, David J. (David James)

2012-01-01T23:59:59.000Z

209

EA-1008: Continued Development of Naval Petroleum Reserve No. 3 (Sitewide), Natrona County, Wyoming  

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

This EA evaluates the environmental impacts of the proposal to continue development of the U.S. Department of Energy's Naval Petroleum Reserve No. 3 located in Natrona County, Wyoming over the next...

210

Application and analysis of stiffened side shell panel failure for naval patrol craft  

E-Print Network (OSTI)

Over their lifetime, naval patrol craft are subjected to many different types of loading scenarios, most of which are perfectly safe. In rare instances, through a variety of different reasons, these craft are loaded beyond ...

Mothander, Matthew K. A., Lieutenant (Matthew Kristian Alden)

2009-01-01T23:59:59.000Z

211

Analyzing the effects of component reliability on naval Integrated Power System quality of service  

E-Print Network (OSTI)

The Integrated Power System (IPS) is a key enabling technology for future naval vessels and their advanced weapon systems. While conventional warship designs utilize separate power systems for propulsion and shipboard ...

Hawbaker, Benjamin F. (Benjamin Forrest)

2008-01-01T23:59:59.000Z

212

Hanford Laboratories monthly activities report, March 1963  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation March 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1963-04-15T23:59:59.000Z

213

Hanford Laboratories monthly activities report, March 1964  

SciTech Connect

The monthly report for the Hanford Laboratories Operation, March 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operation, and programming operations are discussed.

1964-04-15T23:59:59.000Z

214

Hanford Laboratories monthly activities report, October 1963  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, October 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1963-11-15T23:59:59.000Z

215

Hanford Laboratories monthly activities report, September 1963  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, September 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1963-10-15T23:59:59.000Z

216

Hanford Laboratories monthly activities report, August 1963  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, August 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1963-09-16T23:59:59.000Z

217

Hanford Laboratories monthly activities report, June 1963  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, June 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1963-07-15T23:59:59.000Z

218

Hanford Laboratories monthly activities report, April 1964  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, April 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

1964-05-15T23:59:59.000Z

219

Karen Swider-Lyons, Peter Bouwman, Norma Ugarte Naval Research Laboratory  

E-Print Network (OSTI)

), as the maximum mass change of oxygen in the oxygen carrier as follows: RO ¼ mox � mred mox ð6� where mox and mred carrier,, is defined as ¼ m mox ð7� where m is the actual mass of the oxygen carrier during analyzer: i ¼ i�1 � Z t1 t0 _noutMO mox ð4xCO2 þ 3xCO þ 2xO2 � xH2 �dt ð8� i ¼ i�1 þ Z t1 t0 2MO mox ð

220

Southwest Division, Naval Facilities Engineering Command, Demand Side Management Program Implementation  

E-Print Network (OSTI)

This paper covers some of the major aspects of the development and execution of the Southwest Division, Naval Facilities Engineering Command (SOUTHWESTNAVFACENGCOM) Energy and Water Program. The program covers Naval and Marine facilities in 14 western states. It started from zero in 1992 and has grown to a program which has identified and is in the process of implementing energy and water savings projects totaling over $115,000,000.

Gates, G. G.

1997-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Department of Energy Designates the Idaho National Laboratory...  

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

Designates the Idaho National Laboratory Advanced Test Reactor as a National Scientific User Facility Department of Energy Designates the Idaho National Laboratory Advanced Test...

222

Generation -IV Reactor Concepts  

NLE Websites -- All DOE Office Websites (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),

223

Final Report Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York  

Science Conference Proceedings (OSTI)

On May 9, 2011, ORISE conducted verification survey activities including scans, sampling, and the collection of smears of the remaining soils and off-gas pipe associated with the 802 Fan House within the HFBR (High Flux Beam Reactor) Complex at BNL. ORISE is of the opinion, based on independent scan and sample results obtained during verification activities at the HFBR 802 Fan House, that the FSS (final status survey) unit meets the applicable site cleanup objectives established for as left radiological conditions.

Evan Harpeneau

2011-06-24T23:59:59.000Z

224

Naval Station Newport Wind Resource Assessment. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites, and The Naval Facilities Engineering Service Center  

DOE Green Energy (OSTI)

The U.S. Environmental Protection Agency (EPA) launched the RE-Powering America's Land initiative to encourage development of renewable energy (RE) on potentially contaminated land and mine sites. EPA is collaborating with the U.S. Department of Energy's (DOE's) National Renewable Energy Laboratory (NREL) to evaluate RE options at Naval Station (NAVSTA) Newport in Newport, Rhode Island where multiple contaminated areas pose a threat to human health and the environment. Designated a superfund site on the National Priorities List in 1989, the base is committed to working toward reducing the its dependency on fossil fuels, decreasing its carbon footprint, and implementing RE projects where feasible. The Naval Facilities Engineering Service Center (NFESC) partnered with NREL in February 2009 to investigate the potential for wind energy generation at a number of Naval and Marine bases on the East Coast. NAVSTA Newport was one of several bases chosen for a detailed, site-specific wind resource investigation. NAVSTA Newport, in conjunction with NREL and NFESC, has been actively engaged in assessing the wind resource through several ongoing efforts. This report focuses on the wind resource assessment, the estimated energy production of wind turbines, and a survey of potential wind turbine options based upon the site-specific wind resource.

Robichaud, R.; Fields, J.; Roberts, J. O.

2012-02-01T23:59:59.000Z

225

NALDA (Naval Aviation Logistics Data Analysis) CAI (computer aided instruction)  

SciTech Connect

Data Systems Engineering Organization (DSEO) personnel developed a prototype computer aided instruction CAI system for the Naval Aviation Logistics Data Analysis (NALDA) system. The objective of this project was to provide a CAI prototype that could be used as an enhancement to existing NALDA training. The CAI prototype project was performed in phases. The task undertaken in Phase I was to analyze the problem and the alternative solutions and to develop a set of recommendations on how best to proceed. The findings from Phase I are documented in Recommended CAI Approach for the NALDA System (Duncan et al., 1987). In Phase II, a structured design and specifications were developed, and a prototype CAI system was created. A report, NALDA CAI Prototype: Phase II Final Report, was written to record the findings and results of Phase II. NALDA CAI: Recommendations for an Advanced Instructional Model, is comprised of related papers encompassing research on computer aided instruction CAI, newly developing training technologies, instructional systems development, and an Advanced Instructional Model. These topics were selected because of their relevancy to the CAI needs of NALDA. These papers provide general background information on various aspects of CAI and give a broad overview of new technologies and their impact on the future design and development of training programs. The paper within have been index separately elsewhere.

Handler, B.H. (Oak Ridge K-25 Site, TN (USA)); France, P.A.; Frey, S.C.; Gaubas, N.F.; Hyland, K.J.; Lindsey, A.M.; Manley, D.O. (Oak Ridge Associated Universities, Inc., TN (USA)); Hunnum, W.H. (North Carolina Univ., Chapel Hill, NC (USA)); Smith, D.L. (Memphis State Univ., TN (USA))

1990-07-01T23:59:59.000Z

226

Reactor Operations informal monthly report September 1994  

SciTech Connect

This paper presents operations at the MRR and HFBR reactors at Brookhaven National Laboratory for September 1994. Reactor run-times, instrumentation, mechanical maintenance, occurrence reports and safety information are listed. Irradiation summaries are included.

Junker, L.

1994-09-01T23:59:59.000Z

227

Final Report Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York  

SciTech Connect

The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

Evan Harpeneau

2011-06-24T23:59:59.000Z

228

Advanced Reactor Technologies | Department of Energy  

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

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

229

Idaho National Laboratory - Technology Transfer - Technologies ...  

Idaho National Laboratory Technologies Available for Licensing ... Environmental Flow-Through Reactor for the In Situ Assessment of Remediation Technologies in Vadose ...

230

PROCEEDINGS OF THE BIOMAGNETIC EFFECTS WORKSHOP, APRIL 6-7, 1978, LAWRENCE BERKELEY LAB  

E-Print Network (OSTI)

Naval Aerospace Medical Research Laboratory, Pensacola,Naval Aerospace Medical Research Laboratory, Pensacola,Naval Aerospace Medical Research Laboratory, Pensacola)

Tenforde, Tom S.

2011-01-01T23:59:59.000Z

231

National Laboratories  

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

Laboratories Los Alamos National Laboratory (the Laboratory) is one of 17 National Laboratories in the United States and is one of the two located in New Mexico. The Laboratory has...

232

Carl Vinson and pre-war naval legislation 1932-1940  

E-Print Network (OSTI)

At the end of World War I, the United States Navy was in the midst of a building program designed to make it a "Navy Second to None." However, the post-war desire to avoid involvement in another international conflict led the United States to retreat from the aggressive naval policy of President Woodrow Wilson. America initiated and supported conferences which led to the Washington Naval Treaty of 1922 and the London Naval Treaty of 1930, both of which limited the maximum strength of the world's naval powers. In addition, throughout the 1920's and early 1930's the United States failed to build up to the levels allowed by the treaties, causing the Navy to slowly age toward obsolescence. This situation changed in the period from 1933 to 1940 as Congressman Carl Vinson of Georgia, chairman of the House Naval Affairs Committee, drafted and saw to the passage of legislation designed to once again provide the United States with a powerful navy as part of a strong national defense. Vinson obtained passage of naval construction legislation in 1934, 1937, 1938, and 1940, and supported the annual and supplemental appropriation acts which funded the newly authorized construction. In doing so, Vinson overcame opposition from pacifists and isolationists in Congress who feared America would be drawn into another European war. Vinson also had to persuade fiscal conservatives opposed to increasing the budget deficit that funding naval construction was in the nation's best interests. Additionally, Vinson obtained the often reluctant support of President Franklin Roosevelt to insure final approval of his legislation. This study examines Vinson's efforts to provide the Navy the ships with which it eventually fought World War II. it looks at committee hearings, House and Senate debates, and behind the scenes conferences between Vinson and officials of the Navy Department and Roosevelt Administration which helped decide the course of naval expansion. It shows that while many people contributed passing naval construction legislation, Carl Vinson was the driving force behind the expansion of the Navy. Without Vinson's pre-war legislation, the Navy could not have been prepared to effectively fight the Second World War.

Svonavec, Stephen Charles

1994-01-01T23:59:59.000Z

233

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

Science Conference Proceedings (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 Wisconsin’s 1.7MV Tandem Accelerator Facility. This facility is now capable of irradiating of materials to high dose while controlling sample temperature up to 800ºC.

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

2006-09-01T23:59:59.000Z

234

DOE - Office of Legacy Management -- Naval Ordnance Test Station - CA 06  

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

Ordnance Test Station - CA 06 Ordnance Test Station - CA 06 FUSRAP Considered Sites Site: NAVAL ORDNANCE TEST STATION (CA.06) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: China Lake Naval Weapons Center Salt Wells Pilot Plant CA.06-1 Location: Inyokern , California CA.06-1 Evaluation Year: 1987 CA.06-1 Site Operations: Naval facility; experimental development work on shape charges and quality castings on a pilot plant scale. CA.06-1 Site Disposition: Eliminated - No indication that radioactive materials were handled at the site CA.06-1 Radioactive Materials Handled: None Indicated CA.06-1 Primary Radioactive Materials Handled: None CA.06-1 Radiological Survey(s): No Site Status: Eliminated from consideration under FUSRAP Also see

235

Nuclear Reactors  

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

Reactors Nuclear reactors created not only large amounts of plutonium needed for the weapons programs, but a variety of other interesting and useful radioisotopes. They produced...

236

This document was downloaded on May 22, 2013 at 14:23:58 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

Selection Procedures 20 Naval Officers 20 Other U.S. Military Officers 20 International Students 20 Civilian

237

This document was downloaded on May 22, 2013 at 14:29:51 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

- graduate School a naval university, un- ified in policy, procedure and purpose. In addition to its Naval PROCEDURES U.S. NAVAL OFFICERS U.S. Navy officers interested in admis- sion to one of the curricula offered in the submission. Requests for admission or questions regarding admission procedures should be directed to the Dean

238

This document was downloaded on May 22, 2013 at 14:28:55 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

, procedures and objectives. In 1973, the Naval Postgraduate School, together with the Naval War College. ADMISSIONS PROCEDURES U.S. NAVAL OFFICERS U.S. Navy officers interested in ad- mission to one- ity of quotas assigned to each country. The procedures for application are con- tained in OPNAV

239

This document was downloaded on May 22, 2013 at 14:29:10 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

, procedures and objectives. In 1973, the Naval Postgraduate School, together with the Naval War College or local bookstores, or from other students. ADMISSIONS PROCEDURES U.S. NAVAL OFFICERS U.S. Navy officers. Their admission is subject to availabil- ity of quotas assigned to each country. The procedures for application

240

This document was downloaded on May 22, 2013 at 14:28:34 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

, procedures and objectives. In 1973, the Naval Postgraduate School, together with the Naval War College Navy West Coast Match racing cham- pionships. ADMISSIONS PROCEDURES U.S. NAVAL OFFICERS U.S. Navy, and procedural guidance for the Navy's graduate education program. Included is material concerning officer

Note: This page contains sample records for the topic "naval reactors laboratory" 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

This document was downloaded on May 22, 2013 at 14:29:21 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

, procedures and objectives. In 1973, the Naval Postgraduate School, together with the Naval War College MILITARY OFFICERS ADMISSIONS PROCEDURES U.S. NAVAL OFFICERS U.S. Navy officers interested in ad- Military- ity of quotas assigned to each country. The procedures for application are con- 8 #12;GENERAL

242

This document was downloaded on May 22, 2013 at 14:28:45 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

, procedures and objectives. In 1973, the Naval Postgraduate School, together with the Naval War College- change system and stocks all required supplies. ADMISSIONS PROCEDURES U.S. NAVAL OFFICERS ACADEMIC of quotas assigned to each country. The procedures for application are con- 10 #12;GENERAL INFORMATION

243

This document was downloaded on May 22, 2013 at 14:29:42 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

the Naval Postgraduate School, in effect, a naval university, unified in policies, procedures and objec bookstores, or from other students. ADMISSIONS PROCEDURES U.S. NAVAL OFFICERS U. S. Navy officers interested. The procedures for application are contained in OPNAV INSTRUCTION 4950. IE. Corre- spondence must be processed

244

This document was downloaded on May 22, 2013 at 14:28:23 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

, procedures and objectives. In 1973, the Naval Postgraduate School, together with the Naval War College Navy West Coast Match racing cham- pionships. ADMISSIONS PROCEDURES U.S. NAVAL OFFICERS U.S. Navy, policy, and procedural guidance for the Navy's graduate education program. Included is material

245

Reactor Thermal-Hydraulics  

NLE Websites -- All DOE Office Websites (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

246

Mitigation action plan sale of Naval Petroleum Reserve No. 1 (Elk Hills) Kern County, California  

Science Conference Proceedings (OSTI)

Naval Petroleum Reserve No. 1 (NPR-1, also called {open_quotes}Elk Hills{close_quotes}), a Federally-owned oil and gas production field in Kern County, California, was created by an Executive Order issued by President Taft on September 2, 1912. He signed another Executive Order on December 13, 1912, to establish Naval Petroleum Reserve No. 2 (NPR-2), located immediately south of NPR-1 and containing portions of the town of Taft, California. NPR-1 was not developed until the 1973-74 oil embargo demonstrated the nation`s vulnerability to oil supply interruptions. Following the embargo, Congress passed the Naval Petroleum Reserves Production Act of 1976 which directed that the reserve be explored and developed to its fall economic potential at the {open_quotes}maximum efficient rate{close_quotes} (MER) of production. Since Elk Hills began full production in 1976, it has functioned as a commercial operation, with total revenues to the Federal government through FY 1996 of $16.4 billion, compared to total exploration, development and production costs of $3.1 billion. In February 1996, Title 34 of the National Defense Authorization Act for Fiscal Year 1996 (P.L. 104-106), referred to as the Elk Hills Sales Statute, directed the Secretary of Energy to sell NPR-1 by February 10, 1998.The Secretary was also directed to study options for enhancing the value of the other Naval Petroleum and Oil Shale Reserve properties such as NPR-2, located adjacent to NPR-1 in Kern County- Naval Petroleum Reserve No. 3 (NPR-3) located in Natrona County, Wyoming; Naval Oil Shale Reserves No. 1 and No. 3 (NOSR-1 and NOSR-3) located in Garfield County, Colorado; and Naval Oil Shale Reserve No. 2 (NOSR-2) located in Uintah and Carbon Counties, Utah. The purpose of these actions was to remove the Federal government from the inherently non-Federal function of operating commercial oil fields while making sure that the public would obtain the maximum value from the reserves.

NONE

1998-01-01T23:59:59.000Z

247

Nevis Cyclotron Laboratories Columbia University  

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

'i 'i ~ . 0 p 4 Nevis Cyclotron Laboratories Columbia University Department of Physics New York, New York THEORY OF MULTIPLE COULOMB SCATTERING FROM EXTENDED NUCLEI Leon N. Cooper and James Rainwater z , I i -- Joint ONR-AEC Program Office of Naval Research Contract Contract N6-ori-110-Task No. 1 Nevis - 4 - cu - 7 0 P-" This report has been photostated to fill your request as our sup- ply of copies w a s exhausted. If you should find that you do not need to retain this copy permanently in your files, we would greatly appreciate your returning it to TIS so that i t may be used to fill future requests from other AEC installations. t ? DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States

248

Achievements: Nuclear Reactors designed/built by Argonne National  

NLE Websites -- All DOE Office Websites (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

249

Experimental Breeder Reactor I Preservation Plan  

SciTech Connect

Experimental Breeder Reactor I (EBR I) is a National Historic Landmark located at the Idaho National Laboratory, a Department of Energy laboratory in southeastern Idaho. The facility is significant for its association and contributions to the development of nuclear reactor testing and development. This Plan includes a structural assessment of the interior and exterior of the EBR I Reactor Building from a preservation, rather than an engineering stand point and recommendations for maintenance to ensure its continued protection.

