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Note: This page contains sample records for the topic "defueled naval reactor" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

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

2

EIS-0259: Disposal of Decommissioned, Defueled Cruiser, Ohio Class and Los Angeles Class Naval Reactor Plants, Hanford Site, Richland (adopted from Navy)  

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

This EIS analyzes the alternate ways for disposing of decommissioned, defieled reactor compliments from U.S. Navy nuclear-powered cruisers, (Bainbridge, Truxtun, Long Beach, California Class and Virginia Class) and Los Angeles Class, and Ohio Class submarines.

3

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.

4

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

5

naval reactors  

National Nuclear Security Administration (NNSA)

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

6

EIS-0275: Disposal of the S1C Prototype Reactor Plant, Hanford Site, Richland, WA (Navy Document)  

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

This EIS analyzes the Office of Naval Reactors (Naval Reactors) proposed action to dismantle the defueled S1C Prototype reactor plant.

7

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor defueling and disassembly. Summary status report. Volume 3  

SciTech Connect

This document summarizes information relating to the preparations for defueling the Three Mile Island Unit 2 (TMI-2) reactor and disassembly activities being performed concurrently with decontamination of the facility. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data sysem which permits extraction/manipulation of specific data which can be used in planning for recovery from a loss of coolant event similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during the period of April 23, 1979 to April 16, 1985, in the completion of activities related to preparation for reactor defueling. Support activities conducted outside of radiation areas are not included within the scope of this report. Computerized reports included in this document are: A chronological summary listing work performed for the period; and summary reports for each major task undertaken in connection with the specific scope of this report. Presented in chronological order for the referenced time period. Manually-assembled table summaries are included for: Labor and exposures by department; and labor and exposures by major activity.

Doerge, D.H.; Miller, R.L.; Scotti, K.S.

1986-05-01T23:59:59.000Z

8

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

9

Reactor Safety Planning for Prometheus Project, for Naval Reactors Information  

SciTech Connect

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

P. Delmolino

2005-05-06T23:59:59.000Z

10

2014 Annual Planning Summary for the NNSA Naval Reactors  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2014 and 2015 within the NNSA Naval Reactors.

11

Integrated defueling system for Three Mile Island Unit 2  

SciTech Connect

The unique clean-up requirements of Three Mile Island Unit 2 have posed first-of-a-kind challenges for the equipment, tools, and operators involved in the defueling effort. Various equipment components and specialty remote tools were designed as an integrated defueling system to provide a means of safely working above the reactor and removing core debris. The basic defueling system consists of support equipment and specialty remote tools for specific operations. This paper describes the different equipment and tools, and explains the key interfaces and features of the integrated defueling system.

Brown, D.A.; Gallagher, R.E.; Rider, R.L.

1986-01-01T23:59:59.000Z

12

About Naval Reactors | National Nuclear Security Administration  

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

fleet to remain on station is further enhanced by our ability to forward-deploy repair and maintenance activities. Schools and Training Facilities The Naval Nuclear...

13

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

14

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

15

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

16

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

17

Naval Reactors Facility Environmental Monitoring Report, Calendar Year 2003  

SciTech Connect

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

18

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

19

Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station  

SciTech Connect

For the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), defueling of the fuel debris in the reactor core of Units 1-3 is planned to start within 10 years. Preferential items in the characterization of the fuel debris were identified for this work, in which the procedure and handling tools were assumed on the basis of information on 1F and experience after the Three Mile Island Unit 2 (TMI-2) accident. The candidates for defueling tools for 1F were selected from among the TMI- 2 defueling tools. It was found that they could be categorized into six groups according to their operating principles. The important properties of the fuel debris for defueling were selected considering the effect of the target materials on the tool performance. The selected properties are shape, size, density, thermal conductivity, heat capacity, melting point, hardness, elastic modulus, and fracture toughness. Of these properties, the mechanical properties (hardness, elastic modulus, fracture toughness) were identified as preferential items, because too few data on these characteristics of fuel debris are available in past severe accident studies. (authors)

Yano, Kimihiko; Kitagaki, Toru; Ikeuchi, Hirotomo; Wakui, Ryohei; Higuchi, Hidetoshi; Kaji, Naoya; Koizumi, Kenji; Washiya, Tadahiro [Japan Atomic Energy Agency 4-33 Muramatsu, Tokaimura, Nakagun, Ibaraki 319-1194 (Japan)

2013-07-01T23:59:59.000Z

20

TMI defueling project fuel debris removal system  

SciTech Connect

The three mile Island Unit 2 (TMI-2) pressurized water reactor loss-of-coolant accident on March 28, 1979, presented the nuclear community with many challenging remediation problems; most importantly, the removal of the fission products within the reactor containment vessel. To meet this removal problem, an air-lift system (ALS) can be used to employ compressed air to produce the motive force for transporting debris. Debris is separated from the transport stream by gravity separation. The entire method does not rely on any moving parts. Full-scale testing of the ALS at the Idaho National Engineering Laboratory (INEL) has demonstrated the capability of transporting fuel debris from beneath the LCSA into a standard fuel debris bucket at a minimum rate of 230 kg/min.

Burdge, B.

1992-01-01T23:59:59.000Z

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


21

TMI defueling project fuel debris removal system  

SciTech Connect

The three mile Island Unit 2 (TMI-2) pressurized water reactor loss-of-coolant accident on March 28, 1979, presented the nuclear community with many challenging remediation problems; most importantly, the removal of the fission products within the reactor containment vessel. To meet this removal problem, an air-lift system (ALS) can be used to employ compressed air to produce the motive force for transporting debris. Debris is separated from the transport stream by gravity separation. The entire method does not rely on any moving parts. Full-scale testing of the ALS at the Idaho National Engineering Laboratory (INEL) has demonstrated the capability of transporting fuel debris from beneath the LCSA into a standard fuel debris bucket at a minimum rate of 230 kg/min.

Burdge, B.

1992-08-01T23:59:59.000Z

22

Accident Investigation of the June 17, 2012, Construction Accident- Structural Steel Collapse at The Over pack Storage Expansion #2 at the Naval Reactors Facility at the Idaho National Laboratory, Idaho Falls, Idaho  

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

This report documents the Naval Reactors investigation into the collapse ofa partially-erected spent fuel storage building, Overpack Storage Expansion #2 (OSE2), at the Naval Reactors Facility. The Accident Investigation Board inspected the scene, collected physical and photographic evidence, interviewed involved personnel, and reviewed relevant documents to determine the key causes of the accident. Based on the information gathered during the investigation, the Board identified several engineering and safety deficiencies that need to be addressed to prevent recurrence.

23

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.

The TMI defueling project fuel debris removal system  

SciTech Connect

The Three Mile Island (TMI) unit 2 pressurized water reactor loss-of-coolant accident on March 28, 1979, presented the nuclear community with many challenging remediation problems. A plethora of techniques, systems, and tools have been employed for the recovery and packaging of the postaccident configuration of the reactor core. Of particular difficulty was the removal of the fuel debris located beneath the lower core support structure. Fuel debris located beneath the lower core support structure was the result of rapid cooling of the previously molten UO{sub 2} and ZrO{sub 2}, causing formation of a ceramic like rubble. Approximately 19,100 kg of this rubble settled beneath the lower core support structure and onto the lower head of the reactor containment vessel. The development and implementation of a debris collection system based on the air lift principle proved to be an effective method for gathering the fuel debris from beneath the lower core support structure.

Burge, B. (EG and G Idaho, Inc., Idaho Falls (United States))

1992-01-01T23:59:59.000Z

25

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

26

Naval Engineering A National Naval Obligation  

E-Print Network (OSTI)

As part of its national obligations, ONR must ensure US world leadership in those unique technology areas that insure naval superiority. ONR accomplishes this mission through research, recruitment and education, maintaining ...

Chryssostomidis, Chryssostomos

2000-05-16T23:59:59.000Z

27

Early American Naval Sigint  

Science Journals Connector (OSTI)

After the Battle of Midway, Laurance Safford, The primary source on early USN Comint work is the booklet US Naval Communications Intelligence Activities by Laurance Safford, J. N. Wenger and at le...

Peter Donovan; John Mack

2014-01-01T23:59:59.000Z

28

EA-1889-FEA-FONSI-2012.pdf  

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

UNITED STATES UNITED STATES DEPARTMENT OF THE NAVY FINAL ENVIRONMENTAL ASSESSMENT ON THE DISPOSAL OF DECOMMISSIONED, DEFUELED NAVAL REACTOR PLANTS FROM USS ENTERPRISE (CVN 65) AUGUST 2012 FINAL USS ENTERPRISE EA RESPONSIBLE AGENCIES: Lead Federal Agency: U.S. Department of the Navy Cooperating Agency: U.S. Department of Energy TITLE: Final Environmental Assessment on the Disposal of Decommissioned, Defueled, Naval Reactor Plants from USS ENTERPRISE (CVN 65) FINAL USS ENTERPRISE EA S-1 SUMMARY: The United States Navy proposes to remove the reactor compartments of USS ENTERPRISE (CVN 65), hereafter referred to as ENTERPRISE, at Puget Sound Naval Shipyard & Intermediate Maintenance Facility (PSNS & IMF), prepare the reactor compartments for disposal

29

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 ...

30

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 ...

31

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

32

Naval Spent Fuel Rail Shipment Accident Exercise Objectives ...  

Office of Environmental Management (EM)

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

33

A slow comeback (clean up at the damaged Three Mile Island Unit 2 reactor)  

SciTech Connect

This article reports on the progress that has been made in cleaning up the damaged Three Mile Island Unit 2 reactor, with radioactive debris present not only in the reactor core, but throughout the primary cooling system. Delays in the cleanup operation have been caused by extraordinary technical challenges, regulatory procedures, and funding shortages. The initial stabilization and decontamination of the containment building, which included the removal and processing of the radioactive water, are essentially complete. Reactor disassembly and defueling have yet to begin. The NRC has reported that radiation doses at Unit 2 since the accident have been lower than those experienced at operating reactors, but the estimates for the collective radiation exposure for the work force have recently increased. The NRC has proposed that if robotic devices are used in the defueling and decontamination processes, work-force exposure could be cut by more than half. The projected completion rates for defueling Unit 2 and decontaminating the containment building now range from 1990 to past the year 2000. A five-part inspection program was conducted that included the use of video and sonar probes inside the reactor vessel, and the gathering of debris samples from the core.

Adam, J.A.

1984-04-01T23:59:59.000Z

34

Naval Petroleum Reserves | Department of Energy  

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

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...

35

The Institution of Naval Architects  

Science Journals Connector (OSTI)

... THE annual spring meeting of the Institution of Naval Architects was held on Wednesday, Thursday, and Friday ... U.S. Navy."On the Method of initial Condensation and Heat Waste in Steam Engine Cylinders,"by Prof. R. H. Thurston, Sibley College, Cornell University, New ...

1895-04-11T23:59:59.000Z

36

The Institution of Naval Architects  

Science Journals Connector (OSTI)

... LAST week the Institution of Naval Architects held their annual spring meeting, under the chairmanship of Admiral Sir John Dalrymple Hay, one of the Vice ... Chief Surveyor Lloyd's Registry of Shipping; (13) "Steam pressure losses in marine engines,"by C. E. Stromeyer, Engineer Surveyor Lloyd's Registry of Shipping; (15 ...

1894-03-22T23:59:59.000Z

37

The Institution of Naval Architects  

Science Journals Connector (OSTI)

... THE annual spring meeting of the Institution of Naval Architects was held last week at the Society of ... elements of design of three imaginary battleships, propelled respectively by steam, gas, or oil engines. It is somewhat startling to find the chief engineer of one of our most ...

1907-03-28T23:59:59.000Z

38

Microsoft Word - Enterprise EA (for public)2.docx  

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

enclosure to letter enclosure to letter UNITED STATES DEPARTMENT OF THE NAVY DRAFT ENVIRONMENTAL ASSESSMENT ON THE DISPOSAL OF DECOMMISSIONED, DEFUELED NAVAL REACTOR PLANTS FROM USS ENTERPRISE (CVN 65) SEPTEMBER 2011 DRAFT USS ENTERPRISE EA RESPONSIBLE AGENCIES: Lead Federal Agency: U.S. Department of the Navy Cooperating Agency: U.S. Department of Energy TITLE: Draft Environmental Assessment on the Disposal of Decommissioned, Defueled, Naval Reactor Plants from USS ENTERPRISE (CVN 65) DRAFT USS ENTERPRISE EA i TABLE OF CONTENTS 1. PURPOSE AND NEED ..................................................................................................................... 1-1 1.1 Background ................................................................................................................................. 1-2

39

Demand response at the Naval Postgraduate School .  

E-Print Network (OSTI)

??The purpose of this MBA project is to assist the Naval Postgraduate School's Public Works department to assimilate into a Demand Response program that will (more)

Stouffer, Dean

2008-01-01T23:59:59.000Z

40

U.S. Naval war College Application | Department of Energy  

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

College Application U.S. Naval war College Application U.S. Naval War College Civilian Student Application. Naval War College Application More Documents & Publications DOE F 471.1...

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


41

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

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

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

42

EA-1889: Final Environmental Assessment and Finding of No Significant  

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

Final Environmental Assessment and Finding of No Final Environmental Assessment and Finding of No Significant Impact EA-1889: Final Environmental Assessment and Finding of No Significant Impact Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) The Department of the Navy has prepared a Final Environmental Assessment (EA) and Finding of No Significant Impact (FONSI) on the Disposal of Decommissioned, Defueled, Naval Reactor Plants from the USS Enterprise. Because the preferred alternative is to dispose of the Enterprise reactor plants at the Department of Energy's Hanford Site*, the Department of Energy is a cooperating agency for this EA. For additional information on the Enterprise EA and FONSI, please contact Mary Mascianica at (360) 476-7111. *Naval reactor compartments, reactor core barrels, reactor closure heads,

43

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

44

The Naval Petroleum and Oil Shale Reserves | Department of Energy  

Office of Energy Efficiency and Renewable Energy (EERE) 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...

45

Fuel Cell Power Plant Experience Naval Applications | Department...  

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

Plant Experience Naval Applications Fuel Cell Power Plant Experience Naval Applications Presented at the DOE-DOD Shipboard APU Workshop on March 29, 2011. apu20118wolak.pdf More...

46

EA-1889: Draft Environmental Assessment | Department of Energy  

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

9: Draft Environmental Assessment 9: Draft Environmental Assessment EA-1889: Draft Environmental Assessment Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) The Department of the Navy has prepared a Draft Environmental Assessment (EA) on the Disposal of Decommissioned, Defueled, Naval Reactor Plants from the USS Enterprise. The world's first nuclear-powered naval aircraft carrier, Enterprise, is scheduled for decommissioning in 2013, following 51 consecutive years of service. Because the preferred alternative is to dispose of the Enterprise reactor plants at the Department of Energy's Hanford Site*, the Department of Energy is a cooperating agency for this EA. For additional information on the Draft Enterprise EA, please contact Mary Mascianica at (360) 476-7111.

47

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

48

Naval Academy: Lockstep Program Is Abandoned  

Science Journals Connector (OSTI)

...and the building of safe water systems and sewers...Academy adopted two fundamental changes of policy...were descriptions of boilers, pumps, and guns included...Instruction in the operation of specific naval radar...such details of the operation as aquanaut experiences...

Luther J. Carter

1965-11-19T23:59:59.000Z

49

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

50

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

51

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

Office of Legacy Management (LM)

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...

52

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

53

Naval Construction Battalion Center Gulfport- Mississippi Power Partnership Success Story  

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

Presentation covers the Naval Construction Battalion Center Gulfport - Mississippi Power Partnership success storygiven at the Spring 2009 Federal Utility Partnership Working Group (FUPWG) meeting...

54

DOE - Office of Legacy Management -- Naval Petroleum Reserve...  

Office of Legacy Management (LM)

Naval Petroleum Reserve No. 3 is located in Natrona County, Wyoming. The site is a small oil field and covers approximately 9400 acres. Environmental remediation efforts are...

55

EIS-0259: Final Environmental Impact Statement | Department of Energy  

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

EIS-0259: Final Environmental Impact Statement EIS-0259: Final Environmental Impact Statement EIS-0259: Final Environmental Impact Statement Disposal of Decommissioned, Defueled Cruiser, Ohio Class, Los Angeles and Class Naval Reactor Plants This Environmental Impact Statement analyzes the alternate ways for disposing of decommissioned, defieled reactor compliments from U.S. Navy nuclear-powered cruisers, (Bainbridge, Truxtun, Long Beach, California Class and Virginia Class) and Los Angeles Class, and Ohio Class submarines. Final Environmental Impact Statement on the Disposal of Decommissioned, Defueled Cruiser, Ohio Class, Los Angeles and Class Naval Reactor Plants, DOE/EIS-0259 (April 1996) EIS-0259-FEIS-01-1996_0.pdf EIS-0259-FEIS-02-1996_0.pdf More Documents & Publications EA-1889: Final Environmental Assessment and Finding of No Significant

56

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

57

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

58

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

59

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.

60

DOE - Office of Legacy Management -- Naval Gun Factory and Bureau...  

Office of Legacy Management (LM)

Gun Factory and Bureau of Ordnance - DC 0-01 FUSRAP Considered Sites Site: NAVAL GUN FACTORY AND BUREAU OF ORDNANCE (DC.0-01) Eliminated from consideration under FUSRAP - Referred...

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


61

Record of Decision, Shutdown of the River Water System at the Savannah River Site, Savannah River Operations Office, Aiken, South Carolina  

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

6 6 Federal Register / Vol. 63, No. 18 / Wednesday, January 28, 1998 / Notices have to be addressed during dismantlement. The no action alternative would involve keeping the defueled S3G and D1G Prototype reactor plants in protective storage indefinitely. Since there is some residual radioactivity with long half-lives, such as nickel-59, in the defueled reactor plant, this alternative would leave some radioactivity at the Kesselring Site indefinitely. The Naval Reactors Program distributed the Draft Environmental Impact Statement on the Disposal of the S3G and D1G Prototype Reactor Plants in July 1997. Comments from 14 individuals and agencies were received in either oral or written statements at a public hearing or in comment letters. Approximately one-third of the commenters expressed a preference for

62

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

63

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

64

362 SDSU General Catalog 2012-2013 Naval Science  

E-Print Network (OSTI)

turbine, and diesel propulsion engines receive in-depth study. Leadership topics in an engineering setting Power and Maritime Affairs (3) Sea power and maritime affairs; general concept of sea power including Merchant Marine; role of naval warfare components used to support the Navy's mission; sea power

Gallo, Linda C.

65

368 SDSU General Catalog 2013-2014 Naval Science  

E-Print Network (OSTI)

turbine, and diesel propulsion engines receive in-depth study. Leadership topics in an engineering setting Power and Maritime Affairs (3) Sea power and maritime affairs; general concept of sea power including Merchant Marine; role of naval warfare components used to support the Navy's mission; sea power

Gallo, Linda C.

66

Naval Postgraduate School Monterey, California 93943-5138  

E-Print Network (OSTI)

-related challenges of the future. To fulfill its mission, the Naval Postgraduate School strives to sustain excellence to achieve three major goals: 1) academic programs that are nationally recognized and support the current that focus on the integration of teaching and research in direct support of the four pillars of Joint Visions

67

Naval Postgraduate School Monterey, California 93943-5138  

E-Print Network (OSTI)

challenges of the future. To fulfill its mission, the Naval Postgraduate School strives to sustain excellence research programs to achieve three major goals: 1) academic programs that are nationally recognized of the four pillars of Joint Visions 2010 and 2020 and their enabling technologies; and, 3) executive

68

Naval Postgraduate School Monterey, California 93943-5138  

E-Print Network (OSTI)

related challenges of the future. To fulfill its mission, the Naval Postgraduate School strives to sustain programs to achieve three major goals: 1) academic programs that are nationally recognized and support) institutes that focus on the integration of teaching and research in direct support of the four pillars

69

Naval Postgraduate School Monterey, California 93943-5138  

E-Print Network (OSTI)

the security of the United States. To fulfill its mission, the Naval Postgraduate School strives to sustain programs to achieve three major goals: 1) academic programs that are nationally recognized and support) institutes that focus on the integration of teaching and research in direct support of the four pillars

70

Naval Postgraduate School Monterey, California 93943-5138  

E-Print Network (OSTI)

-related challenges of the future. To fulfill its mission, the Naval Postgraduate School strives to sustain excellence Postgraduate School has aligned its education and supporting research programs to achieve three major goals: 1 of teaching and research in direct support of the four pillars of Joint Visions 2010 and 2020

71

Calculation of the Naval Long and Short Waste Package Three-Dimensional Thermal Interface Temperatures  

SciTech Connect

The purpose of this calculation is to evaluate the thermal performance of the Naval Long and Naval Short spent nuclear fuel (SNF) waste packages (WP) in the repository emplacement drift. The scope of this calculation is limited to the determination of the temperature profiles upon the surfaces of the Naval Long and Short SNF waste package for up to 10,000 years of emplacement. The temperatures on the top of the outside surface of the naval canister are the thermal interfaces for the Naval Nuclear Propulsion Program (NNPP). The results of this calculation are intended to support Licensing Application design activities.

H. Marr

2006-10-25T23:59:59.000Z

72

Nuclear Reactor (atomic reactor)  

Science Journals Connector (OSTI)

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

2008-01-01T23:59:59.000Z

73

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;

74

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

75

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":""}]}

76

E-Print Network 3.0 - andreyev bay naval Sample Search Results  

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

at the exact location (inside the bay) where the naval operations take place... . Armstrong, 2004. Prediction of instantaneous currents in San Diego ... Source: Chu, Peter C. -...

77

Board of Advisors to the Presidents of the Naval Postgraduate School and the Naval War College Annual Joint Meeting of the Subcommittees: Board of Advisors to the President, Naval Postgraduate  

E-Print Network (OSTI)

as the NPS sub-committee board members reviewed SECNAVINST 1524.2B. During the lunch (Advanced Education Review Board). The AERB was originally put in placeBoard of Advisors to the Presidents of the Naval Postgraduate School

78

SPECKLE INTERFEROMETRY AT THE U.S. NAVAL OBSERVATORY. XVII  

SciTech Connect

The results of 3362 intensified CCD observations of double stars, made with the 26 inch refractor of the U.S. Naval Observatory, are presented. Each observation of a system represents a combination of over 2000 short-exposure images. These observations are averaged into 1970 mean relative positions and range in separation from 0.''78 to 72.''17, with a mean separation of 14.''76. This is the 17th in this series of papers and covers the period 2010 January 6 through December 20. Also presented are 10 pairs that are resolved for the first time.

Mason, Brian D.; Hartkopf, William I.; Wycoff, Gary L., E-mail: bdm@usno.navy.mil, E-mail: wih@usno.navy.mil [U.S. Naval Observatory, 3450 Massachusetts Avenue, NW, Washington, DC 20392-5420 (United States)

2011-08-15T23:59:59.000Z

79

SPECKLE INTERFEROMETRY AT THE U.S. NAVAL OBSERVATORY. XV  

SciTech Connect

Results of 2433 intensified CCD observations of double stars, made with the 26 inch refractor of the U.S. Naval Observatory, are presented. Each observation of a system represents a combination of over 2000 short-exposure images. These observations are averaged into 1013 mean relative positions and range in separation from 0.''96 to 58.''05, with a mean separation of 13.''50. This paper is the 15th in the series of papers and covers the period 2008 January 3 through 2008 December 21.

Mason, Brian D.; Hartkopf, William I.; Wycoff, Gary L., E-mail: bdm@usno.navy.mi, E-mail: wih@usno.navy.mi, E-mail: glw@usno.navy.mi [U.S. Naval Observatory, 3450 Massachusetts Avenue, NW, Washington, DC 20392-5420 (United States)

2010-08-15T23:59:59.000Z

80

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":""}]}

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


81

Coastal Inundation due to Tide, Surge, Waves, and Sea Level Rise at Naval Station Norfolk  

E-Print Network (OSTI)

Coastal Inundation due to Tide, Surge, Waves, and Sea Level Rise at Naval Station Norfolk Honghai of future sea level rise (SLR) scenarios and to evaluate the potential coastal inundation at Naval Station and sea level rise threats to coastal residents and coastal military facilities, the US Strategic

US Army Corps of Engineers

82

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

83

Laser in situ keratomileusis in United States Naval aviators  

Science Journals Connector (OSTI)

Purpose To evaluate the safety and efficacy of femtosecond-assisted wavefront-guided laser in situ keratomileusis (LASIK) as well as higher-order aberrometric changes in a population of active-duty United States Naval aviators. Setting Navy Refractive Surgery Centers, San Diego, California, and Portsmouth, Virginia, USA. Design Prospective noncomparative 2-site study. Methods In this study of femtosecond-assisted wavefront-guided LASIK, 3 groups were differentiated according to the refractive status: myopia, mixed astigmatism, and hyperopia. Uncorrected (UDVA) and corrected (CDVA) distance visual acuities, refraction, mesopic low-contrast CDVA, higher-order aberrations (HOAs), and patient satisfaction were evaluated during a 3-month follow-up. Results The study enrolled, treated, and included for analysis 548 eyes with myopia, 60 eyes with mixed astigmatism, and 25 eyes with hyperopia. The UDVA was 20/20 or better in 98.3% of eyes with myopia and mixed astigmatism at all postoperative visits and in 95.7% of hyperopic eyes 3months postoperatively. The gain in CDVA was 1 or more lines in 39.2%, 41.1%, and 30.4% of myopic, mixed astigmatic and hyperopic eyes, respectively. Loss of 2 lines of CDVA after surgery occurred in 2 myopic eyes (0.4%). At 3 months, a mean change of +0.03 ?m 0.10(SD) and +0.05 0.08 ?m was observed in higher-order root mean square and primary spherical aberration, respectively. Of the patients, 95.9% said they believed that LASIK had helped their effectiveness as Naval aviators and 99.6% would recommend the same treatment to others. Conclusion Femtosecond-assisted wavefront-guided LASIK was an efficacious and safe option for refractive correction in Naval aviators, enabling a quick return to flight status. Financial Disclosure Drs. Tanzer and Schallhorn are consultants to Abbott Medical Optics, Inc. Noauthor has a financial or proprietary interest in any material or method mentioned.

