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Note: This page contains sample records for the topic "reactor site summary" 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.


1

Untitled Page -- Considered Sites Summary  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are here Home » Sites » Sites Pending Transfer

2

Untitled Page -- Other Sites Summary  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are here Home » Sites » Sites Pending

3

Nevada Test Site Environmental Summary Report 2006  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2006 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and its satellite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

Cathy Wills

2007-10-01T23:59:59.000Z

4

Nevada Test Site Summary 2006 (Volume 2)  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security-related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2006 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and its satellite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

Cathy Wills

2007-10-01T23:59:59.000Z

5

Nevada Test Site Environmental Report 2007 Summary  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2007 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

Cathy Wills

2008-09-01T23:59:59.000Z

6

Independent Oversight Inspection, Nevada Test Site, Summary Report...  

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

Summary Report - October 2002 Independent Oversight Inspection, Nevada Test Site, Summary Report - October 2002 October 2002 Inspection of Environment, Safety, and Health and...

7

Savannah River Site production reactor technical specifications. K Production Reactor  

SciTech Connect (OSTI)

These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This report describes requirements on thermal-hydraulic limits; limiting conditions for operation and surveillance for the reactor, power distribution control, instrumentation, process water system, emergency cooling and emergency shutdown systems, confinement systems, plant systems, electrical systems, components handling, and special test exceptions; design features; and administrative controls.

NONE

1996-02-01T23:59:59.000Z

8

Reactor siting risk comparisons related to recommendations of NUREG-0625  

SciTech Connect (OSTI)

This document evaluates how implementing the remote siting recommendations for nuclear reactors (NUREG-0625) made by the Siting Policy Task Force of the US Nuclear Regulatory Commission (NRC) can reduce potential public risk. The document analyzes how population density affects site-specific risk for both light water reactors (LWRs) and high-temperature gas-cooled reactors (HTGRs).

Barsell, A.W.; Dombek, F.S.; Orvis, D.D.

1980-11-01T23:59:59.000Z

9

COLORADO SCHOOL OF MINES RESEARCH INSTITUTE SITE REMEDIATION PROJECT SUMMARY  

E-Print Network [OSTI]

COLORADO SCHOOL OF MINES RESEARCH INSTITUTE SITE REMEDIATION PROJECT SUMMARY May 15, 2007 · The Colorado School of Mines Research Institute Site (the "Site) has been undergoing additional investigation 400 cubic yards of the dredged material had been buried in the "Clay Pits" area south of the Colorado

10

Nevada Test Site Environmental Report 2008 Summary  

SciTech Connect (OSTI)

The Nevada Test Site Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

Cathy A. Wills

2009-09-01T23:59:59.000Z

11

Summary Site Environmental Report for 1998  

SciTech Connect (OSTI)

Sandia National Laboratories' California Laboratory (Sandia/California) publishes a complete environmental report annually to communicate environmental monitoring results and efforts to reduce pollution at the site. Information presented includes impacts to the surrounding area and the local community from operations at Sandia/California. The Site Environmental Report is distributed to the Department of Energy Federal, State, and local regulatory agencies; community officials; and the public (available in public reading rooms). This booklet summarizes the information provided in the Sandia/California Site Environmental Report for 1998. It is intended to serve the general public by presenting environmental information in less technical language than is used in the formal report.

Holland, R.C.

1999-06-01T23:59:59.000Z

12

COMPLIANCE SUMMARY 1997 BNL Site Environmental Report 2 -1  

E-Print Network [OSTI]

COMPLIANCE SUMMARY 1997 BNL Site Environmental Report 2 - 1 Chapter 2 COMPLIANCE SUMMARY regulations and DOE Orders. This section briefly summarizes the compliance status for existing facilities to regulatory permits. They include one SPDES permit, a Major Petroleum Facility (MPF) license, two Resource

13

Paducah Site annual environmental report summary for 1994  

SciTech Connect (OSTI)

This pamphlet contains summaries of the environmental programs at the Paducah Gaseous Plant site, environmental monitoring and the results, and the impact of operations on the environment and the public for 1994.

Horak, C.M. [ed.] [Oak Ridge National Lab., TN (United States)

1996-02-01T23:59:59.000Z

14

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors | DepartmentHANFORDHaier:FriendsLeads9066

15

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors | DepartmentHANFORDHaier:FriendsLeads9066K1)

16

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors | DepartmentHANFORDHaier:FriendsLeads9066K1)

17

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors |

18

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors |DOCUMENT RELEASE FORM ! I (1) Document

19

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors |DOCUMENT RELEASE FORM ! I (1) DocumentFORM

20

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors |DOCUMENT RELEASE FORM ! I (1) DocumentFORM

Note: This page contains sample records for the topic "reactor site summary" 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

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors |DOCUMENT RELEASE FORM ! I (1)

22

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors |DOCUMENT RELEASE FORM ! I (1)RPP-48144,

23

Hanford Site C Tank Farm Meeting Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Celland Contractors |DOCUMENT RELEASE FORM ! I

24

Summary of Weldon Spring Site Focus Area  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C.Green River, Utah,Tuba City,'1Dearof Weldon

25

Committee Meeting Summaries and Presentations - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation InInformationCenterResearchCASLNanoporous Materials | CenterCommittee Meeting Information

26

2008 Annual Site Environmental Report Summary Pamphlet  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert SouthwestTechnologies | BlandinePrincetonOPTFebruary 2001May57SeptemberNovemberAnnual

27

Expedited site characterization. Innovative technology summary report  

SciTech Connect (OSTI)

Expedited Site Characterization (ESC) has been developed, demonstrated, and deployed as a new time-saving, cost-effective approach for hazardous waste site investigations. ESC is an alternative approach that effectively shortens the length of the assessment period and may significantly reduce costs at many sites. It is not a specific technology or system but is a methodology for most effectively conducting a site characterization. The principal elements of ESC are: a field investigation conducted by an integrated team of experienced professionals working in the field at the same time, analysis, integration and initial validation of the characterization data as they are obtained in the field, and a dynamic work plan that enables the team to take advantage of new insights from recent data to adjust the work plan in the field. This report covers demonstrations that took place between 1989 and 1996. This paper gives a description of the technology and discusses its performance, applications, cost, regulatory and policy issues, and lessons learned.

NONE

1998-12-01T23:59:59.000Z

28

Light Water Reactor Sustainability Constellation Pilot Project FY13 Summary Report  

SciTech Connect (OSTI)

Summary report for Light Water Reactor Sustainability (LWRS) activities related to the R. E. Ginna and Nine Mile Point Unit 1 for FY13.

R. Johansen

2013-09-01T23:59:59.000Z

29

Light Water Reactor Sustainability Constellation Pilot Project FY12 Summary Report  

SciTech Connect (OSTI)

Summary report for Light Water Reactor Sustainability (LWRS) activities related to the R. E. Ginna and Nine Mile Point Unit 1 for FY12.

R. Johansen

2012-09-01T23:59:59.000Z

30

Tank Waste Committee Summaries - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatus TomAboutManus Site-Inactive TWPCarbonTakeRV 14800TankSection

31

Nevada Test Site Resource Management Plan: Annual summary, January 2000  

SciTech Connect (OSTI)

The Nevada Test Site Resource Management Plan published in December of 1998 (DOE/NV--518) describes the Nevada Test Site stewardship mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. As part of the Nevada Test Site Resource Management Plan, DOE Nevada Operations Office has committed to perform and publish an annual summary review of DOE Nevada Operations' stewardship of the Nevada Test Site. This annual summary includes a description of progress made toward the goals of the Nevada Test Site Resource Management Plan, pertinent monitoring data, actions that were taken to adapt to changing conditions, and any other changes to the Nevada Test Site Resource Management Plan.

NONE

2000-01-01T23:59:59.000Z

32

Idaho Site Obtains Patent for Nuclear Reactor Sodium Cleanup...  

Office of Environmental Management (EM)

Idaho Site Obtains Patent for Nuclear Reactor Sodium Cleanup Treatment March 28, 2013 - 12:00pm Addthis CWI engineers Jeff Jones, David Tolman, right, and Kirk Dooley...

33

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

Energy Savers [EERE]

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

34

Commercial Light Water Reactor Tritium Extraction Facility Geotechnical Summary Report  

SciTech Connect (OSTI)

A geotechnical investigation program has been completed for the Circulating Light Water Reactor - Tritium Extraction Facility (CLWR-TEF) at the Savannah River Site (SRS). The program consisted of reviewing previous geotechnical and geologic data and reports, performing subsurface field exploration, field and laboratory testing and geologic and engineering analyses. The purpose of this investigation was to characterize the subsurface conditions for the CLWR-TEF in terms of subsurface stratigraphy and engineering properties for design and to perform selected engineering analyses. The objectives of the evaluation were to establish site-specific geologic conditions, obtain representative engineering properties of the subsurface and potential fill materials, evaluate the lateral and vertical extent of any soft zones encountered, and perform engineering analyses for slope stability, bearing capacity and settlement, and liquefaction potential. In addition, provide general recommendations for construction and earthwork.

Lewis, M.R.

2000-01-11T23:59:59.000Z

35

Light Water Reactor Sustainability Constellation Pilot Project FY11 Summary Report  

SciTech Connect (OSTI)

Summary report for Fiscal Year 2011 activities associated with the Constellation Pilot Project. The project is a joint effor between Constellation Nuclear Energy Group (CENG), EPRI, and the DOE Light Water Reactor Sustainability Program. The project utilizes two CENG reactor stations: R.E. Ginna and Nine Point Unit 1. Included in the report are activities associate with reactor internals and concrete containments.

R. Johansen

2011-09-01T23:59:59.000Z

36

Fusion-reactor-control study. Volume 1: summary  

SciTech Connect (OSTI)

The study included the exploration of reactor dynamic response and the delineation of functional control requirements. Where possible, candidate control solutions were conceptualized and evaluated using a reactor control simulator that portrayed the evolution of the plasma over the entire reactor operating cycle.