Julie Braun

2006-10-01T23:59:59.000Z

250

Idaho National Laboratory Site Pollution Prevention Plan  

SciTech Connect

It is the policy of the Department of Energy (DOE) that pollution prevention and sustainable environmental stewardship will be integrated into DOE operations as a good business practice to reduce environmental hazards, protect environmental resources, avoid pollution control costs, and improve operational efficiency and mission sustainability. In furtherance of this policy, DOE established five strategic, performance-based Pollution Prevention (P2) and Sustainable Environmental Stewardship goals and included them as an attachment to DOE O 450.1, Environmental Protection Program. These goals and accompanying strategies are to be implemented by DOE sites through the integration of Pollution Prevention into each site's Environmental Management System (EMS). This document presents a P2 and Sustainability Program and corresponding plan pursuant to DOE Order 450.1 and DOE O 435.1, Radioactive Waste Management. This plan is also required by the state of Idaho, pursuant to the Resource Conservation and Recovery Act (RCRA) partial permit. The objective of this document is to describe the Idaho National Laboratory (INL) Site P2 and Sustainability Program. The purpose of the program is to decrease the environmental footprint of the INL Site while providing enhanced support of its mission. The success of the program is dependent on financial and management support. The signatures on the previous page indicate INL, ICP, and AMWTP Contractor management support and dedication to the program. P2 requirements have been integrated into working procedures to ensure an effective EMS as part of an Integrated Safety Management System (ISMS). This plan focuses on programmatic functions which include environmentally preferable procurement, sustainable design, P2 and Sustainability awareness, waste generation and reduction, source reduction and recycling, energy management, and pollution prevention opportunity assessments. The INL Site P2 and Sustainability Program is administratively managed by the INL Site P2 Coordinator. Development and maintenance of this overall INL Site plan is ultimately the responsibility of DOE-ID. This plan is applicable to all INL Site contractors except those at the Naval Reactors Facility.

E. D. Sellers

2007-03-01T23:59:59.000Z

251

Idaho National Laboratory Site Pollution Prevention Plan  

SciTech Connect

It is the policy of the Department of Energy (DOE) that pollution prevention and sustainable environmental stewardship will be integrated into DOE operations as a good business practice to reduce environmental hazards, protect environmental resources, avoid pollution control costs, and improve operational efficiency and mission sustainability. In furtherance of this policy, DOE established five strategic, performance-based Pollution Prevention (P2) and Sustainable Environmental Stewardship goals and included them as an attachment to DOE O 450.1, Environmental Protection Program. These goals and accompanying strategies are to be implemented by DOE sites through the integration of Pollution Prevention into each site's Environmental Management System (EMS). This document presents a P2 and Sustainability Program and corresponding plan pursuant to DOE Order 450.1 and DOE O 435.1, Radioactive Waste Management. This plan is also required by the state of Idaho, pursuant to the Resource Conservation and Recovery Act (RCRA) partial permit. The objective of this document is to describe the Idaho National Laboratory (INL) Site P2 and Sustainability Program. The purpose of the program is to decrease the environmental footprint of the INL Site while providing enhanced support of its mission. The success of the program is dependent on financial and management support. The signatures on the previous page indicate INL, ICP, and AMWTP Contractor management support and dedication to the program. P2 requirements have been integrated into working procedures to ensure an effective EMS as part of an Integrated Safety Management System (ISMS). This plan focuses on programmatic functions which include environmentally preferable procurement, sustainable design, P2 and Sustainability awareness, waste generation and reduction, source reduction and recycling, energy management, and pollution prevention opportunity assessments. The INL Site P2 and Sustainability Program is administratively managed by the INL Site P2 Coordinator. Development and maintenance of this overall INL Site plan is ultimately the responsibility of DOE-ID. This plan is applicable to all INL Site contractors except those at the Naval Reactors Facility.

E. D. Sellers

2007-03-01T23:59:59.000Z

252

Fission energy: The integral fast reactor  

SciTech Connect

The Integral Fast Reactor (IFR) is an innovative reactor concept being developed at Argonne National Laboratory as a such next- generation reactor concept. The IFR concept has a number of specific technical advantages that collectively address the potential difficulties facing the expansion of nuclear power deployment. In particular, the IFR concept can meet all three fundamental requirements needed in a next-generation reactor as discussed below. This document discusses these requirements.

Chang, Yoon I.

1989-01-01T23:59:59.000Z

253

Hanford Laboratories Operation monthly activities report, November 1960  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, November 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

Sale, W.

1960-12-15T23:59:59.000Z

254

Hanford Laboratories Operation monthly activities report, August 1961  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation August 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1961-09-15T23:59:59.000Z

255

Hanford Laboratories Operation monthly activities report, February 1962  

SciTech Connect

The monthly report for the Hanford Laboratories Operation, February 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, and programming are discussed.

1962-03-15T23:59:59.000Z

256

Hanford Laboratories Operation monthly activities report, October 1962  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation October 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1962-11-15T23:59:59.000Z

257

Hanford Laboratories Operation monthly activities report, September 1961  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation September 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1961-10-16T23:59:59.000Z

258

Hanford Laboratories Operation monthly activities report, May 1962  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, May, 1962. Reactor fuels, chemistry, dosimetry, separation process, reactor technology employee relations, operations research and synthesis operation, programming, and radiation protection are discussed.

1962-06-15T23:59:59.000Z

259

Hanford Laboratories Operation monthly activities report, November 1962  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, November 1962. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1962-12-14T23:59:59.000Z

260

Hanford Laboratories Operation monthly activities report, August 1962  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation August 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1962-09-14T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Hanford Laboratories Operation monthly activities report, July 1959  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, July, 1959. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1959-08-15T23:59:59.000Z

262

Hanford Laboratories Operation monthly activities report, July 1961  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, July 1969. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1961-08-15T23:59:59.000Z

263

Hanford Laboratories Operation monthly activities report, April 1961  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, April 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1961-05-15T23:59:59.000Z

264

Hanford Laboratories Operation monthly activities report, February 1961  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, February 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1961-03-15T23:59:59.000Z

265

Hanford Laboratories Operation monthly activities report, July 1962  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation July 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1962-08-15T23:59:59.000Z

266

Hanford Laboratories Operation monthly activities report, May 1957  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, May, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1957-06-15T23:59:59.000Z

267

Hanford Laboratories Operation monthly activities report, June 1957  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, July 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1957-07-15T23:59:59.000Z

268

Hanford Laboratories Operation monthly activities report, September 1960  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, October, 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1960-10-15T23:59:59.000Z

269

Hanford Laboratories Operation monthly activities report, March 1962  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation March 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1962-04-16T23:59:59.000Z

270

Hanford Laboratories Operation monthly activities report, November 1959  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, November 1959. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1959-12-15T23:59:59.000Z

271

Hanford Laboratories Operation monthly activities report, September 1962  

SciTech Connect

The monthly report for the Hanford Laboratories Operation, September 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, and programming are discussed.

1962-10-15T23:59:59.000Z

272

Hanford Laboratories Operation monthly activities report, January 1961  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

1961-02-15T23:59:59.000Z

273

Hanford Laboratories Operation monthly activities report, October 1961  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation October 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1961-11-15T23:59:59.000Z

274

Hanford Laboratories Operation monthly activities report, June 1962  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation June 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

1962-07-16T23:59:59.000Z

275

Neutron beam characterization at the Neutron Radiography Reactor (NRAD)  

Science Conference Proceedings (OSTI)

The Neutron Radiography Reactor (NRAD) is a 250-kW TRIGA Reactor operated by Argonne National Laboratory and is located near Idaho Falls, Idaho. The reactor and its facilities regarding radiography are detailed in another paper at this conference; this paper summarizes neutron flux measurements and calculations that have been performed to better understand and potentially improve the neutronics characteristics of the reactor.

Imel, G.R.; Urbatsch, T.; Pruett, D.P.; Ross, J.R.

1990-01-01T23:59:59.000Z

276

NUCLEAR REACTOR  

DOE Patents (OSTI)

A boiling-water nuclear reactor is described wherein control is effected by varying the moderator-to-fuel ratio in the reactor core. This is accomplished by providing control tubes containing a liquid control moderator in the reactor core and providing means for varying the amount of control moderatcr within the control tubes.

Treshow, M.

1961-09-01T23:59:59.000Z

277

NEUTRONIC REACTOR  

DOE Patents (OSTI)

A reactor in which at least a portion of the moderator is in the form of movable refractory balls is described. In addition to their moderating capacity, these balls may serve as carriers for fissionable material or fertile material, or may serve in a coolant capacity to remove heat from the reactor. A pneumatic system is used to circulate the balls through the reactor.

Daniels, F.

1959-10-27T23:59:59.000Z

278

Princeton Plasma Physics Laboratory:  

SciTech Connect

This paper discusses progress on experiments at the Princeton Plasma Physics Laboratory. The projects and areas discussed are: Principal Parameters Achieved in Experimental Devices, Tokamak Fusion Test Reactor, Princeton Large Torus, Princeton Beta Experiment, S-1 Spheromak, Current-Drive Experiment, X-ray Laser Studies, Theoretical Division, Tokamak Modeling, Spacecraft Glow Experiment, Compact Ignition Tokamak, Engineering Department, Project Planning and Safety Office, Quality Assurance and Reliability, and Administrative Operations.

Phillips, C.A. (ed.)

1986-01-01T23:59:59.000Z

279

Documents | Argonne National Laboratory  

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

& simulation ---Nuclear fuel cycle ----Geology & disposal ---Reactors ----Nuclear reactor safety ----Nuclear reactor materials ----Nuclear system technologies & diagnostics...

280

CONVECTION REACTOR  

DOE Patents (OSTI)

An homogeneous nuclear power reactor utilizing convection circulation of the liquid fuel is proposed. The reactor has an internal heat exchanger looated in the same pressure vessel as the critical assembly, thereby eliminating necessity for handling the hot liquid fuel outside the reactor pressure vessel during normal operation. The liquid fuel used in this reactor eliminates the necessity for extensive radiolytic gas rocombination apparatus, and the reactor is resiliently pressurized and, without any movable mechanical apparatus, automatically regulates itself to the condition of criticality during moderate variations in temperature snd pressure and shuts itself down as the pressure exceeds a predetermined safe operating value.

Hammond, R.P.; King, L.D.P.

1960-03-22T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Laboratory Reagents  

SciTech Connect

Replaced by WMH-310, Section 4.17. This document outlined the basic methodology for preparing laboratory reagents used in the 222-S Standards Laboratory. Included were general guidelines for drying, weighing, transferring, dissolving, and diluting techniques common when preparing laboratory reagents and standards. Appendix A contained some of the reagents prepared by the laboratory.

CARLSON, D.D.

1999-10-08T23:59:59.000Z

282

DOE - Office of Legacy Management -- Naval Ordnance Plant - MI 0-03  

Office of Legacy Management (LM)

Plant - MI 0-03 Plant - MI 0-03 FUSRAP Considered Sites Site: NAVAL ORDNANCE PLANT (MI.0-03) Eliminated from further consideration under FUSRAP - Referred to DoD for action Designated Name: Not Designated Alternate Name: None Location: Centerline , Michigan MI.0-03-1 Evaluation Year: 1987 MI.0-03-1 Site Operations: Assembled bomb components. MI.0-03-1 Site Disposition: Eliminated - No Authority - Referred to DoD MI.0-03-1 Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None Radiological Survey(s): None Indicated Site Status: Eliminated from further consideration under FUSRAP - Referred to DoD for action MI.0-03-1 Also see Documents Related to NAVAL ORDNANCE PLANT MI.0-03-1 - DOE Letter; J.Fiore to C.Shafer; Subject: Information on

283

DOE - Office of Legacy Management -- Naval Proving Ground - VA 0-01  

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

Proving Ground - VA 0-01 Proving Ground - VA 0-01 FUSRAP Considered Sites Site: NAVAL PROVING GROUND (VA.0-01 ) Eliminated from further consideration under FUSRAP - Referred to DOD Designated Name: Not Designated Alternate Name: None Location: Dahlgren , Virginia VA.0-01-1 Evaluation Year: 1987 VA.0-01-1 Site Operations: Site operations were not specified; this site was identified on the 1954 Accountable Station Lists. VA.0-01-1 VA.0-01-2 Site Disposition: Eliminated - Referred to DOD VA.0-01-1 Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None Radiological Survey(s): None Indicated Site Status: Eliminated from further consideration under FUSRAP - Referred to DOD VA.0-01-1 Also see Documents Related to NAVAL PROVING GROUND VA.0-01-1 - DOE Letter; Fiore to Schafer; Referral of DOD or Former

284

Success Story: Naval Medical Center San Diego Co-Generation Project  

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

Success Story Success Story Success Story Naval Medical Center San Diego Naval Medical Center San Diego Co-Generation Project Co-Generation Project Karen Jackson, SDG&E Karen Jackson, SDG&E Project Manager Project Manager Edward Thibodo, NAVFAC SW Edward Thibodo, NAVFAC SW Energy Team Contract Energy Team Contract ' ' s Lead s Lead NAVFAC Contractor NAVFAC Contractor ' ' s Guide: s Guide:   Partnering Philosophy Partnering Philosophy - - " " We W are partners e are partners in every contract we award. Partnering is in every contract we award. Partnering is an attitude that we both work hard to an attitude that we both work hard to develop, an it requires both of us to take develop, an it requires both of us to take some extra risk and trust one another. some extra risk and trust one another.

285

DOE - Office of Legacy Management -- Naval Office at the University of New  

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

Office at the University of Office at the University of New Mexico - NM 0-03 FUSRAP Considered Sites Site: NAVAL OFFICE AT THE UNIVERSITY OF NEW MEXICO (NM.0-03) Eliminated from further consideration under FUSRAP - Referred to DOD Designated Name: Not Designated Alternate Name: None Location: Albuquerque , New Mexico NM.0-03-1 Evaluation Year: 1987 NM.0-03-1 Site Operations: Site was a transshipment station for equipment to the Los Alamos site. NM.0-03-1 Site Disposition: Eliminated - Referred to DOD NM.0-03-1 Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None NM.0-03-1 Radiological Survey(s): None Indicated Site Status: Eliminated from further consideration under FUSRAP - Referred to DOD NM.0-03-1 Also see Documents Related to NAVAL OFFICE AT THE UNIVERSITY OF NEW MEXICO

286

Investigation on the continued production of the Naval Petroleum Reserves beyond April 5, 1991  

SciTech Connect

The authority to produce the Naval Petroleum Reserves (NPRs) is due to expire in April 1991, unless extended by Presidential finding. As provided in the Naval Petroleum Reserves Production act of 1976 (Public Law 94-258), the President may continue production of the NPRs for a period of up to three years following the submission to Congress, at least 180 days prior to the expiration of the current production period, of a report that determines that continued production of the NPRs is necessary and a finding by the President that continued production is in the national interest. This report assesses the need to continue production of the NPRs, including analyzing the benefits and costs of extending production or returning to the shut-in status that existed prior to 1976. This continued production study considers strategic, economic, and energy issues at the local, regional, and national levels. 15 figs., 13 tabs.

Not Available

1990-09-01T23:59:59.000Z

287

Naval Petroleum and Oil Shale Reserves annual report of operations, Fiscal year 1991  

Science Conference Proceedings (OSTI)

During FY 1991 the Reserves generating $654 million in revenues, a $52 million increase from the Fy 1990 revenues, reflecting the increase in FY 1991 oil prices during the Gulf War. Total costs were $200 million, resulting in net cash flow of $454 million, compared with $423 million in FY 1990. Revenues for FY 1992 are expected to decrease, reflecting a decrease in production and prices. In FY 1991, production at the NPRs at maximum efficient rates yielded 28 million barrels of crude oil, 125 billion cubic feet of natural gas, and 183 million gallons of natural gas liquids. Additional highlights on the following topics are included: legislative change, Naval Petroleum Reserve-1 (NPR-1) exploration, NPR-1 horizontal drilling, NPR-1 shallow oil zone gas injection project, NPR-1 FY 1991-1997 long range plan, NPR-1 environment and safety, NPR-2 exploration drilling, NPR-3 steamflood, Naval Oil Shale Reserves gas migration prevention.

Not Available

1991-01-01T23:59:59.000Z

288

Naval Petroleum and Oil Shale Reserves annual report of operations, Fiscal year 1991  

Science Conference Proceedings (OSTI)

During FY 1991 the Reserves generating $654 million in revenues, a $52 million increase from the Fy 1990 revenues, reflecting the increase in FY 1991 oil prices during the Gulf War. Total costs were $200 million, resulting in net cash flow of $454 million, compared with $423 million in FY 1990. Revenues for FY 1992 are expected to decrease, reflecting a decrease in production and prices. In FY 1991, production at the NPRs at maximum efficient rates yielded 28 million barrels of crude oil, 125 billion cubic feet of natural gas, and 183 million gallons of natural gas liquids. Additional highlights on the following topics are included: legislative change, Naval Petroleum Reserve-1 (NPR-1) exploration, NPR-1 horizontal drilling, NPR-1 shallow oil zone gas injection project, NPR-1 FY 1991-1997 long range plan, NPR-1 environment and safety, NPR-2 exploration drilling, NPR-3 steamflood, Naval Oil Shale Reserves gas migration prevention.