David J. Tanzer; Tyson Brunstetter; Richard Zeber; Elizabeth Hofmeister; Sandor Kaupp; Neil Kelly; Myah Mirzaoff; William Sray; Mitch Brown; Steven Schallhorn

2013-01-01T23:59:59.000Z

84

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

85

SPECKLE INTERFEROMETRY AT THE U.S. NAVAL OBSERVATORY. XIX  

SciTech Connect

The results of 2916 intensified CCD observations of double stars, made with the 26 inch refractor of the U.S. Naval Observatory, are presented. Each observation of a system represents a combination of over two thousand short-exposure images. These observations are averaged into 1584 mean relative positions and range in separation from 0.''54 to 98.''09, with a median separation of 11.''73. This is the 19th in this series of papers and covers the period 2012 January 5 through 2012 December 18. Also presented are 10 pairs that are reported for the first time, 17 pairs that appear to be lost, linear elements for 18 pairs, and orbital elements for 2 additional pairs.

Mason, Brian D.; Hartkopf, William I.; Hurowitz, Haley M., E-mail: bdm@usno.navy.mil, E-mail: wih@usno.navy.mil, E-mail: hurowitz@mit.edu [U.S. Naval Observatory, 3450 Massachusetts Avenue, NW, Washington, DC 20392-5420 (United States)

2013-09-15T23:59:59.000Z

86

SPECKLE INTERFEROMETRY AT THE U.S. NAVAL OBSERVATORY. XVIII  

SciTech Connect

The results of 2490 intensified CCD observations of double stars, made with the 26 inch refractor of the U.S. Naval Observatory, are presented. Each observation of a system represents a combination of over 2000 short-exposure images. These observations are averaged into 1462 mean relative positions and range in separation from 0.''56 to 71.''80, with a mean separation of 14.''81. This is the 18th in this series of papers and covers the period 2011 January 3 through 2011 December 18. Also presented are four pairs which are resolved for the first time, thirteen other pairs which appear to be lost, and linear elements for four additional pairs.

Mason, Brian D.; Hartkopf, William I.; Friedman, Elizabeth A., E-mail: bdm@usno.navy.mil, E-mail: wih@usno.navy.mil, E-mail: efriedman09@ucla.edu [U.S. Naval Observatory, 3450 Massachusetts Avenue, NW, Washington, DC 20392-5420 (United States)

2012-05-15T23:59:59.000Z

87

Naval Petroleum Reserves: assessment of alternative operating strategies beyond 1982  

SciTech Connect

Legislation authorizing production from two Naval Petroleum Reserves, i.e., NPR-1 (Elk Hills, California) and NPR-3 (Teapot Dome, Wyoming), expires in 1982. This paper presents an assessment of the trade-offs of extending production or returning to a shut-in status. Strategic, economic, and energy factors at the national, regional, and local levels are considered. The results of the study indicate that the only major local impact of shut-in will be on small refineries near NPR-1. At the national level, shut-in increases the size of the national petroleum reserve system. However, economic losses as measured by changes in the present value of real GNP also occur. The estimate of the increase in the size of the national petroleum reserve with shut-in of the NPRs was found to be most sensitive to the assumed length of future import interruptions.

Gsellman, L.R.; Mendis, M.S.; Rosenberg, J.I.

1981-08-01T23:59:59.000Z

88

Environmental Assessments (EA) | Department of Energy  

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

November 4, 2011 November 4, 2011 EA-1905: Final Environmental Assessment Department of Energy Funding For Double Eagle Water System, Carlsbad, New Mexico (November 2011) November 1, 2011 EA-1866: Final Environmental Assessment and Finding of No Significant Impact Argonne National Laboratory Modernization Planning October 31, 2011 EA-1769: Final Environmental Assessment and Finding of No Significant Impact Houston Advanced Research Center, Battleground Energy Recovery Project, Deer Park, Harris County, Texas (October 2011) October 28, 2011 EA-1889: Draft Environmental Assessment Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) October 20, 2011 EA-1812: Draft Environmental Assessment Haxtun Wind Energy Project, Logan and Phillips Counties, Colorado

89

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).

90

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

91

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.

92

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...

93

EIS-0158: Sale of the Naval Petroleum Reserve No. 1 at Elk Hills, California (1997)  

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

The U.S. Department of Energy developed this EIS to assess the potential environmental impacts of the continued operation of the Naval Petroleum Reserve No. 1 at the Maximum Efficient Rate authorized by Public Law 94-258.

94

Carl Vinson and pre-war naval legislation 1932-1940  

E-Print Network (OSTI)

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...

Svonavec, Stephen Charles

2012-06-07T23:59:59.000Z

95

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

96

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

97

Analysis of harmonic distortion in an Integrated Power System for naval applications  

E-Print Network (OSTI)

This research quantifies the voltage distortion over the broad range of operating conditions experienced by a Naval warship. A steady state model of an Integrated Power System (IPS) was developed in a commercially available ...

West, Edward G., S.M. Massachusetts Institute of Technology

2005-01-01T23:59:59.000Z

98

EIS-0068: Development Policy Options for the Naval Oil Shale Reserves in Colorado  

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

The U.S. Department of Energy Office of Naval Petroleum and Oil Shale Reserves prepared this programmatic statement to examine the environmental and socioeconomic impacts of development projects on the Naval Oil Shale Reserve 1, and examine select alternatives, such as encouraging production from other liquid fuel resources (coal liquefaction, biomass, offshore oil and enhanced oil recovery) or conserving petroleum in lieu of shale oil production.

99

SPECKLE INTERFEROMETRY AT THE U.S. NAVAL OBSERVATORY. XVI  

SciTech Connect

The results of 1031 speckle-interferometric observations of double stars, made with the 26 inch refractor of the U.S. Naval Observatory, are presented. Each speckle-interferometric observation of a system represents a combination of over two thousand short-exposure images. These observations are averaged into 457 mean relative positions and range in separation from 0.''15 to 16.''94, with a median separation of 3.''03. The range in V-band magnitudes for the primary (secondary) of observed targets is 3.1-12.9 (3.2-13.3). This is the sixteenth in a series of papers presenting measurements obtained with this system and covers the period 2009 January 12 through 2009 December 17. Included in these data are 12 older measurements whose positions were previously deemed possibly aberrant, but are no longer classified this way following a confirming observation. Also, 10 pairs with a single observation are herein confirmed. This paper also includes the first data obtained using a new ICCD with fiber optic cables.

Mason, Brian D.; Hartkopf, William I.; Wycoff, Gary L., E-mail: bdm@usno.navy.mil, E-mail: wih@usno.navy.mil [U.S. Naval Observatory, 3450 Massachusetts Avenue, NW, Washington, DC 20392-5420 (United States)

2011-05-15T23:59:59.000Z

100

Renewable Energy Optimization Report for Naval Station Newport  

SciTech Connect

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

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


101

Distributed energy resources at naval base ventura county building 1512  

SciTech Connect

This paper reports the findings of a preliminary assessment of the cost effectiveness of distributed energy resources at Naval Base Ventura County (NBVC) Building 1512. This study was conducted in response to the base's request for design assistance to the Federal Energy Management Program. Given the current tariff structure there are two main decisions facing NBVC: whether to install distributed energy resources (DER), or whether to continue the direct access energy supply contract. At the current effective rate, given assumptions about the performance and structure of building energy loads and available generating technology characteristics, the results of this study indicate that if the building installed a 600 kW DER system with absorption cooling and heat capabilities chosen by cost minimization, the energy cost savings would be about 14 percent, or $55,000 per year. However, under current conditions, this study also suggests that significant savings could be obtained if Building 1 512 changed from the direct access contract to a SCE TOU-8 (Southern California Edison time of use tariff number 8) rate without installing a DER system. At current SCE TOU-8 tariffs, the potential savings from installation of a DER system would be about 4 percent, or $15,000 per year.

Bailey, Owen C.; Marnay, Chris

2004-10-01T23:59:59.000Z

102

Radiation exposure assessment for portsmouth naval shipyard health studies  

Science Journals Connector (OSTI)

......shipyards 226 0.49 Training 177 0.79 Industry...working near an operating submarine reactor...number of affected personnel and the low doses...worker safety and training programmes. Figure...individuals eligible for selection to nested case-control...P. Study of a selection of 10 historical......

R. D. Daniels; T. D. Taulbee; P. Chen

2004-09-01T23:59:59.000Z

103

Naval R & D: Conversion Sought for Radiological Defense Lab  

Science Journals Connector (OSTI)

...7. W. E. Hoehn, The Economics of Nuclear Reactors for Power...P. Sporn in Nuclear Power Economics-1962 through 1967, report...First Int. Symp. Water Desalination [cited by Wolfo-witz...of the Committee on the Economics of Water Resource Development...

John Walsh

1969-06-06T23:59:59.000Z

104

New case for naval arms control. Interim report, September-December 1992  

SciTech Connect

This paper opens with an examination of existing legal restraints on naval forces and arms control agreements and concludes that the U.S. is already heavily engaged in naval arms control. Given the new international security environment and the new U.S. regionally-oriented national security and military strategies, the author then recommends a series of additional naval arms control measures that should be taken: exchanges of data, transparency, INCSEA, cooperative measures, an agreement on the laws of submarine warfare, abolishing NCND, no first tactical nuclear use at sea, NWFZs, advanced notification of operational-level exercises, environmental protection measures, controls over maritime technologies, armed escorts of nuclear shipments, new Roes, PALs, the resolution of outstanding political issues at sea, deep cuts in nuclear forces, CFE follow-on, limits on specific types of naval forces, geographic limits, expanded standing naval forces, and a re negotiation of the ABM Treaty. The paper then addresses verification and compliance issues. Author concludes that since the U.S. Navy has already managed to avoid major arms control while balanced on the precarious slippery slope, there is no reason to continue its stonewalling policies.

Tritten, J.J.

1992-12-04T23:59:59.000Z

105

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

106

Updated 1-12 Mr. John C. Goodhart became the Vice Commander and senior civilian of the Naval Supply  

E-Print Network (OSTI)

is responsible for quality-of-life issues for our naval forces, including food service, postal services, Navy Executive Service since July 2002. NAVSUP's primary mission is to provide U.S. naval forces with quality supplies and services. The organization oversees logistics programs in the areas of supply operations

107

NUCLEAR REACTORS.  

E-Print Network (OSTI)

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

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

108

Modeling of Coastal Inundation, Storm Surge, and Relative Sea-Level Rise at Naval Station Norfolk, Norfolk, Virginia, U.S.A.  

E-Print Network (OSTI)

Modeling of Coastal Inundation, Storm Surge, and Relative Sea- Level Rise at Naval Station Norfolk. Modeling of coastal inundation, storm surge, and relative sea-level rise at Naval Station Norfolk, Norfolk, and relative sea-level-rise (RSLR) scenarios were examined at the U.S. Naval Station, Norfolk, Virginia

US Army Corps of Engineers

109

Naval Research Laboratory Memorandum Report, 2003 Perceptual and Ergonomic Issues in  

E-Print Network (OSTI)

Naval Research Laboratory Memorandum Report, 2003 1 Perceptual and Ergonomic Issues in Mobile paradigm, the field needs a much better understanding of the fundamental perceptual and ergonomic issues aimed at both understanding the fundamental perceptual and ergonomic issues in AR display

Swan II, J. Edward

110

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

E-Print Network (OSTI)

metal oxides for PEMFC cathodes Low-platinum hydrous metal oxides for PEMFC cathodes #12;Naval Research-NbPOx compounds Receive LANL test results for Pt-FePOx catalyst performance in a PEMFC - poor performance Acquire on lowering Pt in fuel cell cathode · Cathode has most Pt because slow oxygen reduction kinetics poor Pt

111

Naval Station Norfolk, VA- Energy Conservation Program UESC Partnership Success Story  

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

Presentationgiven at the Federal Utility Partnership Working Group (FUPWG) Fall 2008 meetingcovers the basis for success of a U.S. Navy utility energy service contract (UESC) project at a Naval Station in Norfolk, Virginia, including the project phases and why the utility partnership works.

112

Boiler Upgrades and Decentralizing Steam Systems Save Water and Energy at Naval Air Station Oceana  

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

Case study details Naval Air Station Oceana findings that its heating needs could be met more efficiently by replacing its central plant with a combination of distributed boilers and ground source heat pumps. The results saved more than 1 million MBtu in energy and 19,574 Kgal of water annually.

113

Don AtwoodNaval Postgraduate School Workshop 9 August 1 Monitoring Marine Ecosystems  

E-Print Network (OSTI)

School Workshop ­ 9 August 9 NRT Support Walrus Tracking U.S. Fish and Wildlife Service USGS Alaska Environment U.S. Fish and Wildlife Service USGS Alaska Science Center #12;Don AtwoodNaval Postgraduate School Interactions Hurricane Ivan What does SAR see? · surface roughness of the water Fortunately, wind, atmospheric

114

Symposium on Naval Hydrodynamics Gothenburg, Sweden, 26-31 August 2012  

E-Print Network (OSTI)

29th Symposium on Naval Hydrodynamics Gothenburg, Sweden, 26-31 August 2012 High will be dramatically different from current mainstream supercomputers in terms of computing power and parallel are demonstrated for plunging breaking waves behind a bump using 2.2 billion grid points running on thousands

Yang, Jianming

115

Low Energy Nuclear Reaction Research at the Naval Research Laboratory D.A. Kidwell1  

E-Print Network (OSTI)

Low Energy Nuclear Reaction Research at the Naval Research Laboratory D.A. Kidwell1 , D have explored the field of Low Energy Nuclear Reactions (LENR) for about eight years focusing energy (as heat) is produced ­ neither nuclear products nor transmutations have been firmly established

Noble, James S.

116

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

117

Light Water Reactor Sustainability  

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

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

118

"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...

Wadle, Ryan David

2012-07-16T23:59:59.000Z

119

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

120

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

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


121

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

122

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.

123

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

124

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

125

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

SciTech Connect

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

126

Zircaloy performance in light water reactors  

SciTech Connect

Zircaloy has been successfully used as the primary light water reactor (LWR) core structural material since its introduction in the early days of the US naval nuclear program. Its unique combination of low neutron absorption cross section, fabricability, mechanical strength, and corrosion resistance in water and steam near 300{degrees}C has resulted in remarkable reliability of operation of pressurized and boiling water reactor (PWR, BWR) fuel through the years. At present time, BWRs use Zircaloy-2 and PWRs use Zircaloy-4 for fuel cladding. In BWRs, both Zircaloy-2 and -4 have been successfully used for spacer grids and channels, and in PWRs Zircaloy-4 is used for spacer grids and control rod guide tubes. Performance of fuel rods has been excellent thus far. The current trend for utilities worldwide is to expect both higher fuel reliability in the future. Fuel suppliers have already achieved extended exposures in lead use assemblies, and have demonstrated excellent performance in all areas; therefore unsuspected problems are not likely to arise. However, as exposure and expectations continue to increase, Zircaloy is being taken toward the limits of its known capabilities. This paper reviews Zircaloy performance capabilities in areas related to environmentally affected microstructure, mechanical properties, corrosion resistance, and dimensional stability. The effects of radiation and reactor environment on each property is illustrated with data, micrographs, and analysis.

Adamson, R.B.; Cheng, B.C.; Kruger, R.M. [GE Nuclear Energy, Pleasanton, CA (United States)

1992-12-31T23:59:59.000Z

127

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 Statementaddresses six general alternative systems for the loading, storage, transport, and possible disposal of naval spent nuclear fuel following examination.

128

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

129

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

SciTech Connect

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

130

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

131

Photocatalytic reactor  

DOE Patents (OSTI)

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

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

1999-01-19T23:59:59.000Z

132

Reconnaissance of geothermal resources near US naval facilities in the San Diego area, California  

SciTech Connect

A reconnaissance study has found little evidence of potential geothermal resources useful at naval facilities in the greater San Diego metropolitan area. However, there is a zone of modest elevated water well temperatures and slightly elevated thermal gradients that may include the eastern portion of the Imperial Beach Naval Air Station south of San Diego Bay. An increase of 0.3/sup 0/ to 0.4/sup 0/F/100 ft over the regional thermal gradient of 1.56/sup 0/F/100 ft was conservatively calculated for this zone. The thermal gradient can be used to predict 150/sup 0/F temperatures at a depth of approximately 4000 ft. This zone of greatest potential for a viable geothermal resource lies within a negative gravity anomaly thought to be caused by a tensionally developed graben, approximately centered over the San Diego Bay. Water well production in this zone is good to high, with 300 gpm often quoted as common for wells in this area. The concentration of total dissolved solids (TDS) in the deeper wells in this zone is relatively high due to intrusion of sea water. Productive geothermal wells may have to be drilled to depths economically infeasible for development of the resource in the area of discussion.

Youngs, L.G.

1984-01-01T23:59:59.000Z

133

Hybrid adsorptive membrane reactor  

DOE Patents (OSTI)

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

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

2011-03-01T23:59:59.000Z

134

REPORT NT-14-3  

National Nuclear Security Administration (NNSA)

3 MAY 2014 OCCUPATIONAL RADIATION EXPOSURE FROM NAVAL REACTORS' DEPARTMENT OF ENERGY FACILITIES NAVAL NUCLEAR PROPULSION PROGRAM OFFICE OF NAVAL REACTORS WASHINGTON, D.C. 20585...

135

GEN-IV Reactors  

Science Journals Connector (OSTI)

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

Taek K. Kim

2013-01-01T23:59:59.000Z

136

The Netherlands Reactor Centre  

Science Journals Connector (OSTI)

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

S. WEINTROUB

1964-04-04T23:59:59.000Z

137

EIS-0158-S2: Supplemental Environmental Impact Statement Naval Petroleum Reserve No. 1 (Elk Hills), Kern County, California  

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

The U.S. Department of Energy developed this statement, the supplement to DOE/EIS-0158, to analyze the environmental and socioeconomic impacts of the sale of Naval Petroleum Reserve No. 1 in Kern County, California to Occidental Petroleum Corporation.

138

Multi-star multi-phase winding for a high power naval propulsion machine with low ripple torques  

E-Print Network (OSTI)

Permanent Magnet (SMPM) Machine designed for naval propulsion is proposed. The design objective of this high if the magnetic couplings between the stars is weak. The 4-star 3-phase winding proposed in this paper is designed star being magnetically shifted by an angle of 15 degrees. This 4-star 3-phase configuration allows

Boyer, Edmond

139

COMPUTER SIMULATION OF THE UMER ELECTRON GUN* I. Haber, Plasma Physics Division, Naval Research Laboratory, Washington, DC 20375  

E-Print Network (OSTI)

COMPUTER SIMULATION OF THE UMER ELECTRON GUN* I. Haber, Plasma Physics Division, Naval Research conducted with the aim of understanding the space-charge-dominated physics in the gun and injector transport is on simulating the beam propagation in the gun region between the cathode grid and the anode grid for comparison

Valfells, Ágúst

140

The Immortal Fausto: The Life, Works, and Ships of the Venetian Humanist and Naval Architect Vettor Fausto (1490-1546)  

E-Print Network (OSTI)

At the beginning of the sixteenth century, the maritime power of the Republic of Venice was seriously threatened by the Ottoman Sultan Suleiman I in the East, and by the Holy Roman Emperor Charles V in the West. In order to regain its naval power...

Campana, Lilia

2014-06-11T23:59:59.000Z

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


141

SRS Small Modular Reactors  

SciTech Connect

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

None

2012-04-27T23:59:59.000Z

142

SRS Small Modular Reactors  

ScienceCinema (OSTI)

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

None

2014-05-21T23:59:59.000Z

143

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

144

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

145

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:

146

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

147

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

148

Environmental Survey preliminary report, Naval Petroleum Reserves in California (NPRC), Tupman, California  

SciTech Connect

This report presents the preliminary environmental findings from the first phase of the Environmental Survey of the US Department of Energy (DOE) Naval Petroleum Reserves 1 (NPR-1) and 2 (NPR-2) in California (NPRC), conducted May 9--20, 1988. The Survey is being conducted by an interdisciplinary team of environmental specialists, led 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 NPRC. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involved the review of existing site environmental data, observations of the operations carried on at NPRC, and interviews with site personnel. 120 refs., 28 figs., 40 tabs.

Not Available

1989-02-01T23:59:59.000Z

149

Vertical Drop of the Naval SNF Long Waste Package On Unyielding Surface  

SciTech Connect

The purpose of this calculation is to determine the structural response of a Naval SNF (Spent Nuclear Fuel) Long Waste Package (WP) subjected to 2 m-vertical drop on unyielding surface (US). The scope of this document is limited to reporting the calculation results in terms of maximum stress intensities. This calculation is associated with the waste package design; calculation is performed by the Waste Package Design group. AP-3.12Q, Revision 0, ICN 0, Calculations, is used to perform the calculation and develop the document. The finite element calculation is performed by using the commercially available ANSYS Version (V) 5.4 finite element code. The result of this calculation is provided in terms of maximum stress intensities.

S. Mastilovic

2006-07-21T23:59:59.000Z

150

Naval Petroleum Reserves: assessment of alternative operating strategies beyond 1982. Analysis and supporting data  

SciTech Connect

Legislation authorizing production from two of the Naval Petroleum Reserves, i.e., NPR-1 (Elk Hills, California) and NPR-3 (Teapot Dome, Wyoming), expires in 1982. This paper presents analyses and supporting data concerning the trade-offs of extending production or returning to a shut-in status in order to provide the Department of Energy with information needed to formulate a recommendation. The primary objective of the study is to evaluate a range of possible futures (through 1990) to determine technical, economic, energy, strategic and political trade-offs between the two options. A secondary objective is to develop a data base for use by DOE to respond to questions and issues raised by interested parties during executive branch and Congressional reviews.

Gsellman, L.R.; Mendis, M.S.; Rosenberg, J.I.

1981-06-01T23:59:59.000Z

151

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

152

Nuclear reactor  

DOE Patents (OSTI)

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

Thomson, Wallace B. (Severna Park, MD)

2004-03-16T23:59:59.000Z

153

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.

Not Available

1994-06-01T23:59:59.000Z

154

Washington | Department of Energy  

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

February 26, 1997 February 26, 1997 EIS-0189: Record of Decision Tank Waste Remediation System, Hanford Site, Richland, WA December 1, 1996 EA-1111: Final Environmental Assessment K Pool Fish Rearing, Hanford Site, Richland, Washington October 21, 1996 EA-1177: Final Environmental Assessment Salvage/Demolition of 200 West Area, 200 East Area, and 300 Area Steam Plants August 1, 1996 EIS-0189: Final Environmental Impact Statement Tank Waste Remediation System, Hanford Site, Richland, Washington May 1, 1996 EIS-0244: Final Environmental Impact Statement Plutonium Finishing Plant Stabilization April 1, 1996 EIS-0259: Final Environmental Impact Statement Disposal of Decommissioned, Defueled Cruiser, Ohio Class, Los Angeles and Class Naval Reactor Plants April 1, 1996 EIS-0259: Final Environmental Impact Statement

155

Findings of No Significant Impact (FONSI) | Department of Energy  

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

August 28, 2012 August 28, 2012 EA-1909: Finding of No Significant Impact South Table Wind Project, Kimball County, NE August 24, 2012 EA-1929: Finding of No Significant Impact NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99 August 23, 2012 EA-1889: Final Environmental Assessment and Finding of No Significant Impact Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) August 15, 2012 EA-1917: Finding of No Significant Impact Wave Energy Test Facility Project, Newport, OR August 7, 2012 EA-1845: Finding of No Significant Impact Sabine Pass Liquefaction, LLC Regarding Order Granting Long-Term Authorization to Export Liquefied Natural Gas from Sabine Pass LNG Terminal to Non-Free Trade Agreement Nations, Cameron Parish, LA

156

Latest Documents and Notices | Department of Energy  

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

24, 2012 24, 2012 EA-1929: Finding of No Significant Impact NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99 August 24, 2012 EA-1929: Final Environmental Assessment NorthStar Medical Technologies LLC, Commercial Domestic Production of the Medical Isotope Molybdenum-99 August 23, 2012 EA-1889: Final Environmental Assessment and Finding of No Significant Impact Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) August 21, 2012 EA-1886: Draft Environmental Assessment Big Sky Regional Carbon Sequestration Partnership - Phase III: Kevin Dome Carbon Storage Project, Shelby, Toole County, MT August 17, 2012 EIS-0414: Record of Decision Energia Sierra Juarez Transmission Project August 15, 2012

157

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

158

Elementary Reactor Physics  

Science Journals Connector (OSTI)

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

J. F. HILL

1962-02-10T23:59:59.000Z

159

Colliding Beam Fusion Reactors  

Science Journals Connector (OSTI)

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

Norman Rostoker; Artan Qerushi; Michl Binderbauer

2003-06-01T23:59:59.000Z

160

Superfund record of decision (EOA Region 1): Newport Naval Education/Training Center, Newport, RI, September 1993  

SciTech Connect

The U.S. Naval Education and Training Center (NETC) Newport is a National Priorities List (NPL) site. There are currently four areas of contamination (AOC) and six study areas (SAs) within NETC Newport that are under investigation. This Record of Decision (ROD) relates to the presence of the existing landfill area at McAllister Point as a source of contamination. McAllister Point Landfill was the site of a sanitary landfill which operated over a 20-year period. From 1955 until the mid-1970's, the site accepted all wastes generated at the Naval complex. The landfill received waste from all operational areas (machine shops, ship repair, etc.), Navy housing areas (domestic refuse), and from the 55 ships homeported at Newport prior to 1973 (approximately fourteen 40-cubic yard containers each day). The materials disposed of at the site reportedly included spent acids, paints, solvents, waste oils (diesel, lube and fuel), and polychlorinated biphenyl (PCB)-contaminated transformer oil.

Not Available

1993-09-01T23:59:59.000Z

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


161

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.

Not Available

1994-08-01T23:59:59.000Z

162

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

SciTech Connect

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

163

Prospects for spheromak fusion reactors  

Science Journals Connector (OSTI)

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

T. K. Fowler; D. D. Hua

1995-06-01T23:59:59.000Z

164

Advanced Test Reactor Tour  

SciTech Connect

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

Miley, Don

2011-01-01T23:59:59.000Z

165

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

166

Advanced Test Reactor Tour  

ScienceCinema (OSTI)

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

Miley, Don

2013-05-28T23:59:59.000Z

167

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.

NONE

1995-07-01T23:59:59.000Z

168

The Argonaut Reactor - Reactors designed/built by Argonne National  

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

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

169

Reactor vessel support system  

DOE Patents (OSTI)

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

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

1982-01-01T23:59:59.000Z

170

EIS-0275: Record of Decision | Department of Energy  

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

proposed disposal of the defueled S1C Prototype reactor plant, located in Windsor, Connecticut, pursuant to Section 102(2) of the National Environmental Policy Act of 1969...