Not Available

1982-03-01T23:59:59.000Z

37

Paducah Site annual environmental report summary for 1995  

SciTech Connect (OSTI)

This report contains summaries of the environmental programs at the Paducah Site, as well as the impacts of its operations on the environment and the public for 1995. The results of environmental monitoring are presented. The goal is to keep emissions as low as possible, enhance the strict safety controls that are in place and use state-of-the-art technology to complete environmental remediation projects in the most cost-effective and efficient manner possible.

Belcher, G. [ed.

1997-01-01T23:59:59.000Z

38

FORMERLY USED SITES REMEDIAL ACTION PROGRAM DESIGNATION SUMMARY  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North - Consequences ofr t l t (

39

Savannah River Site Federal Facility Agreement, January 15, 1993 Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 Page 1 of 1Sandra L.155-W StateSite

40

Nevada Test Site FFCA Consent Order, March 27, 1996 Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September 15, 2010 PrintingNeed for An Integrated Risk ModelNevadaTest Site

Note: This page contains sample records for the topic "reactor site summary" 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

Nevada National Security Site Environmental Report 2011 Summary  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada National Security Site (NNSS). NNSA/NSO prepares the Nevada National Security Site Environmental Report (NNSSER) to provide the public an understanding of the environmental monitoring and compliance activities that are conducted on the NNSS to protect the public and the environment from radiation hazards and from nonradiological impacts. The NNSSER is a comprehensive report of environmental activities performed at the NNSS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. This summary provides an abbreviated and more readable version of the NNSSER. It does not contain detailed descriptions or presentations of monitoring designs, data collection methods, data tables, the NNSS environment, or all environmental program activities performed throughout the year. The NNSS is currently the nation's unique site for ongoing national security-related missions and high-risk operations. The NNSS is located about 65 miles northwest of Las Vegas. The approximately 1,360-square-mile site is one of the largest restricted access areas in the United States. It is surrounded by federal installations with strictly controlled access, as well as by lands that are open to public entry.

Cathy Wills, ed

2012-09-12T23:59:59.000Z

42

SAVANNAH RIVER SITE ENVIRONMENTAL REPORT SUMMARY FOR 2012  

SciTech Connect (OSTI)

This report's purpose is to: ? Present summary environmental data that characterize Site environmental management performance, ? Describe compliance status with respect to environmental standards and requirements, and ? Highlight significant programs and efforts. Environmental monitoring is conducted extensively with a 2,000-square-mile network extending 25 miles from SRS, with some monitoring performed as far as 100 miles from the Site. The area includes neighboring cities, towns, and counties in Georgia (GA) and South Carolina (SC). Thousands of samples of air, rainwater, surface water, drinking water, groundwater, food products, wildlife, soil, sediment, and vegetation are collected by SRS and analyzed for the presence of radioactive and nonradioactive contaminants. During 2012, SRS accomplished several significant milestones while maintaining its record of environmental excellence, as its operations continued to result in minimal impact to the public and the environment. The Site?s radioactive and chemical discharges to air and water were well below regulatory standards for environmental and public health protection; its air and water quality met applicable requirements; and the potential radiation dose to the public was well below the DOE public dose limit.

Griffith, M.; Meyer, A.

2013-09-12T23:59:59.000Z

43

Oak Ridge reservation, annual site environmental report summary for 1993  

SciTech Connect (OSTI)

The U.S. Department of Energy requires annual site environmental reports from facilities that operate under its auspices. To fulfill that requirement, such an annual report is published for the Oak Ridge Reservation, which comprises three major sites, each of which has unique monitoring requirements in addition to many shared obligations. As a result, the report is complex and highly detailed. Annual site environmental reports are public documents that are read by government regulators, scientists, engineers, business people, special interest groups, and members of the public at large. For that reason, the reports need to be accessible to a variety of audiences in addition to being accurate and complete. This pamphlet summarizes environmental activities on the reservation, which for some readers may be adequate; for those who seek more detail, it will lend coherence to their approach to the report itself. The content of this summary was taken from Oak Ridge Reservation Annual Site Environmental Report for 1993. Results of the many environmental monitoring and surveillance activities are detailed in this report.

Not Available

1994-11-01T23:59:59.000Z

44

Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2  

SciTech Connect (OSTI)

The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.

Olson, Gail Lynn; Mc Cardell, Richard Keith; Illum, Douglas Brent

2002-09-01T23:59:59.000Z

45

Fuel Summary Report: Shippingport Light Water Breeder Reactor  

SciTech Connect (OSTI)

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

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

1999-01-01T23:59:59.000Z

46

Piqua, Ohio, Decommissioned Reactor Site Fact Sheet  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*.MSE Cores" _August.. .._

47

Hallam, Nebraska, Decommissioned Reactor Site Fact Sheet  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$ EGcG ENERGYELIkNATIONHEALXH ANDHEMORANDUM TO: F

48

Summary of the Hanford Site Environmental Report for Calendar Year 2004  

SciTech Connect (OSTI)

This booklet summarizes the information contained in ''Hanford Site Environmental Report for Calendar Year 2004.'' The Hanford Site environmental report, published annually since 1958, includes information and summary data that provide an overview of the activities at DOE's Hanford Site.

Hanf, Robert W.; Morasch, Launa F.; Poston, Ted M.; Dirkes, Roger L.

2005-09-26T23:59:59.000Z

49

Summary of space nuclear reactor power systems, 1983--1992  

SciTech Connect (OSTI)

This report summarizes major developments in the last ten years which have greatly expanded the space nuclear reactor power systems technology base. In the SP-100 program, after a competition between liquid-metal, gas-cooled, thermionic, and heat pipe reactors integrated with various combinations of thermoelectric thermionic, Brayton, Rankine, and Stirling energy conversion systems, three concepts:were selected for further evaluation. In 1985, the high-temperature (1,350 K), lithium-cooled reactor with thermoelectric conversion was selected for full scale development. Since then, significant progress has been achieved including the demonstration of a 7-y-life uranium nitride fuel pin. Progress on the lithium-cooled reactor with thermoelectrics has progressed from a concept, through a generic flight system design, to the design, development, and testing of specific components. Meanwhile, the USSR in 1987--88 orbited a new generation of nuclear power systems beyond the, thermoelectric plants on the RORSAT satellites. The US has continued to advance its own thermionic fuel element development, concentrating on a multicell fuel element configuration. Experimental work has demonstrated a single cell operating time of about 1 1/2-y. Technology advances have also been made in the Stirling engine; an advanced engine that operates at 1,050 K is ready for testing. Additional concepts have been studied and experiments have been performed on a variety of systems to meet changing needs; such as powers of tens-to-hundreds of megawatts and highly survivable systems of tens-of-kilowatts power.

Buden, D.

1993-08-11T23:59:59.000Z

50

FMDP reactor alternative summary report: Volume 4, Evolutionary LWR alternative  

SciTech Connect (OSTI)

Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] have become surplus to national defense needs both in the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. The purpose of this report is to provide schedule, cost, and technical information that will be used to support the Record of Process (ROD). Following the screening process, DOE/MD via its national laboratories initiated a more detailed analysis activity to further evaluate each of the ten plutonium disposition alternatives that survived the screening process. Three ``Alternative Teams,`` chartered by DOE and comprised of technical experts from across the DOE national laboratory complex, conducted these analyses. One team was chartered for each of the major disposition classes (borehole, immobilization, and reactors). During the last year and a half, the Fissile Materials Disposition Program (FMDP) Reactor Alternative Team (RxAT) has conducted extensive analyses of the cost, schedule, technical maturity, S&S, and other characteristics of reactor-based plutonium disposition. The results of the RxAT`s analyses of the existing LWR, CANDU, and partially complete LWR alternatives are documented in Volumes 1-3 of this report. This document (Volume 4) summarizes the results of these analyses for the ELWR-based plutonium disposition option.

NONE

1996-09-01T23:59:59.000Z

51

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

SciTech Connect (OSTI)

This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

1994-10-01T23:59:59.000Z

52

Oak Ridge Reservation Annual Site Environmental Report Summary, 2004  

SciTech Connect (OSTI)

The Department of Energy (DOE) and our contractors strive to provide our stakeholders a comprehensive understanding of the consequences of DOE operations past and present. Toward this end a far-reaching multimillion-dollar annual monitoring and surveillance program collects and analyzes tens of thousands of air, surface and groundwater, soil, mud, plant, and animal samples. This effort represents the work of many dedicated environmental scientists who carry out these extensive programs and work hard to protect and enhance the environment. We publish the results in a detailed Annual Site Environmental Report (ASER), and a separate Data Volume for those who wish to see the supporting data. These documents present all the facts and figures, but are highly technical and not easily understood, and it's essential we provide a summary document simple to read and understand. So each year I team with Karns High School and ask students to write an Annual Site Environmental Report Summary that will be both informative and enjoyable to read. These environmental documents are perhaps the most important DOE reports because they explain the environmental monitoring programs and show the consequences of our operations in great detail to our legislatures, stakeholders, and the public. This ASER summary is written for you, the public, our most important stakeholder, with the hope that you find it comprehensible and of value in gaining an accurate understanding of the Oak Ridge Reservation. All three documents can be found on the web, along with previous publications, at http://www.ornl.gov/aser. It's a great pleasure to meet my new class each year and capture fresh creative ideas. I'm always delighted to see their interest and desire to learn and to produce a document for the public that reflects their personality and skills, and one the public will utilize and find of value. I sincerely thank these talented Karns High School students and their exceptional teacher, Mrs. Heather Bock, for accepting my challenge to think out of the box and put together this DOE document. Thanks go out as well to each contributing art student, and of course to Principal Clifford Davis, Jr., for his enthusiastic support. When I gave this College Preparation English 4 Class the challenge I was given back all smiles, eagerness, and an ardent zeal to succeed. I hope you, our public, find this product of their effort of value and quality.

Hughes, JF

2005-11-30T23:59:59.000Z

53

FMDP reactor alternative summary report. Volume 1 - existing LWR alternative  

SciTech Connect (OSTI)

Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] are becoming surplus to national defense needs in both the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. This document summarizes the results of analysis concerned with existing light water reactor plutonium disposition alternatives.