Not Available

1991-12-31T23:59:59.000Z

289

History of Research Reactors at Brookhaven  

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

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

290

U.S. Department of Energy Naval Petroleum and Oil Shale Reserves combined financial statements, September 30, 1996 and 1995  

Science Conference Proceedings (OSTI)

The Naval Petroleum and Oil Shale Reserves (NPOSR) produces crude oil and associated hydrocarbons from the Naval Petroleum Reserves (NPR) numbered 1, 2, and 3, and the Naval Oil Shale Reserves (NOSR) numbered 1, 2, and 3 in a manner to achieve the greatest value and benefits to the US taxpayer. NPOSR consists of the Naval Petroleum Reserve in California (NPRC or Elk Hills), which is responsible for operations of NPR-1 and NPR-2; the Naval Petroleum Oil Shale Reserve in Colorado, Utah, and Wyoming (NPOSR-CUW), which is responsible for operations of NPR-3, NOSR-1, 2, and 3 and the Rocky Mountain Oilfield Testing Center (RMOTC); and NPOSR Headquarters in Washington, DC, which is responsible for overall program direction. Each participant shares in the unit costs and production of hydrocarbons in proportion to the weighted acre-feet of commercially productive oil and gas formations (zones) underlying the respective surface lands as of 1942. The participating shares of NPR-1 as of September 30, 1996 for the US Government and Chevron USA, Inc., are listed. This report presents the results of the independent certified public accountants` audit of the Department of Energy`s (Department) Naval Petroleum and Oil Shale Reserves (NPOSR) financial statements as of September 30, 1996.

NONE

1997-03-01T23:59:59.000Z

291

Nuclear Energy Enabling Technologies (NEET) Reactor Materials  

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

Enabling Technologies (NEET) Reactor Materials Enabling Technologies (NEET) Reactor Materials Award Recipient Estimated Award Amount* Award Location Supporting Organizations Project Description University of Nebraska $979,978 Lincoln, NE Massachusetts Institute of Technology (Cambridge, MA), Texas A&M (College Station, TX) Project will explore the development of advanced metal/ceramic composites. These improvements could lead to more efficient production of electricity in advanced reactors. Oak Ridge National Laboratory $849,000 Oak Ridge, TN University of Wisconsin-Madison (Madison, WI) Project will develop novel high-temperature high-strength steels with the help of computational modeling, which could lead to increased efficiency in advanced reactors. Pacific Northwest National Laboratory

292

Audit Report: OIG-0884 | Department of Energy  

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

OIG-0884 Audit Report: OIG-0884 April 12, 2013 Management of Naval Reactors' Cyber Security Program The Naval Reactors Program (Naval Reactors), an organization within the National...

293

Nevis Cyclotron Laboratories Columbia University Physics Department  

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

Nevis Cyclotron Laboratories Nevis Cyclotron Laboratories Columbia University Physics Department Irvington-on-Hudson, New York WEAK INTERACTIONS T. D. Lee CU-144-57-ONR-110-l-Physics Reproduction in whole or in part is permitted for any purpose of the United States Government June, 1957 Joint ONR-AEC Program Office of Naval Research Contract Contract N6-ori-110-Task No. 1 Contract AT(30-1)-1932 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process

294

Alamos National Laboratory  

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

record neutron beam at Los record neutron beam at Los Alamos National Laboratory July 10, 2012 New method has potential to advance materials measurement LOS ALAMOS, New Mexico, July 10, 2012-Using a one-of-a-kind laser system at Los Alamos National Laboratory, scientists have created the largest neutron beam ever made by a short-pulse laser, breaking a world record. Neutron beams are usually made with particle accelerators or nuclear reactors and are commonly used in a wide variety of scientific research, particularly in advanced materials science. Using the TRIDENT laser, a unique and powerful 200 trillion-watt short-pulse laser, scientists from Los Alamos, the Technical University of Darmstadt, Germany, and Sandia National Laboratories focus high-intensity light on an ultra-thin plastic sheet

295

NEUTRONIC REACTOR  

DOE Patents (OSTI)

A neutronic reactor in which neutron moderation is achieved primarily in its reflector is described. The reactor structure consists of a cylindrical central "island" of moderator and a spherical moderating reflector spaced therefrom, thereby providing an annular space. An essentially unmoderated liquid fuel is continuously passed through the annular space and undergoes fission while contained therein. The reactor, because of its small size, is particularly adapted for propulsion uses, including the propulsion of aircraft. (AEC)

Fraas, A.P.; Mills, C.B.

1961-11-21T23:59:59.000Z

296

REACTOR COOLING  

DOE Patents (OSTI)

A nuclear reactor with provisions for selectively cooling the fuel elements is described. The reactor has a plurality of tubes extending throughout. Cylindrical fuel elements are disposed within the tubes and the coolant flows through the tubes and around the fuel elements. The fuel elements within the central portion of the reactor are provided with roughened surfaces of material. The fuel elements in the end portions of the tubes within the reactor are provlded with low conduction jackets and the fuel elements in the region between the central portion and the end portions are provided with smooth surfaces of high heat conduction material.

Quackenbush, C.F.

1959-09-29T23:59:59.000Z

297

A Review: Solar Thermal Reactors for Materials Production  

Science Conference Proceedings (OSTI)

Currently, there are no industrial scale solar reactors used for material processing and only small research units have been tried. Various laboratory scale solar ...

298

Neutronics and radiation damage calculations for fusion reactors  

DOE Green Energy (OSTI)

Some of the neutronics calculations that have been carried out at the Oak Ridge National Laboratory to assess radiation damage problems in fusion reactors are presented and discussed.

Alsmiller, R.G. Jr.; Gabriel, T.A.; Santoro, R.T.

1977-01-01T23:59:59.000Z

299

Brookhaven National Laboratory | Department of Energy  

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

Brookhaven National Laboratory Brookhaven National Laboratory Brookhaven National Laboratory Site Overview The Brookhaven National Laboratory (BNL) was established in 1947 by the Atomic Energy Commission (AEC) (predecessor to U.S. Department of Energy [DOE]). Formerly Camp Upton, a U.S. Army installation site, Brookhaven is located on 5,263-acre site on Long Island in Upton, New York, approximately 60 miles east of New York City. Historically, BNL was involved in the construction of accelerators and research reactors such as the Cosmotron, the High Flux Beam Reactor (HFBR) and the Brookhaven Graphite Research Reactor (BGRR). These accelerators and reactors lead the way in high-energy physics experiments and subsequent discoveries. To complete the EM BNL mission the following must be completed, all

300

Gas-cooled reactors  

SciTech Connect

Experience to date with operation of high-temperature gas-cooled reactors has been quite favorable. Despite problems in completion of construction and startup, three high-temperature gas-cooled reactor (HTGR) units have operated well. The Windscale Advanced Gas-Cooled Reactor (AGR) in the United Kingdom has had an excellent operating history, and initial operation of commercial AGRs shows them to be satisfactory. The latter reactors provide direct experience in scale-up from the Windscale experiment to fullscale commercial units. The Colorado Fort St. Vrain 330-MWe prototype helium-cooled HTGR is now in the approach-to-power phase while the 300-MWe Pebble Bed THTR prototype in the Federal Republic of Germany is scheduled for completion of construction by late 1978. THTR will be the first nuclear power plant which uses a dry cooling tower. Fuel reprocessing and refabrication have been developed in the laboratory and are now entering a pilot-plant scale development. Several commercial HTGR power station orders were placed in the U.S. prior to 1975 with similar plans for stations in the FRG. However, the combined effects of inflation, reduced electric power demand, regulatory uncertainties, and pricing problems led to cancellation of the 12 reactors which were in various stages of planning, design, and licensing.

Schulten, R.; Trauger, D.B.

1976-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

BNL | Our History: Reactors as Research Tools  

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

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

302

LETTER REPORT. INDEPENDENT CONFIRMATORY SURVEY RESULTS OF SOILS ASSOCIATED WITH THE ARGYLE STREET SEWER LINE AT THE UNITED NUCLEAR CORPORATION NAVAL PRODUCTS SITE, NEW HAVEN, CONNECTICUT  

SciTech Connect

Oak Ridge Institute for Science and Education (ORISE) personnel visited the United Nuclear Corporation (UNC) Naval Products site on three separate occasions during the months of October and November 2011. The purpose of these visits was to conduct confirmatory surveys of soils associated with the Argyle Street sewer line that was being removed. Soil samples were collected from six different, judgmentally determined locations in the Argyle Street sewer trench. In addition to the six soil samples collected by ORISE, four replicate soil samples were collected by Cabrera Services, Inc. (CSI) for analysis by the ORISE laboratory. Replicate samples S0010 and S0011 were final status survey (FSS) bias samples; S0012 was an FSS systematic sample; and S0015 was a waste characterization sample. Six soil samples were also collected for background determination. Uranium-235 and uranium-238 concentrations were determined via gamma spectroscopy; the spectra were also reviewed for other identifiable photopeaks. Radionuclide concentrations for these soil samples are provided. In addition to the replicate samples and the samples collected by ORISE, CSI submitted three soil samples for inter-laboratory comparison analyses. One sample was from the background reference area, one was from waste characterization efforts (material inside the sewer line), and one was a FSS sample. The inter-laboratory comparison analyses results between ORISE and CSI were in agreement, except for one sample collected in the reference area. Smear results For Argyle Street sewer pipes are tabulated.

Adams, Wade C.

2012-01-24T23:59:59.000Z

303

DOE - Office of Legacy Management -- Argonne National Laboratory - West -  

Office of Legacy Management (LM)

Argonne National Laboratory - West Argonne National Laboratory - West - 014 FUSRAP Considered Sites Site: Argonne National Laboratory - West (014) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The primary mission of the Argonne National Laboratory-West was to support liquid metal reactor research and development for the Department of Energy¿s Integral Fast Reactor Program, but the program was terminated. Activities at the Laboratory now include technology development for spent nuclear fuel and waste treatment, reactor and fuel cycle safety, and facility decommissioning. The decommissioning and other clean up is being

304

EIS-0251: Department of the Navy Final Environmental Impact Statement for a Container System for the Management of Naval Spent Nuclear Fuel (November 1996)  

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

This Final Environmental Impact Statement addresses six general alternative systems for the loading, storage, transport, and possible disposal of naval spent nuclear fuel following examination.

305

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope  

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

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Nuclear Safety Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

306

NEUTRONIC REACTOR  

DOE Patents (OSTI)

A nuclear reactor for isotope production is described. This reactor is designed to provide a maximum thermal neutron flux in a region adjacent to the periphery of the reactor rather than in the center of the reactor. The core of the reactor is generally centrally located with respect tn a surrounding first reflector, constructed of beryllium. The beryllium reflector is surrounded by a second reflector, constructed of graphite, which, in tune, is surrounded by a conventional thermal shield. Water is circulated through the core and the reflector and functions both as a moderator and a coolant. In order to produce a greatsr maximum thermal neutron flux adjacent to the periphery of the reactor rather than in the core, the reactor is designed so tbat the ratio of neutron scattering cross section to neutron absorption cross section averaged over all of the materials in the reflector is approximately twice the ratio of neutron scattering cross section to neutron absorption cross section averaged over all of the material of the core of the reactor.

Wigner, E.P.

1958-04-22T23:59:59.000Z

307

Fast Reactor Fuel Type and Reactor Safety Performance  

Science Conference Proceedings (OSTI)

Fast Reactor Fuel Type and Reactor Safety Performance R. Wigeland , Idaho National Laboratory J. Cahalan, Argonne National Laboratory The sodium-cooled fast neutron reactor is currently being evaluated for the efficient transmutation of the highly-hazardous, long-lived, transuranic elements that are present in spent nuclear fuel. One of the fundamental choices that will be made is the selection of the fuel type for the fast reactor, whether oxide, metal, carbide, nitride, etc. It is likely that a decision on the fuel type will need to be made before many of the related technologies and facilities can be selected, from fuel fabrication to spent fuel reprocessing. A decision on fuel type should consider all impacts on the fast reactor system, including safety. Past work has demonstrated that the choice of fuel type may have a significant impact on the severity of consequences arising from accidents, especially for severe accidents of low probability. In this paper, the response of sodium-cooled fast reactors is discussed for both oxide and metal fuel types, highlighting the similarities and differences in reactor response and accident consequences. Any fast reactor facility must be designed to be able to successfully prevent, mitigate, or accommodate all consequences of potential events, including accidents. This is typically accomplished by using multiple barriers to the release of radiation, including the cladding on the fuel, the intact primary cooling system, and most visibly the reactor containment building. More recently, this has also included the use of ‘inherent safety’ concepts to reduce or eliminate the potential for serious damage in some cases. Past experience with oxide and metal fuel has demonstrated that both fuel types are suitable for use as fuel in a sodium-cooled fast reactor. However, safety analyses for these two fuel types have also shown that there can be substantial differences in accident consequences due to the neutronic and thermophysical properties of the fuel and their compatibility with the reactor coolant, with corresponding differences in the challenges presented to the reactor developers. Accident phenomena are discussed for the sodium-cooled fast reactor based on the mechanistic progression of conditions from accident initiation to accident termination, whether a benign state is achieved or more severe consequences are expected. General principles connecting accident phenomena and fuel properties are developed from the oxide and metal fuel safety analyses, providing guidelines that can be used as part of the evaluation for selection of fuel type for the sodium-cooled fast reactor.

R. Wigeland; J. Cahalan

2009-09-01T23:59:59.000Z

308

Naval Petroleum and Oil Shale Reserves. Annual report of operations, Fiscal year 1993  

Science Conference Proceedings (OSTI)

During fiscal year 1993, the reserves generated $440 million in revenues, a $33 million decrease from the fiscal year 1992 revenues, primarily due to significant decreases in oil and natural gas prices. Total costs were $207 million, resulting in net cash flow of $233 million, compared with $273 million in fiscal year 1992. From 1976 through fiscal year 1993, the Naval Petroleum and Oil Shale Reserves generated $15.7 billion in revenues for the US Treasury, with expenses of $2.9 billion. The net revenues of $12.8 billion represent a return on costs of 441 percent. See figures 2, 3, and 4. In fiscal year 1993, production at the Naval Petroleum and Oil Shale Reserves at maximum efficient rates yielded 25 million barrels of crude oil, 123 billion cubic feet of natural gas, and 158 million gallons of natural gas liquids. The Naval Petroleum and Oil Shale Reserves has embarked on an effort to identify additional hydrocarbon resources on the reserves for future production. In 1993, in cooperation with the US Geological Survey, the Department initiated a project to assess the oil and gas potential of the program`s oil shale reserves, which remain largely unexplored. These reserves, which total a land area of more than 145,000 acres and are located in Colorado and Utah, are favorably situated in oil and gas producing regions and are likely to contain significant hydrocarbon deposits. Alternatively the producing assets may be sold or leased if that will produce the most value. This task will continue through the first quarter of fiscal year 1994.

Not Available

1993-12-31T23:59:59.000Z

309

Naval petroleum and oil shale reserves: Annual report of operations, Fiscal Year 1986  

Science Conference Proceedings (OSTI)

Market prices for curde oil experienced their greatest decline in history during 1986, with substantial effect on the Naval Petroleum and Oil Shale Reserves. Sales procedures which had served the Department well in prior years during periods when oil prices were stable or rising were found inadequate to cope with these declines, and new sales procedures were developed and implemented. Congressional concern that the Government receive fair prices from Naval Petroleum Reserves (NPR) petroleum sales also led to Public Law No. 99-413, enacted on August 29, 1986, which amended title 10, United States Code, Chapter 641. This law sets a minimum price, using two criteria, under which petroleum from the NPR cannot be sold. Notwithstanding the decline in oil and gas prices, revenues from the sale of NPR petroleum totaled $763 million in 1986. Although this represented a 41% decline from 1985 receipts, the 1986 revenues well exceeded net program expenditures of $157 million. Because of the decline in prevailing oil prices during the second quarter of 1986, major cost reductions of $3.4 million were implemented at NPR-3, and even greater reductions are planned for 1987 to ensure the profitability of that field. The decline in energy prices also affected plans to protect natural gas underlying Naval Oil Shale Reserve No. 3 (NOSR-3). Two of 14 planned wells were drilled and are available for production. Unfortunately, efforts to sell gas from these wells have been unsuccessful, and further drilling has been delayed until the gas market is stronger. 16 figs., 20 tabs.

Not Available

1987-01-01T23:59:59.000Z

310

Rocky Mountain Oilfield Testing Center RMOTC at the Naval Petroleum Reserve No. 3  

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

RMOTC RMOTC The Rocky Mountain Oilfield Testing Center (RMOTC), is an operating oil field focusing on environmentally-balanced energy technologies and alternatives, and is the premiere energy testing and demonstration field in the nation. 3 3 * the opportunity to explore environmentally- balanced solutions to the nation's energy issues * opportunities to develop, demonstrate, and evaluate a variety of energy related technologies * a chance to collaborate with top professionals in the energy, environmental technology, and engineering fields * shared industry knowledge through technology transfer via reports, journal articles, and presentations Located within the Naval Petroleum Reserve No. 3 (NPR-3) near Casper, Wyoming, RMOTC offers: RMOTC Offers Solutions 4 4 The Administration and Engineering

311

Quality assurance assessment of new efficient lighting systems for Naval ships. Final report  

SciTech Connect

Ballasts and lamps, which have been selected to replace existing lamp/ballast systems based on improved performance, were tested to determine if they meet standard Naval MIL specifications. Fifty ballasts manufactured by Advance Transformer Corporation and Universal Manufacturing Corp., and 100 lamps manufactured by GTE were tested to determine their quality assurance and durability. These components met all of the MIL specifications that lamp/ballast systems in use must meet. In addition, these new systems have an improved system efficacy, 62 lumens per watt, and lower third harmonics, which will reduce the need for generating capacity for lighting on ships.