171

Reactor water cleanup system  

DOE Patents (OSTI)

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

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

1994-01-01T23:59:59.000Z

172

Reactor water cleanup system  

DOE Patents (OSTI)

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

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

1994-12-20T23:59:59.000Z

173

Endangered species and cultural resources program, Naval Petroleum Reserves in California: Annual report FY95  

SciTech Connect

In FY95, EG and G Energy Measurements, Inc. (EG and G/EM) continued to support efforts to protect endangered species and cultural resources at the Naval Petroleum Reserves in California (NPRC). These efforts are conducted to ensure NPRC compliance with regulations regarding the protection of listed species and cultural resources on Federal properties. Population monitoring activities are conducted annually for San Joaquin kit foxes, giant kangaroo rats, blunt-nosed leopard lizards, and Hoover`s wooly-star. To mitigate impacts of oil field activities on listed species, 674 preactivity surveys covering approximately 211 hectares (521 acres) were conducted in FY95. EG and G/EM also assisted with mitigating effects from third-party projects, primarily by conducting biological and cultural resource consultations with regulatory agencies. EG and G/EM has conducted an applied habitat reclamation program at NPRC since 1985. In FY95, an evaluation of revegetation rates on reclaimed and non-reclaimed disturbed lands was completed, and the results will be used to direct future habitat reclamation efforts at NPRC. In FY95, reclamation success was monitored on 50 sites reclaimed in 1985. An investigation of factors influencing the distribution and abundance of kit foxes at NPRC was initiated in FY94. Factors being examined include habitat disturbance, topography, grazing, coyote abundance, lagomorph abundance, and shrub density. This investigation continued in FY95 and a manuscript on this topic will be completed in FY96. Also, Eg and G/EM completed collection of field data to evaluate the effects of a well blow-out on plant and animal populations. A final report will be prepared in FY96. Finally, EG and G/EM completed a life table analysis on San Joaquin kit foxes at NPRC.

NONE

1996-04-01T23:59:59.000Z

174

Human health risk assessment for off-shore media at Portsmouth Naval Shipyard  

SciTech Connect

A human health risk assessment for off-shore media was performed at the Portsmouth Naval Shipyard, Kittery, Maine. The purpose was to determine whether any potential human health risks could be posed by exposures to the estuary. Included in the study were the evaluations of potential risks existing from human exposures to surface water and sediment, as well as potential risks posed by ingestion of various species of fish and shellfish which are caught commercially and recreationally in the estuary. Three species were chosen for study. They were lobsters, mussels, and flounder. The USEPA prescribed protocols for performing human health risk assessments under CERCLA and RCRA were followed to estimate risks associated with ingestion of these species caught in the lower estuary, in the vicinity of the Shipyard. USEPA required the evaluation of two potential seafood ingestion scenarios recreational fishermen and subsistence fishermen. The results indicated that the USEPA risk target of 10{sup {minus}6} for carcinogens or the hazard index of one was exceeded in at least one species for the subsistence ingestion scenario for some inorganics and organic compounds. Based on these results, it was necessary to propose Media Protection Standards in the biota, which would represent the USEPA target risk level for carcinogens and noncarcinogens, as potential cleanup targets. In performing this task, a review of regional background levels for these chemicals found in biota throughout the Great Bay Estuarine System, at locations removed from the Shipyard, was performed. Also examined were regional Maine data from the NOAA Mussel Watch Program. Biota concentrations near the Shipyard were found to be within the range of biota concentrations for most of these chemicals throughout the region, suggesting possible multiple, non-point sources for the contaminants found in seafood throughout the region.

Mahoney, E. [Eileen Mahoney Associates, Inc., Philadelphia, PA (United States)

1995-12-31T23:59:59.000Z

175

Use of microbes for paraffin cleanup at Naval Petroleum Reserve No. 3  

SciTech Connect

Naval Petroleum Reserve No. 3 (NPR-3), also known as Teapot Dome, is a government-owned oil field in Natrona County, Wyoming. It is an asymmetrical anticline located on the western edge of the Powder River Basin, just south of the Salt Creek Anticline. Production started in 1922, and today the field is a marginally economic stripper field with average production of less than 3 BOPD (0.5 m{sup 3}/D) per well. Total field production is about 1,800 BOPD (286 m{sup 3}/D). The Second Wall Creek Formation was waterflooded from 1979 until June 1992 with poor results due to the extensive natural fracture system in this sandstone unit. Since water injection ceased, reservoir pressure has declined to very low levels. Liquids extraction and reinjection of the gas produced from high-GOR wells along the gas-oil contact continues, but the average gas cap pressure has fallen to approximately 150 psi (1.03 MPa) from an original pressure of 1,120 psi (7.72 MPa). Since the oil is highly paraffinic, wax deposition in the hydraulic fractures and the perforations has become a serious production problem. Microbial treatment was considered as a possible low-cost solution. Four wells were selected in the Second Wall Creek Reservoir with severe paraffin problems and production rates high enough to economically justify the treatment. Problems were experienced with the production of thick oil after approximately three months. This was interpreted to be a result of previously immobile paraffin being cleaned up. A slight decrease in the decline rate was seen in the wells, although some external factors cloud the interpretation. Microbial treatments were discontinued because of marginal economics. Three of the four wells produced additional oil and had a positive incremental cash flow. Oil viscosity tests did indicate that some positive microbial thinning was occurring, and changes to the treatment procedure may potentially yield more economic results in the future.

Giangiacomo, L.; Khatib, A.

1995-12-31T23:59:59.000Z

176

DATE  

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

The Advanced Test Reactor (ATR) uses the Naval Reactors (NR) Casks to transport test trains between the Naval Reactors Facility (NRF) Expended Core Facility and the ATR. The...

177

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),

178

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

179

Power Reactor Progress  

Science Journals Connector (OSTI)

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

1957-02-25T23:59:59.000Z

180

Improved vortex reactor system  

DOE Patents (OSTI)

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

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

1995-05-09T23:59:59.000Z

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


181

AEC Pushes Fusion Reactors  

Science Journals Connector (OSTI)

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

1955-10-10T23:59:59.000Z

182

Tokamak reactor first wall  

DOE Patents (OSTI)

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

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

1984-11-20T23:59:59.000Z

183

Advanced Nuclear Research Reactor  

SciTech Connect

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

Lolich, J.V.

2004-10-06T23:59:59.000Z

184

Technical Feasibility Study for Deployment of Ground-Source Heat Pump Systems: Portsmouth Naval Shipyard -- Kittery, Maine  

SciTech Connect

The U.S. Environmental Protection Agency (EPA) Office of Solid Waste and Emergency Response, in accordance with the RE-Powering America's Lands initiative, engaged the U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to conduct feasibility studies to assess the viability of developing renewable energy generating facilities on contaminated sites. Portsmouth Naval Shipyard (PNSY) is a United States Navy facility located on a series of conjoined islands in the Piscataqua River between Kittery, ME and Portsmouth, NH. EPA engaged NREL to conduct a study to determine technical feasibility of deploying ground-source heat pump systems to help PNSY achieve energy reduction goals.

Hillesheim, M.; Mosey, G.

2014-11-01T23:59:59.000Z

185

Naval Petroleum Reserve No. 3 (NPR-3), Teapot Dome Field, Wyoming: Case history of the in situ combustion pilot operation  

SciTech Connect

Naval Petroleum Reserve No. 3 (NPR-3) is a federally owned oil field that has been in operation since 1922 and has produced more than 15 million barrels of oil since full production began in 1976. The Shannon sandstone is the shallowest and most productive of nine producing formations at NPR-3. Since only 5% of the Shannon`s estimated 144 million bbl of original oil in place (OOIP) was estimated to be recoverable by primary means, studies were undertaken in 1978 to determine the most suitable enhanced oil recovery (EOR) method which would merit a pilot test and could ultimately lead to a fieldwide application.

Sarathi, P.S.; Olsen, D.K.; Williams, C.R.

1995-02-01T23:59:59.000Z

186

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

Office of Scientific and Technical Information (OSTI)

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

187

Portfolio for fast reactor collaboration  

SciTech Connect

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

Rippon, S.

1981-12-01T23:59:59.000Z

188

Naval Research Laboratory`s programs in advanced indium phosphide solar cell development  

SciTech Connect

The Naval Research Laboratory has been involved in developing InP solar cell technology since 1988. The purpose of these programs was to produce advanced cells for use in very high radiation environments, either as a result of operating satellites in the Van Allen belts or for very long duration missions in other orbits. Richard Statler was technical representative on the first program, with Spire Corporation as the contractor, which eventually produced several hundred, high efficiency 2 x 2 sq cm single crystal InP cells. The shallow homojunction technology which was developed in this program enabled cells to be made with AMO, one sun efficiencies greater than 19%. Many of these cells have been flown on space experiments, including PASP Plus, which have confirmed the high radiation resistance of InP cells. NRL has also published widely on the radiation response of these cells and also on radiation-induced defect levels detected by DLTS, especially the work of Rob Walters and Scott Messenger. In 1990 NRL began another Navy-sponsored program with Tim Coutts and Mark Wanlass at the National Renewable Energy Laboratory (NREL), to develop a one sun, two terminal space version of the InP-InGaAs tandem junction cell being investigated at NREL for terrestrial applications. These cells were grown on InP substrates. Several cells with AMO, one sun efficiencies greater than 22% were produced. Two 2 x 2 sq cm cells were incorporated on the STRV lA/B solar cell experiment. These were the only two junction, tandem cells on the STRV experiment. The high cost and relative brittleness of InP wafers meant that if InP cell technology were to become a viable space power source, the superior radiation resistance of InP would have to be combined with a cheaper and more robust substrate. The main technical challenge was to overcome the effect of the dislocations produced by the lattice mismatch at the interface of the two materials.

Summers, G.P.

1995-10-01T23:59:59.000Z

189

Handbook of Reactor Physics  

Science Journals Connector (OSTI)

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

PETER W. MUMMERY

1956-08-25T23:59:59.000Z

190

Fast reactor safety  

Science Journals Connector (OSTI)

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

R.D. SMITH

1979-08-23T23:59:59.000Z

191

Instrumentation of Nuclear Reactors  

Science Journals Connector (OSTI)

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

1953-03-07T23:59:59.000Z

192

Nuclear Research Reactors  

Science Journals Connector (OSTI)

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

T. E. ALLIBONE

1963-07-20T23:59:59.000Z

193

Canadian university research reactors  

SciTech Connect

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

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

1989-11-01T23:59:59.000Z

194

Reactor & Nuclear Systems Publications | ORNL  

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

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

195

EIS-0020: Crude Oil Transport Alternate From Naval Petroleum Reserve No. 1 Elk Hills/SOHIO Pipeline Connection Conveyance System, Terminal Tank Farm Relocation to Rialto, California  

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

The Office of Naval Petroleum and Oil Shale Reserves developed this supplemental statement to evaluate the environmental impacts associated with a modified design of a proposed 250,000 barrels per day crude oil conveyance system from Navel Petroleum Reserve No. 1 to connect to the proposed SOHIO West Coast to Midcontinent Pipeline at Rialto, California. This SEIS is a supplement to DOE/EIS-0020, Crude Oil Transport Alternate From Naval Petroleum Reserve No. 1 Elk Hills/SOHIO Pipeline Connection Conveyance System, Terminal Tank Farm Relocation to Rialto, California.

196

Nuclear reactor control column  

DOE Patents (OSTI)

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

Bachovchin, Dennis M. (Plum Borough, PA)

1982-01-01T23:59:59.000Z

197

Reactor Safety Research Programs  

SciTech Connect

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S. K.

1981-07-01T23:59:59.000Z

198

Nuclear reactor reflector  

DOE Patents (OSTI)

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

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

1994-01-01T23:59:59.000Z

199

Spherical torus fusion reactor  

DOE Patents (OSTI)

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

Martin Peng, Y.K.M.

1985-10-03T23:59:59.000Z

200

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

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


201

Reactor hot spot analysis  

SciTech Connect

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

Vilim, R.B.

1985-08-01T23:59:59.000Z

202

Molten metal reactors  

DOE Patents (OSTI)

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

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

2013-11-05T23:59:59.000Z

203

EA-1956: Site-Wide Environmental Assessment for the Divestiture of Rocky Mountain Oilfield Testing Center and Naval Petroleum Reserve No. 3, Natrona County, Wyoming  

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

Draft Site-Wide EA: Public Comment Period Ends 04/14/2014DOE is preparing an EA to assess potential environmental impacts of the proposed discontinuation of DOE operations at, and the proposed divestiture of, the Rocky Mountain Oilfield Testing Center (RMOTC) and Naval Petroleum Reserve Number 3 (NPR-3).

204

Captain Erik Stohlmann graduated from high school in Fort Worth, TX before attending the United States Naval Academy. He was commissioned in 1992 after earning a Bachelor of  

E-Print Network (OSTI)

Science. Following the Naval Academy, he was assigned to NAS Pensacola, FL for Flight Training. After flown during OPERATION IRAQI FREEDOM as well as numerous contingency operations in the CENTCOM AOR. He was selected for redesignation as a Navy Foreign Area Officer. Captain Stohlmann' s staff assignments include

205

F Reactor Inspection  

ScienceCinema (OSTI)

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

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-11-24T23:59:59.000Z

206

F Reactor Inspection  

SciTech Connect

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

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-10-29T23:59:59.000Z

207

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

208

REACTOR GROUT THERMAL PROPERTIES  

SciTech Connect

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

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

2011-01-28T23:59:59.000Z

209

B Reactor | Department of Energy  

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

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

210

Vettor Fausto (1490-1546), Professor of Greek and a Naval Architect: A New Light on the 16th-century Manuscript Misure di vascelli etc. diproto dellArsenale di Venetia  

E-Print Network (OSTI)

century in Venetian naval architecture. Early in the 16th century, the maritime power of Venice was seriously threatened by the Ottoman Sultan Suleiman II in the East and by the Holy Roman Emperor Charles V in the West. In order to regain its naval... power in the Mediterranean, the Republic of Venice strongly encouraged Venetian shipwrights to submit new designs for war galleys. The undisputed founder and champion of this naval program was not a skilled shipwright but a young professor of Greek...

Campana, Lilia 1975-

2010-12-06T23:59:59.000Z

211

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

212

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

213

Reactor for exothermic reactions  

DOE Patents (OSTI)

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

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

1993-03-02T23:59:59.000Z

214

Thermionic Reactor Design Studies  

SciTech Connect

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

Schock, Alfred

1994-08-01T23:59:59.000Z

215

EIS-0290-SA-02: Supplement Analysis | Department of Energy  

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

2: Supplement Analysis EIS-0290-SA-02: Supplement Analysis Naval Reactors Facility Sludge Pan Container Disposition Project DOEEIS-0290-SA-02: Supplement Analysis Naval Reactors...

216

Diagnostics for hybrid reactors  

SciTech Connect

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

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

2012-06-19T23:59:59.000Z

217

Structural materials for fusion reactors  

Science Journals Connector (OSTI)

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

P. M. Raole; S. P. Deshpande

2009-04-01T23:59:59.000Z

218

Reactor Materials | Department of Energy  

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

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

219

Reactor operation safety information document  

SciTech Connect

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

Not Available

1990-01-01T23:59:59.000Z

220

Fossil fuel furnace reactor  

DOE Patents (OSTI)

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

Parkinson, William J. (Los Alamos, NM)

1987-01-01T23:59:59.000Z

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


221

Transport reactor development status  

SciTech Connect

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

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

1994-10-01T23:59:59.000Z

222

Thermal Reactor Safety  

SciTech Connect

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

Not Available

1980-06-01T23:59:59.000Z

223

NETL - Chemical Looping Reactor  

ScienceCinema (OSTI)

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

None

2014-06-26T23:59:59.000Z

224

The Navy seeks to identify responsible sources and obtain information in regard to purchasing renewable power for Naval Air Station (NAS) Fallon, located in Fallon, NV  

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

REQUEST FOR INFORMATION (RFI) for Renewable Generation REQUEST FOR INFORMATION (RFI) for Renewable Generation Opportunities at NAWS China Lake, NAS Fallon, MCAGCC 29 Palms, and MCAS Yuma The Department of Navy (DoN) intends to issue a Request for Proposal (RFP) in early 2009 for renewable energy generation opportunities at Naval Air Weapons Station (NAWS) China Lake, California; Naval Air Station (NAS) Fallon, Nevada; Marine Corps Air Ground Combat Center (MCAGCC) Twentynine Palms, California, and Marine Corps Air Station (MCAS) Yuma, Arizona. The DoN will consider opportunities for the purchase of renewable power, developer wholesale generation, distributed generation, and the combination of those opportunities. Specifically, the Navy will provide Government land on these installations for large

225

Reactor vessel support system. [LMFBR  

DOE Patents (OSTI)

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

Golden, M.P.; Holley, J.C.

1980-05-09T23:59:59.000Z

226

Fusion reactor systems  

Science Journals Connector (OSTI)

In this review we consider deuterium-tritium (D-T) fusion reactors based on four different plasma-confinement and heating approaches: the tokamak, the theta-pinch, the magnetic-mirror, and the laser-pellet system. We begin with a discussion of the dynamics of reacting plasmas and basic considerations of reactor power balance. The essential plasma physical aspects of each system are summarized, and the main characteristics of the corresponding conceptual power plants are described. In tokamak reactors the plasma densities are about 1020 m-3, and the ? values (ratio of plasma pressure to confining magnetic pressure) are approximately 5%. Plasma burning times are of the order of 100-1000 sec. Large superconducting dc magnets furnish the toroidal magnetic field, and 2-m thick blankets and shields prevent heat deposition in the superconductor. Radially diffusing plasma is diverted away from the first wall by means of null singularities in the poloidal (or transverse) component of the confining magnetic field. The toroidal theta-pinch reactor has a much smaller minor diameter and a much larger major diameter, and operates on a 10-sec cycle with 0.1-sec burning pulses. It utilizes shock heating from high-voltage sources and adabatic-compression heating powered by low-voltage, pulsed cryogenic magnetic or inertial energy stores, outside the reactor core. The plasma has a density of about 1022 m-3 and ? values of nearly unity. In the power balance of the reactor, direct-conversion energy obtained by expansion of the burning high-? plasma against the containing magnetic field is an important factor. No divertor is necessary since neutral-gas flow cools and replaces the "spent" plasma between pulses. The open-ended mirror reactor uses both thermal conversion of neutron energy and direct conversion of end-loss plasma energy to dc electrical power. A fraction of this direct-convertor power is then fed back to the ioninjection system to sustain the reaction and maintain the plasma. The average ion energy is 600 keV, plasma diameter 6 m, and the plasma beta 85%. The power levels of the three magnetic-confinement devices are in the 500-2000 MWe range, with the exception of the mirror reactor, for which the output is approximately 200 MWe. In Laser-Pellet reactors, frozen D-T pellets are ignited in a cavity which absorbs the electromagnetic, charged particle, and neutron energy from the fusion reaction. The confinement is "inertial," since the fusion reaction occurs during the disassembly of the heated pellet. A pellet-cavity unit would produce about 200 MWt in pulses with a repetition rate of the order of 10 sec-1. Such units could be clustered to give power plants with outputs in the range of 1000 MWe.

F. L. Ribe

1975-01-01T23:59:59.000Z

227

Nuclear reactor construction with bottom supported reactor vessel  

DOE Patents (OSTI)

An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core within the pool. The reactor vessel has an open top end, a closed flat bottom end wall and a continuous cylindrical closed side wall interconnecting the top end and bottom end wall. The reactor also has a generally cylindrical concrete containment structure surrounding the reactor vessel and being formed by a cylindrical side wall spaced outwardly from the reactor vessel side wall and a flat base mat spaced below the reactor vessel bottom end wall. A central support pedestal is anchored to the containment structure base mat and extends upwardly therefrom to the reactor vessel and upwardly therefrom to the reactor core so as to support the bottom end wall of the reactor vessel and the lower end of the reactor core in spaced apart relationship above the containment structure base mat. Also, an annular reinforced support structure is disposed in the reactor vessel on the bottom end wall thereof and extends about the lower end of the core so as to support the periphery thereof. In addition, an annular support ring having a plurality of inward radially extending linear members is disposed between the containment structure base mat and the bottom end of the reactor vessel wall and is connected to and supports the reactor vessel at its bottom end on the containment structure base mat so as to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event. The reactor construction also includes a bed of insulating material in sand-like granular form, preferably being high density magnesium oxide particles, disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall on the containment structure base mat so as to insulate the reactor vessel bottom end wall from the containment structure base mat and allow the reactor vessel bottom end wall to freely expand as it heats up while providing continuous support thereof. Further, a deck is supported upon the side wall of the containment structure above the top open end of the reactor vessel, and a plurality of serially connected extendible and retractable annular bellows extend between the deck and the top open end of the reactor vessel and flexibly and sealably interconnect the reactor vessel at its top end to the deck. An annular guide ring is disposed on the containment structure and extends between its side wall and the top open end of the reactor vessel for providing lateral support of the reactor vessel top open end by limiting imposition of lateral loads on the annular bellows by the occurrence of a lateral seismic event.

Sharbaugh, John E. (Bullskin Township, Fayette County, PA)

1987-01-01T23:59:59.000Z

228

Proposed natural gas protection program for Naval Oil Shale Reserves Nos. 1 and 3, Garfield County, Colorado  

SciTech Connect

As a result of US Department of Energy (DOE) monitoring activities, it was determined in 1983 that the potential existed for natural gas resources underlying the Naval Oil Shales Reserves Nos. 1 and 3 (NOSrs-1 3) to be drained by privately-owned gas wells that were being drilled along the Reserves borders. In 1985, DOE initiated a limited number of projects to protect the Government's interest in the gas resources by drilling its own offset production'' wells just inside the boundaries, and by formally sharing in the production, revenues and costs of private wells that are drilled near the boundaries ( communitize'' the privately-drilled wells). The scope of these protection efforts must be expanded. DOE is therefore proposing a Natural Gas Protection Program for NOSRs-1 3 which would be implemented over a five-year period that would encompass a total of 200 wells (including the wells drilled and/or communitized since 1985). Of these, 111 would be offset wells drilled by DOE on Government land inside the NOSRs' boundaries and would be owned either entirely by the Government or communitized with adjacent private land owners or lessees. The remainder would be wells drilled by private operators in an area one half-mile wide extending around the NOSRs boundaries and communitized with the Government. 23 refs., 2 figs., 6 tabs.

Not Available

1991-08-01T23:59:59.000Z

229

Analysis of the potential for enhanced oil recovery in the Shannon Formation at Naval Petroleum Reserve Number 3. Master's thesis  

SciTech Connect

Three EOR processes were evaluated for potential application in the Shannon reservoir at Naval Petroleum Reserve No. 3, in the Teapot Dome Oilfield near Casper, Wyoming. This reservoir is estimated to have originally held 180 million barrels of oil, of which only 8 million barrels are recoverable by primary means. Simplified computer models were used to predict the performance of in-situ combustion, polymer flooding, and steam flooding. Economic analyses were done on the results of these predictions and sensitivity studies were performed for various physical and economic parameters. This report provides a foundation of information, offers a template for economic decisions, and makes preliminary recommendations based on performance predictions. Before field-wide application of any project is undertaken, a better characterization of the reservoir must be accomplished and pilot projects evaluated. However, this analysis suggest that the most favorable application in the Shannon Sandstone is polymer flooding operated on 2.5-acre spacing. This technique is predicted to give a net present value of $5.43 million per 10-acre unit with a present value ration of 9.4 for its four year economic life.

Chappelle, H.H.

1985-05-01T23:59:59.000Z

230

Spherical torus fusion reactor  

DOE Patents (OSTI)

A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.

Peng, Yueng-Kay M. (Oak Ridge, TN)

1989-01-01T23:59:59.000Z

231

Nuclear divisional reactor  

SciTech Connect

A nuclear divisional reactor including a reactor core having side and top walls, a heat exchanger substantially surrounding the core, the heat exchanger including a plurality of separate fluid holding and circulating chambers each in contact with a portion of the core, control rod means associated with the core and external of the heat exchanger including control rods and means for moving said control rods, each of the chambers having separate means for delivering and removing fluid therefrom, separate means associated with each of the delivering and removing means for producing useable energy external of the chambers, each of the means for producing useable energy having separate variable capacity energy outputs thereby making available a plurality of individual sources of useable energy of varying degrees.

Administratrix, A.P.; Rugh, J.L.

1982-11-02T23:59:59.000Z

232

Fusion reactor pumped laser  

DOE Patents (OSTI)

A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam. 10 figs.

Jassby, D.L.

1987-09-04T23:59:59.000Z

233

Evaluation of Concepts for Mulitiple Application Thermal Reactor for Irradiation eXperiments (MATRIX)  

SciTech Connect

The Advanced Test Reactor (ATR) is a high power density test reactor specializing in fuel and materials irradiation. For more than 45 years, the ATR has provided irradiations of materials and fuels testing along with radioisotope production. Originally operated primarily in support of the Offcie of Naval Reactors (NR), the mission has gradually expanded to cater to other customers, such as the DOE Office of Nuclear Energy (NE), private industry, and universities. Unforeseen circumstances may lead to the decommissioning of ATR, thus leaving the U.S. Government without a large-scale materials irradiation capability to meet the needs of its nuclear energy and naval reactor missions. In anticipation of this possibility, work was performed under the Laboratory Directed Research and Development (LDRD) program to investigate test reactor concepts that could satisfy the current missions of the ATR along with an expanded set of secondary missions. This work can be viewed as an update to a project from the 1990s called the Broad Application Test Reactor (BATR). In FY 2012, a survey of anticipated customer needs was performed, followed by analysis of the original BATR concepts with fuel changed to low-enriched uranium. Departing from these original BATR designs, four concepts were identified for further analysis in FY2013. The project informally adopted the acronym MATRIX (Multiple-Application Thermal Reactor for Irradiation eXperiments). This report discusses analysis of the four MATRIX concepts along with a number of variations on these main concepts. Designs were evaluated based on their satisfaction of anticipated customer requirements and the Cylindrical variant was selected for further analysis of options. This downselection should be considered preliminary and the backup alternatives should include the other three main designs. The baseline Cylindrical MATRIX design is expected to be capable of higher burnup than the ATR (or longer cycle length given a particular batch scheme). The volume of test space in IPTs is larger in MATRIX than in ATR with comparable magnitude of neutron flux. In addition to the IPTs, the Cylindrical MATRIX concept features test spaces at the centers of fuel assemblies where very high fast flux can be achieved. This magnitude of fast flux is similar to that achieved in the ATR A-positions, however, the available volume having these conditions is greater in the MATRIX design than in the ATR. From the analyses performed in this work, it appears that the Cylindrical MATRIX design can be designed to meet the anticipated needs of the ATR replacement reactor. However, this statement must be qualified by acknowledging that this design is quite immature, and therefore any requirements currently met must be re-evaluated as the design matures. Also, some of the requirements were not strictly met, but are believed to be achievable once features to be added later are designed.