Greene, S.R.; Bevard, B.B. [and others

1996-10-07T23:59:59.000Z

54

MHTGR: New production reactor summary of experience base  

SciTech Connect (OSTI)

Worldwide interest in the Modular High-Temperature Gas-Cooled Reactor (MHTGR) stems from the capability of the system to retain the advanced fuel and thermal performance while providing unparalleled levels of safety. The small power level of the MHTGR and its passive systems give it a margin of safety not attained by other concepts being developed for power generation. This report covers the experience base for the key nuclear system, components, and processes related to the MHTGR-NPR. 9 refs., 39 figs., 9 tabs.

Not Available

1988-03-01T23:59:59.000Z

55

BONUS, Puerto Rico, Decommissioned Reactor Site Fact Sheet  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North SiteD&D D&D BONUS,

56

Advanced Test Reactor probabilistic risk assessment methodology and results summary  

SciTech Connect (OSTI)

The Advanced Test Reactor (ATR) probabilistic risk assessment (PRA) Level 1 report documents a comprehensive and state-of-the-art study to establish and reduce the risk associated with operation of the ATR, expressed as a mean frequency of fuel damage. The ATR Level 1 PRA effort is unique and outstanding because of its consistent and state-of-the-art treatment of all facets of the risk study, its comprehensive and cost-effective risk reduction effort while the risk baseline was being established, and its thorough and comprehensive documentation. The PRA includes many improvements to the state-of-the-art, including the following: establishment of a comprehensive generic data base for component failures, treatment of initiating event frequencies given significant plant improvements in recent years, performance of efficient identification and screening of fire and flood events using code-assisted vital area analysis, identification and treatment of significant seismic-fire-flood-wind interactions, and modeling of large loss-of-coolant accidents (LOCAs) and experiment loop ruptures leading to direct damage of the ATR core. 18 refs.

Eide, S.A.; Atkinson, S.A.; Thatcher, T.A.

1992-01-01T23:59:59.000Z

57

A Small Secure Transportable Autonomous Lead-Cooled Fast Reactor for Deployment at Remote Sites  

SciTech Connect (OSTI)

This presentation discusses a small secure transportable autonomous lead-cooled fast reactor for deployment at remote sites.

Sienicki, J .J.; Smith, M.A.; Mosseytsev, A.V.; Yang, W.S.; Wade, D.C.

2004-10-06T23:59:59.000Z

58

Site Suitability and Hazard Assessment Guide for Small Modular Reactors  

SciTech Connect (OSTI)

Commercial nuclear reactor projects in the U.S. have traditionally employed large light water reactors (LWR) to generate regional supplies of electricity. Although large LWRs have consistently dominated commercial nuclear markets both domestically and abroad, the concept of small modular reactors (SMRs) capable of producing between 30 MW(t) and 900 MW(t) to generating steam for electricity is not new. Nor is the idea of locating small nuclear reactors in close proximity to and in physical connection with industrial processes to provide a long-term source of thermal energy. Growing problems associated continued use of fossil fuels and enhancements in efficiency and safety because of recent advancements in reactor technology suggest that the likelihood of near-term SMR technology(s) deployment at multiple locations within the United States is growing. Many different types of SMR technology are viable for siting in the domestic commercial energy market. However, the potential application of a particular proprietary SMR design will vary according to the target heat end-use application and the site upon which it is proposed to be located. Reactor heat applications most commonly referenced in connection with the SMR market include electric power production, district heating, desalinization, and the supply of thermal energy to various processes that require high temperature over long time periods, or a combination thereof. Indeed, the modular construction, reliability and long operational life purported to be associated with some SMR concepts now being discussed may offer flexibility and benefits no other technology can offer. Effective siting is one of the many early challenges that face a proposed SMR installation project. Site-specific factors dealing with support to facility construction and operation, risks to the plant and the surrounding area, and the consequences subsequent to those risks must be fully identified, analyzed, and possibly mitigated before a license will be granted to construct and operate a nuclear facility. Examples of significant site-related concerns include area geotechnical and geological hazard properties, local climatology and meteorology, water resource availability, the vulnerability of surrounding populations and the environmental to adverse effects in the unlikely event of radionuclide release, the socioeconomic impacts of SMR plant installation and the effects it has on aesthetics, proximity to energy use customers, the topography and area infrastructure that affect plant constructability and security, and concerns related to the transport, installation, operation and decommissioning of major plant components.

Wayne Moe

2013-10-01T23:59:59.000Z

59

Summary of the Hanford Site Environmental Report for Calendar Year 2005  

SciTech Connect (OSTI)

This small booklet provides highlights of the environmental monitoring at the Hanford Site during 2005. It is a summary of the information contained in the larger report: Hanford Site Environmental Monitoring for Calendar Year 2005.

Hanf, Robert W.; Morasch, Launa F.; Poston, Ted M.; Dirkes, Roger L.

2006-09-28T23:59:59.000Z

60

Licensed operating reactors: Status summary report, data as of December 31, 1995. Volume 20  

SciTech Connect (OSTI)

The US Nuclear Regulatory Commission`s monthly summary of licensed nuclear power reactor data is based primarily on the operating data report submitted by licensees for each unit. This report is divided into two sections: the first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 availability factors, capacity factors, and forced outage rates are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensees and notes to the use of weighted averages and starting dates other than commercial operation are provided.

NONE

1996-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor site summary" 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

Nevada National Security Site Environmental Report Summary 2010  

SciTech Connect (OSTI)

This document summarizes the data reported in the Nevada National Security Site Environmental Report 2010.

C. Wills, ed.

2011-09-13T23:59:59.000Z

62

Independent Oversight Inspection, Savannah River Site, Summary Report- February 2004  

Broader source: Energy.gov [DOE]

Inspection of Environment, Safety, and Health Management and Emergency Management at the Savannah River Site

63

FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative  

SciTech Connect (OSTI)

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative.

Greene, S.R.; Spellman, D.J.; Bevard, B.B. [and others

1996-09-01T23:59:59.000Z

64

SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING  

SciTech Connect (OSTI)

The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs and testing, and fill placement strategy. This information is applicable to decommissioning both the 105-P and 105-R facilities. The ISD process for the entire 105-P and 105-R reactor facilities will require approximately 250,000 cubic yards (191,140 cubic meters) of grout and 2,400 cubic yards (1,840 cubic meters) of structural concrete which will be placed over a twelve month period to meet the accelerated schedule ISD schedule. The status and lessons learned in the SRS Reactor Facility ISD process will be described.

Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

2009-12-03T23:59:59.000Z

65

2014 Annual Planning Summary for the Berkeley Site Office  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2014 and 2015 within theBerkeley Site Office.

66

2013 Annual Planning Summary for the SLAC Site Office  

Broader source: Energy.gov [DOE]

?The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2013 and 2014 within the SLAC Site Office.

67

2013 Annual Planning Summary for the Argonne Site Office  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2013 and 2014 within theArgonne Site Office

68

2013 Annual Planning Summary for the FERMI Site Office  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2013 and 2014 within the FERMI Site Office.

69

2012 Annual Planning Summary for Thomas Jefferson Site Office  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within Thomas Jefferson Site Office.

70

Summary of Activities at the ST LOUIS NORTH COUNTY SITE  

E-Print Network [OSTI]

, the SLAPS wastes were purchased, moved, and stored at a property on Latty Avenue. The eastern part the materials along haul routes and to adjacent properties forming the SLAPS and Latty Avenue Vicinity Site. The North County Site is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP

US Army Corps of Engineers

71

June 28, 2005 France to Be Site of World's First Nuclear Fusion Reactor  

E-Print Network [OSTI]

June 28, 2005 France to Be Site of World's First Nuclear Fusion Reactor By CRAIG S. SMITH PARIS fusion reactor, an estimated $12 billion project that many scientists see as essential to solving chose the country as the site for the International Thermonuclear Experimental Reactor. Japan, which had

72

Savannah River Site environmental report for 1993 summary pamphlet  

SciTech Connect (OSTI)

This pamphlet summarizes the impact of 1993 Savannah River Site operations on the environment and the off-site public. It includes an overview of site operations; the basis for radiological and nonradiological monitoring; 1993 radiological releases and the resulting dose to the off-site population; and results of the 1993 nonradiological program. The Savannah River Site Environmental Report for 1993 describes the findings of the environmental monitoring program for 1993. The report contains detailed information about site operations,the environmental monitoring and surveillance programs, monitoring and surveillance results, environmental compliance activities, and special programs. The report is distributed to government officials, members of the US Congress, universities, government facilities, environmental and civic groups, the news media, and interested individuals.

Karapatakis, L.

1994-05-01T23:59:59.000Z

73

Nevada National Security Site Environmental Report 2013 Summary  

SciTech Connect (OSTI)

The information presented in this document is explained in greater detail in the Nevada National Security Site Environmental Report 2013 (DOE/NV/25946--2182).

Wills, C.

2014-09-09T23:59:59.000Z

74

Data Summary Report for Hanford Site Coal Ash Characterization  

SciTech Connect (OSTI)

The purpose of this report is to present data and findings from sampling and analysis of five distinct areas of coal ash within the Hanford Site River Corridor

Sulloway, H. M.