Verderber, R.

1984-08-01T23:59:59.000Z

312

The Laboratory  

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

existing programs in climate change science and infrastructure. The Laboratory has a 15- year history in climate change science. The Climate, Ocean and Sea Ice Modeling (COSIM)...

313

NUCLEAR REACTOR  

DOE Patents (OSTI)

A heterogeneous, natural uranium fueled, solid moderated, gas cooled reactor is described, in which the fuel elements are in the form of elongated rods and are dlsposed within vertical coolant channels ln the moderator symmetrically arranged as a regular lattice in groups. This reactor employs control rods which operate in vertical channels in the moderator so that each control rod is centered in one of the fuel element groups. The reactor is enclosed in a pressure vessel which ls provided with access holes at the top to facilitate loading and unloadlng of the fuel elements, control rods and control rod driving devices.

Moore, R.V.; Bowen, J.H.; Dent, K.H.

1958-12-01T23:59:59.000Z

314

Hanford Laboratories Operation monthly activities report, May 1959  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, May, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.

1959-06-15T23:59:59.000Z

315

Hanford Laboratories operation monthly activities report, October 1956  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for October 1956.

1956-11-21T23:59:59.000Z

316

Hanford Laboratories Operation monthly activities report, January 1962  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, January, 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, laboratory auxiliaries operation, and technical administration operation area discussed.

1962-02-15T23:59:59.000Z

317

Hanford Laboratories Operation monthly activities report, June 1961  

SciTech Connect

The monthly report for the Hanford Laboratories Operation, June 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.

1961-07-15T23:59:59.000Z

318

Hanford Laboratories Operation monthly activities report, June 1958  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation, June, 1958. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics, instrumentation research, employee relations, operations research, synthesis operation, programming, radiation protection, and laboratory auxiliaries operation are discussed.

1958-07-15T23:59:59.000Z

319

Hanford Laboratories Operation monthly activities report, December 1961  

SciTech Connect

The monthly report for the Hanford Laboratories Operation, May 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and technical administration operation are discussed.

1962-01-15T23:59:59.000Z

320

Hanford Laboratories Operation monthly activities report, December 1957  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for December 1957.

1958-01-15T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Hanford Laboratories Operation monthly activities report, May 1961  

SciTech Connect

The monthly report for the Hanford Laboratories Operation, May 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.

1961-06-15T23:59:59.000Z

322

Hanford Laboratories operation monthly activities report, November 1956  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operations research, inventions, visits, and personnel status are discussed. This report is for November, 1956.

1956-12-21T23:59:59.000Z

323

Hanford Laboratories operation monthly activities report, February 1958  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for February 1958.

1958-03-15T23:59:59.000Z

324

Hanford Laboratories operation monthly activities report, November 1957  

SciTech Connect

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for November 1957.

1957-12-15T23:59:59.000Z

325

CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

326

Reactor Materials  

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

The reactor materials crosscut effort will enable the development of innovative and revolutionary materials and provide broad-based, modern materials science that will benefit all four DOE-NE...

327

NEUTRONIC REACTORS  

DOE Patents (OSTI)

A nuclear reactor is described wherein horizontal rods of thermal- neutron-fissionable material are disposed in a body of heavy water and extend through and are supported by spaced parallel walls of graphite.

Wigner, E.P.

1960-11-22T23:59:59.000Z

328

REACTOR SHIELD  

DOE Patents (OSTI)

Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

1959-02-17T23:59:59.000Z

329

NUCLEAR REACTOR  

DOE Patents (OSTI)

A nuclear reactor incorporating seed and blanket assemblies is designed. Means are provided for obtaining samples of the coolant from the blanket assemblies and for varying the flow of coolant through the blanket assemblies. (AEC)

Sherman, J.; Sharbaugh, J.E.; Fauth, W.L. Jr.; Palladino, N.J.; DeHuff, P.G.

1962-10-23T23:59:59.000Z

330

United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support  

SciTech Connect

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

Douglas Morrell

2011-03-01T23:59:59.000Z

331

This document was downloaded on May 22, 2013 at 14:29:32 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

- graduate School in effect, a naval univer- sity, unified in policies, procedures and ob- jectives. In 1973;GENERAL INFORMATION ADMISSIONS PROCEDURES U.S. NAVAL OFFICERS U.S. Navy officers interested in admis- sion to availability of quotas assigned to each country. The procedures for application are contained in OPNAV

332

This document was downloaded on May 22, 2013 at 14:24:38 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

Organizations 18 Student Council 18 Selection Procedures 19 Naval Officers 19 Other U.S. Military Officers 19 in matters involving curricula, facilities, procedures and policies deemed worthy of attention. The OSAC. SELECTION PROCEDURES NAVAL OFFICERS Selection for the Navy fully funded graduate education program is based

333

This document was downloaded on May 22, 2013 at 14:25:15 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

20 Selection Procedures 20 Naval Officers 20 Other U.S. Military Officers 20 International Military administration. It functions in an advisory capacity in matters involving curricula, facilities, procedures graduate education program. SELECTION PROCEDURES NAVAL OFFICERS Selection for the Navy fully funded

334

This document was downloaded on May 22, 2013 at 14:23:11 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

Center for Executive Education 11 NPS Curricula Summary 13 ADMISSIONS 16 Selection Procedures 16 Naval SELECTION PROCEDURES NAVAL OFFICERS Selection for the Navy fully funded graduate education program is based may be admitted to most curricula. The procedures for application are available from the Security

335

This document was downloaded on May 22, 2013 at 14:27:00 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

15 Faculty Organizations 16 Student Council 17 Admissions 18 Selection Procedures 18 Naval Officers, procedures and policies deemed worthy of attention. The OSAC is comprised of thirty-five student for the Navy's fully funded graduate education program. SELECTION PROCEDURES NAVAL OFFICERS Selection

336

This document was downloaded on May 22, 2013 at 14:23:43 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

Organizations 17 Student Council 17 ADMISSIONS 18 Selection Procedures 18 Naval Officers 18 Other U.S. Military. It functions in an advisory capacity in matters involving curricula, facilities, procedures and policies deemed funded graduate education program. SELECTION PROCEDURES NAVAL OFFICERS Selection for the Navy fully

337

This document was downloaded on May 22, 2013 at 14:24:49 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

Council 18 Selection Procedures 19 Naval Officers 19 Other U.S. Military Officers 19 International involving curricula, facilities, procedures and policies deemed worthy of attention. The OSAC is comprised. SELECTION PROCEDURES NAVAL OFFICERS Selection for the Navy fully funded graduate education program is based

338

This document was downloaded on May 22, 2013 at 14:24:27 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

Selection Procedures 20 Naval Officers 20 Other U.S. Military Officers 20 International Military Officers 20 administration. It functions in an advisory capacity in matters involving curricula, facilities, procedures funded graduate education program. SELECTION PROCEDURES NAVAL OFFICERS Selection for the Navy fully

339

NUCLEAR REACTOR  

DOE Patents (OSTI)

High temperature reactors which are uniquely adapted to serve as the heat source for nuclear pcwered rockets are described. The reactor is comprised essentially of an outer tubular heat resistant casing which provides the main coolant passageway to and away from the reactor core within the casing and in which the working fluid is preferably hydrogen or helium gas which is permitted to vaporize from a liquid storage tank. The reactor core has a generally spherical shape formed entirely of an active material comprised of fissile material and a moderator material which serves as a diluent. The active material is fabricated as a gas permeable porous material and is interlaced in a random manner with very small inter-connecting bores or capillary tubes through which the coolant gas may flow. The entire reactor is divided into successive sections along the direction of the temperature gradient or coolant flow, each section utilizing materials of construction which are most advantageous from a nuclear standpoint and which at the same time can withstand the operating temperature of that particular zone. This design results in a nuclear reactor characterized simultaneously by a minimum critiral size and mass and by the ability to heat a working fluid to an extremely high temperature.

Grebe, J.J.

1959-07-14T23:59:59.000Z

340

Sandia National Laboratories is a multi-program laboratory operated by Sandia Co  

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

Sandia National Laboratories is a multi-program laboratory operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Sandia National Laboratories is a multi-program laboratory operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin company, for the U.S. Department of Energy's National Nuclear Security Administration. With main facilities in Albuquerque, N.M., and Livermore, Calif., Sandia has major R&D responsibilities in national security, energy and environmental technologies and economic competitiveness. Annular Core Research Reactor Facility At the Annular Core Research Reactor (ACRR) facility, Sandia researchers can subject various test objects to a

Note: This page contains sample records for the topic "naval reactors laboratory" 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

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

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

Light Water Reactor Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program The Light Water Reactor Sustainability (LWRS) Program is developing the scientific basis to extend existing nuclear power plant operating life beyond the current 60-year licensing period and ensure long-term reliability, productivity, safety, and security. The program is conducted in collaboration with national laboratories, universities, industry, and international partners. Idaho National Laboratory serves as the Technical Integration Office and coordinates the research and development (R&D) projects in the following pathways: Materials Aging and Degradation Assessment, Advanced Instrumentation, Information, and Control Systems

342

NEW HOT LABORATORY FACILITIES AT LOS ALAMOS  

SciTech Connect

New Hot Laboratory Facilities which support three major research programs directed by the Los Alamos Scientific Laboratory of the University of California are described. For the Nuclear Rocket Propulsion Program, a hot cell addition to the Radio Chemistry Building at Los Alamos will be completed early in 1963, and construction is expected to start soon on the hot cell addition to the Maintenance, Assembly and Disassembly Building at the Nuclear Rocket Development Station in Nevada. Integral hot laboratories are designed in the facilities for the Ultra High Temperature Reactor Experiment and the Fast Reactor Core Test at Los Alamos. (auth)

Wherritt, C.R.; Franke, P.; Field, R.E.; Lyle, A.R.

1962-01-01T23:59:59.000Z

343

Downloads | Argonne National Laboratory  

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

-Energy sources --Renewable energy ---Bioenergy ---Solar energy ---Wind energy --Fossil fuels ---Natural Gas --Hydrogen --Nuclear energy ---Reactors ----Nuclear reactor...

344

NEVIS CYCLOTRON LABORATORY COLUMBIA UNIVERSITY PHYSICS DEPARTMENT  

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

u u NEVIS- 97 'FASTER NEVIS CYCLOTRON LABORATORY COLUMBIA UNIVERSITY PHYSICS DEPARTMENT I rvington-on-Hudson, New York The Parity of the Neutral Pion and the Decay Tr° - 2e + 2e~ N. P. SAMIOS, R. PLANO, A. PRODELL, M. SCHWARTZ and J. STEINBERGER Office of Naval Research Contract Nonr-265(7 2) Atomic Energy Commission Contract AT( 30-l)-1932 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately

345

Research reactors - an overview  

SciTech Connect

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

West, C.D.

1997-03-01T23:59:59.000Z

346

CRAD, Emergency Management - Oak Ridge National Laboratory High Flux  

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

Oak Ridge National Laboratory High Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Emergency Management Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Emergency Management - Oak Ridge National Laboratory High Flux

347

CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope  

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

Oak Ridge National Laboratory High Flux Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope Reactor A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a DOE independent oversight assessment of the Oak Ridge National Laboratory programs for oversight of its contractors. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor

348

Advanced Test Reactor National Scientific User Facility  

Science Conference Proceedings (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

349

NEUTRONIC REACTOR  

DOE Patents (OSTI)

This patent relates to neutronic reactors of the heterogeneous water cooled type, and in particular to a fuel element charging and discharging means therefor. In the embodiment illustrated the reactor contains horizontal, parallel coolant tubes in which the fuel elements are disposed. A loading cart containing a magnzine for holding a plurality of fuel elements operates along the face of the reactor at the inlet ends of the coolant tubes. The loading cart is equipped with a ram device for feeding fuel elements from the magazine through the inlot ends of the coolant tubes. Operating along the face adjacent the discharge ends of the tubes there is provided another cart means adapted to receive irradiated fuel elements as they are forced out of the discharge ends of the coolant tubes by the incoming new fuel elements. This cart is equipped with a tank coataining a coolant, such as water, into which the fuel elements fall, and a hydraulically operated plunger to hold the end of the fuel element being discharged. This inveation provides an apparatus whereby the fuel elements may be loaded into the reactor, irradiated therein, and unloaded from the reactor without stopping the fiow of the coolant and without danger to the operating personnel.

Ohlinger, L.A.; Wigner, E.P.; Weinberg, A.M.; Young, G.J.

1958-09-01T23:59:59.000Z

350

Brookhaven Medical Research Reactor  

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

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

351

REACTOR CONTROL  

DOE Patents (OSTI)

A control system employed with a high pressure gas cooled reactor in which a control rod is positioned for upward and downward movement into the neutron field from a position beneath the reactor is described. The control rod is positioned by a coupled piston cylinder releasably coupled to a power drive means and the pressurized coolant is directed against the lower side of the piston. The coolant pressure is offset by a higher fiuid pressure applied to the upper surface of the piston and means are provided for releasing the higher pressure on the upper side of the piston so that the pressure of the coolant drives the piston upwardly, forcing the coupled control rod into the ncutron field of the reactor. (AEC)

Fortescue, P.; Nicoll, D.

1962-04-24T23:59:59.000Z

352

NUCLEAR REACTOR  

DOE Patents (OSTI)

A nuclear reactor of the homogeneous liquid fuel type is described wherein the fissionable isotope is suspended or dissolved in a liquid moderator such as water. The reactor core is comprised essentially of a spherical vessel for containing the reactive composition surrounded by a reflector, preferably of beryllium oxide. The reactive composition may be an ordinary water solution of a soluble salt of uranium, the quantity of fissionable isotope in solution being sufficient to provide a critical mass in the vessel. The liquid fuel is stored in a tank of non-crtttcal geometry below the reactor vessel and outside of the reflector and is passed from the tank to the vessel through a pipe connecting the two by air pressure means. Neutron absorbing control and safety rods are operated within slots in the reflector adjacent to the vessel.

Christy, R.F.

1958-07-15T23:59:59.000Z

353

POWER REACTOR  

DOE Patents (OSTI)

A fast nuclear reactor system ls described for producing power and radioactive isotopes. The reactor core is of the heterogeneous, fluid sealed type comprised of vertically arranged elongated tubular fuel elements having vertical coolant passages. The active portion is surrounded by a neutron reflector and a shield. The system includes pumps and heat exchangers for the primary and secondary coolant circuits. The core, primary coolant pump and primary heat exchanger are disposed within an irapenforate tank which is filled with the primary coolant, in this case a liquid metal such as Na or NaK, to completely submerge these elements. The tank is completely surrounded by a thick walled concrete shield. This reactor system utilizes enriched uranium or plutonium as the fissionable material, uranium or thorium as a diluent and thorium or uranium containing less than 0 7% of the U/sup 235/ isotope as a fertile material.

Zinn, W.H.

1958-07-01T23:59:59.000Z

354

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

355

NEUTRONIC REACTORS  

DOE Patents (OSTI)

A method is presented for loading and unloading rod type fuel elements of a neutronic reactor of the heterogeneous, solld moderator, liquid cooled type. In the embodiment illustrated, the fuel rods are disposed in vertical coolant channels in the reactor core. The fuel rods are loaded and unloaded through the upper openings of the channels which are immersed in the coolant liquid, such as water. Unloading is accomplished by means of a coffer dam assembly having an outer sleeve which is placed in sealing relation around the upper opening. A radiation shield sleeve is disposed in and reciprocable through the coffer dam sleeve. A fuel rod engaging member operates through the axial bore in the radiation shield sleeve to withdraw the fuel rod from its position in the reactor coolant channel into the shield, the shield snd rod then being removed. Loading is accomplished in the reverse procedure.

Wigner, E.P.; Young, G.J.

1958-10-14T23:59:59.000Z

356

PROTEUS - Simulation Toolset for Reactor Physics and Fuel Cycle Analysis  

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

Simulation Toolset for Simulation Toolset for Reactor Physics and Fuel Cycle Analysis PROTEUS Faster and more accurate neutronics calculations enable optimum reactor design... Argonne National Laboratory's powerful reactor physics toolset, PROTEUS, empowers users to create optimal reactor designs quickly, reliably and accurately. ...Reducing costs for designers of fast spectrum reactors. PROTEUS' long history of validation provides confidence in predictive simulations Argonne's simulation tools have more than 30 years of validation history against numerous experiments and measurements. The tools within PROTEUS work together, using the same interface files for easier integration of calculations. Multi-group Fast Reactor Cross Section Processing: MC 2 -3 No other fast spectrum multigroup generation tool

357

NUCLEAR REACTOR  

DOE Patents (OSTI)

This patent covers a power-producing nuclear reactor in which fuel rods of slightly enriched U are moderated by heavy water and cooled by liquid metal. The fuel rods arranged parallel to one another in a circle are contained in a large outer closed-end conduit that extends into a tank containing the heavy water. Liquid metal is introduced into the large conduit by a small inner conduit that extends within the circle of fuel rods to a point near the lower closed end of the outer conduit. (AEC) Production Reactors

Young, G.

1963-01-01T23:59:59.000Z

358

NEUTRONIC REACTOR  

DOE Patents (OSTI)

A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

Wigner, E.P.; Weinberg, A.W.; Young, G.J.