Michael A. Pope; Hans D. Gougar; John M. Ryskamp

2013-09-01T23:59:59.000Z

234

Thermionic Reactor Design Studies  

SciTech Connect

During the 1960's and early 70's the author performed extensive design studies, analyses, and tests aimed at thermionic reactor concepts that differed significantly from those pursued by other investigators. Those studies, like most others under Atomic Energy Commission (AEC and DOE) and the National Aeronautics and Space Administration (NASA) sponsorship, were terminated in the early 1970's. Some of this work was previously published, but much of it was never made available in the open literature. U.S. interest in thermionic reactors resumed in the early 80's, and was greatly intensified by reports about Soviet ground and flight tests in the late 80's. This recent interest resulted in renewed U.S. thermionic reactor development programs, primarily under Department of Defense (DOD) and Department of Energy (DOE) sponsorship. Since most current investigators have not had an opportunity to study all of the author's previous work, a review of the highlights of that work may be of value to them. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling. Where the author's concepts differed from the later Topaz-2 design was in the relative location of the emitter and the collector. Placing the fueled emitter on the outside of the cylindrical diodes permits much higher axial conductances to reduce ohmic losses in the electrodes of full-core-height diodes. Moreover, placing the fuel on the outside of the diode makes possible reactors with much higher fuel volume fractions, which enable power-flattened fast reactors scalable to very low power levels without the need for life-limiting hydride moderators or the use of efficiency-limiting driver fuel. In addition, with the fuel on the outside its swelling does not increase the emitter diameter or reduce the interelectrode gap. This should permit long lifetimes even with closer spacings, which can significantly improve the system efficiences. This was confirmed by coupled neutronic, thermal, thermionic, and electrical system analyses - some of which are presented in this paper - and by subsequent experiments. A companion paper presented next describes the fabrication and testing of full-scale converter elements, both fueled and unfueled, and summarizes the test results obtained. There is a duplicate copy in the file.

Schock, Alfred

1994-06-01T23:59:59.000Z

235

CX-008819: Categorical Exclusion Determination  

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

Naval Reactors Facility Parking Lot Expansion General Plant Project CX(s) Applied: B1.15 Date: 06/20/2012 Location(s): Idaho Offices(s): Naval Nuclear Propulsion Program, Naval Reactors

236

Massive Hanford Test Reactor Removed - Plutonium Recycle Test...  

Office of Environmental Management (EM)

Massive Hanford Test Reactor Removed - Plutonium Recycle Test Reactor removed from Hanford's 300 Area Massive Hanford Test Reactor Removed - Plutonium Recycle Test Reactor removed...

237

Nuclear Reactor Severe Accident Experiments  

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

Nuclear Reactor Severe Accident Experiments Nuclear Reactor Severe Accident Experiments Capabilities Engineering Experimentation Reactor Safety Testing and Analysis Overview Nuclear Reactor Severe Accident Experiments MAX NSTF SNAKE 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 Nuclear Reactor Severe Accident Experiments 1 2 3 4 5 6 7 We perform experiments simulating reactor core melt phenomena in which molten core debris ("corium") erodes the concrete floor of a containment building. This occurred during the Fukushima nuclear power plant accident though the extent of concrete damage is yet unknown. This video shows the top view of a churning molten pool of uranium oxide at 2000°C (3600°F) seen during an experiment at Argonne. Corium behaves much like lava.

238

Nuclear Reactor Materials and Fuels  

Science Journals Connector (OSTI)

Nuclear reactor materials and fuels can be classified into six categories: Nuclear fuel materials Nuclear clad materials Nuclear coolant materials Nuclear poison materials Nuclear moderator materials

Dr. James S. Tulenko

2012-01-01T23:59:59.000Z

239

Thermonuclear Reflect AB-Reactor  

E-Print Network (OSTI)

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

Alexander Bolonkin

2008-03-26T23:59:59.000Z

240

Light Water Reactor Sustainability Newsletter  

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

hydraulics software RELAP-7 (which is under development in the Light Water Reactor Sustainability LWRS Program). A novel interaction between the probabilistic part (i.e., RAVEN)...

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


241

Joint environmental assessment for western NPR-1 3-dimensional seismic project at Naval Petroleum Reserve No. 1, Kern County, California  

SciTech Connect

The Department of Energy (DOE), in conjunction with the Bureau of Land Management (BLM), has prepared an Environmental Assessment (DOE/EA-1124) to identify and evaluate the potential environmental impacts of the proposed geophysical seismic survey on and adjacent to the Naval Petroleum Reserve No.1 (NPR-1), located approximately 35 miles west of Bakersfield, California. NPR-1 is jointly owned and operated by the federal government and Chevron U.S.A. Production Company. The federal government owns about 78 percent of NPR-1, while Chevron owns the remaining 22 percent. The government`s interest is under the jurisdiction of DOE, which has contracted with Bechtel Petroleum Operations, Inc. (BPOI) for the operation and management of the reserve. The 3-dimensional seismic survey would take place on NPR-1 lands and on public and private lands adjacent to NPR-1. This project would involve lands owned by BLM, California Department of Fish and Game (CDFG), California Energy Commission (CEC), The Nature Conservancy, the Center for Natural Lands Management, oil companies (Chevron, Texaco, and Mobil), and several private individuals. The proposed action is designed to provide seismic data for the analysis of the subsurface geology extant in western NPR-1 with the goal of better defining the commercial limits of a currently producing reservoir (Northwest Stevens) and three prospective hydrocarbon bearing zones: the {open_quotes}A Fan{close_quotes} in Section 7R, the 19R Structure in Section 19R, and the 13Z Structure in Section 13Z. Interpreting the data is expected to provide NPR-1 owners with more accurate locations of structural highs, faults, and pinchouts to maximize the recovery of the available hydrocarbon resources in western NPR-1. Completion of this project is expected to increase NPR-1 recoverable reserves, and reduce the risks and costs associated with further exploration and development in the area.

NONE

1996-05-01T23:59:59.000Z

242

Reactor coolant pump flywheel  

DOE Patents (OSTI)

A flywheel for a pump, and in particular a flywheel having a number of high density segments for use in a nuclear reactor coolant pump. The flywheel includes an inner member and an outer member. A number of high density segments are provided between the inner and outer members. The high density segments may be formed from a tungsten based alloy. A preselected gap is provided between each of the number of high density segments. The gap accommodates thermal expansion of each of the number of segments and resists the hoop stress effect/keystoning of the segments.

Finegan, John Raymond; Kreke, Francis Joseph; Casamassa, John Joseph

2013-11-26T23:59:59.000Z

243

Biparticle fluidized bed reactor  

DOE Patents (OSTI)

A fluidized bed reactor system utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves. 3 figs.

Scott, C.D.; Marasco, J.A.

1995-04-25T23:59:59.000Z

244

Biparticle fluidized bed reactor  

DOE Patents (OSTI)

A fluidized bed reactor system is described which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary and tertiary particulate phases, continuously introduced and removed simultaneously in the cocurrent and countercurrent mode, act in a role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Means for introducing and removing the sorbent phases include feed screw mechanisms and multivane slurry valves. 3 figs.

Scott, C.D.; Marasco, J.A.

1996-02-27T23:59:59.000Z

245

Nuclear reactor control apparatus  

DOE Patents (OSTI)

Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additional magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

Sridhar, Bettadapur N. (Cupertino, CA)

1983-11-01T23:59:59.000Z

246

Modular Pebble Bed Reactor High Temperature Gas Reactor  

E-Print Network (OSTI)

Modular Pebble Bed Reactor High Temperature Gas Reactor Andrew C Kadak Massachusetts Institute For 1150 MW Combined Heat and Power Station Oil Refinery Hydrogen Production Desalinization Plant VHTR/Graphite Discrimination system Damaged Sphere ContainerGraphiteReturn FuelReturn Fresh Fuel Container Spent Fuel Tank #12

247

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

Assessment of High Value Surveillance Materials Assessment of High Value Surveillance Materials Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Assessment of High Value Surveillance Materials The reactor pressure vessel (RPV) in a light-water reactor (LWR) represents the first line of defense against a release of radiation in case of an accident. Thus, regulations that govern the operation of commercial nuclear power plants require conservative margins of fracture toughness, both during normal operation and under accident scenarios. In the unirradiated condition, the RPV has sufficient fracture toughness such that failure is implausible under any postulated condition, including pressurized thermal shock (PTS) in pressurized water reactors (PWR). In the irradiated condition, however, the fracture toughness of the RPV may be severely

248

DOE Drops Plan to Restart Reactor  

Science Journals Connector (OSTI)

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

Robert F. Service

2000-12-01T23:59:59.000Z

249

Operational Analysis of Multiregional Nuclear Reactor Kinetics  

Science Journals Connector (OSTI)

......Operational Analysis of Multiregional Nuclear Reactor Kinetics NASSAR H. S. HAIDAR...analytically for a multiregional nuclear reactor whose subregions are of arbitrary...Operational Analysis of Multiregional Nuclear Reactor Kinetics NASSAU H. S. HAIDAR......

NASSAR H. S. HAIDAR

1983-05-01T23:59:59.000Z

250

Solvent refined coal reactor quench system  

DOE Patents (OSTI)

There is described an improved SRC reactor quench system using a condensed product which is recycled to the reactor and provides cooling by evaporation. In the process, the second and subsequent reactors of a series of reactors are cooled by the addition of a light oil fraction which provides cooling by evaporation in the reactor. The vaporized quench liquid is recondensed from the reactor outlet vapor stream. 1 fig.

Thorogood, R.M.

1983-11-08T23:59:59.000Z

251

Temperature effects on chemical reactor  

Science Journals Connector (OSTI)

In this paper we had to study some characteristics of the chemical reactors from which we can understand the reactor operation in different circumstances; from these and the most important factor that has a great effect on the reactor operation is the temperature it is a mathematical processing of a chemical problem that was already studied but it may be developed by introducing new strategies of control; in our case we deal with the analysis of a liquid?gas reactor which can make the flotation of the benzene to produce the ethylene; this type of reactors can be used in vast domains of the chemical industry especially in refinery plants where we find the oil separation and its extractions whether they are gases or liquids which become necessary for industrial technology especially in our century.

M. Azzouzi

2008-01-01T23:59:59.000Z

252

THE MATERIALS OF FAST BREEDER REACTORS  

E-Print Network (OSTI)

metal fast breeder reactor (LMFBR) concern the behavior ofmetal fast breeder reactor (LMFBR). Despite the simplicityinduced by irradiation. LMFBR funding is the largest single

Olander, Donald R.

2013-01-01T23:59:59.000Z

253

Nuclear reactors in the United States  

Science Journals Connector (OSTI)

Nuclear reactors in the United States ... A chart listing the operating and planned nuclear reactors in the United States. ... Nuclear / Radiochemistry ...

Hubert N. Alyea

1956-01-01T23:59:59.000Z

254

Advanced Reactor Research and Development Funding Opportunity...  

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

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

255

LIGHT WATER REACTOR SUSTAINABILITY PROGRAM: INTRODUCTION  

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

LIGHT WATER REACTOR SUSTAINABILITY PROGRAM: INTRODUCTION The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1...

256

MOOSE simulating nuclear reactor CRUD buildup  

SciTech Connect

This simulation uses multiple physical models to show how the buildup of boron deposits on reactor fuel can affect performance and the reactor's power profile.

None

2014-02-06T23:59:59.000Z

257

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

258

Granular Dynamics in Pebble Bed Reactor Cores  

E-Print Network (OSTI)

pebble bed reactor, Nuclear Engineering and Design, vol.the AVR reactor, Nuclear Engineering and Design, vol. 121,Operating Experience, Nuclear Engineering and Design, vol.

Laufer, Michael Robert

2013-01-01T23:59:59.000Z

259

F Reactor Inspection | Department of Energy  

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

Inspection F Reactor Inspection Addthis Description Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor last week before...

260

Physics of nuclear reactor safety  

Science Journals Connector (OSTI)

Provides a concise review of the physical aspects of safety of nuclear fission reactors. It covers the developments of roughly the last decade. The introductory chapter contains an analysis of the changes in safety philosophy that are characteristic of the last decade and that have given rise to an increased importance of physical aspects because of the emphasis on passive or natural safety. The second chapter focuses on the basics of reactor safety, identifying the main risk sources and the main principles for a safe design. The third chapter concerns a systematic treatment of the physical processes that are fundamental for the properties of fission chain reacting processes and the control of those processes. Because of the rather specialized nature of the field of reactor physics, each paragraph contains a very concise description of the theory of the phenomenon under consideration, before presenting a review of the developments. Chapter 4 contains a short review of the thermal aspects of reactor safety, restricted to those aspects that are characteristic of the nuclear reactor field, because thermal hydraulics of fission reactors is not principally different from that of other physical systems. In chapter 5 the consequences of the physics treated in the preceding chapters for the dynamics and safety of actual reactors are reviewed. The systematics of the treatment is mainly based on a division of reactors into three categories according to the type of coolant, which to a large extent determines the safety properties of the reactors. The last chapter contains a physical analysis of the Chernobyl accident that occurred in 1986. The reason for an attempt to give a review of this accident, as complete as possible within the space limits set by the editors, is twofold: the Chernobyl accident is the most severe accident in history and physical properties of the reactor played a decisive role, thereby serving as an illustration of the material of the preceding chapters.

H van Dam

1992-01-01T23:59:59.000Z

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


261

13 - Generation IV reactor designs, operation and fuel cycle  

Science Journals Connector (OSTI)

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

N. Cerullo; G. Lomonaco

2012-01-01T23:59:59.000Z

262

University Reactor Conversion Lessons Learned Workshop for Purdue University Reactor  

SciTech Connect

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

Eric C. Woolstenhulme; Dana M. Hewit

2008-09-01T23:59:59.000Z

263

Assessment of torsatrons as reactors  

SciTech Connect

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R[sub 0] = 6.6-8.8 m, on-axis magnetic field B[sup 0] = 4.8-7.5 T, B[sub max] (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions.

Lyon, J.F. (Oak Ridge National Lab., TN (United States)) [Oak Ridge National Lab., TN (United States); Painter, S.L. (Australian National Univ., Canberra, ACT (Australia)) [Australian National Univ., Canberra, ACT (Australia)

1992-12-01T23:59:59.000Z

264

Assessment of torsatrons as reactors  

SciTech Connect

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R{sub 0} = 6.6-8.8 m, on-axis magnetic field B{sup 0} = 4.8-7.5 T, B{sub max} (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions.

Lyon, J.F. [Oak Ridge National Lab., TN (United States); Painter, S.L. [Australian National Univ., Canberra, ACT (Australia)

1992-12-01T23:59:59.000Z

265

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

266

Nuclear reactor downcomer flow deflector  

DOE Patents (OSTI)

A nuclear reactor having a coolant flow deflector secured to a reactor core barrel in line with a coolant inlet nozzle. The flow deflector redirects incoming coolant down an annulus between the core barrel and the reactor vessel. The deflector has a main body with a front side facing the fluid inlet nozzle and a rear side facing the core barrel. The rear side of the main body has at least one protrusion secured to the core barrel so that a gap exists between the rear side of the main body adjacent the protrusion and the core barrel. Preferably, the protrusion is a relief that circumscribes the rear side of the main body.

Gilmore, Charles B. (Greensburg, PA); Altman, David A. (Pittsburgh, PA); Singleton, Norman R. (Murrysville, PA)

2011-02-15T23:59:59.000Z

267

Naval electrochemical corrosion reducer  

DOE Patents (OSTI)

A corrosion reducer for use with ships having a hull, a propeller mounted a propeller shaft and extending through the hull, bearings supporting the shaft, at least one thrust bearing and one seal. The improvement includes a current collector and a current reduction assembly for reducing the voltage between the hull and shaft in order to reduce corrosion due to electrolytic action. The current reduction assembly includes an electrical contact, the current collector, and the hull. The current reduction assembly further includes a device for sensing and measuring the voltage between the hull and the shaft and a device for applying a reverse voltage between the hull and the shaft so that the resulting voltage differential is from 0 to 0.05 volts. The current reduction assembly further includes a differential amplifier having a voltage differential between the hull and the shaft. The current reduction assembly further includes an amplifier and a power output circuit receiving signals from the differential amplifier and being supplied by at least one current supply. The current selector includes a brush assembly in contact with a slip ring over the shaft so that its potential may be applied to the differential amplifier.

Clark, Howard L. (Ballston Lake, NY)

1991-10-01T23:59:59.000Z

268

Institution of Naval Architects  

Science Journals Connector (OSTI)

... H. C. Anstey for papers, respectively, on the resistance of thin plates and models in a current of water, and on the application of internal-combustion ... in a current of water, and on the application of internal-combustion engines for marine propulsion. Thirteen papers in all were presented at the meetings, abstracts from ...

1910-03-24T23:59:59.000Z

269

Annual Report: 2010-2011 Storm Season Sampling For NON-DRY DOCK STORMWATER MONITORING FOR PUGET SOUND NAVAL SHIPYARD, BREMERTON, WA  

SciTech Connect

This interim report summarizes the stormwater monitoring conducted for non-dry dock outfalls in both the confined industrial area and the residential areas of Naval Base Kitsap within the Puget Sound Naval Shipyard (referred to as the Shipyard). This includes the collection, analyses, and descriptive statistics for stormwater sampling conducted from November 2010 through April 2011. Seven stormwater basins within the Shipyard were sampled during at least three storm events to characterize non-dry dock stormwater discharges at selected stormwater drains located within the facility. This serves as the Phase I component of the project and Phase II is planned for the 2011-2012 storm season. These data will assist the Navy, USEPA, Ecology and other stakeholders in understanding the nature and condition of stormwater discharges from the Shipyard and inform the permitting process for new outfall discharges. The data from Phase I was compiled with current stormwater data available from the Shipyard, Sinclair/Dyes Inlet watershed, and Puget Sound in order to support technical investigations for the Draft NPDES permit. The permit would require storm event sampling at selected stormwater drains located within the Shipyard. However, the data must be considered on multiple scales to truly understand potential impairments to beneficial uses within Sinclair and Dyes Inlets.

Brandenberger, Jill M.; Metallo, David; Johnston, Robert K.; Gebhardt, Christine; Hsu, Larry

2012-09-01T23:59:59.000Z

270

DOE/EA-1583: Final Site-wide Environmental Assessment and Finding of No Significant Impact for Rocky Mountain Oilfield Testing Center/Naval Petroleum Reserve No. 3 (October 2008)  

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

ROCKY MOUNTAIN OILFIELD TESTING CENTER / ROCKY MOUNTAIN OILFIELD TESTING CENTER / NAVAL PETROLEUM RESERVE NO. 3 FINAL Site-wide Environmental Assessment and Finding of No Significant Impact October 2008 U.S. Department of Energy Rocky Mountain Oilfield Testing Center 907 N. Poplar Street, Suite 150 Casper WY 82601 DOE/EA-1583 Rocky Mountain Oilfield Testing Center / Naval Petroleum Reserve No.3 Final Site-Wide Environmental Assessment i TABLE OF CONTENTS Section Page ABBREVIATIONS AND ACRONYMS.................................................................................................vii SUMMARY ................................................................................................................................................ix 1.0 INTRODUCTION .........................................................................................................................1

271

2012 Annual Report Research Reactor Infrastructure Program  

SciTech Connect

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

Douglas Morrell

2012-11-01T23:59:59.000Z

272

Tritium diagnostics in a fusion reactor  

Science Journals Connector (OSTI)

Methods for controlling tritium in a fusion reactor are reviewed. The characteristic features of the...

A. I. Markin; N. I. Syromyatnikov; A. M. Belov

2010-05-01T23:59:59.000Z

273

Combustion synthesis continuous flow reactor  

DOE Patents (OSTI)

The present invention is a reactor for combustion synthesis of inorganic powders. The reactor includes a reaction vessel having a length and a first end and a second end. The reaction vessel further has a solution inlet and a carrier gas inlet. The reactor further has a heater for heating both the solution and the carrier gas. In a preferred embodiment, the reaction vessel is heated and the solution is in contact with the heated reaction vessel. It is further preferred that the reaction vessel be cylindrical and that the carrier gas is introduced tangentially into the reaction vessel so that the solution flows helically along the interior wall of the reaction vessel. As the solution evaporates and combustion produces inorganic material powder, the carrier gas entrains the powder and carries it out of the reactor.

Maupin, Gary D. (Richland, WA); Chick, Lawrence A. (West Richland, WA); Kurosky, Randal P. (Maple Valley, WA)

1998-01-01T23:59:59.000Z

274

Interfacial effects in fast reactors  

E-Print Network (OSTI)

The problem of increased resonance capture rates near zone interfaces in fast reactor media has been examined both theoretically and experimentally. An interface traversing assembly was designed, constructed and employed ...

Saidi, Mohammad Said

1979-01-01T23:59:59.000Z

275

Unique features of space reactors  

SciTech Connect

Space reactors are designed to meet a unique set of requirements; they must be sufficiently compact to be launched in a rocket to their operational location, operate for many years without maintenance and servicing, operate in extreme environments, and reject heat by radiation to space. To meet these restrictions, operating temperatures are much greater than in terrestrial power plants, and the reactors tend to have a fast neutron spectrum. Currently, a new generation of space reactor power plants is being developed. The major effort is in the SP-100 program, where the power plant is being designed for seven years of full power, and no maintenance operation at a reactor outlet operating temperature of 1350 K. 8 refs., 3 figs., 1 tab.

Buden, D.

1990-01-01T23:59:59.000Z

276

Nuclear Reactors and Technology; (USA)  

SciTech Connect

Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

Cason, D.L.; Hicks, S.C. (eds.)

1991-01-01T23:59:59.000Z

277

Reactor physics project final report  

E-Print Network (OSTI)

This is the final report in an experimental and theoretical program to develop and apply single- and few-element methods for the determination of reactor lattice parameters. The period covered by the report is January 1, ...

Driscoll, Michael J.

1970-01-01T23:59:59.000Z

278

Alternate-fuel reactor studies  

SciTech Connect

A number of studies related to improvements and/or greater understanding of alternate-fueled reactors is presented. These studies cover the areas of non-Maxwellian distributions, materials and lifetime analysis, a /sup 3/He-breeding blanket, tritium-rich startup effects, high field magnet support, and reactor operation spanning the range from full D-T operation to operation with no tritium breeding.

Evans, K. Jr.; Ehst, D.A.; Gohar, Y.; Jung, J.; Mattas, R.F.; Turner, L.R.

1983-02-01T23:59:59.000Z

279

Solar solids reactor  

DOE Patents (OSTI)

A solar powered kiln is provided, that is of relatively simple design and which efficiently uses solar energy. The kiln or solids reactor includes a stationary chamber with a rearward end which receives solid material to be reacted and a forward end through which reacted material is disposed of, and a screw conveyor extending along the bottom of the chamber for slowly advancing the material between the chamber ends. Concentrated solar energy is directed to an aperture at the forward end of the chamber to heat the solid material moving along the bottom of the chamber. The solar energy can be reflected from a mirror facing at an upward incline, through the aperture and against a heat-absorbing material near the top of the chamber, which moves towards the rear of the chamber to distribute heat throughout the chamber. Pumps at the forward and rearward ends of the chamber pump heated sweep gas through the length of the chamber, while minimizing the flow of gas through an open aperture through which concentrated sunlight is received.

Yudow, Bernard D. (Chicago, IL)

1987-01-01T23:59:59.000Z

280

Solar solids reactor  

DOE Patents (OSTI)

A solar powered kiln is provided, that is of relatively simple design and which efficiently uses solar energy. The kiln or solids reactor includes a stationary chamber with a rearward end which receives solid material to be reacted and a forward end through which reacted material is disposed of, and a screw conveyor extending along the bottom of the chamber for slowly advancing the material between the chamber ends. Concentrated solar energy is directed to an aperture at the forward end of the chamber to heat the solid material moving along the bottom of the chamber. The solar energy can be reflected from a mirror facing at an upward incline, through the aperture and against a heat-absorbing material near the top of the chamber, which moves towards the rear of the chamber to distribute heat throughout the chamber. Pumps at the forward and rearward ends of the chamber pump heated sweep gas through the length of the chamber, while minimizing the flow of gas through an open aperture through which concentrated sunlight is received.

Yudow, B.D.

1986-02-24T23:59:59.000Z

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


281

Novel Catalytic Membrane Reactors  

SciTech Connect

There are many industrial catalytic organic reversible reactions with amines or alcohols that have water as one of the products. Many of these reactions are homogeneously catalyzed. In all cases removal of water facilitates the reaction and produces more of the desired chemical product. By shifting the reaction to right we produce more chemical product with little or no additional capital investment. Many of these reactions can also relate to bioprocesses. Given the large number of water-organic compound separations achievable and the ability of the Compact Membrane Systems, Inc. (CMS) perfluoro membranes to withstand these harsh operating conditions, this is an ideal demonstration system for the water-of-reaction removal using a membrane reactor. Enhanced reaction synthesis is consistent with the DOE objective to lower the energy intensity of U.S. industry 25% by 2017 in accord with the Energy Policy Act of 2005 and to improve the United States manufacturing competitiveness. The objective of this program is to develop the platform technology for enhancing homogeneous catalytic chemical syntheses.

Stuart Nemser, PhD

2010-10-01T23:59:59.000Z

282

Evaluation of Torsatrons as reactors  

SciTech Connect

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors. This scoping study, which uses an integrated cost-minimization code that incorporates costing and reactor component models self-consistently with a 1-D energy transport calculation, shows that a torsatron reactor could also be economically competitive with a tokamak reactor. The projected cost of electricity (COE) estimated using the Advanced Reactor Innovation and Evaluation Studies (ARIES) costing algorithms is 65.6 mill/kW(e)h in constant 1992 dollars for a reference 1-GW(e) Compact Torsatron reactor case. The COE is relatively insensitive (<10% variation) over a wide range of assumptions, including variations in the maximum field allowed on the coils, the coil elongation, the shape of the density profile, the beta limit, the confinement multiplier, and the presence of a large loss region for alpha particles. The largest variations in the COE occur for variations in the electrical power output demanded and the plasma-coil separation ratio.

Lyon, J.F. [Oak Ridge National Lab., TN (United States); Gulec, K. [Univ. of Tennessee, Knoxville, TN (United States); Miller, R.L. [Los Alamos National Lab., NM (United States); El-Guebaly, L. [Univ. of Wisconsin, Madison, WI (United States)

1994-03-01T23:59:59.000Z

283

When Do Commercial Reactors Permanently Shut Down?  

Reports and Publications (EIA)

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

2011-01-01T23:59:59.000Z

284

Audit Report: OIG-0884 | Department of Energy  

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

Naval Reactors maintains responsibility for activities supporting the United States Naval fleet nuclear propulsion systems, including research and design, operations and...