2012-03-06T23:59:59.000Z

75

Remotely operated excavator needs assessment/site visit summary  

SciTech Connect (OSTI)

The Uranium in Soils Integrated Demonstration requested an assessment of soil excavation needs relative to soil remediation. The following list identifies the DOE sites assessed: Mound Laboratory, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, Nevada Test Site, Lawrence Livermore National Laboratory, Rocky Flats Plant, Los Alamos National Laboratory, Sandia National Laboratory, Idaho National Engineering Laboratory, Hanford Site, and Fernald Site. The reviewed sites fall into one or more of the following three categories: production, EPA National Priorities List, or CERCLA (superfund) designation. Only three of the sites appear to have the need for a remotely operated excavator rope. Hanford and Idaho Falls have areas of high-level radioactive contamination either buried or in/under buildings. The Fernald site has a need for remote operated equipment of different types. It is their feeling that remote equipment can be used to remove the health dangers to humans by removing them from the area. Most interviewees stated that characterization technologies needs are more immediate concern over excavation. In addition, the sites do not have similar geographic conditions which would aid in the development of a generic precision excavator. The sites visited were not ready to utilize or provide the required design information necessary to draft a performance specification. This creates a strong case against the development of one type of ROPE for use at these sites. Assuming soil characterization technology/methodology is improved sufficiently to allow accurate and real time field characterization then development of a precision excavator might be pursued based on FEMP needs, since the FEMP`s sole scope of work is remediation. The excavator could then be used/tested and then later modified for other sites as warranted.

Straub, J.; Haller, S.; Worsley, R. [Westinghouse Environmental Management Co. of Ohio, Cincinnati, OH (United States); King, M. [THETA Technology Inc. (United States)

1992-12-02T23:59:59.000Z

76

Hanford Site Climatological Summary 2004 with Historical Data  

SciTech Connect (OSTI)

This document presents the climatological data measured on the DOE Hanford Site for calendar year 2004. This report contains updated historical information for temperature, precipitation, wind, and normal and extreme values of temperature, and precipitation.

Hoitink, Dana J.; Burk, Kenneth W.; Ramsdell, James V.; Shaw, William J.

2005-06-03T23:59:59.000Z

77

Summary of the Hanford Site Environmental Report for Calendar Year 2008  

SciTech Connect (OSTI)

This summary booklet summarizes the "Hanford Site Environmental Report for Calendar Year 2008." The Hanford Site environmental report, published annually since 1958, includes information and summary data that provide an overview of activities at the U.S. Department of Energy's (DOE) Hanford Site. The Hanford Site environmental report provides an overview of activities at the site; demonstrates the status of the sites compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2009 information is included where appropriate.

Duncan, Joanne P.; Poston, Ted M.; Dirkes, Roger L.

2009-09-15T23:59:59.000Z

78

Summary of the Hanford Site Environmental Report for Calendar Year 2007  

SciTech Connect (OSTI)

This summary booklet summarizes the "Hanford Site Environmental Report for Calendar Year 2007." The Hanford Site environmental report, published annually since 1958, includes information and summary data that provide an overview of activities at the U.S. Department of Energy's (DOE) Hanford Site. The Hanford Site environmental report provides an overview of activities at the site; demonstrates the status of the sites compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights signifi cant environmental and public protection programs and efforts. Some historical and early 2008 information is included where appropriate.

Duncan, Joanne P.; Poston, Ted M.; Dirkes, Roger L.

2008-09-10T23:59:59.000Z

79

Summary of the Hanford Site Environmental Report for Calendar Year 2009  

SciTech Connect (OSTI)

This summary booklet summarizes the "Hanford Site Environmental Report for Calendar Year 2009." The Hanford Site environmental report, published annually since 1958, includes information and summary data that provide an overview of activities at the U.S. Department of Energy's (DOE) Hanford Site. The Hanford Site environmental report provides an overview of activities at the site; demonstrates the status of the sites compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2010 information is included where appropriate.

Duncan, Joanne P.; Poston, Ted M.; Dirkes, Roger L.

2010-09-30T23:59:59.000Z

80

Savannah River Site Settlement Agreement Amendment, June 15, 1989 Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 Page 1 of 1Sandra L.155-WSavannah River

Note: This page contains sample records for the topic "reactor site summary" 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

Savannah River Site Settlement Agreement, August 26, 1991 Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 Page 1 of 1Sandra L.155-WSavannah

82

Savannah River Site Settlement Agreement, May 1, 1987 Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 Page 1 of 1Sandra L.155-WSavannah27-SW State

83

Savannah River Site Settlement Agreement, November 10, 1987 Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 Page 1 of 1Sandra L.155-WSavannah27-SW

84

Draft Site-Wide Environmental Impact Statement Nevada Summary Draft |  

National Nuclear Security Administration (NNSA)

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85

Draft Site-Wide Environmental Impact Statement Nevada Summary | National  

National Nuclear Security Administration (NNSA)

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86

Met and Climate Data Summary Products - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell Batteries & Fuel Cells In This SectionMesdi

87

Monticello Mill site Federal Facility Agreement, December 22, 1988 Summary  

Office of Environmental Management (EM)

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88

Nevada Test Site FFCA Consent Order, May 10, 1996 Summary  

Office of Environmental Management (EM)

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89

Summary - Disposal Practices at the Savannah River Site  

Office of Environmental Management (EM)

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90

Summary - Plutonium Preparation Project at the Savannah River Site  

Office of Environmental Management (EM)

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91

Summary - Savannah River Site Tank 48H Waste Treatment Project  

Office of Environmental Management (EM)

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92

Summary - Tank 48 at the Savannah River Site  

Office of Environmental Management (EM)

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93

2007 Annual Site Environmental Report Summary Pamphlet 1  

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

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94

Licensed operating reactors: Status summary report data as of December 31, 1991. Volume 16  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission`s annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1991) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.

NONE

1992-03-01T23:59:59.000Z

95

Licensed operating reactors. Status summary report data as of December 31, 1993  

SciTech Connect (OSTI)

The Nuclear Regulatory Commissions annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December, the year to date (in this case calendar year 1993) and cumulative data, usually for the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.

Hartfield, R.A.

1994-03-01T23:59:59.000Z

96

Licensed operating reactors. Status summary report data as of 12-31-94: Volume 19  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission`s annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1994) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.

NONE

1995-04-01T23:59:59.000Z

97

EIS-0119: Decommissioning of Eight Surplus Production Reactors at the Harford Site, Richland, WA  

Broader source: Energy.gov [DOE]

This EIS presents analyses of potential environmental impacts of decommissioning the eight surplus production reactors at the Hanford Site near Richland, Washington.

98

EIS-0119: Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

This EIS presents analyses of potential environmental impacts of decommissioning the eight surplus production reactors at the Hanford Site near Richland, Washington.

99

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

SciTech Connect (OSTI)

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

Sarah Roberts

2006-10-18T23:59:59.000Z

100

Summary of Activities at the ST. LOUIS DOWNTOWN SITE  

E-Print Network [OSTI]

, USACE FUSRAP Project Office 8945 Latty Avenue Berkeley, Missouri 63134 And St. Louis Public Library 1301/CentersofExpertise/ FormerlyUtilizedSitesRemedialAc- tionProgram.aspx Or write St. Louis District, USACE FUSRAP Project Office 8945 Latty Avenue Berkeley, Missouri 63134 Background From 1942 to 1957, the Mallinckrodt Chemical

US Army Corps of Engineers

Note: This page contains sample records for the topic "reactor site summary" 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

Summary of Activities at the ST LOUIS NORTH COUNTY SITE  

E-Print Network [OSTI]

the SLAPS and Latty Avenue Vicinity Properties (VPs). Today these sites, including impacted areas along) 260-3905 Or write St. Louis District, Corps of Engineers FUSRAP Project Office 8945 Latty Avenue were purchased, moved, and stored at a property on Latty Avenue, which became known as the Hazelwood

US Army Corps of Engineers

102

Hanford Site climatological data summary 1996, with historical data  

SciTech Connect (OSTI)

This document presents the climatological data measured at the US Department of Energy`s Hanford Site for calendar year 1996. Pacific Northwest National Laboratory operates the Hanford Meteorology Station and the Hanford Meteorological Monitoring Network from which these data were collected. The information includes updated historical climatologies for temperature, precipitation, normal and extreme values of temperature and precipitation, and other miscellaneous meteorological parameters.

Hoitink, D.J.; Burk, K.W.

1997-04-01T23:59:59.000Z

103

Site A/Plot M, Illinois, Decommissioned Reactor Site Fact Sheet  

Office of Legacy Management (LM)

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104

Hanford Site climatological data summary 1997, with historical data  

SciTech Connect (OSTI)

This document presents the climatological data measured at the U.S. Department of Energy`s Hanford Site for calendar year 1997. Pacific Northwest National Laboratory operates the Hanford Meteorology Station and the Hanford Meteorological Monitoring Network from which these data were collected. The information contained herein includes updated historical climatologies for temperature, precipitation, normal and extreme values of temperature and precipitation, and other miscellaneous meteorological parameters. Further, the data are adjunct to and update Hoitink and Burk; however, Appendix B - Wind Climatology is excluded.

Hoitink, D.J.; Burk, K.W.

1998-03-01T23:59:59.000Z

105

Annual Site Environmental Report Summary Pamphlet Sandia National Laboratories,  

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

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106

Summary of the Hanford Site environmental report for calendar year 1996  

SciTech Connect (OSTI)

This report summarizes the 420-page Hanford Site Environmental Report for Calendar Year 1996. The Hanford Site environmental report is prepared annually to summarize environmental data and information, describe environmental management performance, demonstrate the status of compliance with environmental regulations, and highlight major environmental programs and efforts. The summary is designed to briefly: describe the Hanford Site and its mission; summarize the status in 1996 of compliance with environmental regulations; describe environmental programs at the Hanford Site; discuss estimated radionuclide exposure to the public from 1996 Hanford Site activities; present information on effluent monitoring and environmental surveillance, including groundwater protection and monitoring; and discuss activities to ensure quality.

Hanf, R.W.; O`Connor, G.P.; Dirkes, R.L. [eds.] [comps.