1958-04-15T23:59:59.000Z

359

Power Burst Facility (PBF) Reactor Reactor Decommissioning  

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

Reactor Decommissioning Click here to view Click here to view Reactor Decommissioning Click on an image to enlarge A crane removes the reactor vessel from the Power Burst Facility...

360

Purdue Hydrogen Systems Laboratory  

DOE Green Energy (OSTI)

The Hydrogen Systems Laboratory in a unique partnership between Purdue University's main campus in West Lafayette and the Calumet campus was established and its capabilities were enhanced towards technology demonstrators. The laboratory engaged in basic research in hydrogen production and storage and initiated engineering systems research with performance goals established as per the USDOE Hydrogen, Fuel Cells, and Infrastructure Technologies Program. In the chemical storage and recycling part of the project, we worked towards maximum recycling yield via novel chemical selection and novel recycling pathways. With the basic potential of a large hydrogen yield from AB, we used it as an example chemical but have also discovered its limitations. Further, we discovered alternate storage chemicals that appear to have advantages over AB. We improved the slurry hydrolysis approach by using advanced slurry/solution mixing techniques. We demonstrated vehicle scale aqueous and non-aqueous slurry reactors to address various engineering issues in on-board chemical hydrogen storage systems. We measured the thermal properties of raw and spent AB. Further, we conducted experiments to determine reaction mechanisms and kinetics of hydrothermolysis in hydride-rich solutions and slurries. We also developed a continuous flow reactor and a laboratory scale fuel cell power generation system. The biological hydrogen production work summarized as Task 4.0 below, included investigating optimal hydrogen production cultures for different substrates, reducing the water content in the substrate, and integrating results from vacuum tube solar collector based pre and post processing tests into an enhanced energy system model. An automated testing device was used to finalize optimal hydrogen production conditions using statistical procedures. A 3 L commercial fermentor (New Brunswick, BioFlo 115) was used to finalize testing of larger samples and to consider issues related to scale up. Efforts continued to explore existing catalytic methods involving nano catalysts for capture of CO2 from the fermentation process.

Jay P Gore; Robert Kramer; Timothee L Pourpoint; P. V. Ramachandran; Arvind Varma; Yuan Zheng

2011-12-28T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Heat Transfer Laboratory of the Savannah River Laboratory  

SciTech Connect

The Heat Transfer Laboratory, recently- constructed adjacent to the main Savannah River Laboratory building, was designed to mock up nuclear heating and cooling of reactor components under a variety- of conditions. Nuclear heating is simulated by electrical resistance heating of test sections with a 3 MW directcurrent power supply. Cooling is provided by water. Three test stations (A, B, and C) are available for testing full-size fuel assemblies, measuring flow instabilities, and for measuring burnout heat fluxes. Safeguards provided in the design of the facility and conservative operating procedures minimize or elimnate potential hazards. (auth)

Knoebel, D.H.; Harris, S.D.

1973-10-01T23:59:59.000Z

362

CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux  

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

High High Flux Isotope Reactor CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Radiation Protection Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

363

CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux  

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

Reactor Reactor CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February, 2007 assessment of the Conduct of Operations Program in preparation for restart of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope

364

FEMP ESPC Success Story - U.S. Naval Station, Guantanamo Bay, Cuba  

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

a m a m ESPC Success Stories Environmental Stewardship and Cost Savings These photographs chronicle the installation of the wind turbines at John Paul Jones Hill, Guantanamo Bay. The four wind turbine towers are about 185 feet high. The blade lengths are 90 feet. The top of the blades are about 275 feet off the g round. The blades rotate at a maximum of 22 RPM, or a rotation every three seconds. This translates to a blade tip speed of 140 mph. During construction there were as many as 20 workers on the project. However, operating the wind turbines will only take one part-time staff-person who will check on them daily. Photos courtesy of: Jeffrey M. Johnston, Public Works Officer, Guantanamo Bay; Paul DelSignore, NFESC; Daniel Ingold, NORESCO. U.S. NAVAL STATION

365

DOE - Office of Legacy Management -- Naval Supply Depot AEC Warehouse - NY  

Office of Legacy Management (LM)

Supply Depot AEC Warehouse - Supply Depot AEC Warehouse - NY 36 FUSRAP Considered Sites Site: NAVAL SUPPLY DEPOT, AEC WAREHOUSE (NY.36) Eliminated from further consideration under FUSRAP - Referred to DOD Designated Name: Not Designated Alternate Name: None Location: Building 546 , Scotia , New York NY.36-1 Evaluation Year: 1987 NY.36-1 Site Operations: This facility served as a storage and transshipment point for feed materials between the Hanford and commercial metal fabricators in the northeastern states. NY.36-1 NY.36-2 NY.36-3 Site Disposition: Eliminated - Referred to DOD NY.36-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium, Thorium Metals NY.36-1 NY.36-2 NY.36-3 Radiological Survey(s): None Indicated Site Status: Eliminated from further consideration under FUSRAP - Referred to DOD NY.36-1

366

Rocky Mountain Oilfield Testing Center RMOTC at the Naval Petroleum Reserve No. 3  

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

& Renewable Energy Scoping Meeting & Renewable Energy Scoping Meeting March 26, 2004 2 2 RMOTC The Rocky Mountain Oilfield Testing Center (RMOTC), is an operating oil field focusing on environmentally-balanced energy technologies and alternatives, and is the premiere energy testing and demonstration field in the nation. 3 3 * the opportunity to explore environmentally- balanced solutions to the nation's energy issues * opportunities to develop, demonstrate, and evaluate a variety of energy related technologies * a chance to collaborate with top professionals in the energy, environmental technology, and engineering fields * shared industry knowledge through technology transfer via reports, journal articles, and presentations Located within the Naval Petroleum Reserve No. 3 (NPR-3) near Casper, Wyoming, RMOTC offers:

367

Department of Energy, Office of Naval Petroleum & Oil Shale Reserves  

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

Request for Records Disposition Authority Leave Blank (NARA Use Only) (See Instructions on reverse) Job Number I / {£. 0- _~ To. National Archives and Records Administration (NIR) NI-'-r 3 7- 6 6 J Washington, DC 20408 Date Received 1 From (Agencyor establishment) Department of Energy Notification to Agency 2 MajorSubdivrsion In accordance with the provisions of 44 Assistant Secretary for Fossil Energy USC 3303a. the disposition request. In- cluding amendments. ISapproved except for 3 Minorsubcrvrsron Items that may be marked "disposrtron not Office of Naval Petroleum & Oil Shale Reserves approved" or "withdrawn" In column 10 4 Nameof Personwith whom to confer 5 Telephone (Includearea code) [ Pamela Gentel 301-903-1856 6 Agency Certification

368

Major General Harold Holesinger The Adjutant General Illinois Kilitary and Naval Dept.  

Office of Legacy Management (LM)

General Harold Holesinger General Harold Holesinger The Adjutant General Illinois Kilitary and Naval Dept. 1301 North MacArthur Boulevard Springfield, Illinois 62702-2399 Dear General Holesinger: I am enclosing a copy of the radiological survey report for the National Guard Armory, Chicago, Illinois. Although the data ncted in the report indicate levels of radioactivity in excess of current guidelines, the radioactive residues presently there do not pose a health hazard provided they were not disturbed in the past and will not be disturbed in the future; i.e., no excavation, building, or construction that would disturb the areas in which contamination was found. Based on these data and on an authority record review, the National Guard Armory property is being authorized for remedial action and will be

369

Rocky Mountain Oilfield Testing Center RMOTC at the Naval Petroleum Reserve No. 3  

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

OILFIELD TESTING OILFIELD TESTING OILFIELD TESTING CENTER CENTER 2 2 HISTORY OF TEAPOT DOME Mark Milliken 3 3 TEAPOT DOME LOCATION 4 4 Salt Creek 670 MMBBLS 722 BCF Teapot Dome 27 MMBBLS 57 BCF N P R - 3 Cumulative Production 5 5 The Great White Fleet December 1907 - February 1909 6 6 THE END OF COAL-FIRED SHIPS * 2-week cruising time. * Labor and time intensive cleaning and reloading. * At the mercy of foreign countries for coal supply. * 1912: All battleships will be oil-powered. Great White Fleet 7 7 NAVAL PETROLEUM RESERVES ARE BORN * 1908: Dr. Otis Smith, USGS Director, recommends DOI retain oil lands for fuel reserve for Navy. * 1909: Taft withdraws 3,000,000 acres in Wyoming and California. * 1910: Concern over the President's authority to withdraw lands, so Congress passed the Pickett Act. * 1910: Taft issues a 2nd land withdrawal executive

370

Quality assurance assessment of new efficient lighting systems for naval ships. Final report. Revision  

SciTech Connect

Ballasts and lamps, which have been selected to replace existing lamp/ballast systems based on improved performance, were tested to determine if they meet standard Naval MIL specifications. Fifty ballasts manufactured by Advance Transformer Corporation and Universal Manufacturing Corporation and 100 lamps manufactured by GTE were tested to determine their quality assurance and durability. These components met all of the MIL specifications that lamp/ballast systems in use must meet. These new systems have an improved system efficacy, 62 lumens per watt, and lower third harmonics, which will reduce the need for generating capacity for lighting on ships. An addendum to the original study describes the assessment of the performance of the advanced ballast system with a new F-17 fluorescent lamp. The results indicate the system performs reliably and shows increased efficacy. This new lamp/ballast system reduces the harmonic content to within Navy limits, and improves the power factor, resulting in a 50% reduction in line current.

Verderber, R.R.; Morse, O.; Dumm, C.

1984-12-01T23:59:59.000Z

371

Independent Activity Report, Sandia National Laboratories - March 2013 |  

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

Sandia National Laboratories - March Sandia National Laboratories - March 2013 Independent Activity Report, Sandia National Laboratories - March 2013 March 2013 Operational Awareness Oversight of Sandia National Laboratories [HIAR SNL-2013-03-18] The purpose of this Office of Health, Safety and Security (HSS) Independent Oversight activity was to perform an operational awareness site visit to Sandia National Laboratories (SNL) to discuss Annular Core Research Reactor (ACRR) issues and improvement plan. SNL management also briefed Independent Oversight on engineered safety implementation. Independent Activity Report, Sandia National Laboratories - March 2013 More Documents & Publications Independent Activity Report, Sandia National Laboratories - April 2012 Independent Oversight Targeted Review, Sandia National Laboratories -

372

NEUTRONIC REACTOR  

DOE Patents (OSTI)

A reactor is described comprising a plurality of horizontal trays containing a solution of a fissionable material, the trays being sleeved on a vertical tube which contains a vertically-reciprocable control rod, a gas-tight chamber enclosing the trays, and means for conducting vaporized moderator from the chamber and for replacing vaporized moderator in the trays. (AEC)

Wigner, E.P.

1962-12-25T23:59:59.000Z

373

Neutronic reactor  

DOE Patents (OSTI)

A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield.

Wende, Charles W. J. (West Chester, PA)

1976-08-17T23:59:59.000Z

374

NEUTRONIC REACTOR  

DOE Patents (OSTI)

BS>A reactor cooled by water, biphenyl, helium, or other fluid with provision made for replacing the fuel rods with the highest plutonium and fission product content without disassembling the entire core and for promptly cooling the rods after their replacement in order to prevent build-up of heat from fission product activity is described.

Creutz, E.C.; Ohlinger, L.A.; Weinberg, A.M.; Wigner, E.P.; Young, G.J.

1959-10-27T23:59:59.000Z

375

NEUTRONIC REACTORS  

DOE Patents (OSTI)

The design of control rods for nuclear reactors are described. In this design the control rod consists essentially of an elongated member constructed in part of a neutron absorbing material and having tube means extending therethrough for conducting a liquid to cool the rod when in use.

Anderson, H.L.

1958-10-01T23:59:59.000Z

376

NUCLEAR REACTOR  

DOE Patents (OSTI)

A nuclear reactor is described that includes spaced vertical fuel elements centrally disposed in a pressure vessel, a mass of graphite particles in the pressure vessel, means for fluidizing the graphite particles, and coolant tubes in the pressure vessel laterally spaced from the fuel elements. (AEC)

Post, R.G.

1963-05-01T23:59:59.000Z

377

NUCLEAR REACTOR  

DOE Patents (OSTI)

This patent relates to a combination useful in a nuclear reactor and is comprised of a casing, a mass of graphite irapregnated with U compounds in the casing, and at least one coolant tube extending through the casing. The coolant tube is spaced from the mass, and He is irtroduced irto the space between the mass and the coolant tube. (AEC)

Starr, C.

1963-01-01T23:59:59.000Z

378

AUTOMATED RADIOLOGICAL MONITORING AT A RUSSIAN MINISTRY OF DEFENCE NAVAL SITE.  

SciTech Connect

The Arctic Military Environmental Cooperation (AMEC) Program is a cooperative effort between the military establishments of the Kingdom of Norway, the Russian Federation, and the US. This paper discusses joint activities conducted over the past year among Norwegian, Russian, and US technical experts on a project to develop, demonstrate and implement automated radiological monitoring at Russian Navy facilities engaged in the dismantlement of nuclear-powered strategic ballistic missile launching submarines. Radiological monitoring is needed at these facilities to help protect workers engaged in the dismantlement program and the public living within the footprint of routine and accidental radiation exposure areas. By providing remote stand-alone monitoring, the Russian Navy will achieve added protection due to the defense-in-depth strategy afforded by local (at the site), regional (Kola) and national-level (Moscow) oversight. The system being implemented at the Polyaminsky Russian Naval Shipyard was developed from a working model tested at the Russian Institute for Nuclear Safety, Moscow, Russia. It includes Russian manufactured terrestrial and underwater gamma detectors, smart controllers for graded sampling, radio-modems for offsite transmission of the data, and a data fusion/display system: The data fusion/display system is derived from the Norwegian Picasso AMEC Environmental Monitoring software package. This computer package allows monitoring personnel to review the real-time and historical status of monitoring at specific sites and objects and to establish new monitoring protocols as required, for example, in an off-normal accident situation. Plans are being developed to implement the use of this system at most RF Naval sites handling spent nuclear fuel.

MOSKOWITZ,P.D.; POMERVILLE,J.; GAVRILOV,S.; KISSELEV,V.; DANIYLAN,V.; BELIKOV,A.; EGORKIN,A.; SOKOLOVSKI,Y.; ENDREGARD,M.; KROSSHAVN,M.; SUNDLING,C.V.; YOKSTAD,H.

2001-02-25T23:59:59.000Z

379

AUTOMATED RADIOLOGICAL MONITORING AT A RUSSIAN MINISTRY OF DEFENSE NAVAL SITE.  

SciTech Connect

The Arctic Military Environmental Cooperation (AMEC) Program is a cooperative effort between the military establishments of the Kingdom of Norway, the Russian Federation, and the US. This paper discusses joint activities conducted over the past year among Norwegian, Russian, and US technical experts on a project to develop, demonstrate and implement automated radiological monitoring at Russian Navy facilities engaged in the dismantlement of nuclear-powered strategic ballistic missile launching submarines. Radiological monitoring is needed at these facilities to help protect workers engaged in the dismantlement program and the public living within the footprint of routine and accidental radiation exposure areas. By providing remote stand-alone monitoring, the Russian Navy will achieve added protection due to the defense-in-depth strategy afforded by local (at the site), regional (Kola) and national-level (Moscow) oversight. The system being implemented at the Polyaminsky Russian Naval Shipyard was developed from a working model tested at the Russian Institute for Nuclear Safety, Moscow, Russia. It includes Russian manufactured terrestrial and underwater gamma detectors, smart controllers for graded sampling, radio-modems for offsite transmission of the data, and a data fusion/display system: The data fusion/display system is derived from the Norwegian Picasso AMEC Environmental Monitoring software package. This computer package allows monitoring personnel to review the real-time and historical status of monitoring at specific sites and objects and to establish new monitoring protocols as required, for example, in an off-normal accident situation. Plans are being developed to implement the use of this system at most RF Naval sites handling spent nuclear fuel.

MOSKOWITZ,P.D.; POMERVILLE,J.; GAVRILOV,S.; KISSELEV,V.; DANIYLAN,V.; BELIKOV,A.; EGORKIN,A.; SOKOLOVSKI,Y.; ENDREGARD,M.; KROSSHAVN,M.; SUNDLING,C.V.; YOKSTAD,H.

2001-02-25T23:59:59.000Z

380

Press Releases | Argonne National Laboratory  

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

& simulation ---Nuclear fuel cycle ----Geology & disposal ---Reactors ----Nuclear reactor safety ----Nuclear reactor materials ----Nuclear system technologies & diagnostics...

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Feature Stories | Argonne National Laboratory  

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

& simulation ---Nuclear fuel cycle ----Geology & disposal ---Reactors ----Nuclear reactor safety ----Nuclear reactor materials ----Nuclear system technologies & diagnostics...

382

Science Highlights | Argonne National Laboratory  

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

& simulation ---Nuclear fuel cycle ----Geology & disposal ---Reactors ----Nuclear reactor safety ----Nuclear reactor materials ----Nuclear system technologies & diagnostics...

383

Success Stories | Argonne National Laboratory  

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

& simulation ---Nuclear fuel cycle ----Geology & disposal ---Reactors ----Nuclear reactor safety ----Nuclear reactor materials ----Nuclear system technologies & diagnostics...

384

Employee Spotlights | Argonne National Laboratory  

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

& simulation ---Nuclear fuel cycle ----Geology & disposal ---Reactors ----Nuclear reactor safety ----Nuclear reactor materials ----Nuclear system technologies & diagnostics...