285

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

SciTech Connect

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

Homan, F.J.

1990-06-20T23:59:59.000Z

286

Advanced Nuclear Reactors | Department of Energy  

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

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

287

Advanced Reactor Technology Documents | Department of Energy  

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

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

288

Microsoft Word - power_reactors_briggs.doc  

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

Most common - Boiling Water and Pressurized Most common - Boiling Water and Pressurized Water Reactors About 80% of the world's nuclear reactors used for generating electricity are either boiling water reactors or pressurized water reactors. Of these, about 30% are boiling water reactors and 70% are pressurized water reactors. All power reactors currently in use in the United States are of these two types. Both types of reactors have been very successfully used for reliable, on-demand, emissions-free electricity generation for decades. How does a boiling water reactor work? Water flows from the bottom of the fuel to the top of the fuel, and as it moves past the fuel, it carries away the heat produced by the

289

PIA - Advanced Test Reactor National Scientific User Facility...  

Energy Savers (EERE)

Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor...

290

Global Optimization of Chemical Reactors and Kinetic Optimization  

E-Print Network (OSTI)

Model; 3-D; Monolith; Reactor; Optimization Introduction TheAngeles Global Optimization of Chemical Reactors and KineticGlobal Optimization of Chemical Reactors and Kinetic

ALHUSSEINI, ZAYNA ISHAQ

2013-01-01T23:59:59.000Z

291

UCLA program in reactor studies: The ARIES tokamak reactor study  

SciTech Connect

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

Not Available

1991-01-01T23:59:59.000Z

292

Rapid starting methanol reactor system  

DOE Patents (OSTI)

The invention relates to a methanol-to-hydrogen cracking reactor for use with a fuel cell vehicular power plant. The system is particularly designed for rapid start-up of the catalytic methanol cracking reactor after an extended shut-down period, i.e., after the vehicular fuel cell power plant has been inoperative overnight. Rapid system start-up is accomplished by a combination of direct and indirect heating of the cracking catalyst. Initially, liquid methanol is burned with a stoichiometric or slightly lean air mixture in the combustion chamber of the reactor assembly. The hot combustion gas travels down a flue gas chamber in heat exchange relationship with the catalytic cracking chamber transferring heat across the catalyst chamber wall to heat the catalyst indirectly. The combustion gas is then diverted back through the catalyst bed to heat the catalyst pellets directly. When the cracking reactor temperature reaches operating temperature, methanol combustion is stopped and a hot gas valve is switched to route the flue gas overboard, with methanol being fed directly to the catalytic cracking reactor. Thereafter, the burner operates on excess hydrogen from the fuel cells.

Chludzinski, Paul J. (38 Berkshire St., Swampscott, MA 01907); Dantowitz, Philip (39 Nancy Ave., Peabody, MA 01960); McElroy, James F. (12 Old Cart Rd., Hamilton, MA 01936)

1984-01-01T23:59:59.000Z

293

Determination of naval medium speed diesel engine air exhaust emissions and validation of a proposed estimation model. Master`s thesis  

SciTech Connect

Steady state marine diesel engine exhaust emissions are being reviewed by the Environmental Protection Agency for possible regulation. In anticipation of future regulation, the United States Navy is developing appropriate emissions models for naval vessels. A procedure for collecting this data from an U. S. Navy ship with medium speed main propulsion diesels is presented. It is based on similar testing conducted by the U.S. Coast Guard for measuring patrol boat diesel engine emissions and International Standards Organization methodology. The primary challenge of the experiment design was to minimize interference with the engineering plant as the assigned ship was concurrently tasked for other operations. Data gathered allowed calculation of engine rpm, engine load, exhaust gas flow rate, and determination of pollutant amounts. The tests were conducted at a series of predetermined speeds to reflect an 11-Mode duty cycle developed previously for the LSD 41 Class propulsion diesel engines.

Mayeaux, A.M.

1995-05-01T23:59:59.000Z

294

N Reactor Placed In Interim Safe Storage: Largest Hanford Reactor Cocooning  

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

N Reactor Placed In Interim Safe Storage: Largest Hanford Reactor N Reactor Placed In Interim Safe Storage: Largest Hanford Reactor Cocooning Project Now Complete N Reactor Placed In Interim Safe Storage: Largest Hanford Reactor Cocooning Project Now Complete June 14, 2012 - 12:00pm Addthis Media Contacts Cameron Hardy Cameron.Hardy@rl.doe.gov 509-376-5365 Mark McKenna mmckenna@wch-rcc.com 509-372-9032 RICHLAND, WASH. - The U.S. Department of Energy's (DOE's) River Corridor contractor, Washington Closure Hanford, has completed placing N Reactor in interim safe storage, a process also known as "cocooning." N Reactor was the last of nine plutonium production reactors to be shut down at DOE's Hanford Site in southeastern Washington state. It was Hanford's longest-running reactor, operating from 1963 to 1987. "In the 1960's, N Reactor represented the future of energy in America.

295

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

296

Business Opportunities for Small Reactors  

SciTech Connect

This report assesses the market potential and identifies a number of potential paths for developing the small nuclear reactor business. There are several potential opportunities identified and evaluated. Selecting a specific approach for the business development requires additional information related to a specific market and sources of capital to support the investment. If and how a market for small nuclear plants may develop is difficult to predict because of the complexity of the economic and institutional factors that will influence such development. Key factors are; economics, safety, proliferation resistance and investment risk. The economic and political interest of any of the identified markets is also dependent on successful demonstration of the safety and reliability of small nuclear reactor. Obtaining a US-NRC Standard Design approval would be an important development step toward establishing a market for small reactors. (authors)

Minato, Akio; Nishimura, Satoshi [Central Research Institute of Electric Power Industry - CRIEPI, 2-11-1 Iwado-Kita, Komae, Tokyo 201-8511 (Japan); Brown, Neil W. [Lawrence Livermore National Laboratory - LLNL, PO Box 808, Livermore, CA 94551 (United States)

2007-07-01T23:59:59.000Z

297

Actinide Burning in CANDU Reactors  

SciTech Connect

Actinide burning in CANDU reactors has been studied as a method of reducing the actinide content of spent nuclear fuel from light water reactors, and thereby decreasing the associated long term decay heat load. In this work simulations were performed of actinides mixed with natural uranium to form a mixed oxide (MOX) fuel, and also mixed with silicon carbide to form an inert matrix (IMF) fuel. Both of these fuels were taken to a higher burnup than has previously been studied. The total transuranic element destruction calculated was 40% for the MOX fuel and 71% for the IMF. (authors)

Hyland, B.; Dyck, G.R. [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

2007-07-01T23:59:59.000Z

298

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

299

New fast-reactor approach. [LMFBR  

SciTech Connect

The design parameters for a 1000 MW LMFBR type reactor are presented. The design requires the multiple primary coolant pumps and heat exchangers to be located around the core within the reactor vessel.

Folkrod, J.R.; Kann, W.J.; Klocksieben, R.H.

1983-01-01T23:59:59.000Z

300

Reactor accelerator coupling experiments: a feasability study  

E-Print Network (OSTI)

The Reactor Accelerator Coupling Experiments (RACE) are a set of neutron source driven subcritical experiments under temperature feedback conditions. These experiments will involve coupling an accelerator driven neutron source to a TRIGA reactor...

Woddi Venkat Krishna, Taraknath

2006-08-16T23:59:59.000Z

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


301

Reactivity control assembly for nuclear reactor  

DOE Patents (OSTI)

Reactivity control assembly for nuclear reactor comprises supports stacked above reactor core for holding control rods. Couplers associated with the supports and a vertically movable drive shaft have lugs at their lower ends for engagement with the supports.

Bollinger, Lawrence R. (Schenectady, NY)

1984-01-01T23:59:59.000Z

302

Inherent safety concepts in nuclear power reactors  

Science Journals Connector (OSTI)

Different inherent safety concepts being considered in fast and thermal reactors are presented after outlining the basic goals of nuclear reactor safety, the defence in depth philosophy to achieve these goal...

O M Pal Singh; R Shankar Singh

1989-06-01T23:59:59.000Z

303

Choice of coils for a fusion reactor  

Science Journals Connector (OSTI)

...configurations. The most ambitious is the International Thermonuclear Experimental Reactor, a large tokamak planned for construction...configuration has features in common with the International Thermonuclear Experimental Reactor experiment. Mathematical Model We...

Romeo Alexander; Paul R. Garabedian

2007-01-01T23:59:59.000Z

304

Computational Analysis of Fluid Flow in Pebble Bed Modular Reactor  

E-Print Network (OSTI)

High Temperature Gas-cooled Reactor (HTGR) is a Generation IV reactor under consideration by Department of Energy and in the nuclear industry. There are two categories of HTGRs, namely, Pebble Bed Modular Reactor (PBMR) and Prismatic reactor. Pebble...

Gandhir, Akshay

2012-10-19T23:59:59.000Z

305

The development of structural materials for fusion reactors  

Science Journals Connector (OSTI)

...severely exposed parts of future fusion reactors and pose key problems...successful implementation of fusion reactors as an efficient source...conditions in the International Thermonuclear Experimental Reactor (ITER...environmental attractiveness of fusion reactors. In this paper...

1999-01-01T23:59:59.000Z

306

Utilization of Refractory Metals and Alloys in Fusion Reactor Structures  

Science Journals Connector (OSTI)

In design of fusion reactors, structural material selection is very crucial to improve reactors performance. Different types of materials have been proposed for use in fusion reactor structures. Among these mate...

Mustafa beyli; ?enay Yal?n

2006-12-01T23:59:59.000Z

307

Digital computer operation of a nuclear reactor  

DOE Patents (OSTI)

A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

Colley, Robert W. (Richland, WA)

1984-01-01T23:59:59.000Z

308

Liquid metal cooled nuclear reactor plant system  

DOE Patents (OSTI)

A liquid metal cooled nuclear reactor having a passive cooling system for removing residual heat resulting for fuel decay during reactor shutdown, or heat produced during a mishap. The reactor system is enhanced with sealing means for excluding external air from contact with the liquid metal coolant leaking from the reactor vessel during an accident. The invention also includes a silo structure which resists attack by leaking liquid metal coolant, and an added unique cooling means.

Hunsbedt, Anstein (Los Gatos, CA); Boardman, Charles E. (Saratoga, CA)

1993-01-01T23:59:59.000Z

309

Digital computer operation of a nuclear reactor  

DOE Patents (OSTI)

A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

Colley, R.W.

1982-06-29T23:59:59.000Z

310

Light Water Reactor Sustainability (LWRS) Program  

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

Light Water Reactor Sustainability (LWRS) Program Login Instructions go here. User ID: Password: Log In Forgot your password?...

311

High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor  

Science Journals Connector (OSTI)

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications

David P. Weber; Tanju Sofu; Won Sik Yang; Thomas J. Downar; Justin W. Thomas; Zhaopeng Zhong; Jin Young Cho; Kang Seog Kim; Tae Hyun Chun; Han Gyu Joo; Chang Hyo Kim

312

How far is a Fusion Power Reactor from an Experimental Reactor?  

E-Print Network (OSTI)

be able to move directly and safely to a "first of a kind" reactor. The main conditions to be satisfied / experimental evidence. To assess the reactor relevance of ITER, rather than a comparison between ITER and one1 How far is a Fusion Power Reactor from an Experimental Reactor? R. Toschi(1) , P. Barabaschi(2

313

Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation  

E-Print Network (OSTI)

Physics Optimization of Breed and Burn Fast Reactor Systems.reactors: Fabrication and properties and their optimization.

Heidet, Florent

2010-01-01T23:59:59.000Z

314

DOSE RATES FROM NEUTRON ACTIVATION OF FUSION REACTOR COMPONENTS  

E-Print Network (OSTI)

NEUTRON ACTIVATION OF FUSION REACTOR C01WONENTS LawrenceNeutron Activation of Fusion Reactor Components Lawrence

Ruby, Lawrence

2014-01-01T23:59:59.000Z

315

Nuclear Reactor Safety Design Criteria  

Directives, Delegations, and Requirements

The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Certified 11-18-10.

1993-01-19T23:59:59.000Z

316

Computer aided nuclear reactor modeling  

E-Print Network (OSTI)

Nuclear reactor modeling is an important activity that lets us analyze existing as well as proposed systems for safety, correct operation, etc. The quality of a analysis is directly proportional to the quality of the model used. In this work we look...

Warraich, Khalid Sarwar

2012-06-07T23:59:59.000Z

317

Nozzle for electric dispersion reactor  

DOE Patents (OSTI)

A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

Sisson, Warren G. (Oak Ridge, TN); Basaran, Osman A. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN)

1998-01-01T23:59:59.000Z

318

Nozzle for electric dispersion reactor  

DOE Patents (OSTI)

A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode. 4 figs.

Sisson, W.G.; Basaran, O.A.; Harris, M.T.

1998-04-14T23:59:59.000Z

319

Laminar Entrained Flow Reactor (Fact Sheet)  

SciTech Connect

The Laminar Entrained Flow Reactor (LEFR) is a modular, lab scale, single-user reactor for the study of catalytic fast pyrolysis (CFP). This system can be employed to study a variety of reactor conditions for both in situ and ex situ CFP.

Not Available

2014-02-01T23:59:59.000Z

320

International Journal of Chemical Reactor Engineering  

E-Print Network (OSTI)

International Journal of Chemical Reactor Engineering Volume 3 2005 Article A17 Optimal Operation, a single re- action takes place in the reactor and the operational objective is to compute the optimal feed is illustrated via simulation of two semi-batch reactor applications. KEYWORDS: Dynamic Optimization, Batch

Palanki, Srinivas

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


321

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

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

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

322

Heterogeneous Recycling in Fast Reactors  

SciTech Connect

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

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

2012-07-30T23:59:59.000Z

323

Control of reactor coolant flow path during reactor decay heat removal  

DOE Patents (OSTI)

An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

Hunsbedt, Anstein N. (Los Gatos, CA)

1988-01-01T23:59:59.000Z

324

Reactor and Nuclear Systems Division (RNSD)  

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

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

325

Shutdown system for a nuclear reactor  

DOE Patents (OSTI)

An ultimate shutdown system is provided for termination of neutronic activity in a nuclear reactor. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for reactor poison material. The bead chains, normally suspended above the reactor core on storage spools, are released for downward travel upon command from an external reactor monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the reactor during their downward motion.

Groh, Edward F. (Naperville, IL); Olson, Arne P. (Western Springs, IL); Wade, David C. (Naperville, IL); Robinson, Bryan W. (Oak Lawn, IL)

1984-01-01T23:59:59.000Z

326

Reactor monitoring and safeguards using antineutrino detectors  

Science Journals Connector (OSTI)

Nuclear reactors have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Measurements made with antineutrino detectors could therefore orer an alternative means for verifying the power history and fissile inventory of a reactors, as part of International Atomic Energy Agency (IAEA) and other reactor safeguards regimes. Several erorts to develop this monitoring technique are underway across the globe.

N S Bowden

2008-01-01T23:59:59.000Z

327

Self isolating high frequency saturable reactor  

DOE Patents (OSTI)

The present invention discloses a saturable reactor and a method for decoupling the interwinding capacitance from the frequency limitations of the reactor so that the equivalent electrical circuit of the saturable reactor comprises a variable inductor. The saturable reactor comprises a plurality of physically symmetrical magnetic cores with closed loop magnetic paths and a novel method of wiring a control winding and a RF winding. The present invention additionally discloses a matching network and method for matching the impedances of a RF generator to a load. The matching network comprises a matching transformer and a saturable reactor.

Moore, James A. (Powell, TN)

1998-06-23T23:59:59.000Z

328

Fast-acting nuclear reactor control device  

DOE Patents (OSTI)

A fast-acting nuclear reactor control device for moving and positioning a fety control rod to desired positions within the core of the reactor between a run position in which the safety control rod is outside the reactor core, and a shutdown position in which the rod is fully inserted in the reactor core. The device employs a hydraulic pump/motor, an electric gear motor, and solenoid valve to drive the safety control rod into the reactor core through the entire stroke of the safety control rod. An overrunning clutch allows the safety control rod to freely travel toward a safe position in the event of a partial drive system failure.

Kotlyar, Oleg M. (Idaho Falls, ID); West, Phillip B. (Idaho Falls, ID)

1993-01-01T23:59:59.000Z

329

Research Program of a Super Fast Reactor  

SciTech Connect

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

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

2006-07-01T23:59:59.000Z

330

Nuclear reactor vessel fuel thermal insulating barrier  

DOE Patents (OSTI)

The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

Keegan, C. Patrick; Scobel, James H.; Wright, Richard F.

2013-03-19T23:59:59.000Z

331

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

332

Nuclear reactor alignment plate configuration  

DOE Patents (OSTI)

An alignment plate that is attached to a core barrel of a pressurized water reactor and fits within slots within a top plate of a lower core shroud and upper core plate to maintain lateral alignment of the reactor internals. The alignment plate is connected to the core barrel through two vertically-spaced dowel pins that extend from the outside surface of the core barrel through a reinforcement pad and into corresponding holes in the alignment plate. Additionally, threaded fasteners are inserted around the perimeter of the reinforcement pad and into the alignment plate to further secure the alignment plate to the core barrel. A fillet weld also is deposited around the perimeter of the reinforcement pad. To accomodate thermal growth between the alignment plate and the core barrel, a gap is left above, below and at both sides of one of the dowel pins in the alignment plate holes through with the dowel pins pass.

Altman, David A; Forsyth, David R; Smith, Richard E; Singleton, Norman R

2014-01-28T23:59:59.000Z

333

Parallel Monte Carlo reactor neutronics  

SciTech Connect

The issues affecting implementation of parallel algorithms for large-scale engineering Monte Carlo neutron transport simulations are discussed. For nuclear reactor calculations, these include load balancing, recoding effort, reproducibility, domain decomposition techniques, I/O minimization, and strategies for different parallel architectures. Two codes were parallelized and tested for performance. The architectures employed include SIMD, MIMD-distributed memory, and workstation network with uneven interactive load. Speedups linear with the number of nodes were achieved.

Blomquist, R.N.; Brown, F.B.

1994-03-01T23:59:59.000Z

334

Microsoft PowerPoint - USWIN - INL_NE_Overview.ppt  

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

* First Breeder Reactor * First Naval Propulsion Reactor * 52 Research, Development, Testing, and Demonstration Reactors * Worldwide Nuclear Safety Basis (LOFTRELAP5) DOE's...

335

Naval Petroleum and Oil Shale Reserve. Hearing before the Subcommittee on Preparedness of the Committee on Armed Services, United States Senate, Ninety-Eighth Congress, First Session on S. 1810, September 29, 1983  

SciTech Connect

Captain Myron E. Smith, Jr., Director of the DOE Office of Naval Petroleum and Oil Shale Reserves, testified at a hearing on S. 1810, which authorizes funds relating to the petroleum and oil shale reserves. Smith reviewed revenues and expenditures since legislation was passed in 1976, noting that production at Elk Hills and Teapot Dome are at peak levels, in his justification of the budget request of $266.1 million. Questions from the committee and Smith's responses follow his formal testimony.

Not Available

1984-01-01T23:59:59.000Z

336

The ARIES tokamak reactor study  

SciTech Connect

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

Not Available

1989-10-01T23:59:59.000Z

337

Nuclear power reactor education and training at the Ford nuclear reactor  

SciTech Connect

Since 1977, staff members of the University of Michigan's Ford nuclear reactor have provided courses and reactor laboratory training programs for reactor operators, engineers, and technicians from seven electric utilities, including Cleveland Electric Illuminating, Consumers Power, Detroit Edison, Indiana and Michigan Electric, Nebraska Public Power, Texas Utilities Generating Company, and Toledo Edison. Reactor laboratories, instrument technician training, and reactor physics courses have been conducted at the university. Courses conducted at plant sites include reactor physics, thermal sciences, materials sciences, and health physics and radiation protection.

Burn, R.R.

1989-01-01T23:59:59.000Z

338

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

SciTech Connect

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

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

1993-07-01T23:59:59.000Z

339

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

340

Study of alternatives for future operations of the naval petroleum and oil shale reserves, NOSR-2, Uintah and Carbon Counties, Utah. Final report  

SciTech Connect

The US Department of Energy (DOE) has asked Gustavson Associates, Inc. to serve as an Independent Petroleum Consultant and authorized a study and recommendations regarding future development of Naval Oil Shale Reserve No. 2 (NOSR-2) in Uintah and Carbon Counties, Utah. The US owns 100% of the mineral rights and about 60% of the surface rights in NOSR-2. The Ute Indian Tribe owns the other 40% of the surface. This 88,890-acre tract was set aside as an oil shale reserve for the US Navy by an Executive Order of President Wilson in 1916. Management of NOSR-2 is the responsibility of DOE. No drilling for oil and gas has occurred on the property and no production has been established. No reserves are present, although the area is hypothesized to overlay gas resources. Mapping by the US Geological Survey and others has resulted in speculative seismic leads for structures that may or may not hold conventional oil and gas. All of the mineral rights (including oil shale) must be considered exploratory and the mineral rights must be valued accordingly. The opinion recommended to maximize value to the US is Option 4, sale of the interest of the US of all or part of NOSR-2. Evaluation of this option results in an estimated value which is more than three times greater than the next highest estimated value, for Option 2, transfer to the Department of the Interior for leasing.

NONE

1996-12-01T23:59:59.000Z

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


341

Naval Petroleum and Oil Shale Reserves Combined Financial Statements September 30, 1994 and 1993 and Management Overview and Supplemental Financial and Management Information  

SciTech Connect

This report presents the results of the independent certified public accountant`s audit of the Department of Energy`s (Department) Naval Petroleum and Oil Shale Reserves (NPOSR) financial statements as of September 30, 1994. The auditors have expressed an unqualified opinion on the 1994 statements. Their reports on the NPOSR internal control structure and on compliance with laws and regulations, and management letter on addressing needed improvements are also provided. NPOSR consists of petroleum reserves in California and Wyoming, and oil shale reserves in Colorado and Utah. The Government`s interests in NPOSR are managed by the Department through its headquarters office in Washington, D.C. In addition, the Department has site offices in both California and Wyoming that are responsible for contractor oversight functions. Daily operations are conducted under contract by two management and operating contractors. By law, NPOSR was authorized to produce crude oil at the maximum efficient rate for six years. The law allowed production to be extended for three year periods, provided that the President of the United States certified that continued maximum production was in the best interest of the nation. The current three year period ends on April 5, 1997. Additional information about NPOSR is provided in the overview and notes to the financial statements.

NONE

1994-12-31T23:59:59.000Z

342

Evaluation of in-vessel corium retention through external reactor vessel cooling for integral reactor  

SciTech Connect

In-vessel corium retention through external reactor vessel cooling (IVR-ERVC) for a small integral reactor has been evaluated to determine the thermal margin for the prevention of a reactor vessel failure. A thermal load analysis from the corium pool to the outer reactor vessel wall in the lower plenum of the reactor vessel has been performed to determine the heat flux distribution. The critical heat flux (CHF) on the outer reactor vessel wall has been determined to fix the maximum heat removal rate through the external coolant between the outer reactor vessel and the insulation of the reactor vessel. Finally, the thermal margin has been evaluated by comparison of the thermal load with the maximum heat removal rate of the CHF on the outer reactor vessel wall. The maximum heat flux from the corium pool to the outer reactor vessel is estimated at approximately 0.25 MW/m{sup 2} in the metallic layer because of the focusing effect. The CHF of the outer reactor vessel is approximately 1.1 MW/m{sup 2} because of a two phase natural circulation mass flow. Since the thermal margin for the IVR-ERVC is sufficient, the reactor vessel integrity is maintained during a severe accident of a small integral reactor. (authors)

Park, R. J.; Lee, J. R.; Kim, S. B.; Jin, Y.; Kim, H. Y. [Korea Atomic Energy Research Inst., 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2012-07-01T23:59:59.000Z

343

E-Print Network 3.0 - argonne fast source reactor Sample Search...  

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

of the Omega Reactor Facility, Summary: fission. The benefits of a fast reactor over the water boiler reactor were a high intensity source offast... Reactors at Other Locations...

344

X-10 Graphite Reactor | Department of Energy  

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

X-10 Graphite Reactor X-10 Graphite Reactor X-10 Graphite Reactor X-10 Graphite Reactor When President Roosevelt in December 1942 authorized the Manhattan Project, the Oak Ridge site in eastern Tennessee had already been obtained and plans laid for an air-cooled experimental pile, a pilot chemical separation plant, and support facilities. The X-10 Graphite Reactor, designed and built in ten months, went into operation on November 4, 1943. The X-10 used neutrons emitted in the fission of uranium-235 to convert uranium-238 into a new element, plutonium-239. The reactor consists of a huge block of graphite, measuring 24 feet on each side, surrounded by several feet of high-density concrete as a radiation shield. The block is pierced by 1,248 horizontal diamond-shaped channels in

345

Ordered bed modular reactor design proposal  

SciTech Connect

The Ordered Bed Modular Reactor (OBMR) is a design as an advanced modular HTGR in which the annular reactor core is filled with an ordered bed of fuel spheres. This arrangement allows fuel elements to be poured into the core cavity which is shaped so that an ordered bed is formed and to be discharged from the core through the opening holes in the reactor top. These operations can be performed in a shutdown shorter time. The OBMR has the most of advantages from both the pebble bed reactor and block type reactor. Its core has great structural flexibility and stability, which allow increasing reactor output power and outlet gas temperature as well as decreasing core pressure drop. This paper introduces ordered packing bed characteristics, unloading and loading technique of the fuel spheres and predicted design features of the OBMR. (authors)

Tian, J. [Inst. of Nuclear Energy Technology, Tsinghua Univ., Beijing 100084 (China)

2006-07-01T23:59:59.000Z

346

Nuclear Reactor Technologies | Department of Energy  

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

Reactor Technologies Reactor Technologies Nuclear Reactor Technologies TVA Watts Bar Nuclear Power Plant | Photo courtesy of Tennessee Valley Authority TVA Watts Bar Nuclear Power Plant | Photo courtesy of Tennessee Valley Authority Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Small Modular Reactor Technologies Small modular reactors can also be made in factories and transported to sites where they would be ready to "plug and play" upon arrival, reducing both capital costs and construction times. The smaller size also makes these reactors ideal for small electric grids and for locations that

347

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

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

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

348

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

349

Ignition reactor and pump pulse parameters in a reactorlaser system  

Science Journals Connector (OSTI)

The experience gained in operating a demonstration nuclear-pumped laser in stand B (Physics and Power- Engineering Institute (FEI)) with a pulsed ignition reactor based on the 235U BARS-6 reactor is analyzed. It ...