1997-08-01T23:59:59.000Z

107

Summary of SMIRT20 Preconference Topical Workshop Identifying Structural Issues in Advanced Reactors  

SciTech Connect (OSTI)

Summary of SMIRT20 Preconference Topical Workshop Identifying Structural Issues in Advanced Reactors William Richins1, Stephen Novascone1, and Cheryl OBrien1 1Idaho National Laboratory, US Dept. of Energy, Idaho Falls, Idaho, USA, e-mail: William.Richins@inl.gov The Idaho National Laboratory (INL, USA) and IASMiRT sponsored an international forum Nov 5-6, 2008 in Porvoo, Finland for nuclear industry, academic, and regulatory representatives to identify structural issues in current and future advanced reactor design, especially for extreme conditions and external threats. The purpose of this Topical Workshop was to articulate research, engineering, and regulatory Code development needs. The topics addressed by the Workshop were selected to address critical industry needs specific to advanced reactor structures that have long lead times and can be the subject of future SMiRT technical sessions. The topics were; 1) structural/materials needs for extreme conditions and external threats in contemporary (Gen. III) and future (Gen. IV and NGNP) advanced reactors and 2) calibrating simulation software and methods that address topic 1 The workshop discussions and research needs identified are presented. The Workshop successfully produced interactive discussion on the two topics resulting in a list of research and technology needs. It is recommended that IASMiRT communicate the results of the discussion to industry and researchers to encourage new ideas and projects. In addition, opportunities exist to retrieve research reports and information that currently exists, and encourage more international cooperation and collaboration. It is recommended that IASMiRT continue with an off-year workshop series on select topics.

William Richins; Stephen Novascone; Cheryl O'Brien

2009-08-01T23:59:59.000Z

108

Reactor operation safety information document  

SciTech Connect (OSTI)

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

Not Available

1990-01-01T23:59:59.000Z

109

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2  

SciTech Connect (OSTI)

This document summarizes information relating to decontamination of the Three Mile Island Unit 2 (TMI-2) reactor building. The report covers activities for the period of June 1, 1979 through March 29, 1985. The data collected from activity reports, reactor containment entry records, and other sources were entered into a computerized data system which permits extraction/manipulation of specific information which can be used in planning for recovery from an accident similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during decontamination of the reactor building. Support activities conducted outside of radiation areas are excluded from the scope of this report. Computerized reports included in this document are: a chronological summary listing work performed relating to reactor building decontamination for the period specified; and summary reports for each major task during the period. Each task summary is listed in chronological order for zone entry and subtotaled for the number of personnel entries, exposures, and man-hours. 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

110

Weldon Spring Site Remedial Action Project quarterly environmental data summary (QEDS) for fourth quarter 1998  

SciTech Connect (OSTI)

This report contains the Quarterly Environmental Data Summary (QEDS) for the fourth quarter of 1998 in support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement. The data, except for air monitoring data and site KPA generated data (uranium analyses) were received from the contract laboratories, verified by the Weldon Spring Site verification group, and merged into the database during the fourth quarter of 1998. KPA results for on-site total uranium analyses performed during fourth quarter 1998 are included. Air monitoring data presented are the most recent complete sets of quarterly data.

NONE

1999-02-01T23:59:59.000Z

111

Hanford Site Environmental Safety and Health Fiscal Year 2001 Budget-Risk management summary  

SciTech Connect (OSTI)

The Hanford Site Environment, Safety and Health (ES&H) Budget-Risk Management Summary report is prepared to support the annual request to sites in the U.S. Department of Energy (DOE) Complex by DOE, Headquarters. The request requires sites to provide supplementary crosscutting information related to ES&H activities and the ES&H resources that support these activities. The report includes the following: (1) A summary status of fiscal year (FY) 1999 ES&H performance and ES&H execution commitments; (2)Status and plans of Hanford Site Office of Environmental Management (EM) cleanup activities; (3) Safety and health (S&H) risk management issues and compliance vulnerabilities of FY 2001 Target Case and Below Target Case funding of EM cleanup activities; (4) S&H resource planning and crosscutting information for FY 1999 to 2001; and (5) Description of indirect-funded S&H activities.

REEP, I.E.

1999-05-12T23:59:59.000Z

112

http://www3.nhk.or.jp/news/2003/12/27/k20031227000018.html 3 national visits related to proposed site for experimental reactor  

E-Print Network [OSTI]

Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor realize the Japanese proposed site for the international thermonuclear fusion experimental reactor (ITER international support for experimental reactor ITER of the fusion centering on proposed site in Aomori

113

Oak Ridge Reservation Annual Site Environmental Report Summary 2002 Taking a Close Look Together  

E-Print Network [OSTI]

1 Oak Ridge Reservation Annual Site Environmental Report Summary 2002 #12;2 Taking a Close Look down our thoughts on what we wanted to tell you about the Oak Ridge Reservation and about working the Oak Ridge Reservation and even thought the Department of Energy produced energy in Oak Ridge

Pennycook, Steve

114

Data Summary Report for teh Remedial Investigation of Hanford Site Releases to the Columbia River, Hanford Site, Washington  

SciTech Connect (OSTI)

This data summary report summarizes the investigation results to evaluate the nature and distribution of Hanford Site-related contaminants present in the Columbia River. As detailed in DOE/RL-2008-11, more than 2,000 environmental samples were collected from the Columbia River between 2008 and 2010. These samples consisted of island soil, sediment, surface water, groundwater upwelling (pore water, surface water, and sediment), and fish tissue.

Hulstrom, L.

2011-02-07T23:59:59.000Z

115

Site Transition Summary: Cleanup Completion to Long-Term Stewardship at Department of Energy On-going Mission Sites  

Office of Environmental Management (EM)

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116

U.N. report concludes that Syrian site destroyed in 2007 was a nuclear reactor  

E-Print Network [OSTI]

U.N. report concludes that Syrian site destroyed in 2007 was a nuclear reactor Joby Warrick, 24 May.N. claims was a nuclear plant before and after a Sept. 6 Israeli airstrike. The left image is from 5 Aug that Syria "very likely" was building a secret nuclear reactor in 2007 when the partially completed project

117

Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment  

Office of Environmental Management (EM)

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118

Post-remedial action report for the Water Boiler Reactor Site  

SciTech Connect (OSTI)

The TA-2 Water Boiler Reactor Decommissioning Project decontaminated and decommissioned the Water Boiler Reactor, TA-2-1-122, at Los Alamos National Laboratory in Los Alamos, New Mexico, to provide reusable space at the TA-2 site and to eliminate the hazard of accidental intrusion into a contaminated structure. This report documents the radiological condition of the site after the decommissioning and decontamination between June 1989 and April 1990. 7 refs., 3 figs., 5 tabs.

Montoya, G.M.

1991-05-01T23:59:59.000Z

119

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

SciTech Connect (OSTI)

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

120

Argonne National Laboratory summary site environmental report for calendar year 2007.  

SciTech Connect (OSTI)

This summary of Argonne National Laboratory's Site Environmental Report for calendar year 2007 was written by 20 students at Downers Grove South High School in Downers Grove, Ill. The student authors are classmates in Mr. Howard's Bio II course. Biology II is a research-based class that teaches students the process of research by showing them how the sciences apply to daily life. For the past seven years, Argonne has worked with Biology II students to create a short document summarizing the Site Environmental Report to provide the public with an easy-to-read summary of the annual 300-page technical report on the results of Argonne's on-site environmental monitoring program. The summary is made available online and given to visitors to Argonne, researchers interested in collaborating with Argonne, future employees, and many others. In addition to providing Argonne and the public with an easily understandable short summary of a large technical document, the participating students learn about professional environmental monitoring procedures, achieve a better understanding of the time and effort put forth into summarizing and publishing research, and gain confidence in their own abilities to express themselves in writing. The Argonne Summary Site Environmental Report fits into the educational needs for 12th grade students. Illinois State Educational Goal 12 states that a student should understand the fundamental concepts, principles, and interconnections of the life, physical, and earth/space sciences. To create this summary booklet, the students had to read and understand the larger technical report, which discusses in-depth many activities and programs that have been established by Argonne to maintain a safe local environment. Creating this Summary Site Environmental Report also helps students fulfill Illinois State Learning Standard 12B5a, which requires that students be able to analyze and explain biodiversity issues, and the causes and effects of extinction. The same standard requires that Illinois students examine the impact of diminishing biodiversity due to human activity. An example of this would be the Argonne Restoration Prairie, which is discussed within the report. Because humans had to destroy part of a natural prairie in order to build, they must also plant an equivalent amount of prairie to make up for what was destroyed. The summary project perfectly meets Illinois State Learning Standard 13B section 5b, which requires students to be able to design and conduct an environmental impact study, analyze findings, and justify recommendations. Students volunteered for the project for two main reasons: We would become published authors, and could include that fact on important documents, like college applications, and we felt we were doing a good deed for the public, considering that without our summary the public may have no real idea how Argonne complies with various environmental protection acts and programs within the state. The summarization process was not easy, considering that we had never seen much of this kind of information before, especially in such detail. The project required a high level of commitment from all involved. This commitment ensured that the summary would be done on time and would be available to the public in the shortest time possible. Argonne representatives Norbert Golchert and Dave Baurac met with students and gave background information on Argonne and explained the importance of the research being done. In addition, they explained in-depth how the public benefits from the summarization. At the end of the presentation, students asked some questions, which were answered in specifics. The Report was divided into 10 sections, with groups of two students covering each section. The groups were eager to begin work on their assigned sections. After reading the complete report each group focused on a particular section. After much careful reading and analysis, we produced an outline. From the outline, partners divided work equally and began to carefully summarize. Groups summaries were edited,

Golchert, N. W.