385

CRAD, Environmental Protection - Oak Ridge National Laboratory High Flux  

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

Environmental Protection - Oak Ridge National Laboratory High Environmental Protection - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Environmental Protection - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Environmental Compliance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Environmental Protection - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications

386

CRAD, Configuration Management - Oak Ridge National Laboratory High Flux  

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

Configuration Management - Oak Ridge National Laboratory High Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Configuration Management Program in preparation for restart of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications

387

CRAD, Emergency Management - Oak Ridge National Laboratory High Flux  

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

Oak Ridge National Laboratory High Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Emergency Management Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Emergency Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR

388

Advanced Safeguards Approaches for New Fast Reactors  

SciTech Connect

This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.

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

2007-12-15T23:59:59.000Z

389

Laboratory Access | Sample Preparation Laboratories  

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

Access Access Planning Ahead Planning Ahead Please complete the Beam Time Request (BTR) and Support Request forms thourgh the User Portal. Thorough chemical and sample information must be included in your BTR. Support Request forms include a list of collaborators that require laboratory access and your group's laboratory equipment requests. Researcher safety is taken seriously at SLAC. Please remember that radioactive materials, nanomaterials, and biohazardous materials have additional safety requirements. Refer to the SSRL or LCLS Safety Offices for further guidance. Upon Arrival Upon Arrival Once you arrive you must complete training and access forms before accessing the Sample Preparation Laboratories (SPL). All Sample Prep Lab doors are locked with access key codes. Once your SPL

390

REACTOR UNLOADING  

DOE Patents (OSTI)

This patent is related to gas cooled reactors wherein the fuel elements are disposed in vertical channels extending through the reactor core, the cooling gas passing through the channels from the bottom to the top of the core. The invention is a means for unloading the fuel elements from the core and comprises dump values in the form of flat cars mounted on wheels at the bottom of the core structure which support vertical stacks of fuel elements. When the flat cars are moved, either manually or automatically, for normal unloading purposes, or due to a rapid rise in the reproduction ratio within the core, the fuel elements are permtted to fall by gravity out of the core structure thereby reducing the reproduction ratio or stopping the reaction as desired.

Leverett, M.C.

1958-02-18T23:59:59.000Z

391

NUCLEAR REACTOR  

DOE Patents (OSTI)

A neuclear reactor is described of the heterogeneous type and employing replaceable tubular fuel elements and heavy water as a coolant and moderator. A pluraltty of fuel tubesa having their axes parallel, extend through a tank type pressure vessel which contatns the liquid moderator. The fuel elements are disposed within the fuel tubes in the reaetive portion of the pressure vessel during normal operation and the fuel tubes have removable plug members at each end to permit charging and discharging of the fuel elements. The fuel elements are cylindrical strands of jacketed fissionable material having helical exterior ribs. A bundle of fuel elements are held within each fuel tube with their longitudinal axes parallel, the ribs serving to space them apart along their lengths. Coolant liquid is circulated through the fuel tubes between the spaced fuel elements. Suitable control rod and monitoring means are provided for controlling the reactor.

Treshow, M.

1958-08-19T23:59:59.000Z

392

Advanced reactor development: The LMR integral fast reactor program at Argonne  

SciTech Connect

Reactor technology for the 21st Century must develop with characteristics that can now be seen to be important for the future, quite different from the things when the fundamental materials and design choices for present reactors were made in the 1950s. Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 3 figs.

Till, C.E.

1990-01-01T23:59:59.000Z

393

Neutronic reactor  

DOE Patents (OSTI)

A graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels.

Lewis, Warren R. (Richland, WA)

1978-05-30T23:59:59.000Z

394

NUCLEAR REACTORS  

DOE Patents (OSTI)

An active portion assembly for a fast neutron reactor is described wherein physical distortions resulting in adverse changes in the volume-to-mass ratio are minimized. A radially expandable locking device is disposed within a cylindrical tube within each fuel subassembly within the active portion assembly, and clamping devices expandable toward the center of the active portion assembly are disposed around the periphery thereof. (AEC)

Koch, L.J.; Rice, R.E. Jr.; Denst, A.A.; Rogers, A.J.; Novick, M.

1961-12-01T23:59:59.000Z

395

"The Fourth Dimension of Naval Tactics": The U.S. Navy and Public Relations, 1919-1939  

E-Print Network (OSTI)

Prior to 1917, the United States Navy only utilized public relations techniques during times of war or to attract recruits into naval service. Following World I, the Navy confronted several daunting problems, including the postwar demobilization of naval assets, the proposed creation of an independent air service, and a public desire for naval arms limitation which many officers believed would endanger the Navy's ability to fulfill its missions. These issues threatened the generous support that the Navy had received from Congress for a quarter of a century, and also hampered the service's attempts to incorporate new weapons systems into its arsenal and recruit high-quality manpower. In response to these challenges, the Navy developed a peacetime public relations capability during the interwar period, despite the fact that many senior naval officials placed a low priority on public relations. Their attitude led subordinates in different parts of the Navy Department to perform public relations tasks despite lacking official orders to carry out such work. Such efforts were haphazard, redundant, handicapped by tradition, and dependent largely upon individual initiative. To augment its meager capabilities, the Navy relied upon external groups, such as the Navy League, to lobby the public for naval expansion. The service also developed formal and informal ties to the mass media, particularly the rapidly expanding motion picture industry. These disparate elements attempted to convince the public that the Navy was a haven for morally upright masculine behavior, a service able to integrate aircraft and submarines into its force structure and keep their operators safe, and a vital national asset with value beyond basic national defense. During the interwar period, the Navy expanded and reorganized the ways in which it courted public opinion. By forging ties with motion picture studios, radio broadcasters, and the print media, it was able to improve the image of the service, attract high quality recruits, and gained the public support for its drive to gain the resources needed to modernize and expand the fleet. During the same era, naval officials became more adept at minimizing the negative impact of the accidents linked to the development of aviation and submarines. Developments of the era laid the foundation for the institutional development of public relations and enhanced media relations during World War II and in the decades that followed.

Wadle, Ryan David

2011-05-01T23:59:59.000Z

396

REACTOR CONTROL  

DOE Patents (OSTI)

This patent relates to nuclear reactors of the type which utilize elongited rod type fuel elements immersed in a liquid moderator and shows a design whereby control of the chain reaction is obtained by varying the amount of moderator or reflector material. A central tank for containing liquid moderator and fuel elements immersed therein is disposed within a surrounding outer tank providing an annular space between the two tanks. This annular space is filled with liquid moderator which functions as a reflector to reflect neutrons back into the central reactor tank to increase the reproduction ratio. Means are provided for circulating and cooling the moderator material in both tanks and additional means are provided for controlling separately the volume of moderator in each tank, which latter means may be operated automatically by a neutron density monitoring device. The patent also shows an arrangement for controlling the chain reaction by injecting and varying an amount of poisoning material in the moderator used in the reflector portion of the reactor.

Ruano, W.J.

1957-12-10T23:59:59.000Z

397

Graphite Reactor | ornl.gov  

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

Graphite Reactor Graphite Reactor 'In the early, desperate days of World War II, the United States launched the top-secret, top-priority Manhattan Project...' In the early, desperate days of U.S. involvement in World War II, American scientists began to fear that the German discovery of uranium fission in 1939 might enable the Nazis to develop a super bomb. Afraid of losing this crucial race, the United States launched the top-secret, top-priority Manhattan Project. The plan was to create two atomic weapons-one fueled by plutonium, the other by enriched uranium. Hanford, Washington, was selected as the site for plutonium production, but before large reactors could be built there, a pilot plant was necessary to prove the feasibility of scaling up from laboratory experiments. A secluded, rural area near Clinton, Tennessee, was

398

Aerosol Laboratory - Nuclear Engineering Division (Argonne)  

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

Capabilities > Engineering Capabilities > Engineering Experimentation > Aerosol Laboratory Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Aerosol Laboratory The Aerosol Laboratory (AL) houses equipment to measure and record the physical parameters necessary to characterize the formation and transport of aerosols. Bookmark and Share The Aerosol Laboratory (AL) has extensive analytic and experimental capabilities to characterize the formation and transport of aerosols formed from the condensation of vapors. Computer codes have been developed to

399

National Laboratory  

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

Homesteading on the Pajarito Plateau Homesteading on the Pajarito Plateau topic of inaugural lecture at Los Alamos National Laboratory January 4, 2013 Lecture series begins yearlong commemoration of 70th anniversary LOS ALAMOS, NEW MEXICO, Jan. 3, 2013-In commemoration of its 70th anniversary, Los Alamos National Laboratory kicks off a yearlong lecture series on Wednesday, Jan. 9, at 5:30 p.m. with a presentation about homesteading on the Pajarito Plateau at the Bradbury Science Museum, 1350 Central Avenue, Los Alamos. - 2 - The inaugural lecture is based on a book by local writers Dorothy Hoard, Judy Machen and Ellen McGehee about the area's settlement between 1887 and 1942. On hikes across the Pajarito Plateau, Hoard envisioned the Los Alamos area before modern roads and bridges made transportation much easier. The trails she walked

400

Department of Energy National Laboratories  

Idaho National Laboratory SLAC National Accelerator Laboratory Department of Energy National Laboratories. Laboratory or Facility Website ...

Note: This page contains sample records for the topic "naval reactors laboratory" 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

Light Water Reactors Technology Development - Nuclear Reactors  

NLE Websites -- All DOE Office Websites (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

402

This document was downloaded on May 22, 2013 at 14:34:19 Author(s) Naval Postgraduate School (U.S.)  

E-Print Network (OSTI)

to the Naval Auxiliary Air Station to house trans- sonic and supersonic wind tunnels and jet com- bustion pits tunnels and jet com- bustion pits. The third and next building increment is expected to comprise a General

403

Solid State Reactor Final Report  

DOE Green Energy (OSTI)

The Solid State Reactor (SSR) is an advanced reactor concept designed to take advantage of Oak Ridge National Laboratory's (ORNL's) recently developed graphite foam that has enhanced heat transfer characteristics and excellent high-temperature mechanical properties, to provide an inherently safe, self-regulated, source of heat for power and other potential applications. This work was funded by the U.S. Department of Energy's Nuclear Energy Research Initiative (NERI) program (Project No. 99-064) from August 1999 through September 30, 2002. The initial concept of utilizing the graphite foam as a basis for developing an advanced reactor concept envisioned that a suite of reactor configurations and power levels could be developed for several different applications. The initial focus was looking at the reactor as a heat source that was scalable, independent of any heat removal/power conversion process. These applications might include conventional power generation, isotope production and destruction (actinides), and hydrogen production. Having conducted the initial research on the graphite foam and having performed the scoping parametric analyses from neutronics and thermal-hydraulic perspectives, it was necessary to focus on a particular application that would (1) demonstrate the viability of the overall concept and (2) require a reasonably structured design analysis process that would synthesize those important parameters that influence the concept the most as part of a feasible, working reactor system. Thus, the application targeted for this concept was supplying power for remote/harsh environments and a design that was easily deployable, simplistic from an operational standpoint, and utilized the new graphite foam. Specifically, a 500-kW(t) reactor concept was pursued that is naturally load following, inherently safe, optimized via neutronic studies to achieve near-zero reactivity change with burnup, and proliferation resistant. These four major areas of research were undertaken: (1) establishing the design and safety-related basis via neutronic and reactor control assessments with the graphite foam as heat transfer medium; (2) evaluating the thermal performance of the graphite foam for heat removal, reactor stability, reactor operations, and overall core thermal characteristics; (3) characterizing the physical properties of the graphite foam under normal and irradiated conditions to determine any effects on structure, dimensional stability, thermal conductivity, and thermal expansion; and (4) developing a power conversion system design to match the reactor operating parameters.

Mays, G.T.

2004-03-10T23:59:59.000Z

404

Photo of the Week: The Sixth Zero Power Reactor | Department of Energy  

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

The Sixth Zero Power Reactor The Sixth Zero Power Reactor Photo of the Week: The Sixth Zero Power Reactor November 13, 2013 - 4:41pm Addthis In 1958, Argonne National Laboratory began the construction of several zero-power reactors (ZPRs), which are nuclear fission reactors that don't actually generate any power. Scientists developed ZPRs to assess the performance of various reactor core configurations before actually building a full nuclear reactor. A series of ZPRs were built leading up to the construction of the Experimental Breeder Reactor-II, a sodium-cooled fast reactor power plant. In this 1970 photo, an Argonne scientist is loading the matrices of the ZPR-VI reactor prior to its first operation using plutonium fuel. | Photo courtesy of the Department of Energy. In 1958, Argonne National Laboratory began the construction of several

405

Using Net-Zero Energy Projects to Enable Sustainable Economic Redevelopment at the Former Brunswick Air Naval Base  

SciTech Connect

A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites. The Brunswick Naval Air Station is a naval air facility and Environmental Protection Agency (EPA) Super Fund site that is being cleaned up, and closed down. The objective of this report is not only to look at the economics of individual renewable energy technologies, but also to look at the systemic benefits that can be gained when cost-effective renewable energy technologies are integrated with other systems and businesses in a community; thus multiplying the total monetary, employment, and quality-of-life benefits they can provide to a community.

Huffman, S.

2011-10-01T23:59:59.000Z

406

CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February, 2007 assessment of the Conduct of Operations Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications

407

Report to the President on agreements and programs relating to the Naval Petroleum and Oil Shale Reserves  

SciTech Connect

The Department of Energy monitors commercial natural gas production activities along the boundaries of Naval Oil Shale Reserve No. 1 and Naval Oil Shale Reserve No. 3, which are located in Garfield County, Colorado, and were created in the early part of this century to provide a future source of shale oil for the military. In response to the private sector`s drilling of natural gas wells along the south and southwest boundaries of the Reserves, which began in the early 1980`s, the Department developed a Natural Gas Protection Program to protect the Government`s resources from drainage due to the increasing number of commercial gas wells contiguous to Naval Oil Shale Reserve No. 3. This report provides an update of the Gas Protection Program being implemented and the agreements that have been placed in effect since December 19, 1991, and also includes the one communitized well containing Naval Petroleum Reserve No. 3 lands. The Protection Program employs two methods to protect the Government`s resources: (1) sharing with the private sector in the costs and production of wells by entering into ``communitization`` agreements; and (2) drilling wholly-owned Government wells to ``offset`` commercial wells that threaten to drain natural gas from the Reserves. The methods designed to protect the Government`s resources are achieving their objective of abating gas drainage and migration. As a result of the Protection Program, the Department of Energy is able to produce natural gas and either sell its share on the open market or transfer it for use at Government facilities. The Natural Gas Protection Program is a reactive, ongoing program that is continually revised as natural gas transportation constraints, market conditions, and nearby commercial production activities change.

1994-08-01T23:59:59.000Z

408

Nuclear reactor  

DOE Patents (OSTI)

A nuclear reactor in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assmblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters and the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters and the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance.

Pennell, William E. (Greensburg, PA); Rowan, William J. (Monroeville, PA)

1977-01-01T23:59:59.000Z

409

ELECTRONUCLEAR REACTOR  

DOE Patents (OSTI)

An electronuclear reactor is described in which a very high-energy particle accelerator is employed with appropriate target structure to produce an artificially produced material in commercial quantities by nuclear transformations. The principal novelty resides in the combination of an accelerator with a target for converting the accelerator beam to copious quantities of low-energy neutrons for absorption in a lattice of fertile material and moderator. The fertile material of the lattice is converted by neutron absorption reactions to an artificially produced material, e.g., plutonium, where depleted uranium is utilized as the fertile material.

Lawrence, E.O.; McMillan, E.M.; Alvarez, L.W.

1960-04-19T23:59:59.000Z

410

Photocatalytic reactor  

DOE Patents (OSTI)

A photocatalytic reactor 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.

Bischoff, Brian L. (Knoxville, TN); Fain, Douglas E. (Oak Ridge, TN); Stockdale, John A. D. (Knoxville, TN)

1999-01-01T23:59:59.000Z

411

Final sitewide environmental assessment for continued development of Naval Petroleum Reserve No. 3 (NPR-3), Natrona County, Wyoming  

SciTech Connect

The Secretary of Energy is required by law to explore, prospect, conserve, develop, use, and operate the Naval Petroleum and Oil Shale Reserves. The Naval Petroleum Reserves Production Act of 1976 (Public Law 94-258), requires that the Naval Petroleum Reserves be produced at their maximum efficient rate (MER), consistent with sound engineering practices, for a period of six years. To fulfill this mission, DOE is proposing continued development activities which would include the drilling of approximately 250 oil production and injection (gas, water, and steam) wells, the construction of between 25 and 30 miles of associated gas, water, and steam pipelines, the installation of several production and support facilities, and the construction of between 15 and 20 miles of access roads. These drilling and construction estimates include any necessary activities related to the operation of the Rocky Mountain Oilfield Testing Center (RMOTC). The purpose of RMOTC will be to provide facilities and necessary support to government and private industry for testing and evaluating new oilfield and environmental technologies, and to transfer these results to the petroleum industry through seminars and publications. Continued development activities either have no potential to result in adverse environmental impacts or would only result in adverse impacts that could be readily mitigated. The small amounts of disturbed surface area will be reclaimed to its original natural state when production operations terminate. The preparation of an environmental impact statement is not required, and the DOE is issuing this Finding of No Significant Impact (FONSI). 73 refs.