P. P. Dyachenko; G. N. Fokin

2012-09-01T23:59:59.000Z

350

Solid tags for identifying failed reactor components  

DOE Patents (OSTI)

A solid tag material which generates stable detectable, identifiable, and measurable isotopic gases on exposure to a neutron flux to be placed in a nuclear reactor component, particularly a fuel element, in order to identify the reactor component in event of its failure. Several tag materials consisting of salts which generate a multiplicity of gaseous isotopes in predetermined ratios are used to identify different reactor components.

Bunch, Wilbur L. (Richland, WA); Schenter, Robert E. (Richland, WA)

1987-01-01T23:59:59.000Z

351

Argonne step closer to safer nuclear reactor  

Science Journals Connector (OSTI)

Argonne step closer to safer nuclear reactor ... "A key technological link" toward development of meltdown-immune nuclear reactors is now in the demonstration phase at Argonne National Laboratory near Chicago. ... The technique is part of Argonne's continuing interest in the sodium-cooled integral fast reactor (IFR), whose immunity to meltdown derives from molten sodium's function as a heat sink and the use of metallic fuel that conducts heat better than conventional oxide fuels. ...

WARD WORTHY

1988-05-30T23:59:59.000Z

352

Small Reactor for Deep Space Exploration  

ScienceCinema (OSTI)

This is the first demonstration of a space nuclear reactor system to produce electricity in the United States since 1965, and an experiment demonstrated the first use of a heat pipe to cool a small nuclear reactor and then harvest the heat to power a Stirling engine at the Nevada National Security Site's Device Assembly Facility confirms basic nuclear reactor physics and heat transfer for a simple, reliable space power system.

None

2014-05-30T23:59:59.000Z

353

Fuel handling apparatus for a nuclear reactor  

DOE Patents (OSTI)

Fuel handling apparatus for transporting fuel elements into and out of a nuclear reactor and transporting them within the reactor vessel extends through a penetration in the side of the reactor vessel. A lateral transport device carries the fuel elements laterally within the vessel and through the opening in the side of the vessel, and a reversible lifting device raises and lowers the fuel elements. In the preferred embodiment, the lifting device is supported by a pair of pivot arms.

Hawke, Basil C. (Solana Beach, CA)

1987-01-01T23:59:59.000Z

354

Small Reactor for Deep Space Exploration  

SciTech Connect

This is the first demonstration of a space nuclear reactor system to produce electricity in the United States since 1965, and an experiment demonstrated the first use of a heat pipe to cool a small nuclear reactor and then harvest the heat to power a Stirling engine at the Nevada National Security Site's Device Assembly Facility confirms basic nuclear reactor physics and heat transfer for a simple, reliable space power system.

None

2012-11-29T23:59:59.000Z

355

Neutron shielding panels for reactor pressure vessels  

DOE Patents (OSTI)

In a nuclear reactor neutron panels varying in thickness in the circumferential direction are disposed at spaced circumferential locations around the reactor core so that the greatest radial thickness is at the point of highest fluence with lesser thicknesses at adjacent locations where the fluence level is lower. The neutron panels are disposed between the core barrel and the interior of the reactor vessel to maintain radiation exposure to the vessel within acceptable limits.

Singleton, Norman R. (Murrysville, PA)

2011-11-22T23:59:59.000Z

356

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

357

Accelerators for Subcritical Molten-Salt Reactors  

SciTech Connect

Accelerator parameters for subcritical reactors have usually been based on using solid nuclear fuel much like that used in all operating critical reactors as well as the thorium burning accelerator-driven energy amplifier proposed by Rubbia et al. An attractive alternative reactor design that used molten salt fuel was experimentally studied at ORNL in the 1960s, where a critical molten salt reactor was successfully operated using enriched U235 or U233 tetrafluoride fuels. These experiments give confidence that an accelerator-driven subcritical molten salt reactor will work better than conventional reactors, having better efficiency due to their higher operating temperature, having the inherent safety of subcritical operation, and having constant purging of volatile radioactive elements to eliminate their accumulation and potential accidental release in dangerous amounts. Moreover, the requirements to drive a molten salt reactor can be considerably relaxed compared to a solid fuel reactor, especially regarding accelerator reliability and spallation neutron targetry, to the point that much of the required technology exists today. It is proposed that Project-X be developed into a prototype commercial machine to produce energy for the world by, for example, burning thorium in India and nuclear waste from conventional reactors in the USA.

Johnson, Roland (Muons, Inc.) [Muons, Inc.

2011-08-03T23:59:59.000Z

358

Subcritical Fission Reactor Based on Linear Collider  

E-Print Network (OSTI)

The beams of Linear Collider after main collision can be utilized to build an accelerator--driven sub--critical reactor.

I. F. Ginzburg

2005-07-29T23:59:59.000Z

359

Italian hybrid and fission reactors scenario analysis  

SciTech Connect

Italy is a country where a long tradition of studies both in the fission and fusion field is consolidated; nevertheless a strong public opinion concerned with the destination of the Spent Nuclear Fuel hinders the development of nuclear power. The possibility to a severe reduction of the NSF mass generated from a fleet of nuclear reactors employing an hypothetical fusionfission hybrid reactor has been investigated in the Italian framework. The possibility to produce nuclear fuel for the fission nuclear reactors with the hybrid reactor was analyzed too.

Ciotti, M.; Manzano, J.; Sepielli, M. [ENEA CR Frascati, Via Enrico Fermi, 45, 00044, Frascati, Roma (Italy); ENEA CR casaccia, Via Anguillarese, 301, 00123, Santa Maria di Galeria, Roma (Italy)

2012-06-19T23:59:59.000Z

360

Nuclear reactor multiphysics via bond graph formalism  

E-Print Network (OSTI)

This work proposes a simple and effective approach to modeling nuclear reactor multiphysics problems using bond graphs. Conventional multiphysics simulation paradigms normally use operator splitting, which treats the ...

Sosnovsky, Eugeny

2014-01-01T23:59:59.000Z

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


361

Recovery Act Progress Update: Reactor Closure Feature  

ScienceCinema (OSTI)

A Recovery Act Progress Update. Decommissioning of two nuclear reactor sites at the Department of Energy's facilities has been approved and is underway.

Cody, Tom

2012-06-14T23:59:59.000Z

362

Computational evaluation of two reactor benchmark problems.  

E-Print Network (OSTI)

??A neutronic evaluation of two reactor benchmark problems was performed. The benchmark problems describe typical PWR uranium and plutonium (mixed oxide) fueled lattices. WIMSd4m, a (more)

Cowan, James Anthony

2012-01-01T23:59:59.000Z

363

Heat dissipating nuclear reactor with metal liner  

DOE Patents (OSTI)

Disclosed is a nuclear reactor containment including a reactor vessel disposed within a cavity with capability for complete inherent decay heat removal in the earth and surrounded by a cast steel containment member which surrounds the vessel. The member has a thick basemat in contact with metal pilings. The basemat rests on a bed of porous particulate material, into which water is fed to produce steam which is vented to the atmosphere. There is a gap between the reactor vessel and the steel containment member. The containment member holds any sodium or core debris escaping from the reactor vessel if the core melts and breaches the vessel.

Gluekler, Emil L. (San Jose, CA); Hunsbedt, Anstein (Los Gatos, CA); Lazarus, Jonathan D. (Sunnyvale, CA)

1987-01-01T23:59:59.000Z

364

Hallam, Nebraska, Decommissioned Reactor Site Fact Sheet  

Office of Legacy Management (LM)

Program. Objectives for the reactor were fulfilled by 1966, and the Nebraska Public Power District decommissioned and dismantled the facility between 1967 and 1969. Facility...

365

Tanden Mirror Reactor Systems Code (TMRSC)  

SciTech Connect

This paper describes a computer code developed to model a tandem mirror reactor. This is the first tandem mirror reactor model to couple the highly linked physics, magnetics, and neutronic analysis into a single code. Results from this code for two sensitivity studies are included in this paper. These studies are designed (1) to determine the impact of center cell plasma radius, length, and ion temperature on reactor cost and performance at constant fusion power and (2) to determine the impact of reactor power level on cost.

Reid, R.L.; Rothe, K.E.; Barrett, R.J.

1985-01-01T23:59:59.000Z

366

Light Water Reactor Sustainability Program Contact Information  

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

Program Organization LWRS Program Management Richard Reister Federal Project Director Light Water Reactor Deployment Office of Nuclear Energy U.S. Department of Energy...

367

USING LIGA BASED MICROFABRICATION TO IMPROVE OVERALL HEAT TRANSFER EFFICIENCY OF PRESSURIZED WATER REACTOR: I. Effects of Different Micro Pattern on Overall Heat Transfer.  

SciTech Connect

The Pressurized Water Reactors (PWRs in Figure 1) were originally developed for naval propulsion purposes, and then adapted to land-based applications. It has three parts: the reactor coolant system, the steam generator and the condenser. The Steam generator (a yellow area in Figure 1) is a shell and tube heat exchanger with high-pressure primary water passing through the tube side and lower pressure secondary feed water as well as steam passing through the shell side. Therefore, a key issue in increasing the efficiency of heat exchanger is to improve the design of steam generator, which is directly translated into economic benefits. The past research works show that the presence of a pin-fin array in a channel enhances the heat transfer significantly. Hence, using microfabrication techniques, such as LIGA, micro-molding or electroplating, some special microstructures can be fabricated around the tubes in the heat exchanger to increase the heat-exchanging efficiency and reduce the overall size of the heat-exchanger for the given heat transfer rates. In this paper, micro-pin fins of different densities made of SU-8 photoresist are fabricated and studied to evaluate overall heat transfer efficiency. The results show that there is an optimized micro pin-fin configuration that has the best overall heat transfer effects.

Zhang, M.; Ibekwe, S.; Li, G.; Pang, S.S.; and Lian, K.

2006-07-01T23:59:59.000Z

368

Thermal stabilization of chemical reactors. I The mathematical description of the Endex reactor  

Science Journals Connector (OSTI)

...efficiently by steam generation. Conversely...of fossil or nuclear fuels, which...limits of the reactor. The physico...wasted. The Endex reactor can be thought...conventional steam generation that is currently...Rates of heat generation by reaction...functions of reactor temperature...

1999-01-01T23:59:59.000Z

369

NEW OPTIMIZATION-BASED APPROACH TO CHEMICAL REACTOR SYNTHESIS TOWARDS THE FULL INTEGRATION OF REACTOR  

E-Print Network (OSTI)

NEW OPTIMIZATION-BASED APPROACH TO CHEMICAL REACTOR SYNTHESIS ­ TOWARDS THE FULL INTEGRATION solutions. However, it does not provide optimal reactor design from both economical and environmental and methods for reactor design. It also explores the possibilities for actuation improvement for the optimal

Van den Hof, Paul

370

Simulated nuclear reactor fuel assembly  

DOE Patents (OSTI)

An apparatus for electrically simulating a nuclear reactor fuel assembly. It includes a heater assembly having a top end and a bottom end and a plurality of concentric heater tubes having electrical circuitry connected to a power source, and radially spaced from each other. An outer target tube and an inner target tube is concentric with the heater tubes and with each other, and the outer target tube surrounds and is radially spaced from the heater tubes. The inner target tube is surrounded by and radially spaced from the heater tubes and outer target tube. The top of the assembly is generally open to allow for the electrical power connection to the heater tubes, and the bottom of the assembly includes means for completing the electrical circuitry in the heater tubes to provide electrical resistance heating to simulate the power profile in a nuclear reactor. The embedded conductor elements in each heater tube is split into two halves for a substantial portion of its length and provided with electrical isolation such that each half of the conductor is joined at one end and is not joined at the other end.

Berta, V.T.

1993-04-06T23:59:59.000Z

371

Compound cryopump for fusion reactors  

E-Print Network (OSTI)

We reconsider an old idea: a three-stage compound cryopump for use in fusion reactors such as DEMO. The helium "ash" is adsorbed on a 4.5 K charcoal-coated surface, while deuterium and tritium are adsorbed at 15-22 K on a second charcoal-coated surface. The helium is released by raising the first surface to ~30 K. In a separate regeneration step, deuterium and tritium are released at ~110 K. In this way, the helium can be pre-separated from other species. In the simplest design, all three stages are in the same vessel, with a single valve to close the pump off from the tokamak during regeneration. In an alternative design, the three stages are in separate vessels, connected by valves, allowing the stages to regenerate without interfering with each other. The inclusion of the intermediate stage would not affect the overall pumping speed significantly. The downstream exhaust processing system could be scaled down, as much of the deuterium and tritium could be returned directly to the reactor. This could reduce ...

Kovari, M; Shephard, T

2013-01-01T23:59:59.000Z

372

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

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

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

2012-06-01T23:59:59.000Z

373

A next-generation reactor concept: The Integral Fast Reactor (IFR)  

SciTech Connect

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

Chang, Y.I.

1992-01-01T23:59:59.000Z

374

A next-generation reactor concept: The Integral Fast Reactor (IFR)  

SciTech Connect

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

Chang, Y.I.

1992-07-01T23:59:59.000Z

375

Results of analyses of fur samples from the San Joaquin Kit Fox and associated soil and water samples from the Naval Petroleum Reserve No. 1, Tupman, California  

SciTech Connect

The purpose of this study was to determine whether analysis of the elemental content of fur from San Joaquin kit foxes (Vulpes macrotis mutica) and of water and soil from kit fox habitats could be used to make inferences concerning the cause of an observed decline in the kit fox population on Naval Petroleum Reserve No. 1 (NPR-1). Fur samples that had been collected previously from NPR-1, another oil field (NPR-2), and two sites with no oil development were subjected to neutron activation analysis. In addition, soil samples were collected from the home ranges of individual foxes from undisturbed portions of major soil types on NPR-1 and from wastewater samples were collected from tanks and sumps and subjected to neutron activation analysis. Most elemental concentrations in fur were highest at Camp Roberts and lowest on the undeveloped portions of NPR-I. Fur concentrations were intermediate on the developed oil fields but were correlated with percent disturbance and with number of wells on NPR-1 and NPR-2. The fact that most elements covaried across the range of sites suggests that some pervasive source such as soil was responsible. However, fur concentrations were not correlated with soft concentrations. The kit foxes on the developed portion of NPR-1 did not have concentrations of elements in fur relative to other sites that would account for the population decline in the early 1980s. The oil-related elements As, Ba, and V were elevated in fox fur from oil fields, but only As was sufficiently elevated to suggest a risk of toxicity in individual foxes. However, arsenic concentrations suggestive of sublethal toxicity were found in only 0.56% of foxes from developed oil fields, too few to account for a population decline.

Suter, G.W. II; Rosen, A.E.; Beauchamp, J.J. [Oak Ridge National Lab., TN (United States); Kato, T.T. [EG and G Energy Measurements, Inc., Tupman, CA (United States)

1992-12-01T23:59:59.000Z

376

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

SciTech Connect

The Secretary of Energy is authorized to produce the Naval Petroleum Reserves No. 3 (NPR-3) at its maximum efficient rate (MER) consistent with sound engineering practices, for a period extending to April 5, 2000 subject to extension. Production at NPR-3 peaked in 1981 and has declined since until it has become a mature stripper field, with the average well yielding less than 2 barrels per day. The Department of Energy (DOE) has decided to discontinue Federal operation of NPR-3 at the end of its life as an economically viable oilfield currently estimated to be 2003. Although changes in oil and gas markets or shifts in national policy could alter the economic limit of NPR-3, it productive life will be determined largely by a small and declining reserve base. DOE is proposing certain activities over the next six years in anticipation of the possible transfer of NPR-3 out of Federal operation. These activities would include the 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 continued development of the Rocky Mountain Oilfield Testing Center (RMOTC). DOE has prepared this environmental assessment that analyzes the proposed plugging and abandonment of wells, field restoration and development of RMOTC. Based on the analysis in the EA, the DOE finds that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). The preparation of an environmental impact statement is not required, and DOE is issuing this Finding of No Significant Impact (FONSI).

NONE

1998-04-01T23:59:59.000Z

377

University of Virginia Reactor Facility Decommissioning Results  

SciTech Connect

The University of Virginia Reactor Facility started accelerated decommissioning in 2002. The facility consists of two licensed reactors, the CAVALIER and the UVAR. This paper will describe the progress in 2002, remaining efforts and the unique organizational structure of the project team.

Ervin, P. F.; Lundberg, L. A.; Benneche, P. E.; Mulder, R. U.; Steva, D. P.

2003-02-24T23:59:59.000Z

378

Hydrogasification reactor and method of operating same  

SciTech Connect

The present invention provides a system and method for evaluating effects of process parameters on hydrogasification processes. The system includes a hydrogasification reactor, a pressurized feed system, a hopper system, a hydrogen gas source, and a carrier gas source. Pressurized carbonaceous material, such as coal, is fed to the reactor using the carrier gas and reacted with hydrogen to produce natural gas.

Hobbs, Raymond; Karner, Donald; Sun, Xiaolei; Boyle, John; Noguchi, Fuyuki

2013-09-10T23:59:59.000Z

379

The Gas Reactor Makes a Comeback  

Science Journals Connector (OSTI)

...while the operators of a gas reactor can leave the...ofhis high 699 temperature gas-cooled reactor (HTGR...from the highly pressured turbine drive system might get...would produce combustible gas-es, creating the potential...too much to complete the remaining contracts. So General...

ELIOT MARSHALL

1984-05-18T23:59:59.000Z

380

Engineering Development of Ceramic Membrane Reactor  

E-Print Network (OSTI)

ceramic Ion Transport Membrane (ITM) reactor system for low-cost conversion of natural gas to hydrogen;7 A Revolutionary Technology Using Ceramic Membranes Ion Transport Membranes (ITM) ­ Non-porous multiEngineering Development of Ceramic Membrane Reactor Systems for Converting Natural Gas to Hydrogen

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


381

Explosive demolition of K East Reactor Stack  

ScienceCinema (OSTI)

Using $420,000 in Recovery Act funds, the Department of Energy and contractor CH2M HILL Plateau Remediation Company topped off four months of preparations when they safely demolished the exhaust stack at the K East Reactor and equipment inside the reactor building on July 23, 2010.

None

2010-09-02T23:59:59.000Z

382

Dynamic detection of nuclear reactor core incident  

Science Journals Connector (OSTI)

Surveillance, safety and security of evolving systems are a challenge to prevent accident. The dynamic detection of a hypothetical and theoretical blockage incident in the Phenix nuclear reactor is investigated. Such an incident is characterized by abnormal ... Keywords: Contrast, Dynamic detection of perturbations, Evolving system, Fast-neutron reactor, Neighbourhood, Noise

Laurent Hartert; Danielle Nuzillard; Jean-Philippe Jeannot

2013-02-01T23:59:59.000Z

383

SAFETY AND RELIABILITY ANALYSIS OF NUCLEAR REACTORS  

Science Journals Connector (OSTI)

Abstract A survey of the various aspects of safety and reliability analysis of nuclear reactors is presented with particular emphasis on the interrelation between structural reliability and systems reliability. In reactor design this interrelation is of overriding importance since it is the task of the control, protective and containment systems to protect the mechanical system and the structure from accidental overloading.

T.A. JAEGER

1972-01-01T23:59:59.000Z

384

Reactor Antineutrinos Signal all over the world  

E-Print Network (OSTI)

We present an updated estimate of reactor antineutrino signal all over the world, with particular attention to the sites proposed for existing and future geo-neutrino experiment. In our calculation we take into account the most updated data on Thermal Power for each nuclear plant, on reactor antineutrino spectra and on three neutrino oscillation mechanism.

Ricci, B; Baldoncini, M; Esposito, J; Ludhova, L; Zavatarelli, S

2014-01-01T23:59:59.000Z

385

Reactor Antineutrinos Signal all over the world  

E-Print Network (OSTI)

We present an updated estimate of reactor antineutrino signal all over the world, with particular attention to the sites proposed for existing and future geo-neutrino experiment. In our calculation we take into account the most updated data on Thermal Power for each nuclear plant, on reactor antineutrino spectra and on three neutrino oscillation mechanism.

B. Ricci; F. Mantovani; M. Baldoncini; J. Esposito; L. Ludhova; S. Zavatarelli

2014-03-17T23:59:59.000Z

386

CASCADE OPTIMIZATION AND CONTROL OF BATCH REACTORS  

E-Print Network (OSTI)

CASCADE OPTIMIZATION AND CONTROL OF BATCH REACTORS Xiangming Hua, Sohrab Rohani and Arthur Jutan ajutan@uwo.ca Abstract: In this study, a cascade closed-loop optimization and control strategy for batch reactor. Using model reduction a cascade system is developed, which can effectively combine optimization

Jutan, Arthur

387

Chemical Reactor Analysis and Optimal Digestion  

E-Print Network (OSTI)

J 310 Chemical Reactor Analysis and Optimal Digestion An optimal digestion theory can be readily derived from basic principles o f chemical reactor analysis and design Deborah L. Penry and Peter for formulating and solving optimization problems (Bellman 1957), the entire process is optimized only

Jumars, Pete

388

The breeder reactor: a fossil fuel viewpoint  

Science Journals Connector (OSTI)

... elegant and simple: to generate electricity and, at the same time, to produce additional fuel from the uranium discarded by the existing thermal reactor system. Without the breeder reactor, ... seems likely that the role of nuclear energy will begin to be constrained by the price and availability of uranium at about the turn of the century. There is, however ...

David Merrick

1976-12-16T23:59:59.000Z

389

Reactor Project Presses Ahead Despite Protests  

Science Journals Connector (OSTI)

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

Robert Koenig

1995-08-04T23:59:59.000Z

390

Aerosol reactor production of uniform submicron powders  

DOE Patents (OSTI)

A method of producing submicron nonagglomerated particles in a single stage reactor includes introducing a reactant or mixture of reactants at one end while varying the temperature along the reactor to initiate reactions at a low rate. As homogeneously small numbers of seed particles generated in the initial section of the reactor progress through the reactor, the reaction is gradually accelerated through programmed increases in temperature along the length of the reactor to promote particle growth by chemical vapor deposition while minimizing agglomerate formation by maintaining a sufficiently low number concentration of particles in the reactor such that coagulation is inhibited within the residence time of particles in the reactor. The maximum temperature and minimum residence time is defined by a combination of temperature and residence time that is necessary to bring the reaction to completion. In one embodiment, electronic grade silane and high purity nitrogen are introduced into the reactor and temperatures of approximately 770.degree. K. to 1550.degree. K. are employed. In another embodiment silane and ammonia are employed at temperatures from 750.degree. K. to 1800.degree. K.

Flagan, Richard C. (Pasadena, CA); Wu, Jin J. (Pasadena, CA)

1991-02-19T23:59:59.000Z

391

The CANDU Reactor System: An Appropriate Technology  

Science Journals Connector (OSTI)

The CANDU Reactor System: An Appropriate Technology...Chalk River, Ontario, Canada K0J 1J0 CANDU power reactors are characterized by the combination...breeder. These and other features make the CANDU system an appropriate technology for countries...

J. A. L. Robertson

1978-02-10T23:59:59.000Z

392

Ontario to Mothball Two CANDU Reactors  

Science Journals Connector (OSTI)

Ontario to Mothball Two CANDU Reactors 10.1126/science.309.5739...540-megawatt Canada Deuterium-Uranium (CANDU) nuclear reactors more than a decade before...could signal the end of the road for CANDU, says Tom Adams, executive director...

Paul Webster

2005-08-26T23:59:59.000Z

393

Nuclear reactor characteristics and operational history  

Gasoline and Diesel Fuel Update (EIA)

Nuclear > U.S. reactor operation status tables Nuclear > U.S. reactor operation status tables Nuclear Reactor Operational Status Tables Release date: November 22, 2011 Next release date: November 2012 See also: Table 1. Capacity and Generation, Table 2. Ownership Data Table 3. Nuclear Reactor Characteristics and Operational History PDF XLS Plant Name Generator ID Type Reactor Supplier and Model Construction Start Grid Connection Original Expiration Date License Renewal Application License Renewal Issued Extended Expiration Arkansas Nuclear One 1 PWR Babcock&Wilcox, Lower Loop 10/1/1968 8/17/1974 5/20/2014 2/1/2000 6/20/2001 5/20/2034 Arkansas Nuclear One 2 PWR Combustion Eng. 7/1/1971 12/26/1978 7/17/2018 10/15/2003 6/30/2005 7/17/2038

394

Daya Bay Reactor Neutrino Project at NERSC  

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

Daya Bay Reactor Neutrino Daya Bay Reactor Neutrino Experiment Daya Bay Reactor Neutrino Experiment Daya Bay is an international neutrino-oscillation experiment designed to determine the last unknown neutrino mixing angle θ13 using anti-neutrinos produced by the Daya Bay and Ling Ao Nuclear Power Plant reactors. The experiment is being built by blasting three kilometers of tunnel through the granite rock under the mountains where the power plants are located. Data collection is now scheduled to start in in 2011. On the PDSF cluster at NERSC, Daya Bay performs simulations of the detectors, reactors, and surrounding mountains to help design and anticipate detector properties and behavior. Once real data are available, Daya Bay will be using NERSC to analyze data and NERSC HPSS will be the central U.S. repository for all raw

395

Reactivity control assembly for nuclear reactor. [LMFBR  

DOE Patents (OSTI)

This invention, which resulted from a contact with the United States Department of Energy, relates to a control mechanism for a nuclear reactor and, more particularly, to an assembly for selectively shifting different numbers of reactivity modifying rods into and out of the core of a nuclear reactor. It has been proposed heretofore to control the reactivity of a breeder reactor by varying the depth of insertion of control rods (e.g., rods containing a fertile material such as ThO/sub 2/) in the core of the reactor, thereby varying the amount of neutron-thermalizing coolant and the amount of neutron-capturing material in the core. This invention relates to a mechanism which can advantageously be used in this type of reactor control system.

Bollinger, L.R.

1982-03-17T23:59:59.000Z

396

Cooling system for a nuclear reactor  

DOE Patents (OSTI)

A cooling system for a gas-cooled nuclear reactor is disclosed which includes at least one primary cooling loop adapted to pass coolant gas from the reactor core and an associated steam generator through a duct system having a main circulator therein, and at least one auxiliary cooling loop having communication with the reactor core and adapted to selectively pass coolant gas through an auxiliary heat exchanger and circulator. The main and auxiliary circulators are installed in a common vertical cavity in the reactor vessel, and a common return duct communicates with the reactor core and intersects the common cavity at a junction at which is located a flow diverter valve operative to effect coolant flow through either the primary or auxiliary cooling loops.