2009-05-22T23:59:59.000Z

Note: This page contains sample records for the topic "reactor site summary" 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

Interim Safe Storage of Plutonium Production Reactors at the US DOE Hanford Site - 13438  

SciTech Connect (OSTI)

Nine plutonium production reactors located on DOE's Hanford Site are being placed into an Interim Safe Storage (ISS) period that extends to 2068. The Environmental Impact Statement (EIS) for ISS [1] was completed in 1993 and proposed a 75-year storage period that began when the EIS was finalized. Remote electronic monitoring of the temperature and water level alarms inside the safe storage enclosure (SSE) with visual inspection inside the SSE every 5 years are the only planned operational activities during this ISS period. At the end of the ISS period, the reactor cores will be removed intact and buried in a landfill on the Hanford Site. The ISS period allows for radioactive decay of isotopes, primarily Co-60 and Cs-137, to reduce the dose exposure during disposal of the reactor cores. Six of the nine reactors have been placed into ISS by having an SSE constructed around the reactor core. (authors)

Schilperoort, Daryl L.; Faulk, Darrin [Washington Closure Hanford, 2620 Fermi Avenue, Richland, Washington 99352 (United States)] [Washington Closure Hanford, 2620 Fermi Avenue, Richland, Washington 99352 (United States)

2013-07-01T23:59:59.000Z

122

Savannah River Site Removes Dome, Opening Reactor for Recovery Act  

Office of Environmental Management (EM)

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123

Hanford Site C Tank Farm Meeting Summary - May 2009 | Department of Energy  

Office of Environmental Management (EM)

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124

Hanford Site C Tank Farm Meeting Summary - May 2010 | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG | Department ofHTS Cable Projects HTS CableMay 2009 Hanford Site C Tank Farm0

125

Hanford Site C Tank Farm Meeting Summary - May 2011 | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG | Department ofHTS Cable Projects HTS CableMay 2009 Hanford Site C Tank Farm01

126

Hanford Site C Tank Farm Meeting Summary - October 2009 | Department of  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG | Department ofHTS Cable Projects HTS CableMay 2009 Hanford Site C Tank

127

Hanford Site C Tank Farm Meeting Summary - September 2009 | Department of  

Office of Environmental Management (EM)

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128

Hanford Site C Tank Farm Meeting Summary - September 2010 | Department of  

Office of Environmental Management (EM)

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129

Lawrence Livermore National Laboratory Main Site FFA Under CERCLA Section 120, November 1, 1988 Summary  

Office of Environmental Management (EM)

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130

Geologic setting of the New Production Reactor within the Savannah River Site  

SciTech Connect (OSTI)

The geology and hydrology of the reference New Production Reactor (NPR) site at Savannah River Site (SRS) have been summarized using the available information from the NPR site and areas adjacent to the site, particularly the away from reactor spent fuel storage site (AFR site). Lithologic and geophysical logs from wells drilled near the NPR site do not indicate any faults in the upper several hundred feet of the Coastal Plain sediments. However, the Pen Branch Fault is located about 1 mile south of the site and extends into the upper 100 ft of the Coastal Plain sequence. Subsurface voids, resulting from the dissolution of calcareous portions of the sediments, may be present within 200 ft of the surface at the NPR site. The water table is located within 30 to 70 ft of the surface. The NPR site is located on a groundwater divide, and groundwater flow for the shallowest hydraulic zones is predominantly toward local streams. Groundwater flow in deeper Tertiary sediments is north to Upper Three Runs Creek or west to the Savannah River Swamp. Groundwater flow in the Cretaceous sediments is west to the Savannah River.

Price, V. [Westinghouse Savannah River Co., Aiken, SC (United States); Fallaw, W.C. [Furman Univ., Greenville, SC (United States). Dept. of Geology; McKinney, J.B. [Exploration Resources, Inc., Athens, GA (United States)

1991-12-31T23:59:59.000Z

131

E-Print Network 3.0 - aerojet-general nucleonics reactors Sample...  

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

Collection: Chemistry ; Biotechnology 78 Volume 89 number 44 28 october 2008 Summary: antineutrino flux from nuclear reactors,crust,and mantle at project sites. By...

132

E-Print Network 3.0 - auxiliary reactor area-1 Sample Search...  

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

plans eyed for fusion project site Summary: said. The six parties involved in the Thermonuclear Experimental Reactor (ITER) project have been... unable to agree where to locate...

133

Hazelwood Interim Storage Site environmental monitoring summary, Hazelwood, Missouri, calendar year 1984  

SciTech Connect (OSTI)

The Hazelwood Interim Storage Site (HISS) is located at 9200 Latty Avenue, Hazelwood, Missouri. The property on which the HISS is situated is owned by the Jarboe Realty and Investment Company and is leased to Futura Coatings, Inc. Radiological surveys in 1977 and 1982 indicated uranium and thorium contamination and elevated radiation levels in the soil on this property and several others in the immediate vicinity. As part of the research and development program authorized by Congress under the 1984 Energy and Water Appropriations Act, Bechtel National, Inc. (BNI) is conducting remedial action on-site and at the vicinity properties. The work is being performed as part of the US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). Jarboe Realty and Investment Company has agreed to permit DOE to store contaminated material from the FY 1984 and 1985 Latty Avenue cleanup on its property. The contaminated material will be added to the existing pile created during the earlier site cleanup. The pile will then be covered to prevent erosion or migration of contamination. The property will be maintained as the HISS by DOE until final disposition for these materials is determined. BNI is conducting a surveillance monitoring program at the HISS during the interim storage period to detect potential migration of contaminants from the storage pile via air, water, and sediment. This summary provides these monitoring data for calendar year 1984. 6 refs., 4 tabs.

Not Available

1985-07-01T23:59:59.000Z

134

Atoms in Appalachia. Historical report on the Clinch River Breeder Reactor site  

SciTech Connect (OSTI)

The background information concerning the acquisition of the land for siting the Clinch River Breeder Reactor is presented. Historical information is also presented concerning the land acquisition for the Oak Ridge facilities known as the Manhattan Project during World War II.

Schaffer, D

1982-01-01T23:59:59.000Z

135

Weldon Spring Site Remedial Action Project quarterly environmental data summary for second quarter 1998  

SciTech Connect (OSTI)

In support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement, a copy of the Quarterly Environmental Data Summary (QEDS) for the second quarter of 1998 is enclosed. The data presented constitutes the QEDS. The data were received from the contract laboratories, verified by the Weldon Spring Site verification group and, except for air monitoring data and site KPA generated data (uranium analyses), merged into the database during the second quarter of 1998. Air monitoring data presented are the most recent complete sets of quarterly data. Air data are not stored in the database and KPA data are not merged into the regular database. All data received and verified during the second quarter were within a permissible range of variability, except for those listed. Above normal occurrences are cited for groundwater, air, and NPDES data. There were no above normal occurrences for springs or surface water. The attached tables present the most recent data for air and the data merged into the database during the second quarter 1998 for groundwater, NPDES, surface water, and springs.

NONE

1998-08-11T23:59:59.000Z

136

Paducah Gaseous Diffusion Plant Annual Site Environmental Report summary for 1993  

SciTech Connect (OSTI)

This report contains summaries of the environmental programs at Paducah Gaseous Diffusion Plant, environmental monitoring and the results, and the impact of operations on the environment and the public for 1993. The environmental monitoring program at Paducah includes effluent monitoring and environmental surveillance. Effluent monitoring is measurement of releases as they occur. Contaminants are released through either airborne emissions or liquids discharged from the plant. These releases occur as part of normal site operations, such as cooling water discharged from the uranium enrichment cascade operations or airborne releases from ventilation systems. In the event of system failure, this monitoring provides timely warning so that corrective action can be taken before releases reach an unsafe level. Environmental surveillance tracks the dispersion of materials into the environment after they have been released. This involves the collection of samples from various media, such as water, soil, vegetation, and food crops, and the analysis of these samples for certain radionuclides, chemicals, and metals.

Not Available

1994-11-01T23:59:59.000Z

137

Portsmouth Gaseous Diffusion Plant Annual Site Environmental Report summary for 1993  

SciTech Connect (OSTI)

This report contains summaries of the environmental programs at Paducah Gaseous Diffusion Plant, environmental monitoring and the results, and the impact of operations on the environment and the public for 1993. The environmental monitoring program at Paducah includes effluent monitoring and environmental surveillance. Effluent monitoring is measurement of releases as they occur. Contaminants are released through either airborne emissions or liquids discharged from the plant. These releases occur as part of normal site operations, such as cooling water discharged from the uranium enrichment cascade operations or airborne releases from ventilation systems. In the event of system failure, this monitoring provides timely warning so that corrective action can be taken before releases reach an unsafe level. Environmental surveillance tracks the dispersion of materials into the environment after they have been released. This involves the collection of samples from various media, such as water, soil, vegetation, and food crops, and the analysis of these samples for certain radionuclides, chemicals, and metals.

Not Available

1994-11-01T23:59:59.000Z

138

FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative  

SciTech Connect (OSTI)

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative.

Greene, S.R.; Fisher, S.E.; Bevard, B.B. [and others

1996-09-01T23:59:59.000Z

139

Summary report on reprocessing evaluation of selected inactive uranium mill tailings sites  

SciTech Connect (OSTI)

Sandia National Laboratories has been assisting the Department of Energy in the Uranium Mill Tailings Remedial Actions Program (UMTRAP) the purpose of which is to implement the provisions of Title I of Public Law 95-604, Uranium Mill Tailings Radiation Control Act of 1978.'' As part of this program, there was a need to evaluate the mineral concentration of the residual radioactive materials at some of the designated processing sites to determine whether mineral recovery would be practicable. Accordingly, Sandia contracted Mountain States Research and Development (MSRD), a division of Mountain States Mineral Enterprises, to drill, sample, and test tailings at 12 sites to evaluate the cost of and the revenue that could be derived from mineral recovery. UMTRAP related environmental and engineering sampling and support activities were performed in conjunction with the MSRD operations. This summary report presents a brief description of the various activities in the program and of the data and information obtained and summarizes the results. 8 refs., 9 tabs.

Not Available

1983-09-01T23:59:59.000Z

140

Fuel Summary for Peach Bottom Unit 1 High-Temperature Gas-Cooled Reactor Cores 1 and 2  

SciTech Connect (OSTI)

This fuel summary report contains background and summary information for the Peach Bottom Unit 1, High-Temperature, Gas-Cooled Reactor Cores 1 and 2. This report contains detailed information about the fuel in the two cores, the Peach Bottom Unit 1 operating history, nuclear parameters, physical and chemical characteristics, and shipping and storage canister related data. The data in this document have been compiled from a large number of sources and are not qualified beyond the qualification of the source documents. This report is intended to provide an overview of the existing data pertaining to spent fuel management and point to pertinent reference source documents. For design applications, the original source documentation must be used. While all referenced sources are available as records or controlled documents at the Idaho National Engineering and Environmental Laboratory (INEEL), some of the sources were marked as informal or draft reports. This is noted where applicable. In some instances, source documents are not consistent. Where they are known, this document identifies those instances and provides clarification where possible. However, as stated above, this document has not been independently qualified and such clarifications are only included for information purposes. Some of the information in this summary is available in multiple source documents. An effort has been made to clearly identify at least one record document as the source for the information included in this report.