1995-07-01T23:59:59.000Z

412

Ground test facility for nuclear testing of space reactor subsystems  

SciTech Connect

Two major reactor facilities at the INEL have been identified as easily adaptable for supporting the nuclear testing of the SP-100 reactor subsystem. They are the Engineering Test Reactor (ETR) and the Loss of Fluid Test Reactor (LOFT). In addition, there are machine shops, analytical laboratories, hot cells, and the supporting services (fire protection, safety, security, medical, waste management, etc.) necessary to conducting a nuclear test program. This paper presents the conceptual approach for modifying these reactor facilities for the ground engineering test facility for the SP-100 nuclear subsystem. 4 figs.

Quapp, W.J.; Watts, K.D.

1985-01-01T23:59:59.000Z

413

High Flux Beam Reactor | Environmental Restoration Projects | BNL  

NLE Websites -- All DOE Office Websites (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

414

Recovery Act Workers Clear Reactor Shields from Brookhaven Lab | Department  

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

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

415

AN ANALYSIS OF POWER REACTOR FUEL REPROCESSING  

SciTech Connect

This report presents an analysis of the projected economies and processing capacity requirements for a power reactor fuel reprocessing industry based on the recovery of fertile and fissionable materials from presently proposed power reactors within tbe confines of the continental United 8tates for the next five to ten years. An analysis of the present general state of development of a technology required for such an Industry is given. A summary of results of power reactor reprocessing chemical and engineering development at Oak Ridge National Laboratory from July 1955 through December 1956 is given. (auth)

Culler, F.L. Jr.; Blanco, R.E.; Goeller, H.E.; Watson, C.D.

1957-03-27T23:59:59.000Z

416

Laboratory Measurements of Heterogeneous Reactions on Sulfuric Acid Surfaces  

Science Conference Proceedings (OSTI)

Increasing evidence from field, modeling, and laboratory studies suggests that heterogeneous reactions on stratospheric sulfate aerosol particles may contribute to global ozone depiction. Using a Knudsen cell reactor technique, the authors have ...

Leah R. Williams; Jeffrey A. Manion; David M. Golden; Margaret A. Tolbert

1994-07-01T23:59:59.000Z

417

Virtual Laboratories  

E-Print Network (OSTI)

At the frontier of most areas in science, computer simulations play a central role. The traditional division of natural science into experimental and theoretical investigations is now completely outdated. Instead, theory, simulation, and experimentation form three equally essential aspects, each with its own unique flavor and challenges. Yet, education in computational science is still lagging far behind, and the number of text books in this area is minuscule compared to the many text books on theoretical and experimental science. As a result, many researchers still carry out simulations in a haphazard way, without properly setting up the computational equivalent of a well equipped laboratory. The art of creating such a virtual laboratory, while providing proper extensibility and documentation, is still in its infancy. A new approach is described here, Open Knowledge, as an extension of the notion of Open Source software. Besides open source code, manuals, and primers, an open knowledge project provides simulated dialogues between code developers, thus sharing not only the code, but also the motivations behind the code.

Piet Hut

2006-10-07T23:59:59.000Z

418

Distributed Energy Resources at Naval Base Ventura County Building1512: A Sensitivity Analysis  

Science Conference Proceedings (OSTI)

This report is the second of a two-part study by BerkeleyLab of a DER (distributed energy resources) system at Navy Base VenturaCounty (NBVC). First, a preliminary assessment ofthe cost effectivenessof distributed energy resources at Naval Base Ventura County (NBVC)Building 1512 was conducted in response to the base s request for designassistance to the Federal Energy Management Program (Bailey and Marnay,2004). That report contains a detailed description of the site and theDER-CAM (Consumer Adoption Model) parameters used. This second reportcontains sensitivity analyses of key parameters in the DER system modelof Building 1512 at NBVC and additionally considers the potential forabsorption-powered refrigeration.The prior analysis found that under thecurrent tariffs, and given assumptions about the performance andstructure of building energy loads and available generating technologycharacteristics, installing a 600 kW DER system with absorption coolingand recovery heat capabilities could deliver cost savings of about 14percent, worth $55,000 per year. However, under current conditions, thisstudy also suggested that significant savings could be obtained ifBuilding 1512 changed from its current direct access contract to a SCETOU-8 (Southern California Edison time of use tariff number 8) ratewithout installing a DER system. Evaluated on this tariff, the potentialsavings from installation of a DER system would be about 4 percent of thetotal bill, or $16,000 per year.

Bailey, Owen C.; Marnay, Chris

2005-06-05T23:59:59.000Z

419

Oil shale resources of the Naval Oil Shale Reserve No. 1, Colorado  

SciTech Connect

The resource of potential oil represented by Green River Formation oil shale on Naval Oil Shale Reserve No. 1 (NOSR No. 1) in the southeast corner of Colorado's Piceance Creek Basin is evaluated in detail. NOSR No. 1 is the site of intensive long-term oil-shale development studies and is the source of innumerable oil-shale samples for all manner of testing. A brief history of these studies is presented. This oil-shale resource is defined from oil-yield assay data on 33 cores plotted as histograms and correlated into cross sections. Contour maps of thickness, richness and oil resource in place are presented for the Mahogany Zone, the rich zone in the Mahogany zone, and for 2 units beneath and 5 units above the Mahogany zone. Total oil shale resource on NOSR No. 1 is 20.4 billion barrels of which 17.4 billion barrels are particularly suitable for development by vertical modified in-place processes. A previously unknown Mahogany zone outcrop providing much additional development access is described. Now under sole control of the US Department of Energy (DOE), NOSR No. 1 offers DOE a unique site for oil shale testing and development.

Smith, J.W.; Beard, T.N.; Trudell, L.G.

1979-06-01T23:59:59.000Z

420

Laboratory Activities  

Science Conference Proceedings (OSTI)

This chapter summarizes the laboratory activities performed by PNNL’s Vadose Zone Characterization Project in support of the Tank Farm Vadose Zone Program, led by CH2M HILL Hanford Group, Inc. The results of these studies are contained in numerous reports (Lindenmeier et al. 2002; Serne et al. 2002a, 2002b, 2002c, 2002d, 2002e; Lindenmeier et al. 2003; Serne et al. 2004a, 2004b; Brown et al. 2005, 2006a, 2007; Serne et al. 2007) and have generated much of the data reported in Chapter 22 (Geochemistry-Contaminant Movement), Appendix G (Geochemistry-Contaminant Movement), and Cantrell et al. (2007, SST WMA Geochemistry Data Package – in preparation). Sediment samples and characterization results from PNNL’s Vadose Zone Characterization Project are also shared with other science and technology (S&T) research projects, such as those summarized in Chapter 12 (Associated Science Activities).

Brown, Christopher F.; Serne, R. Jeffrey

2008-01-17T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

CONTROL MEANS FOR REACTOR  

DOE Patents (OSTI)

An apparatus for controlling a nuclear reactor includes a tank just below the reactor, tubes extending from the tank into the reactor, and a thermally expansible liquid neutron absorbent material in the tank. The liquid in the tank is exposed to a beam of neutrons from the reactor which heats the liquid causing it to expand into the reactor when the neutron flux in the reactor rises above a predetermincd danger point. Boron triamine may be used for this purpose.

Manley, J.H.

1961-06-27T23:59:59.000Z

422

Transpiring wall supercritical water oxidation test reactor design report  

Science Conference Proceedings (OSTI)

Sandia National Laboratories is working with GenCorp, Aerojet and Foster Wheeler Development Corporation to develop a transpiring wall supercritical water oxidation reactor. The transpiring wall reactor promises to mitigate problems of salt deposition and corrosion by forming a protective boundary layer of pure supercritical water. A laboratory scale test reactor has been assembled to demonstrate the concept. A 1/4 scale transpiring wall reactor was designed and fabricated by Aerojet using their platelet technology. Sandia`s Engineering Evaluation Reactor serves as a test bed to supply, pressurize and heat the waste; collect, measure and analyze the effluent; and control operation of the system. This report describes the design, test capabilities, and operation of this versatile and unique test system with the transpiring wall reactor.

Haroldsen, B.L.; Ariizumi, D.Y.; Mills, B.E.; Brown, B.G. [Sandia National Labs., Livermore, CA (United States). Engineering for Transportation and Environment Dept.; Rousar, D.C. [GenCorp Aerojet, Sacramento, CA (United States)

1996-02-01T23:59:59.000Z

423

Nuclear Reactor Accidents  

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

Reactor Accidents The accidents at the Three Mile Island (TMI) and Chernobyl nuclear reactors have triggered particularly intense concern about radiation hazards. The TMI accident,...

424

Production capabilities in US nuclear reactors for medical radioisotopes  

SciTech Connect

The availability of reactor-produced radioisotopes in the United States for use in medical research and nuclear medicine has traditionally depended on facilities which are an integral part of the US national laboratories and a few reactors at universities. One exception is the reactor in Sterling Forest, New York, originally operated as part of the Cintichem (Union Carbide) system, which is currently in the process of permanent shutdown. Since there are no industry-run reactors in the US, the national laboratories and universities thus play a critical role in providing reactor-produced radioisotopes for medical research and clinical use. The goal of this survey is to provide a comprehensive summary of these production capabilities. With the temporary shutdown of the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) in November 1986, the radioisotopes required for DOE-supported radionuclide generators were made available at the Brookhaven National Laboratory (BNL) High Flux Beam Reactor (HFBR). In March 1988, however, the HFBR was temporarily shut down which forced investigators to look at other reactors for production of the radioisotopes. During this period the Missouri University Research Reactor (MURR) played an important role in providing these services. The HFIR resumed routine operation in July 1990 at 85 MW power, and the HFBR resumed operation in June 1991, at 30 MW power. At the time of the HFBR shutdown, there was no available comprehensive overview which could provide information on status of the reactors operating in the US and their capabilities for radioisotope production. The obvious need for a useful overview was thus the impetus for preparing this survey, which would provide an up-to-date summary of those reactors available in the US at both the DOE-funded national laboratories and at US universities where service irradiations are currently or expected to be conducted.

Mirzadeh, S.; Callahan, A.P.; Knapp, F.F. Jr. [Oak Ridge National Lab., TN (United States); Schenter, R.E. [Westinghouse Hanford Co., Richland, WA (United States)

1992-11-01T23:59:59.000Z

425

NEUTRONIC REACTOR  

DOE Patents (OSTI)

A power plant is described comprising a turbine and employing round cylindrical fuel rods formed of BeO and UO/sub 2/ and stacks of hexagonal moderator blocks of BeO provided with passages that loosely receive the fuel rods so that coolant may flow through the passages over the fuels to remove heat. The coolant may be helium or steam and fiows through at least one more heat exchanger for producing vapor from a body of fluid separate from the coolant, which fluid is to drive the turbine for generating electricity. By this arrangement the turbine and directly associated parts are free of particles and radiations emanating from the reactor. (AEC)

Daniels, F.

1962-12-18T23:59:59.000Z

426

Savannah River Laboratory monthly report, February 1992  

Science Conference Proceedings (OSTI)

This report is a progress report for the Savannah River Laboratory for the month of February 1992. The progress and activities in six categories were described in the report. The categories are reactor, tritium, separations, environmental, waste management, and general. Each category described numerous and varied activities. Some examples of these activities described are such things as radiation monitoring, maintenance, modifications, and remedial action.

Ferrell, J.M. [comp.; Ice, L.W. [ed.

1992-02-01T23:59:59.000Z

427

CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High  

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

Oak Ridge National Laboratory Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Occupational Safety and Health Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High

428

Department of Energy Designates the Idaho National Laboratory Advanced Test  

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

Designates the Idaho National Laboratory Designates the Idaho National Laboratory Advanced Test Reactor as a National Scientific User Facility Department of Energy Designates the Idaho National Laboratory Advanced Test Reactor as a National Scientific User Facility April 23, 2007 - 12:36pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today designated the Idaho National Laboratory's (INL) Advanced Test Reactor (ATR) as a National Scientific User Facility. Establishing the ATR as a National Scientific User Facility will help assert U.S. leadership in nuclear science and technology, and will attract new users - universities, laboratories and industry - to conduct research at the ATR. This facility will support basic and applied nuclear research and development (R&D), furthering

429

CRAD, Configuration Management - Oak Ridge National Laboratory High Flux  

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

Oak Ridge National Laboratory High Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Configuration Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007, A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Configuration Managment Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Configuration Management - Oak Ridge National Laboratory High Flux

430

CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope  

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

Fire Protection - Oak Ridge National Laboratory High Flux Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor February 2006 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2006 Commencement of Operations assessment of the Fire Protection program at the Idaho National Laboratory, Idaho Accelerated Retrieval Project Phase II. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications

431

CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High  

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

Occupational Safety & Health - Oak Ridge National Laboratory Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Industrial Safety and Hygiene Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Occupational Safety & Health - Oak Ridge National Laboratory High

432

Strategic Laboratory Leadership Program | Argonne National Laboratory  

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

Erik Gottschalk (F); Devin Hodge (A); Jeff Chamberlain (A); Brad Ullrick (A); Bill Rainey (J). Image courtesy of Argonne National Laboratory. Strategic Laboratory Leadership...

433

Independent Activity Report, Sandia National Laboratories - March 2013 |  

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

March March 2013 Independent Activity Report, Sandia National Laboratories - March 2013 March 2013 Operational Awareness Oversight of Sandia National Laboratories [HIAR SNL-2013-03-18] The purpose of this Office of Health, Safety and Security (HSS) Independent Oversight activity was to perform an operational awareness site visit to Sandia National Laboratories (SNL) to discuss Annular Core Research Reactor (ACRR) issues and improvement plan. SNL management also briefed Independent Oversight on engineered safety implementation. Independent Activity Report, Sandia National Laboratories - March 2013 More Documents & Publications Independent Activity Report, Sandia National Laboratories - April 2012 Independent Oversight Targeted Review, Sandia National Laboratories -

434

Pressurized Water Reactor Secondary Water Chemistry Guidelines – Revision 6  

Science Conference Proceedings (OSTI)

State-of-the-art water chemistry programs reduce equipment corrosion and enhance steam generator reliability. A committee of industry experts prepared these revised "Pressurized Water Reactor Secondary Water Chemistry Guidelines" to incorporate the latest field and laboratory data on secondary system corrosion and performance issues. Pressurized water reactor (PWR) operators can use these guidelines to update their secondary water chemistry programs.

2004-12-13T23:59:59.000Z

435

PRELIMINARY HAZARD SUMMARY REPORT ON THE BOILING EXPERIMENTAL REACTOR (BER)  

SciTech Connect

A preliminary evaluation of the hazards associated with a 20-Mw boiling reactor for the purpose of determining site requirements is presented. The Boiling Experimental Reactor design, safety features, and performance are given and the surroundings of the site at Argonne National Laboratory are described. (T.R.H.)

West, J.M.; Anderson, C.A.; Dietrich, J.R.; Harrer, J.M.; Jameson, A.S.; Untermyer, S.

1954-05-01T23:59:59.000Z

436

Reactor and method of operation  

DOE Patents (OSTI)

A nuclear reactor having a flattened reactor activity curve across the reactor includes fuel extending over a lesser portion of the fuel channels in the central portion of the reactor than in the remainder of the reactor.

Wheeler, John A. (Princeton, NJ)

1976-08-10T23:59:59.000Z

437

Validation of the RVACS (Reactor Vessel Auxiliary Cooling System)/RACS (Reactor Air Cooling System) model in SASSYS-1  

SciTech Connect

The SASSYS-1 LMR systems analysis code contains a model for transient analysis of heat removal by a RVACS (Reactor Vessel Auxiliary Cooling System) or a RACS (Reactor Air Cooling System) in an LMR (Liquid Metal Reactor). This model has been validated by comparisons of model predictions with experimental data from a large scale RVACS/RACS simulation experiment performed at Argonne National Laboratory. 4 refs., 1 fig.

Dunn, F.E.

1987-01-01T23:59:59.000Z

438

Robotics Laboratory - Nuclear Engineering Division (Argonne)  

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

Capabilities > Engineering Capabilities > Engineering Experimentation > Robotics Laboratory Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Robotics Laboratory The Robotics Laboratory (RL) houses various remote manipulator systems, including the Dual Arm Work Platform, to support enhancements to teleoperation of remote systems for nuclear applications. Bookmark and Share Argonne scientists are using computer simulation and robot task programming tools to enhance the safety and efficiency of telerobotics in applications such as the decontamination and decommissioning (D&D) of nuclear power

439

Russian RBMK reactor design information  

Science Conference Proceedings (OSTI)

This document concerns the systems, design, and operations of the graphite-moderated, boiling, water-cooled, channel-type (RBMK) reactors located in the former Soviet Union (FSU). The Russian Academy of Sciences Nuclear Safety Institute (NSI) in Moscow, Russia, researched specific technical questions that were formulated by the Pacific Northwest Laboratory (PNL) and provided detailed technical answers to those questions. The Russian response was prepared in English by NSI in a question-and-answer format. This report presents the results of that technical exchange in the context they were received from the NSI organization. Pacific Northwest Laboratory is generating this document to support the US Department of Energy (DOE) community in responding to requests from FSU states, which are seeking Western technological and financial assistance to improve the safety systems of the Russian-designed reactors. This report expands upon information that was previously available to the United States through bilateral information exchanges, international nuclear society meetings, International Atomic Energy Agency (IAEA) reactor safety programs, and Research and Development Institute of Power Engineering (RDIPE) reports. The response to the PNL questions have not been edited or reviewed for technical consistency or accuracy by PNL staff or other US organizations, but are provided for use by the DOE community in the form they were received.

Not Available

1993-11-01T23:59:59.000Z

440

Reactor safety method  

DOE Patents (OSTI)

This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature.