Amtmann, Hans H. (Rancho Santa Fe, CA)

1982-01-01T23:59:59.000Z

397

Features of a subcritical nuclear reactor  

Science Journals Connector (OSTI)

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

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

2015-01-01T23:59:59.000Z

398

Operational control of boiling water reactor stability  

SciTech Connect

Boiling water reactor cores are susceptible to instabilities, which generate power oscillations. Specific reactor operating practices can provide a mechanism for control of the instability phenomenon. An axial separation of the core into a single-phase region and a two-phase region resolves the influence of axial flux shapes on core stability. This separation provides the means to derive a core stability control that ensures significant reactor stability margin. The control is achieved by maintaining the core average bulk coolant saturation elevation above a predetermined axial plane. The control can be reliably and efficiently implemented during reactor operations. Analysis demonstrates that variations in parameters important to stability have only secondary influences on stability margin when the control is in effect. Actual plant experience with a large commercial boiling water reactor confirms the capabilities of this stability control in an operational setting.

Mowry, C.M. [PECO Energy, Wayne, PA (United States); Nir, I. [Entergy Operations, Jackson, MS (United States); Newkirk, D.W. [GE Nuclear Energy, San Jose, CA (United States)

1995-03-01T23:59:59.000Z

399

Self-actuating reactor shutdown system  

DOE Patents (OSTI)

A control system for the automatic or self-actuated shutdown or "scram" of a nuclear reactor. The system is capable of initiating scram insertion by a signal from the plant protection system or by independent action directly sensing reactor conditions of low-flow or over-power. Self-actuation due to a loss of reactor coolant flow results from a decrease of pressure differential between the upper and lower ends of an absorber element. When the force due to this differential falls below the weight of the element, the element will fall by gravitational force to scram the reactor. Self-actuation due to high neutron flux is accomplished via a valve controlled by an electromagnet and a thermionic diode. In a reactor over-power, the diode will be heated to a change of state causing the electromagnet to be shorted thereby actuating the valve which provides the changed flow and pressure conditions required for scramming the absorber element.

Barrus, Donald M. (San Jose, CA); Brummond, Willian A (Livermore, CA); Peterson, Leslie F. (Danville, CA)

1988-01-01T23:59:59.000Z

400

Nuclear reactor characteristics and operational history  

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

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

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


401

Small Modular Nuclear Reactors | Department of Energy  

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

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

402

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

403

Consortium for Advanced Simulation of Light Water Reactors (CASL...  

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

behavior in AP1000 reactor core Test run signals emergence of the next generation in nuclear power reactor analysis tools OAK RIDGE, Tenn., Feb. 18, 2014 - Scientists and...

404

SciTech Connect: Nuclear power reactor instrumentation systems...  

Office of Scientific and Technical Information (OSTI)

Nuclear power reactor instrumentation systems handbook. Volume 1 Citation Details In-Document Search Title: Nuclear power reactor instrumentation systems handbook. Volume 1 You...

405

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

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

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

406

Table 3. Nuclear Reactor Characteristics and Operational History  

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

3. Nuclear Reactor Characteristics and Operational History" "Plant Name","Generator ID","Type","Reactor Supplier and Model","Construction Start","Grid Connection","Commercial...

407

Consortium for Advanced Simulation of Light Water Reactors (CASL...  

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

Presentations 2015 back to top Smith, K., Advances in Reactor Physics and Computational Science, Physor 2014 International Conference, "The Role of Reactor Physics toward a...

408

A Stochastic Reactor Based Virtual Engine Model Employing Detailed...  

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

A Stochastic Reactor Based Virtual Engine Model Employing Detailed Chemistry for Kinetic Studies of In-Cylinder Combustion and Exhaust Aftertreatment A Stochastic Reactor Based...

409

Light Water Reactors A DOE Energy Innovation Hub for Modeling...  

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

Consortium for Advanced Simulation of Light Water Reactors A DOE Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors CASL is focused on three issues for nuclear...

410

Analysis of the antineutrino rate during CANDU reactor startup.  

E-Print Network (OSTI)

??Detection systems used to monitor reactor operations are of significant interest as tools for verification of operator declarations. Current reactor site safeguards are limited to (more)

Matthews, Christopher

2012-01-01T23:59:59.000Z

411

Fast Spectrum Molten Salt Reactor Options  

SciTech Connect

During 2010, fast-spectrum molten-salt reactors (FS-MSRs) were selected as a transformational reactor concept for light-water reactor (LWR)-derived heavy actinide disposition by the Department of Energy-Nuclear Energy Advanced Reactor Concepts (ARC) program and were the subject of a preliminary scoping investigation. Much of the reactor description information presented in this report derives from the preliminary studies performed for the ARC project. This report, however, has a somewhat broader scope-providing a conceptual overview of the characteristics and design options for FS-MSRs. It does not present in-depth evaluation of any FS-MSR particular characteristic, but instead provides an overview of all of the major reactor system technologies and characteristics, including the technology developments since the end of major molten salt reactor (MSR) development efforts in the 1970s. This report first presents a historical overview of the FS-MSR technology and describes the innovative characteristics of an FS-MSR. Next, it provides an overview of possible reactor configurations. The following design features/options and performance considerations are described including: (1) reactor salt options-both chloride and fluoride salts; (2) the impact of changing the carrier salt and actinide concentration on conversion ratio; (3) the conversion ratio; (4) an overview of the fuel salt chemical processing; (5) potential power cycles and hydrogen production options; and (6) overview of the performance characteristics of FS-MSRs, including general comparative metrics with LWRs. The conceptual-level evaluation includes resource sustainability, proliferation resistance, economics, and safety. The report concludes with a description of the work necessary to begin more detailed evaluation of FS-MSRs as a realistic reactor and fuel cycle option.

Gehin, Jess C [ORNL; Holcomb, David Eugene [ORNL; Flanagan, George F [ORNL; Patton, Bruce W [ORNL; Howard, Rob L [ORNL; Harrison, Thomas J [ORNL

2011-07-01T23:59:59.000Z

412

New Fuel Cycle and Fuel Management Options in Heavy Liquid Metal-Cooled Reactors  

Science Journals Connector (OSTI)

Technical Paper / Advances in Nuclear Fuel Management - Fuel Management of Reactors Other Than Light Water Reactors

Ehud Greenspan; Pavel Hejzlar; Hiroshi Sekimoto; Georgy Toshinsky; David Wade

413

Feasibility of Burning First- and Second-Generation Plutonium in Pebble Bed High-Temperature Reactors  

Science Journals Connector (OSTI)

Technical Paper / Advances in Nuclear Fuel Management - Fuel Management of Reactors Other Than Light Water Reactors

J. B. M. De Haas; J. C. Kuijper

414

Nuclear reactor internals alignment configuration  

DOE Patents (OSTI)

An alignment system that employs jacking block assemblies and alignment posts around the periphery of the top plate of a nuclear reactor lower internals core shroud to align an upper core plate with the lower internals and the core shroud with the core barrel. The distal ends of the alignment posts are chamfered and are closely received within notches machined in the upper core plate at spaced locations around the outer circumference of the upper core plate. The jacking block assemblies are used to center the core shroud in the core barrel and the alignment posts assure the proper orientation of the upper core plate. The alignment posts may alternately be formed in the upper core plate and the notches may be formed in top plate.

Gilmore, Charles B. (Greensburg, PA); Singleton, Norman R. (Murrysville, PA)

2009-11-10T23:59:59.000Z

415

Solar Thermal Reactor Materials Characterization  

SciTech Connect

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

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

2008-03-01T23:59:59.000Z

416

Gas-cooled nuclear reactor  

DOE Patents (OSTI)

A gas-cooled nuclear reactor includes a central core located in the lower portion of a prestressed concrete reactor vessel. Primary coolant gas flows upward through the core and into four overlying heat-exchangers wherein stream is generated. During normal operation, the return flow of coolant is between the core and the vessel sidewall to a pair of motor-driven circulators located at about the bottom of the concrete pressure vessel. The circulators repressurize the gas coolant and return it back to the core through passageways in the underlying core structure. If during emergency conditions the primary circulators are no longer functioning, the decay heat is effectively removed from the core by means of natural convection circulation. The hot gas rising through the core exits the top of the shroud of the heat-exchangers and flows radially outward to the sidewall of the concrete pressure vessel. A metal liner covers the entire inside concrete surfaces of the concrete pressure vessel, and cooling tubes are welded to the exterior or concrete side of the metal liner. The gas coolant is in direct contact with the interior surface of the metal liner and transfers its heat through the metal liner to the liquid coolant flowing through the cooling tubes. The cooler gas is more dense and creates a downward convection flow in the region between the core and the sidewall until it reaches the bottom of the concrete pressure vessel when it flows radially inward and up into the core for another pass. Water is forced to flow through the cooling tubes to absorb heat from the core at a sufficient rate to remove enough of the decay heat created in the core to prevent overheating of the core or the vessel.

Peinado, Charles O. (La Jolla, CA); Koutz, Stanley L. (San Diego, CA)

1985-01-01T23:59:59.000Z

417

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

SciTech Connect

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

Parma, Edward J., Jr.

2009-06-01T23:59:59.000Z

418

Flexible Conversion Ratio Fast Reactor Systems Evaluation  

SciTech Connect

Conceptual designs of lead-cooled and liquid salt-cooled fast flexible conversion ratio reactors were developed. Both concepts have cores reated at 2400 MWt placed in a large-pool-type vessel with dual-free level, which also contains four intermediate heat exchanges coupling a primary coolant to a compact and efficient supercritical CO2 Brayton cycle power conversion system. Decay heat is removed passively using an enhanced Reactor Vessel Auxiliary Cooling System and a Passive Secondary Auxiliary Cooling System. The most important findings were that (1) it is feasible to design the lead-cooled and salt-cooled reactor with the flexible conversion ratio (CR) in the range of CR=0 and CR=1 n a manner that achieves inherent reactor shutdown in unprotected accidents, (2) the salt-cooled reactor requires Lithium thermal Expansion Modules to overcme the inherent salt coolant's large positive coolant temperature reactivity coefficient, (3) the preferable salt for fast spectrum high power density cores is NaCl-Kcl-MgCl2 as opposed to fluoride salts due to its better themal-hydraulic and neutronic characteristics, and (4) both reactor, but attain power density 3 times smaller than that of the sodium-cooled reactor.

Neil Todreas; Pavel Hejzlar

2008-06-30T23:59:59.000Z

419

Nuclear reactor fissile isotopes antineutrino spectra  

E-Print Network (OSTI)

Positron spectrum from inverse beta decay reaction on proton was measured in 1988-1990 as a result of neutrino exploration experiment. The measured spectrum has the largest statistics and lowest energy threshold between other neutrino experiments made that time at nuclear reactors. On base of the positron spectrum the standard antineutrino spectrum for typical reactor fuel composition was restored. In presented analysis the partial spectra forming this standard spectrum were extracted using specific method. They could be used for neutrino experiments data analysis made at any fuel composition of reactor core.

V. Sinev

2012-07-30T23:59:59.000Z

420

Uncertainties in the Anti-neutrino Production at Nuclear Reactors  

E-Print Network (OSTI)

Anti-neutrino emission rates from nuclear reactors are determined from thermal power measurements and fission rate calculations. The uncertainties in these quantities for commercial power plants and their impact on the calculated interaction rates in electron anti-neutrino detectors is examined. We discuss reactor-to-reactor correlations between the leading uncertainties and their relevance to reactor anti-neutrino experiments.

Z. Djurcic; J. A. Detwiler; A. Piepke; V. R. Foster Jr.; L. Miller; G. Gratta

2008-08-06T23:59:59.000Z

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


421

Today and Future Neutrino Experiments at Krasnoyarsk Nuclear Reactor  

E-Print Network (OSTI)

The results of undergoing experiments and new experiment propositions at Krasnoyarsk underground nuclear reactor are presented

Yu. V. Kozlov; S. V. Khalturtsev; I. N. Machulin; A. V. Martemyanov; V. P. Martemyanov; A. A. Sabelnikov; V. G. Tarasenkov; E. V. Turbin; V. N. Vyrodov; L. A. Popeko; A. V. Cherny; G. A. Shishkina

1999-12-21T23:59:59.000Z

422

LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS  

E-Print Network (OSTI)

LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS M. V. Bazhenov and E. F. Sabaev UDC employed for analyzing reactor dynamics. Equations of this type are used for analyzing the stability of the reactor power, etc. Among these problems the question of the boundedness of reactor power bursts

Bazhenov, Maxim

423

Derivation of Stirred Tank Reactor Optimal Lorenz T. Biegler  

E-Print Network (OSTI)

Derivation of Stirred Tank Reactor Optimal Control Lorenz T. Biegler Department of Chemical reactor shown in Figure 1. We assume Figure 1: Sketch of Hicks Reactor constant liquid volume (V), flow (F balance for the reactor are given by: V dc dt = F(cf -c(t))-Vk10exp(-E/RT)c(t), c(0) = cinit (1) !CpV d

Grossmann, Ignacio E.

424

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.

425

Manhattan Project: F Reactor Plutonium Production Complex  

Office of Scientific and Technical Information (OSTI)

F REACTOR PLUTONIUM PRODUCTION COMPLEX F REACTOR PLUTONIUM PRODUCTION COMPLEX Hanford Engineer Works, 1945 Resources > Photo Gallery Plutonium production area, Hanford, ca. 1945 The F Reactor plutonium production complex at Hanford. The "boxy" building between the two water towers on the right is the plutonium production reactor; the long building in the center of the photograph is the water treatment plant. The photograph was reproduced from Henry DeWolf Smyth, Atomic Energy for Military Purposes: The Official Report on the Development of the Atomic Bomb under the Auspices of the United States Government, 1940-1945 (Princeton, NJ: Princeton University Press, 1945). The Smyth Report was commissioned by Leslie Groves and originally issued by the Manhattan Engineer District. Princeton University Press reprinted it in book form as a "public service" with "reproduction in whole or in part authorized and permitted."

426

Corrosion Minimization for Research Reactor Fuel  

SciTech Connect

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

Eric Shaber; Gerard Hofman

2005-06-01T23:59:59.000Z

427

Control system for a small fission reactor  

DOE Patents (OSTI)

A system for controlling the reactivity of a small fission reactor includes an elongated, flexible hollow tube in the general form of a helical coiled spring axially positioned around and outside of the reactor vessel in an annular space between the reactor vessel and a surrounding cylindrical-shaped neutron reflector. A neutron absorbing material is provided within the hollow tube with the rate of the reaction controlled by the extension and compression of the hollow tube, e.g., extension of the tube increases reactivity while its compression reduces reactivity, in varying the amount of neutron absorbing material disposed between the reactor vessel and the neutron reflector. Conventional mechanical displacement means may be employed to control the coil density of the hollow tube as desired.

Burelbach, J.P.; Kann, W.J.; Saiveau, J.G.

1985-02-08T23:59:59.000Z

428

Heterogeneous effects in fast breeder reactors  

E-Print Network (OSTI)

Heterogeneous effects in fast breeder reactors are examined through development of simple but accurate models for the calculation of a posteriori corrections to a volume-averaged homogeneous representation. Three distinct ...

Gregory, Michael Vladimir

1973-01-01T23:59:59.000Z

429

Fusion Reactor Plasmas with Polarized Nuclei  

Science Journals Connector (OSTI)

Nuclear fusion rates can be enhanced or suppressed by polarization of the reacting nuclei. In a magnetic fusion reactor, the depolarization time is estimated to be longer than the reaction time.

R. M. Kulsrud; H. P. Furth; E. J. Valeo; M. Goldhaber

1982-10-25T23:59:59.000Z

430

Safe new reactor for radionuclide production  

SciTech Connect

In late 1995, DOE is schedule to announce a new tritium production unit. Near the end of the last NPR (New Production Reactors) program, work was directed towards eliminating risks in current designs and reducing effects of accidents. In the Heavy Water Reactor Program at Savannah River, the coolant was changed from heavy to light water. An alternative, passively safe concept uses a heavy-water-filled, zircaloy reactor calandria near the bottom of a swimming pool; the calandria is supported on a light-water-coolant inlet plenum and has upflow through assemblies in the calandria tubes. The reactor concept eliminates or reduces significantly most design basis and severe accidents that plague other deigns. The proven, current SRS tritium cycle remains intact; production within the US of medical isotopes such as Mo-99 would also be possible.

Gray, P.L.

1995-02-15T23:59:59.000Z

431

Neutrino mass hierarchy from nuclear reactor experiments  

Science Journals Connector (OSTI)

Ten years from now reactor neutrino experiments will attempt to determine which neutrino mass eigenstate is the most massive. In this paper we present the results of more than seven million detailed simulations of such experiments, studying the dependence of the probability of successfully determining the mass hierarchy upon the analysis method, the neutrino mass matrix parameters, reactor flux models, geoneutrinos and, in particular, combinations of baselines. We show that a recently reported spurious dependence of the data analysis upon the high energy tail of the reactor spectrum can be removed by using a weighted Fourier transform. We determine the optimal baselines and corresponding detector locations. For most values of the CP-violating, leptonic Dirac phase ?, a degeneracy prevents NO?A and T2K from determining either ? or the hierarchy. We determine the confidence with which a reactor experiment can determine the hierarchy, breaking the degeneracy.

Emilio Ciuffoli; Jarah Evslin; Xinmin Zhang

2013-08-29T23:59:59.000Z

432

Passive heat transfer means for nuclear reactors  

DOE Patents (OSTI)

An improved passive cooling arrangement is disclosed for maintaining adjacent or related components of a nuclear reactor within specified temperature differences. Specifically, heat pipes are operatively interposed between the components, with the vaporizing section of the heat pipe proximate the hot component operable to cool it and the primary condensing section of the heat pipe proximate the other and cooler component operable to heat it. Each heat pipe further has a secondary condensing section that is located outwardly beyond the reactor confinement and in a secondary heat sink, such as air ambient the containment, that is cooler than the other reactor component. Means such as shrouding normally isolated the secondary condensing section from effective heat transfer with the heat sink, but a sensor responds to overheat conditions of the reactor to open the shrouding, which thereby increases the cooling capacity of the heat pipe. By having many such heat pipes, an emergency passive cooling system is defined that is operative without electrical power.

Burelbach, James P. (Glen Ellyn, IL)

1984-01-01T23:59:59.000Z

433

Optimizing Medium Baseline Reactor Neutrino Experiments  

E-Print Network (OSTI)

10 years from now medium baseline reactor neutrino experiments will attempt to determine the neutrino mass hierarchy from the observed antineutrino spectra. In this letter we present the results of more than four million detailed simulations of such experiments, studying the dependence of the probability of successfully determining the hierarchy upon the analysis method, the neutrino mass matrix parameters, reactor flux models and, in particular, combinations of baselines. We show that the strong dependence of the hierarchy determination upon mass differences and flux models found by Qian et al. results from a spurious dependence of the Fourier analysis upon the high energy tail of the reactor spectrum which can be removed by using a weighted Fourier transform. Such experiments necessarily use flux from multiple reactors at distinct baselines, smearing the oscillation signal and thus impeding the determination of the hierarchy. Using the results of our simulations, we determine the optimal baselines and corre...

Ciuffoli, Emilio; Zhang, Xinmin

2013-01-01T23:59:59.000Z

434

Reactor physics project progress report no. 2  

E-Print Network (OSTI)

This is the second annual report in an experimental and theoretical program to develop and apply single and few element heterogeneous methods for the determination of reactor lattice parameters. During the period covered ...

Driscoll, Michael J.

1969-01-01T23:59:59.000Z

435

Rethinking the light water reactor fuel cycle  

E-Print Network (OSTI)

The once through nuclear fuel cycle adopted by the majority of countries with operating commercial power reactors imposes a number of concerns. The radioactive waste created in the once through nuclear fuel cycle has to ...

Shwageraus, Evgeni, 1973-

2004-01-01T23:59:59.000Z

436

Critical assessment of thorium reactor technology .  

E-Print Network (OSTI)

??Thorium-based fuels for nuclear reactors are being considered for use with current and future designs in both large and small-scale energy production. Thorium-232 is as (more)

Drenkhahn, Robert (Robert A.)

2012-01-01T23:59:59.000Z

437

Advanced Test Reactor National Scientific User Facility  

SciTech Connect

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

438

Polarized neutron reflectometry at Dhruva reactor  

Science Journals Connector (OSTI)

Polarized neutron reflectometry (PNR) is an ideal non-destructive ... have installed a position sensitive detector-based polarized neutron reflectometer at Dhruva reactor, Trombay. In ... the chemical structure o...

Surendra Singh; Saibal Basu

2004-08-01T23:59:59.000Z

439

Status and problems of fusion reactor development  

Science Journals Connector (OSTI)

Thermonuclear fusion of deuterium and tritium constitutes an enormous ... inexhaustible. Further, the safety prospects of a fusion reactor are quite favourable due to the inherently self-limiting fusion process,...

Uwe Schumacher

2001-03-01T23:59:59.000Z

440

Dust Divertor for a Tokamak Fusion Reactor  

Science Journals Connector (OSTI)

The conventional tokamak fusion reactor deploys a magnetic divertor design which channels...1], or covered by flowing liquid metals [2...]. A typical estimate for the plasma heat flux to the divertor for a tokama...

X. Z. Tang; G. L. Delzanno

2010-10-01T23:59:59.000Z

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


441

An Acoustically Driven Magnetized Target Fusion Reactor  

Science Journals Connector (OSTI)

We propose a new compression system that offers many advantages. A near spherical vessel ?2m in diameter is filled with liquid lead-lithium alloy (PbLi). This liquid is under consideration for fusion reactor bla...

Michel Laberge

2008-06-01T23:59:59.000Z

442

Chicago Pile reactors create enduring research legacy - Argonne's  

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

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

443

Light Water Reactor Sustainability Technical Documents | Department of  

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

Initiatives » Nuclear Reactor Technologies » Light Water Reactor Initiatives » Nuclear Reactor Technologies » Light Water Reactor Sustainability Program » Light Water Reactor Sustainability Technical Documents Light Water Reactor Sustainability Technical Documents September 30, 2011 Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR licenses are now being extended from 40y to 60y by the U.S. Nuclear Regulatory Commission (NRC) with intentions to extend licenses to 80y and beyond. The RPV materials exhibit varying degrees of sensitivity to irradiation-induced embrittlement

444

Heavy Liquid Metal Reactor Development - Nuclear Engineering Division  

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

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

445

Early Argonne reactor lit the way for worldwide nuclear industry -  

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

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

446

Microsoft Word - illinois_reactors_taiwo.doc  

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

Fission Process and Control Fission Process and Control In nuclear power reactors, energy is produced by the nuclear fission process in which uranium atoms are split into two major atoms, called fission products, with significant heat generation. A nuclear reactor system is controlled to ensure that the fission process is a sustained nuclear chain reaction (see Fig. 1) that neither declines nor increases with operation time, i.e., it is at

447

Status of fast-breeder-reactor safety  

SciTech Connect

The current state of knowledge of fast breeder reactors is reviewed. The primary focus on the analysis of postulated accident sequences and the implications to fast-reactor design. The accidents considered include loss-of-collant flow and transient overpower, both with a postulated failure to scram. The associated accident phenomena considered largely relate to the potential for energetic disassembly and include fuel, clad, and coolant motions during the accident sequence, fuel-coolant thermal interactions, and potential recriticality phenomena.

Avery, R.

1982-01-01T23:59:59.000Z

448

A comparison of radioactive waste from first generation fusion reactors and fast fission reactors with actinide recycling  

SciTech Connect

Limitations of the fission fuel resources will presumably mandate the replacement of thermal fission reactors by fast fission reactors that operate on a self-sufficient closed fuel cycle. This replacement might take place within the next one hundred years, so the direct competitors of fusion reactors will be fission reactors of the latter rather than the former type. Also, fast fission reactors, in contrast to thermal fission reactors, have the potential for transmuting long-lived actinides into short-lived fission products. The associated reduction of the long-term activation of radioactive waste due to actinides makes the comparison of radioactive waste from fast fission reactors to that from fusion reactors more rewarding than the comparison of radioactive waste from thermal fission reactors to that from fusion reactors. Radioactive waste from an experimental and a commercial fast fission reactor and an experimental and a commercial fusion reactor has been characterized. The fast fission reactors chosen for this study were the Experimental Breeder Reactor 2 and the Integral Fast Reactor. The fusion reactors chosen for this study were the International Thermonuclear Experimental Reactor and a Reduced Activation Ferrite Helium Tokamak. The comparison of radioactive waste parameters shows that radioactive waste from the experimental fast fission reactor may be less hazardous than that from the experimental fusion reactor. Inclusion of the actinides would reverse this conclusion only in the long-term. Radioactive waste from the commercial fusion reactor may always be less hazardous than that from the commercial fast fission reactor, irrespective of the inclusion or exclusion of the actinides. The fusion waste would even be far less hazardous, if advanced structural materials, like silicon carbide or vanadium alloy, were employed.

Koch, M.; Kazimi, M.S.

1991-04-01T23:59:59.000Z

449

Solid oxide electrochemical reactor science.  

SciTech Connect

Solid-oxide electrochemical cells are an exciting new technology. Development of solid-oxide cells (SOCs) has advanced considerable in recent years and continues to progress rapidly. This thesis studies several aspects of SOCs and contributes useful information to their continued development. This LDRD involved a collaboration between Sandia and the Colorado School of Mines (CSM) ins solid-oxide electrochemical reactors targeted at solid oxide electrolyzer cells (SOEC), which are the reverse of solid-oxide fuel cells (SOFC). SOECs complement Sandia's efforts in thermochemical production of alternative fuels. An SOEC technology would co-electrolyze carbon dioxide (CO{sub 2}) with steam at temperatures around 800 C to form synthesis gas (H{sub 2} and CO), which forms the building blocks for a petrochemical substitutes that can be used to power vehicles or in distributed energy platforms. The effort described here concentrates on research concerning catalytic chemistry, charge-transfer chemistry, and optimal cell-architecture. technical scope included computational modeling, materials development, and experimental evaluation. The project engaged the Colorado Fuel Cell Center at CSM through the support of a graduate student (Connor Moyer) at CSM and his advisors (Profs. Robert Kee and Neal Sullivan) in collaboration with Sandia.

Sullivan, Neal P. (Colorado School of Mines, Golden, CO); Stechel, Ellen Beth; Moyer, Connor J. (Colorado School of Mines, Golden, CO); Ambrosini, Andrea; Key, Robert J. (Colorado School of Mines, Golden, CO)

2010-09-01T23:59:59.000Z

450

NAVAL POSTGRADUATE SCHOOL Monterey, California  

E-Print Network (OSTI)

-dimensional ship model images and real images derived from video of an AN/AAS-44V Forward Looking Infrared (FLIR

Rowe, Neil C.