Karel I. Kingrey

2003-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor site summary" 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

DOE - Office of Legacy Management -- Reactor Site - Fort Belvoir - VA 0-02  

Office of Legacy Management (LM)

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142

Meeting Summary Advanced Light Water Reactor Fuels Industry Meeting Washington DC October 27 - 28, 2011  

SciTech Connect (OSTI)

The Advanced LWR Fuel Working Group first met in November of 2010 with the objective of looking 20 years ahead to the role that advanced fuels could play in improving light water reactor technology, such as waste reduction and economics. When the group met again in March 2011, the Fukushima incident was still unfolding. After the March meeting, the focus of the program changed to determining what we could do in the near term to improve fuel accident tolerance. Any discussion of fuels with enhanced accident tolerance will likely need to consider an advanced light water reactor with enhanced accident tolerance, along with the fuel. The Advanced LWR Fuel Working Group met in Washington D.C. on October 72-18, 2011 to continue discussions on this important topic.

Not Listed

2011-11-01T23:59:59.000Z

143

2014 Annual Planning Summary for the NNSA Naval Reactors | Department of  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement3 Beryllium-Associated Worker RegistryDepartment ofEnergy Naval Reactors 2014

144

In Summary: Idaho National Engineering and Environmental Laboratory Site Environmental Report for Calendar Year 1998  

SciTech Connect (OSTI)

Scientists from the Environmental Science and Research Foundation, Lockheed Martin Idaho Technologies Company (LMITCO), the US Geological Survey, the Naval Nuclear Propulsion Program Naval Reactors Facility, Argonne National Laboratory-West, and others monitored the environment on and around the INEEL to find contaminants attributable to the INEEL. During 1998, exposures from the INEEL to the public were found to be negligible. The US Department of Energy (DOE) and LMITCO made progress in developing and implementing a site-wide Environmental Management System. This system provides an underlying structure to make the management of environmental activities at the INEEL more systematic and predictable. Pathways by which INEEL contaminants might reach people off the INEEL were monitored. These included air, precipitation, water, locally grown food (milk, lettuce, wheat, and potatoes), livestock, game animals, soil, and direct ionizing radiation. Results from samples collected to monitor these pathways often contain ''background radioactivity,'' which is radioactivity from natural sources and nuclear weapons tests carried out between 1945 and 1980. According to results obtained in 1998, radioactivity from operations at the INEEL could not be distinguished from this background radioactivity in the regions surrounding the INEEL. Because radioactivity from the INEEL was not detected by offsite environmental surveillance methods, computer models were used to estimate the radiation dose to the public. The hypothetical maximum dose to an individual from INEEL operations was calculated to be 0.08 millirem. That is 0.002 percent of an average person's annual dose of 360 millirem from natural background radiation in southeast Idaho.

A. A. Luft; R. B. Evans; T. Saffle; R. G. Mitchell; D. B. Martin

2000-06-01T23:59:59.000Z

145

CERCA LEU fuel assemblies testing in Maria Reactor - safety analysis summary and testing program scope.  

SciTech Connect (OSTI)

The presented paper contains neutronic and thermal-hydraulic (for steady and unsteady states) calculation results prepared to support annex to Safety Analysis Report for MARIA reactor in order to obtain approval for program of testing low-enriched uranium (LEU) lead test fuel assemblies (LTFA) manufactured by CERCA. This includes presentation of the limits and operational constraints to be in effect during the fuel testing investigations. Also, the scope of testing program (which began in August 2009), including additional measurements and monitoring procedures, is described.

Pytel, K.; Mieleszczenko, W.; Lechniak, J.; Moldysz, A.; Andrzejewski, K.; Kulikowska, T.; Marcinkowska, A.; Garner, P. L.; Hanan, N. A.; Nuclear Engineering Division; Institute of Atomic Energy (Poland)

2010-03-01T23:59:59.000Z

146

Lessons learned from applying VIM to fast reactor critical experiments, summary  

SciTech Connect (OSTI)

VIM is a continuous energy Monte Carlo code first developed around 1970 for the analysis of plate-type, fast-neutron, zero-power critical assemblies. In most respects, VIM is functionally equivalent to the MCNP code but it has two features that make uniquely suited to the analysis of fast reactor critical experiments: (1) the place lattice geometry option, which allows efficient description of and neutron tracking in the assembly geometry, and (2) a statistical treatment of neutron cross section data in the unresolved resonance range. Since its inception, VIM`s capabilities have expanded to include numerous features, such as thermal neutron cross sections, photon cross sections, and combinatorial and other geometry options, that have allowed its use in a wide range of neutral-particle transport problems. The earliest validation work at Argonne National Laboratory (ANL) focused on the validation of VIM itself. This work showed that, in order for VIM to be a ``rigomus`` tool, extreme detail in the pointwise Monte Carlo libraries was needed, and the required detail was added. The emphasis soon shifted to validating models, methods, data and codes against VIM. Most of this work was done in the context of analyzing critical experiments in zero power reactor (ZPR) assemblies. The purpose of this paper is to present some of the lessons learned from using VIM in ZPR analysis work.

Schaefer, R.W.; McKnight, R.D.; Collins, P.J.

1995-05-17T23:59:59.000Z

147

Process Knowledge Summary Report for Advanced Test Reactor Complex Contact-Handled Transuranic Waste Drum TRA010029  

SciTech Connect (OSTI)

This Process Knowledge Summary Report summarizes information collected to satisfy the transportation and waste acceptance requirements for the transfer of one drum containing contact-handled transuranic (TRU) actinide standards generated by the Idaho National Laboratory at the Advanced Test Reactor (ATR) Complex to the Advanced Mixed Waste Treatment Project (AMWTP) for storage and subsequent shipment to the Waste Isolation Pilot Plant for final disposal. The drum (i.e., Integrated Waste Tracking System Bar Code Number TRA010029) is currently stored at the Materials and Fuels Complex. The information collected includes documentation that addresses the requirements for AMWTP and applicable sections of their Resource Conservation and Recovery Act permits for receipt and disposal of this TRU waste generated from ATR. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for this TRU waste originating from ATR.

B. R. Adams; R. P. Grant; P. R. Smith; J. L. Weisgerber

2013-09-01T23:59:59.000Z

148

SAVANNAH RIVER SITE R-REACTOR DISASSEMBLY BASIN IN-SITU DECOMMISSIONING -10499  

SciTech Connect (OSTI)

The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate intact, structurally sound facilities that are no longer needed for their original purpose, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the 105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate it from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,384 cubic meters or 31,894 cubic yards. Portland cement-based structural fill materials were designed and tested for the reactor ISD project, and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and material flow considerations, maximum lift heights and differential height requirements were determined. Pertinent data and information related to the SRS 105-R Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs and testing, and fill placement strategy. This information is applicable to decommissioning both the 105-P and 105-R facilities. The ISD process for the entire 105-P and 105-R reactor facilities will require approximately 250,000 cubic yards (191,140 cubic meters) of grout and approximately 3,900 cubic yards (2,989 cubic meters) of structural concrete which will be placed over about an eighteen month period to meet the accelerated schedule ISD schedule. The status and lessons learned in the SRS Reactor Facility ISD process will be described.

Langton, C.; Serrato, M.; Blankenship, J.; Griffin, W.

2010-01-04T23:59:59.000Z

149

Summary report for 1990 inservice inspection (ISI) of SRS 100-L reactor tank  

SciTech Connect (OSTI)

The integrity of the SRS reactor tanks is a key factor affecting their suitability for continued service since, unlike the external piping system and components, the tanks are virtually irreplaceable. Cracking in various areas of the process water piping systems has occurred beginning in about 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. The primary objective of this inspection was to determine if the accessible welds and selected portions of base metal in the L Reactor tank wall contain any indications of IGSCC. This inspection included areas in and beyond the weld HAZ, extending out as far as two to three inches from the centerline of the welds, plus selected areas of base metal at the intersection of the main tank vertical and mid-girth welds. No evidence of such degradation was found in any of the areas examined. Further, additional inspections were conducted of areas that had been damaged and repaired during original fabrication, and on a sample of areas containing linear indications observed during the 1986 visual inspection of the tank. No evidence of IGSCC or other service induced degradation was detected in these areas, either. The inspection was initially planned to cover a minimum of 60% of the accessible welds, plus repair areas and a sample of the indications from the 1986 visual inspection. Direction was received from DOE while the inspection was in progress to expand the scope to cover 100% of the accessible weld areas, and the plan was adjusted accordingly. Initial setup of the tank, which prior to inspection contained Mark 60B target assemblies and nearly a full charge of Mark 22 fuel assemblies, began on October 15, 1990. The inspection was completed on April 12, 1991.

Morrison, J.M.; Loibl, M.W.

1991-07-12T23:59:59.000Z

150

Response of structures to energetic events for the Savannah River Site production reactors probabilistic risk assessment  

SciTech Connect (OSTI)

The response of structures to energetic events postulated to arise in a probabilistic risk assessment (PRA) of a Savannah River Site (SRS) production reactor is addressed. Energetic events that arise in PRAs can damage structures and therefore have a significant influence on subsequent accident progression. Consequently, the structural response is important to the calculated risk of operating a plant. Difficulties are encountered, however, in the analysis of structural response of components to energetic loadings. First, the analysis of energetic events often does not provide well-defined static or dynamic loads acting on the structures. Secondly, risk assessments, by their nature, address a wide range of events that are not necessarily precisely defined. This paper describes an approach taken to develop the structural analysis required to support the PRA of the SRS production reactor, that overcomes these difficulties.