Vachon, Lawrence J. (Clairton, PA)

1980-03-11T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" 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

NEUTRONIC REACTOR MANIPULATING DEVICE  

DOE Patents (OSTI)

A cable connecting a control rod in a reactor with a motor outside the reactor for moving the rod, and a helical conduit in the reactor wall, through which the cable passes are described. The helical shape of the conduit prevents the escape of certain harmful radiations from the reactor. (AEC)

Ohlinger, L.A.

1962-08-01T23:59:59.000Z

442

ARGONNE NATIONAL LABORATORY is....  

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

Scattering June 12-18, 2010 - Argonne National Laboratory June 19-26, 2010 - Oak Ridge National Laboratory Argonne National Laboratory is a U.S. Department of Energy laboratory...

443

Environmental Cleanup, Brookhaven National Laboratory  

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

Lab campus Cleanup Project Details Groundwater Peconic River Surface and Soil Brookhaven Graphite Research Reactor High Flux Beam Reactor Brookhaven Medical Reactor...

444

Don Hillebrand | Argonne National Laboratory  

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

fuel cycle Geology & disposal Reactors Nuclear reactor safety Nuclear reactor materials Energy usage Energy life-cycle analysis Energy storage Batteries Lithium-ion batteries...

445

Ihor Hlohowskyj | Argonne National Laboratory  

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

fuel cycle Geology & disposal Reactors Nuclear reactor safety Nuclear reactor materials Energy usage Energy life-cycle analysis Energy storage Batteries Lithium-ion batteries...

446

Alex Martinson | Argonne National Laboratory  

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

energy Fossil fuels Oil Nuclear energy Nuclear energy modeling & simulation Nuclear fuel cycle Geology & disposal Reactors Nuclear reactor safety Nuclear reactor materials...

447

Irradiated Fuels Examination Laboratory (IFEL) | ORNL  

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

Irradiated Fuels Examination Laboratory Irradiated Fuels Examination Laboratory May 30, 2013 The Irradiated Fuels Examination Laboratory (IFEL) was initially designed and constructed to permit the safe handling of increasing levels of radiation in the chemical, physical, and metallurgical examination of nuclear reactor fuel elements and reactor parts. The IFEL was constructed in 1963 and is a two-story brick building with a partial basement. The front or northern-most section is a single-story office area. The two story area to the immediate rear houses the cell complex, the operating areas, and other supporting activities. The office area is isolated from the main part of the building, so the office area can be excluded from the secondary containment zone. The facility has a gross floor area of about 27,000 ft2.

448

High temperature catalytic membrane reactors  

DOE Green Energy (OSTI)

Current state-of-the-art inorganic oxide membranes offer the potential of being modified to yield catalytic properties. The resulting modules may be configured to simultaneously induce catalytic reactions with product concentration and separation in a single processing step. Processes utilizing such catalytically active membrane reactors have the potential for dramatically increasing yield reactions which are currently limited by either thermodynamic equilibria, product inhibition, or kinetic selectivity. Examples of commercial interest include hydrogenation, dehydrogenation, partial and selective oxidation, hydrations, hydrocarbon cracking, olefin metathesis, hydroformylation, and olefin polymerization. A large portion of the most significant reactions fall into the category of high temperature, gas phase chemical and petrochemical processes. Microporous oxide membranes are well suited for these applications. A program is proposed to investigate selected model reactions of commercial interest (i.e. dehydrogenation of ethylbenzene to styrene and dehydrogenation of butane to butadiene) using a high temperature catalytic membrane reactor. Membranes will be developed, reaction dynamics characterized, and production processes developed, culminating in laboratory-scale demonstration of technical and economic feasibility. As a result, the anticipated increased yield per reactor pass economic incentives are envisioned. First, a large decrease in the temperature required to obtain high yield should be possible because of the reduced driving force requirement. Significantly higher conversion per pass implies a reduced recycle ratio, as well as reduced reactor size. Both factors result in reduced capital costs, as well as savings in cost of reactants and energy.

Not Available

1990-03-01T23:59:59.000Z

449

US graphite reactor D&D experience  

Science Conference Proceedings (OSTI)

This report describes the results of the U.S. Graphite Reactor Experience Task for the Decommissioning Strategy Plan for the Leningrad Nuclear Power Plant (NPP) Unit 1 Study. The work described in this report was performed by the Pacific Northwest National Laboratory (PNNL) for the Department of Energy (DOE).

Garrett, S.M.K.; Williams, N.C.

1997-02-01T23:59:59.000Z

450

Developmental Light-Water Reactor Program  

SciTech Connect

This report summarizes the progress of the Developmental Light-Water Reactor (DLWR) Program at Oak Ridge National Laboratory in FY 1989. It also includes (1) a brief description of the program, (2) definition of goals, (3) earlier achievements, and (4) proposed future activities.

Forsberg, C.W.

1989-12-01T23:59:59.000Z

451

State Laboratory Contacts IL  

Science Conference Proceedings (OSTI)

State Laboratory Contact Information IL. Idaho. ... State of Iowa Metrology Laboratory Ellsworth Community College 1100 College Ave. ...

2013-11-07T23:59:59.000Z

452

PRA insights applicable to the design of the Broad Applications Test Reactor  

SciTech Connect

Design insights applicable to the design of a new Broad Applications Test Reactor (BATR), being studied at Idaho National Engineering Laboratory, are summarized. Sources of design insights include past probabilistic risk assessments and related studies for department of Energy-owned Class A reactors and for commercial reactors. The report includes a preliminary risk allocation scheme for the BATR.

Khericha, S.T.; Reilly, H.J.

1993-01-01T23:59:59.000Z

453

Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors  

SciTech Connect

Background: The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of Generation IV reactor systems such as supercritical water reactors (SCWR) for higher efficiency, improved performance and operation, design simplification, enhanced safety and reduced waste and cost. The objective of this Korean / US / laboratory / university collaboration of coupled fundamental computational and experimental studies is to develop the supporting knowledge needed for improved predictive techniques for use in the technology development of Generation IV reactor concepts and their passive safety systems. The present study emphasizes SCWR concepts in the Generation IV program.

D.M. McEligot; K. G. Condie; G. E. McCreery; H. M. McIlroy; R. J. Pink; L.E. Hochreiter; J.D. Jackson; R.H. Pletcher; B.L. Smith; P. Vukoslavcevic; J.M. Wallace; J.Y. Yoo; J.S. Lee; S.T. Ro; S.O. Park

2005-10-01T23:59:59.000Z

454

An Engineering Test Reactor  

SciTech Connect

A relatively inexpensive reactor for the specific purpose of testing a sub-critical portion of another reactor under conditions that would exist during actual operation is discussed. It is concluded that an engineering tool for reactor development work that bridges the present gap between exponential and criticality experiments and the actual full scale operating reactor is feasible. An example of such a test reactor which would not entail development effort to ut into operation is depicted.

Fahrner, T.; Stoker, R.L.; Thomson, A.S.

1951-03-16T23:59:59.000Z

455

ORGANISATIONAL CHART 2009 Laboratory: Research, Development and Services  

E-Print Network (OSTI)

ORGANISATIONAL CHART 2009 Laboratory: Research, Development and Services *reports to the Director. Sampani Radiation Protection of the Center G. Pantelias* HEALTH PHYSICS & ENVIRONMENTAL HEALTH LABORATORY. Kainourgiakis RADIATION PROTECTION & HEALTH PHYSICS OF THE REACTOR F. Tzika SUPPORT TO GAEC I. A. Papazoglou

456

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

DOE Green Energy (OSTI)

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

Not Available

1987-05-01T23:59:59.000Z

457

SHARP: Reactor Performance and Safety Simulation Suite  

NLE Websites -- All DOE Office Websites (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.

458

Videos | Argonne National Laboratory  

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

energy ---Bioenergy ---Solar energy --Fossil fuels ---Natural Gas --Nuclear energy ---Nuclear energy modeling & simulation ---Nuclear fuel cycle ---Reactors -Energy...

459

Reactor Pressure Vessel Task of Light Water Reactor Sustainability...  

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

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...

460

Memorandum on Chemical Reactors and Reactor Hazards  

SciTech Connect

Two important problems in the investigation of reactor hazards are the chemical reactivity of various materials employed in reactor construction and the chracteristics of heat transfer under transient conditions, specifically heat transfer when driven by an exponentially increasing heat source (exp t/T). Although these problems are independent of each other, when studied in relation to reactor hazards they may occur in a closely coupled sequence. For example the onset of a dangerous chemical reactor may be due to structural failure of various reactor components under an exponentially rising heat source originating with a runaway nuclear reactor. For this reason, these two problems should eventually be studied together after an exploratory experimental survey has been made in which they are considered separately.

Mills, M.M.; Pearlman, H.; Ruebsamen, W.; Steele, G., Chrisney, J.

1951-07-05T23:59:59.000Z

Note: This page contains sample records for the topic "naval reactors laboratory" from the National Library of EnergyBeta (NLEBeta).
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461

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

SciTech Connect

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

Bernard, John A

2003-01-21T23:59:59.000Z

462

Enforcement Documents - Idaho National Laboratory | Department of Energy  

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

Idaho National Laboratory Idaho National Laboratory Enforcement Documents - Idaho National Laboratory October 4, 2012 Preliminary Notice of Violation, Battelle Energy Alliance, LLC - NEA-2012-01 Issued to Battelle Energy Alliance, LLC related to an elevated extremity dose at the Hot Fuel Examination Facility and the plutonium contamination at the Zero Power Physics Reactor facility. January 13, 2012 Consent Order, Battelle Energy Alliance - NCO-2012-01 Issued to Battelle Energy Alliance, LLC, related to the Reactor Coolant Draining Event at the Idaho National Laboratory Advanced Test Reactor October 13, 2011 Consent Order, URS Energy & Construction, Inc. - NCO-2011-02 Issued to URS Energy & Construction, Inc., related to Quality Improvement and Work Control Program Deficiencies associated with Construction of the

463

Hot Fuel Examination Facility's neutron radiography reactor  

SciTech Connect

Argonne National Laboratory-West is located near Idaho Falls, Idaho, and is operated by the University of Chicago for the United States Department of Energy in support of the Liquid Metal Fast Breeder Reactor Program, LMFBR. The Hot Fuel Examination Facility, HFEF, is one of several facilities located at the Argonne Site. HFEF comprises a large hot cell where both nondestructive and destructive examination of highly-irradiated reactor fuels are conducted in support of the LMFBR program. One of the nondestructive examination techniques utilized at HFEF is neutron radiography, which is provided by the NRAD reactor facility (a TRIGA type reactor) below the HFEF hot cell.

Pruett, D.P.; Richards, W.J.; Heidel, C.C.

1983-01-01T23:59:59.000Z

464

Non-intrusive vibration monitoring in US Naval and US Coast Guard ships  

E-Print Network (OSTI)

In 2011, the Laboratory for Electromagnetic and Electronic Systems proposed a new type of vibration monitoring system, entitled vibration assessment monitoring point with integrated recovery of energy or VAMPRIE, in their ...

Gerhard, Katherine Leigh

2013-01-01T23:59:59.000Z

465

LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BNL  

Science Conference Proceedings (OSTI)

5098-LR-01-0 -LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-10-22T23:59:59.000Z

466

Physical protection of power reactors  

SciTech Connect

Sandia Laboratories has applied a systematic approach to designing physical protection systems for nuclear facilities to commercial light-water reactor power plants. A number of candidate physical protection systems were developed and evaluated. Focus is placed on the design of access control subsystems at each of three plant layers: the protected area perimeter, building surfaces, and vital areas. Access control refers to barriers, detectors, and entry control devices and procedures used to keep unauthorized personnel and contraband out of the plant, and to control authorized entry into vital areas within the plant.

Darby, J.L.

1979-01-01T23:59:59.000Z

467

DOE Designated User Facilities Multiple Laboratories * ARM Climate Research Facility  

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

Designated User Facilities Designated User Facilities Multiple Laboratories * ARM Climate Research Facility Argonne National Laboratory * Advanced Photon Source (APS) * Electron Microscopy Center for Materials Research * Argonne Tandem Linac Accelerator System (ATLAS) * Center for Nanoscale Materials (CNM) * Argonne Leadership Computing Facility (ALCF) * Brookhaven National Laboratory * National Synchrotron Light Source (NSLS) * Accelerator Test Facility (ATF) * Relativistic Heavy Ion Collider (RHIC) * Center for Functional Nanomaterials (CFN) * National Synchrotron Light Source II (NSLS-II ) (under construction) Fermi National Accelerator Laboratory * Fermilab Accelerator Complex Idaho National Laboratory * Advanced Test Reactor ** * Wireless National User Facility (WNUF)

468

Summary of advanced LMR (Liquid Metal Reactor) evaluations: PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor)  

Science Conference Proceedings (OSTI)

In support of the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) has performed independent analyses of two advanced Liquid Metal Reactor (LMR) concepts. The designs, sponsored by the US Department of Energy (DOE), the Power Reactor Inherently Safe Module (PRISM) (Berglund, 1987) and the Sodium Advanced Fast Reactor (SAFR) (Baumeister, 1987), were developed primarily by General Electric (GE) and Rockwell International (RI), respectively. Technical support was provided to DOE, RI, and GE, by the Argonne National Laboratory (ANL), particularly with respect to the characteristics of the metal fuels. There are several examples in both PRISM and SAFR where inherent or passive systems provide for a safe response to off-normal conditions. This is in contrast to the engineered safety systems utilized on current US Light Water Reactor (LWR) designs. One important design inherency in the LMRs is the inherent shutdown'', which refers to the tendency of the reactor to transition to a much lower power level whenever temperatures rise significantly. This type of behavior was demonstrated in a series of unscrammed tests at EBR-II (NED, 1986). The second key design feature is the passive air cooling of the vessel to remove decay heat. These systems, designated RVACS in PRISM and RACS in SAFR, always operate and are believed to be able to prevent core damage in the event that no other means of heat removal is available. 27 refs., 78 figs., 3 tabs.

Van Tuyle, G.J.; Slovik, G.C.; Chan, B.C.; Kennett, R.J.; Cheng, H.S.; Kroeger, P.G. (Brookhaven National Lab., Upton, NY (USA))

1989-10-01T23:59:59.000Z

469

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

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

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

470

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.

Scott, Charles D. (Oak Ridge, TN); Davison, Brian H. (Knoxvile, TN)

1993-01-01T23:59:59.000Z

471

Reactor Sharing Program  

Science Conference Proceedings (OSTI)

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

Vernetson, W.G.

1993-01-01T23:59:59.000Z

472

Guidebook to nuclear reactors  

SciTech Connect

A general introduction to reactor physics and theory is followed by descriptions of commercial nuclear reactor types. Future directions for nuclear power are also discussed. The technical level of the material is suitable for laymen.

Nero, A.V. Jr.

1976-05-01T23:59:59.000Z

473

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

474

Laboratory Equipment & Supplies | Sample Preparation Laboratories  

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

Equipment & Supplies Equipment & Supplies John Bargar, SSRL Scientist Equipment is available to serve disciplines from biology to material science. All laboratories contain the following standard laboratory equipment: pH meters with standard buffers, analytical balances, microcentrifuges, vortex mixers, ultrasonic cleaning baths, magnetic stirrers, hot plates, and glassware. Most laboratories offer ice machines and cold rooms. Specialty storage areas for samples include a -80 freezer, argon and nitrogen glove boxes, radiation contamination areas, inert atmosphere chambers, and cold rooms. For specific information please see: Equipment Inventory Checkout Equipment & Supplies To view equipment inventory by laboratory, refer to the following pages: Biology Chemistry & Material Science Laboratory 1 Inventory

475

STATEMENT OF CONSIDERATIONS Advance Test Reactor Class Waiver  

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

Advance Test Reactor Class Waiver Advance Test Reactor Class Waiver W(C)-2008-004 The Advanced Test Reactor (A TR) is a pressurized water test reactor at the Idaho National Laboratory (INL) that operates at low pressure and temperature. The ATR was originally designed to study the effects of intense radiation on reactor material and fuels . It has a "Four Leaf Clover" design that allows a diverse array of testing locations. The unique design allows for different flux in various locations and specialized systems also allow for certain experiments to be run at their own temperature and pressure. The U.S. Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007. This designation will allow the ATR to

476

High Flux Beam Reactor | Environmental Restoration Projects | BNL  

NLE Websites -- All DOE Office Websites (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

477

NEUTRONIC REACTOR POWER PLANT  

DOE Patents (OSTI)

This patent relates to a nuclear reactor power plant incorporating an air-cooled, beryllium oxide-moderated, pebble bed reactor. According to the invention means are provided for circulating a flow of air through tubes in the reactor to a turbine and for directing a sidestream of the circu1ating air through the pebble bed to remove fission products therefrom as well as assist in cooling the reactor. (AEC)

Metcalf, H.E.

1962-12-25T23:59:59.000Z

478

High solids fermentation reactor  

DOE Patents (OSTI)

A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

Wyman, Charles E. (Lakewood, CO); Grohmann, Karel (Littleton, CO); Himmel, Michael E. (Littleton, CO); Richard, Christopher J. (Lakewood, CO)

1993-01-01T23:59:59.000Z

479

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

480

FAST NEUTRON REACTOR  

DOE Patents (OSTI)

A reactor comprising fissionable material in concentration sufficiently high so that the average neutron enengy within the reactor is at least 25,000 ev is described. A natural uranium blanket surrounds the reactor, and a moderating reflector surrounds the blanket. The blanket is thick enough to substantially eliminate flow of neutrons from the reflector.

Soodak, H.; Wigner, E.P.

1961-07-25T23:5