451

The Institution of Naval Architects  

Science Journals Connector (OSTI)

... shown that more heat is absorbed in the fire-box with flaming material than with flameless coke. It is well known that a luminous flame radiates more heat than one ...

1890-04-03T23:59:59.000Z

452

NAVAL POSTGRADUATE SCHOOL Monterey, California  

E-Print Network (OSTI)

, Monterey, CA 93943 10. SPONSORING / MONITORING AGENCY REPORT NUMBER 11. SUPPLEMENTARY NOTES The views Generation (MM5) as the atmospheric component was developed for the east Asian marginal seas (EAMS verified against surface wind data from the National Centers for Environmental Prediction (NCEP) and sea

Chu, Peter C.

453

The Institution of Naval Architects  

Science Journals Connector (OSTI)

... Henderson on the elasticity of ships as deduced from experiments on the vibration of dynamical models. A dynamical ... . A dynamical model of the ship is constructed out of a bar of steel of uniform thickness and ...

1909-04-08T23:59:59.000Z

454

The Institution of Naval Architects  

Science Journals Connector (OSTI)

... , a similar ship in all respects, excepting that she has ordinary crank and cylinder engines. As is well known, the steam turbine is less "flexible,"to use an ... is less "flexible,"to use an expression that has come into use, than the reciprocating ...

1905-04-20T23:59:59.000Z

455

The Institution of Naval Architects  

Science Journals Connector (OSTI)

... to arrange for holding regular autumnal sessions at the principal outports, in addition to the spring sessions in London. The papers read were chiefly "papers of information,"having a ... well received. His recent paper tf On the Theoretical Duty of Heat in the Steam-Engine"was probably understood by only a few of his hearers; and Prof. Cotterill, ...

W. H. W.

1885-04-09T23:59:59.000Z

456

Antineutrino reactor safeguards - a case study  

E-Print Network (OSTI)

Antineutrinos have been proposed as a means of reactor safeguards for more than 30 years and there has been impressive experimental progress in neutrino detection. In this paper we conduct, for the first time, a case study of the application of antineutrino safeguards to a real-world scenario - the North Korean nuclear crisis in 1994. We derive detection limits to a partial or full core discharge in 1989 based on actual IAEA safeguards access and find that two independent methods would have yielded positive evidence for a second core with very high confidence. To generalize our results, we provide detailed estimates for the sensitivity to the plutonium content of various types of reactors, including most types of plutonium production reactors, based on detailed reactor simulations. A key finding of this study is that a wide class of reactors with a thermal power of less than 0.1-1 GWth can be safeguarded achieving IAEA goals for quantitative sensitivity and timeliness with detectors right outside the reactor ...

Christensen, Eric; Jaffke, Patrick

2013-01-01T23:59:59.000Z

457

U.S. domestic reactor conversion program  

SciTech Connect

The RERTR U.S. Domestic Conversion program continues in its support of the Global Treat Reduction Initiative (GTRI) to convert seven U.S reactors to low enriched uranium (LEU) by 2010. These reactors are located at the University of Florida, Texas A and M University, Purdue University, Washington State University, Oregon State University, the University of Wisconsin, and the Idaho National Laboratory. The reactors located at the University of Florida and Texas A and M Nuclear Science Center were successfully converted to LEU in September of 2006 through an integrated and collaborative effort involving INL, Argonne National Laboratory (ANL), DOE (headquarters and the field office), the Nuclear Regulatory Commission (NRC), the universities, and the contractors involved in analyses, fuel design and fabrication, and spent nuclear fuel (SNF) shipping and disposition. With this work completed and in anticipation of other impending conversion projects, a meeting was established to engage the project participants in a structured discussion to capture the lessons learned. The objectives of this meeting were to document the observations, insights, issues, concerns, and ideas of those involved in the reactor conversions so that future efforts could be conducted with greater effectiveness, efficiency, and with fewer challenges. The lessons learned from completing the University of Florida and Texas A and M conversions, the Purdue reactor conversion status, and an overview of the upcoming reactor conversions will be presented at the meeting. (author)

Meyer, Dana M.; Woolstenhulme, Eric C. [Idaho National Laboratory, Idaho Falls, Idaho 83415 (United States)

2008-07-15T23:59:59.000Z

458

Design options for a bunsen reactor.  

SciTech Connect

This work is being performed for Matt Channon Consulting as part of the Sandia National Laboratories New Mexico Small Business Assistance Program (NMSBA). Matt Channon Consulting has requested Sandia's assistance in the design of a chemical Bunsen reactor for the reaction of SO2, I2 and H2O to produce H2SO4 and HI with a SO2 feed rate to the reactor of 50 kg/hour. Based on this value, an assumed reactor efficiency of 33%, and kinetic data from the literature, a plug flow reactor approximately 1%E2%80%9D diameter and and 12 inches long would be needed to meet the specification of the project. Because the Bunsen reaction is exothermic, heat in the amount of approximately 128,000 kJ/hr would need to be removed using a cooling jacket placed around the tubular reactor. The available literature information on Bunsen reactor design and operation, certain support equipment needed for process operation and a design that meet the specification of Matt Channon Consulting are presented.

Moore, Robert Charles

2013-10-01T23:59:59.000Z

459

Micro -Thermonuclear AB-Reactors for Aerospace  

E-Print Network (OSTI)

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

Alexander Bolonkin

2007-01-08T23:59:59.000Z

460

The integral fast reactor fuel cycle  

SciTech Connect

The liquid-metal reactor (LMR) has the potential to extend the uranium resource by a factor of 50 to 100 over current commercial light water reactors (LWRs). In the integral fast reactor (IFR) development program, the entire reactor system - reactor, fuel cycle, and waste process - is being developed and optimized at the same time as a single integral entity. A key feature of the IFR concept is the metallic fuel. The lead irradiation tests on the new U-Pu-Zr metallic fuel in the Experimental Breeder Reactor II have surpassed 185000 MWd/t burnup, and its high burnup capability has now been fully demonstrated. The metallic fuel also allows a radically improved fuel cycle technology. Pyroprocessing, which utilizes high temperatures and molten salt and molten metal solvents, can be advantageously utilized for processing metal fuels because the product is metal suitable for fabrication into new fuel elements. Direct production of a metal product avoids expensive and cumbersome chemical conversion steps that would result from use of the conventional Purex solvent extraction process. The key step in the IFR process is electrorefining, which provides for recovery of the valuable fuel constituents, uranium and plutonium, and for removal of fission products. A notable feature of the IFR process is that the actinide elements accompany plutonium through the process. This results in a major advantage in the high-level waste management.

Chang, Y.I. (Argonne National Lab., IL (United States))

1990-01-01T23:59:59.000Z

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


461

Thermal-hydraulic interfacing code modules for CANDU reactors  

SciTech Connect

The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis.

Liu, W.S.; Gold, M.; Sills, H. [Ontario Hydro Nuclear, Toronto (Canada)] [and others

1997-07-01T23:59:59.000Z

462

A comparison of nuclear reactor control room display panels  

E-Print Network (OSTI)

complex and time consuming task. It is expected that the control room of future commercial nuclear reactor power plants will change considerably as a result of these studies. Currently there are literally hundreds of displays and controls...: Dr. Rodger S. Koppa A study was conducted to investigate the use of computer generated displays to operate nuclear reactor power plants. The AGN-201 reactor at Texas A&M university was the reactor studied. After observing several licensed reactor...

Bowers, Frances Renae

2012-06-07T23:59:59.000Z

463

Lessons Learned From Gen I Carbon Dioxide Cooled Reactors  

SciTech Connect

This paper provides a review of early gas cooled reactors including the Magnox reactors originating in the United Kingdom and the subsequent development of the Advanced Gas-cooled Reactors (AGR). These early gas cooled reactors shared a common coolant medium, namely carbon dioxide (CO2). A framework of information is provided about these early reactors and identifies unique problems/opportunities associated with use of CO2 as a coolant. Reactor designers successfully rose to these challenges. After years of successful use of the CO2 gas cooled reactors in Europe, the succeeding generation of reactors, called the High Temperature Gas Reactors (HTGR), were designed with Helium gas as the coolant. Again, in the 21st century, with the latest reactor designs under investigation in Generation IV, there is a revived interest in developing Gas Cooled Fast Reactors that use CO2 as the reactor coolant. This paper provides a historical perspective on the 52 CO2 reactors and the reactor programs that developed them. The Magnox and AGR design features and safety characteristics were reviewed, as well as the technologies associated with fuel storage, reprocessing, and disposal. Lessons-learned from these programs are noted to benefit the designs of future generations of gas cooled nuclear reactors.

David E. Shropshire

2004-04-01T23:59:59.000Z

464

Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations  

SciTech Connect

Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON the estimated cost of decommissioning a PWR is lowest for ENTOMB and highest for SAFSTOR the estimated cost of decommissioning a BWR is lowest for OECON and highest for SAFSTOR. In all cases, SAFSTOR has the lowest occupational radiation dose and the highest cost.

Wittenbrock, N. G.

1982-01-01T23:59:59.000Z

465

Design of a 25-kWe Surface Reactor System Based on SNAP Reactor Technologies  

SciTech Connect

A Hastelloy-X clad, sodium-potassium (NaK-78) cooled, moderated spectrum reactor using uranium zirconium hydride (UZrH) fuel based on the SNAP program reactors is a promising design for use in surface power systems. This paper presents a 98 kWth reactor for a power system the uses multiple Stirling engines to produce 25 kWe-net for 5 years. The design utilizes a pin type geometry containing UZrHx fuel clad with Hastelloy-X and NaK-78 flowing around the pins as coolant. A compelling feature of this design is its use of 49.9% enriched U, allowing it to be classified as a category III-D attractiveness and reducing facility costs relative to highly-enriched space reactor concepts. Presented below are both the design and an analysis of this reactor's criticality under various safety and operations scenarios.

Dixon, David D. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States); Hiatt, Matthew T. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Department of Nuclear Engineering, Texas A and M University, College Station, TX 77843 (United States); Poston, David I.; Kapernick, Richard J. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

2006-01-20T23:59:59.000Z

466

F Reactor Area Cleanup Complete | Department of Energy  

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

F Reactor Area Cleanup Complete F Reactor Area Cleanup Complete F Reactor Area Cleanup Complete September 19, 2012 - 12:00pm Addthis Media Contact Cameron Hardy, DOE Cameron.Hardy@rl.doe.gov 509-376-5365 RICHLAND, Wash. - U.S. Department of Energy (DOE) contractors have cleaned up the F Reactor Area, the first reactor area at the Hanford Site in southeastern Washington state to be fully remediated. While six of Hanford's nine plutonium production reactors have been sealed up, or cocooned, the F Reactor Area is the first to have all of its associated buildings and waste sites cleaned up in addition to having its reactor sealed up. "The cleanup of the F Reactor Area shows the tremendous progress workers are making along Hanford's River Corridor," said Dave Huizenga, Senior Advisor for the DOE Office of Environmental Management. "The River

467

Brookhaven Lab Completes Decommissioning of Graphite Research Reactor:  

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

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

468

EM's Top Official Celebrates 'Cocooning' of Reactor Dedicated by  

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

Top Official Celebrates 'Cocooning' of Reactor Dedicated Top Official Celebrates 'Cocooning' of Reactor Dedicated by President Kennedy Decades Ago EM's Top Official Celebrates 'Cocooning' of Reactor Dedicated by President Kennedy Decades Ago June 1, 2012 - 12:00pm Addthis Senior Advisor for Environmental Management David Huizenga speaks during an event announcing the completion of work to place N Reactor in safe storage. Senior Advisor for Environmental Management David Huizenga speaks during an event announcing the completion of work to place N Reactor in safe storage. An aerial photo shows the N Reactor complex just before work to place the reactor in safe storage, or "cocooning," was completed. An aerial photo shows the N Reactor complex just before work to place the reactor in safe storage, or "cocooning," was completed.

469

Influence of reactor configuration on reliability of activated sludge process  

Science Journals Connector (OSTI)

The effect of uncertainty in system parameters and the accuracy of the mathematical model used on the design and reliability of the activated sludge process is investigated by Monte Carlo simulations. Simulations indicate that the coefficient of variation for a reactor volume varies from 0.56 for a single mixed tank reactor to 0.44 for a plug flow reactor. The coefficient of variation for effluent for reactors designed on nominal values was found to be 0.56 for a mixed-tank reactor, 1.28 for two reactors in series, 1.56 for three reactors in series and 1.6 for a plug flow reactor. Significant contributing parameters to the reliability of the process are established. Reactor volumes for desired reliability levels are also calculated.

Puneet Sarna; Sanjeev Chaudhari

2006-01-01T23:59:59.000Z

470

CESAR: Center for Exascale Simulation of Advanced Reactors | Argonne  

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

CESAR: Center for Exascale Simulation of Advanced Reactors CESAR: Center for Exascale Simulation of Advanced Reactors CESAR: Center for Exascale Simulation of Advanced Reactors CESAR is an interdisciplinary center for developing an innovative, next-generation nuclear reactor analysis tool that both utilizes and guides the development of exascale computing platforms. Existing reactor analysis codes are highly tuned and calibrated for commercial light-water reactors, but they lack the physics fidelity to seamlessly carry over to new classes of reactors with significantly different design characteristics-as, for example, innovative concepts such as TerraPower's Traveling Wave reactor and Small Modular Reactor concepts. Without vastly improved modeling capabilities, the economic and safety characteristics of these and other novel systems will require tremendous

471

Light Water Reactor Sustainability Technical Documents | Department of  

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

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

472

Plutonium Recycle Test Reactor 309 B-Roll | Department of Energy  

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

Plutonium Recycle Test Reactor 309 B-Roll Plutonium Recycle Test Reactor 309 B-Roll Addthis Description Plutonium Recycle Test Reactor 309 B-Roll...

473

DESIGN OF A TOKAMAK FUSION REACTOR FIRST WALL ARMOR AGAINST NEUTRAL BEAM IMPINGEMENT  

E-Print Network (OSTI)

Hoffman, et. a1. , "Fusion Reactor First Wall Cooling forTheir Signif- icance in Fusion Reactors," Fifth ConferenceProb- lems in Toroidal Fusion Reactors," Fifth Conference

Myers, Richard Allen

2011-01-01T23:59:59.000Z

474

Risk Management for Sodium Fast Reactors.  

SciTech Connect

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

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

2015-01-01T23:59:59.000Z

475

The physics of magnetic fusion reactors  

Science Journals Connector (OSTI)

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

John Sheffield

1994-07-01T23:59:59.000Z

476

Simulation of a marine nuclear reactor  

SciTech Connect

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

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

1995-02-01T23:59:59.000Z

477

Small Modular Reactors (468th Brookhaven Lecture)  

SciTech Connect

With good reason, much more media attention has focused on nuclear power plants than solar farms, wind farms, or hydroelectric plants during the past month and a half. But as nations around the world demand more energy to power everything from cell phone batteries to drinking water pumps to foundries, nuclear plants are the only non-greenhouse-gas producing option that can be built to operate almost anywhere, and can continue to generate power during droughts, after the sun sets, and when winds die down. To supply this demand for power, designers around the world are competing to develop more affordable nuclear reactors of the future: small modular reactors. Brookhaven Lab is working with DOE to ensure that these reactors are designed to be safe for workers, members of surrounding communities, and the environment and to ensure that the radioactive materials and technology will only be used for peaceful purposes, not weapons. In his talk, Bari will discuss the advantages and challenges of small modular reactors and what drives both international and domestic interest in them. He will also explain how Brookhaven Lab and DOE are working to address the challenges and provide a framework for small modular reactors to be commercialized.

Bari, Robert

2011-04-20T23:59:59.000Z

478

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

479

Weld monitor and failure detector for nuclear reactor system  

DOE Patents (OSTI)

Critical but inaccessible welds in a nuclear reactor system are monitored throughout the life of the reactor by providing small aperture means projecting completely through the reactor vessel wall and also through the weld or welds to be monitored. The aperture means is normally sealed from the atmosphere within the reactor. Any incipient failure or cracking of the weld will cause the environment contained within the reactor to pass into the aperture means and thence to the outer surface of the reactor vessel where its presence is readily detected.

Sutton, Jr., Harry G. (Mt. Lebanon, PA)

1987-01-01T23:59:59.000Z

480

Computer simulations help design new nuclear reactors  

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

Computer simulations help design new nuclear reactors Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share Reprinted from "Argonne Now" - Spring 2008 Physicist Won-Sik Yang and computer scientist Andrew Siegel hold a fuel rod assembly in front of a model of the Experimental Breeder Reactor-II

Note: This page contains sample records for the topic "defueled naval reactor" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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481

Brookhaven Graphite Research Reactor | Environmental Restoration Projects |  

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

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

482

2012_AdvReactor_Factsheet.indd  

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

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

483

Gas Reactor Technology R&D  

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

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

484

Tritium issues in commercial pressurized water reactors  

SciTech Connect

Tritium has become an important radionuclide in commercial Pressurized Water Reactors because of its mobility and tendency to concentrate in plant systems as tritiated water during the recycling of reactor coolant. Small quantities of tritium are released in routine regulated effluents as liquid water and as water vapor. Tritium has become a focus of attention at commercial nuclear power plants in recent years due to inadvertent, low-level, chronic releases arising from routine maintenance operations and from component failures. Tritium has been observed in groundwater in the vicinity of stations. The nuclear industry has undertaken strong proactive corrective measures to prevent recurrence, and continues to eliminate emission sources through its singular focus on public safety and environmental stewardship. This paper will discuss: production mechanisms for tritium, transport mechanisms from the reactor through plant, systems to the environment, examples of routine effluent releases, offsite doses, basic groundwater transport and geological issues, and recent nuclear industry environmental and legal ramifications. (authors)

Jones, G. [Constellation Energy Group, R.E. Ginna Nuclear Power Plant, Ontario, NY (United States)

2008-07-15T23:59:59.000Z

485

Generic small modular reactor plant design.  

SciTech Connect

This report gives an overview of expected design characteristics, concepts, and procedures for small modular reactors. The purpose of this report is to provide those who are interested in reducing the cost and improving the safety of advanced nuclear power plants with a generic design that possesses enough detail in a non-sensitive manner to give merit to their conclusions. The report is focused on light water reactor technology, but does add details on what could be different in a more advanced design (see Appendix). Numerous reactor and facility concepts were used for inspiration (documented in the bibliography). The final design described here is conceptual and does not reflect any proposed concept or sub-systems, thus any details given here are only relevant within this report. This report does not include any design or engineering calculations.

Lewis, Tom Goslee,; Cipiti, Benjamin B.; Jordan, Sabina Erteza; Baum, Gregory A.

2012-12-01T23:59:59.000Z

486

Nuclear reactor shutdown control rod assembly  

DOE Patents (OSTI)

A temperature responsive, self-actuated nuclear reactor shutdown control rod assembly 10. The upper end 18 of a lower drive line 17 fits within the lower end of an upper drive line 12. The lower end (not shown) of the lower drive line 17 is connected to a neutron absorber. During normal temperature conditions the lower drive line 17 is supported by detent means 22,26. When an overtemperature condition occurs thermal actuation means 34 urges ring 26 upwardly sufficiently to allow balls 22 to move radially outwardly thereby allowing lower drive line 17 to move downwardly toward the core of the nuclear reactor resulting in automatic reduction of the reactor powder.

Bilibin, Konstantin (North Hollywood, CA)

1988-01-01T23:59:59.000Z

487

Oklo reactors and implications for nuclear science  

E-Print Network (OSTI)

We summarize the nuclear physics interests in the Oklo natural nuclear reactors, focusing particularly on developments over the past two decades. Modeling of the reactors has become increasingly sophisticated, employing Monte Carlo simulations with realistic geometries and materials that can generate both the thermal and epithermal fractions. The water content and the temperatures of the reactors have been uncertain parameters. We discuss recent work pointing to lower temperatures than earlier assumed. Nuclear cross sections are input to all Oklo modeling and we discuss a parameter, the $^{175}$Lu ground state cross section for thermal neutron capture leading to the isomer $^{176\\mathrm{m}}$ Lu, that warrants further investigation. Studies of the time dependence of dimensionless fundamental constants have been a driver for much of the recent work on Oklo. We critically review neutron resonance energy shifts and their dependence on the fine structure constant $\\alpha$ and the ratio $X_q=m_q/\\Lambda$ (where $m_...

Davis, E D; Sharapov, E I

2014-01-01T23:59:59.000Z

488

Mirror Advanced Reactor Study interim design report  

SciTech Connect

The status of the design of a tenth-of-a-kind commercial tandem-mirror fusion reactor is described at the midpoint of a two-year study. When completed, the design is to serve as a strategic goal for the mirror fusion program. The main objectives of the Mirror Advanced Reactor Study (MARS) are: (1) to design an attractive tandem-mirror fusion reactor producing electricity and synfuels (in alternate versions), (2) to identify key development and technology needs, and (3) to exploit the potential of fusion for safety, low activation, and simple disposal of radioactive waste. In the first year we have emphasized physics and engineering of the central cell and physics of the end cell. Design optimization and trade studies are continuing, and we expect additional modifications in the end cells to further improve the performance of the final design.

Not Available

1983-04-01T23:59:59.000Z

489

Neutral reactors on shunt compensated EHV lines  

SciTech Connect

This paper examines the applications of a neutral reactor in limiting resonance overvoltages induced on deenergized conductors due to parallel energized circuits and stuck breaker conditions. These applications are demonstrated through the planned 243 mile long Mead-Phoenix 500 kV line running on the same right of way as the existing Mead-Liberty 345 kV line. Reducing the secondary arc current during single pole reclosing is also examined. In addition to its applications, a procedure for sizing, rating and protection of the neutral reactor is explained.

Atmuri, S.R. [Teshmont Consultants Inc., Winnipeg, Manitoba (Canada); Thallam, R.S.; Gerlach, D.W.; Lundquist, T.G. [Salt River Project, Phoenix, AZ (United States); Selin, D.A. [Arizona Public Service Co., Phoenix, AZ (United States)

1994-12-31T23:59:59.000Z

490

Modeling of Reactor Kinetics and Dynamics  

SciTech Connect

In order to model a full fuel cycle in a nuclear reactor, it is necessary to simulate the short time-scale kinetic behavior of the reactor as well as the long time-scale dynamics that occur with fuel burnup. The former is modeled using the point kinetics equations, while the latter is modeled by coupling fuel burnup equations with the kinetics equations. When the equations are solved simultaneously with a nonlinear equation solver, the end result is a code with the unique capability of modeling transients at any time during a fuel cycle.

Matthew Johnson; Scott Lucas; Pavel Tsvetkov

2010-09-01T23:59:59.000Z

491

Theta 13 Determination with Nuclear Reactors  

E-Print Network (OSTI)

Recently there has been a lot of interest around the world in the use of nuclear reactors to measure theta 13, the last undetermined angle in the 3-neutrino mixing scenario. In this paper the motivations for theta 13 measurement using short baseline nuclear reactor experiments are discussed. The features of such an experiment are described in the context of Double Chooz, which is a new project planned to start data-taking in 2008, and to reach a sensitivity of sinsq(2 theta 13) < 0.03.

F. Dalnoki-Veress

2004-06-24T23:59:59.000Z

492

Distributed computing and nuclear reactor analysis  

SciTech Connect

Large-scale scientific and engineering calculations for nuclear reactor analysis can now be carried out effectively in a distributed computing environment, at costs far lower than for traditional mainframes. The distributed computing environment must include support for traditional system services, such as a queuing system for batch work, reliable filesystem backups, and parallel processing capabilities for large jobs. All ANL computer codes for reactor analysis have been adapted successfully to a distributed system based on workstations and X-terminals. Distributed parallel processing has been demonstrated to be effective for long-running Monte Carlo calculations.

Brown, F.B.; Derstine, K.L.; Blomquist, R.N.

1994-03-01T23:59:59.000Z

493

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

494

Property description and fact-finding report for NPR-3 Natrona County, Wyoming. Addendum to 22 August 1996 study of alternatives for future operations of the naval petroleum and oil shale reserves NPR-3  

SciTech Connect

The U.S. Department of Energy has asked Gustavson Associates, Inc. to serve as an Independent Petroleum Consultant under contract DE-AC01-96FE64202. This authorizes a study and recommendations regarding future development of Naval Petroleum Reserve No. 3 (NPR-3) in Natrona County, Wyoming. The report that follows is the Phase I fact-finding and property description for that study. The United States of America owns 100 percent of the mineral rights and surface rights in 9,321-acre NPR-3. This property comprises the Teapot Dome oil field and related production, processing and other facilities. Discovered in 1914, this field has 632 wells producing 1,807 barrels of oil per day. Production revenues are about $9.5 million per year. Remaining recoverable reserves are approximately 1.3 million barrels of oil. Significant plugging and abandonment (P&A) and environmental liabilities are present.

NONE

1997-05-01T23:59:59.000Z

495

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

496

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

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

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

497

Reactor Core Assembly - HFIR Technical Parameters | ORNL Neutron Sciences  

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

Home › Facilities › HFIR › Reactor Core Assembly Home › Facilities › HFIR › Reactor Core Assembly Reactor Core Assembly The reactor core assembly is contained in an 8-ft (2.44-m)-diameter pressure vessel located in a pool of water. The top of the pressure vessel is 17 ft (5.18 m) below the pool surface, and the reactor horizontal mid-plane is 27.5 ft (8.38 m) below the pool surface. The control plate drive mechanisms are located in a subpile room beneath the pressure vessel. These features provide the necessary shielding for working above the reactor core and greatly facilitate access to the pressure vessel, core, and reflector regions. In-core irradiation and experiment locations (cross section at horizontal midplane) Reactor core assembly Reactor core assembly: (1) in-core irradiation and experiment locations,

498

TABLE 2. U.S. Nuclear Reactor Ownership Data  

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

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

499

Ssessment methodology for proliferation resistant fast breeder reactor  

E-Print Network (OSTI)

Due to perceived proliferation risks, current US fast reactor designs have avoided the use of uranium blankets. While reducing the amount of plutonium produced, this omission also restrains the reactor design space and has ...

Singh, Mohit, S.M. Massachusetts Institute of Technology

2014-01-01T23:59:59.000Z

500

Gamma-ray Energy Spectra Observed around a Nuclear Reactor  

Science Journals Connector (OSTI)

......Energy Spectra Observed around a Nuclear Reactor Yoshiyuki Nakashima * Susumu Minato...Katsurayama ** * Department of Nuclear Engineering, Faculty of Engineering...Nagoya, Japan ** Reseach Reactor Institute, Kyoto Univ., Kumatori-cho......

Yoshiyuki Nakashima; Susumu Minato; Minoru Kawano; Tadashi Tsujimoto; Kousuke Katsurayama

1971-09-01T23:59:59.000Z