Santa Cruz, S.M.; Smith, D.C. (Science Applications International Corp., Albuquerque, NM (United States)); Yau, W.F. (Westinghouse Savannah River Co., Aiken, SC (United States))

1992-01-01T23:59:59.000Z

151

Response of structures to energetic events for the Savannah River Site production reactors probabilistic risk assessment  

SciTech Connect (OSTI)

The response of structures to energetic events postulated to arise in a probabilistic risk assessment (PRA) of a Savannah River Site (SRS) production reactor is addressed. Energetic events that arise in PRAs can damage structures and therefore have a significant influence on subsequent accident progression. Consequently, the structural response is important to the calculated risk of operating a plant. Difficulties are encountered, however, in the analysis of structural response of components to energetic loadings. First, the analysis of energetic events often does not provide well-defined static or dynamic loads acting on the structures. Secondly, risk assessments, by their nature, address a wide range of events that are not necessarily precisely defined. This paper describes an approach taken to develop the structural analysis required to support the PRA of the SRS production reactor, that overcomes these difficulties.

Santa Cruz, S.M.; Smith, D.C. [Science Applications International Corp., Albuquerque, NM (United States); Yau, W.F. [Westinghouse Savannah River Co., Aiken, SC (United States)

1992-10-01T23:59:59.000Z

152

ELECTRICAL RESISTANCE HEATING OF SOILS AT C-REACTOR AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

Chlorinated solvent contamination of soils and groundwater is an endemic problem at the Savannah River Site (SRS), and originated as by-products from the nuclear materials manufacturing process. Five nuclear reactors at the SRS produced special nuclear materials for the nation's defense program throughout the cold war era. An important step in the process was thorough degreasing of the fuel and target assemblies prior to irradiation. Discharges from this degreasing process resulted in significant groundwater contamination that would continue well into the future unless a soil remediation action was performed. The largest reactor contamination plume originated from C-Reactor and an interim action was selected in 2004 to remove the residual trichloroethylene (TCE) source material by electrical resistance heating (ERH) technology. This would be followed by monitoring to determine the rate of decrease in concentration in the contaminant plume. Because of the existence of numerous chlorinated solvent sources around SRS, it was elected to generate in-house expertise in the design and operation of ERH, together with the construction of a portable ERH/SVE system that could be deployed at multiple locations around the site. This paper describes the waste unit characteristics, the ERH system design and operation, together with extensive data accumulated from the first deployment adjacent to the C-Reactor building. The installation heated the vadose zone down to 62 feet bgs over a 60 day period during the summer of 2006 and raised soil temperatures to over 200 F. A total of 730 lbs of trichloroethylene (TCE) were removed over this period, and subsequent sampling indicated a removal efficiency of 99.4%.

Blundy, R; Michael Morgenstern, M; Joseph Amari, J; Annamarie MacMurray, A; Mark Farrar, M; Terry Killeen, T

2007-09-10T23:59:59.000Z

153

Remaining Sites Verification Package for 132-H-1, 116-H Reactor Stack Burial Site, Waste Site Reclassification Form 2006-053  

SciTech Connect (OSTI)

The 132-H-1 waste site includes the 116-H exhaust stack burial trench and the buried stack foundation (which contains an embedded vertical 15-cm (6-in) condensate drain line). The 116-H reactor exhaust stack and foundation were decommissioned and demolished using explosives in 1983, with the rubble buried in situ beneath clean fill at least 1 m (3.3 ft) thick. Residual concentrations support future land uses that can be represented by a rural-residential scenario and pose no threat to groundwater or the Columbia River based on RESRAD modeling.

L. M. Dittmer

2007-06-26T23:59:59.000Z

154

Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics Executive Summary  

SciTech Connect (OSTI)

Research and development (R&D) activities on advanced, higher performance Light Water Reactor (LWR) fuels have been ongoing for the last few years. Following the unfortunate March 2011 events at the Fukushima Nuclear Power Plant in Japan, the R&D shifted toward enhancing the accident tolerance of LWRs. Qualitative attributes for fuels with enhanced accident tolerance, such as improved reaction kinetics with steam resulting in slower hydrogen generation rate, provide guidance for the design and development of fuels and cladding with enhanced accident tolerance. A common set of technical metrics should be established to aid in the optimization and down selection of candidate designs on a more quantitative basis. Metrics describe a set of technical bases by which multiple concepts can be fairly evaluated against a common baseline and against one another. This report describes a proposed technical evaluation methodology that can be applied to evaluate the ability of each concept to meet performance and safety goals relative to the current UO2 zirconium alloy system and relative to one another. The resultant ranked evaluation can then inform concept down-selection, such that the most promising accident tolerant fuel design option(s) can continue to be developed toward qualification.

Shannon Bragg-Sitton

2014-02-01T23:59:59.000Z

155

Drart environmental impact statement siting, construction, and operation of New Production Reactor capacity. Volume 4, Appendices D-R  

SciTech Connect (OSTI)

This Environmental Impact Statement (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site near Aiken, South Carolina. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains 15 appendices.

Not Available

1991-04-01T23:59:59.000Z

156

Process Modeling Phase I Summary Report for the Advanced Gas Reactor Fuel Development and Qualification Program  

SciTech Connect (OSTI)

This report summarizes the results of preliminary work at Oak Ridge National Laboratory (ORNL) to demonstrate application of computational fluid dynamics modeling to the scale-up of a Fluidized Bed Chemical Vapor Deposition (FBCVD) process for nuclear fuels coating. Specifically, this work, referred to as Modeling Scale-Up Phase I, was conducted between January 1, 2006 and March 31, 2006 in support of the Advanced Gas Reactor (AGR) Program. The objective was to develop, demonstrate and "freeze" a version of ORNL's computational model of the TRI ISOtropic (TRISO) fuel-particle coating process that can be specifically used to assist coater scale-up activities as part of the production of AGR-2 fuel. The results in this report are intended to serve as input for making decisions about initiating additional FBCVD modeling work (referred to as Modeling Scale-Up Phase II) in support of AGR-2. The main computational tool used to implement the model is the general-purpose multiphase fluid-dynamics computer code known as MFIX (Multiphase Flow with Interphase eXchanges), which is documented in detail on the DOE-sponsored website http://www.mfix.org. Additional computational tools are also being developed by ORNL for post-processing MFIX output to efficiently summarize the important information generated by the coater simulations. The summarized information includes quantitative spatial and temporal measures (referred to as discriminating characteristics, or DCs) by which different coater designs and operating conditions can be compared and correlated with trends in product quality. The ORNL FBCVD modeling work is being conducted in conjunction with experimental coater studies at ORNL with natural uranium CO (NUCO) and surrogate fuel kernels. Data are also being obtained from ambient-temperature, spouted-bed characterization experiments at the University of Tennessee and theoretical studies of carbon and silicon carbide chemical vapor deposition kinetics at Iowa State University. Prior to the current scale-up activity, considerable effort has gone in to adapting the MFIX code to incorporate the unique features of fuel coating reactors and also in validating the resulting simulation features with experimental observations. Much of this work is documented in previous AGR reports and publications (Pannala et al., 2004, Pannala et al., 2005, Boyalakuntla et al., 2005a, Boyalakuntla et al., 2005b and Finney et al., 2005). As a result of the previous work described above, the ORNL coater model now has the capability for simulating full spatio-temporal details of the gas-particle hydrodynamics and gas-particle heat and mass transfer in the TRISO coater. This capability provides a great deal of information about many of the processes believed to control quality, but the model is not yet sufficiently developed to fully predict coating quality for any given coater design and/or set of operating conditions because the detailed chemical reaction kinetics needed to make the model fully predictive are not yet available. Nevertheless, the model at its current stage of development already provides the most comprehensive and detailed quantitative information available about gas flows, solid flows, temperatures, and species inside the coater during operation. This level of information ought to be highly useful in expediting the scale-up process (e.g., in correlating observations and minimizing the number of pilot-scale tests required). However, previous work had not yet demonstrated that the typical design and/or operating changes known to affect product quality at the lab scale could be clearly discriminated by the existing model. The Modeling Scale-Up Phase I work was initiated to produce such a demonstration, and two detailed examples are discussed in this report.

Pannala, Sreekanth [ORNL; Daw, C Stuart [ORNL; Boyalakuntla, Dhanunjay S [ORNL; FINNEY, Charles E A [ORNL

2006-09-01T23:59:59.000Z

157

2010 Annual Summary Report for the Area 3 and Area 5 Radioactive Management Sites at the Nevada National Security Site, Nye County, Nevada  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 Radioactive Waste Management Site (RWMS) Performance Assessments (PAs) and Composite Analyses (CAs) in fiscal year (FY) 2010. This annual summary report presents data and conclusions from the FY 2010 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

NSTec Environmental Management

2011-03-01T23:59:59.000Z

158

Multi-Site Capacity, Production and Distribution Planning with Reactor Modifications: MILP Model, Bi-level Decomposition  

E-Print Network [OSTI]

-site production facilities to meet the demands of multiple geographically distributed markets. Potential capacityMulti-Site Capacity, Production and Distribution Planning with Reactor Modifications: MILP Model mixed-integer linear programming (MILP) model for the simultaneous capacity, production and distribution

Grossmann, Ignacio E.

159

Field Summary Report for Remedial Investigation of Hanford Site Releases to the Coumbia River, Hanford Site, Washington  

SciTech Connect (OSTI)

This report summarizes field sampling activities conducted in support of WCHs Remedial Investigation of Hanford Site Releases to the Columbia River. This work was conducted form 2008 through 2010. The work included preliminary mapping and measurement of Hanford Site contaminants in sediment, pore water, and surface water located in areas where groundwater upwelling were found.

L.C. Hulstrom

2010-11-10T23:59:59.000Z

160

Field Summary Report for Remedial Investigation of Hanford Site Releases to the Columbia River, Hanford Site, Washington  

SciTech Connect (OSTI)

This report summarizes field sampling activities conducted in support of WCHs Remedial Investigation of Hanford Site Releases to the Columbia River. This work was conducted form 2008 through 2010. The work included preliminary mapping and measurement of Hanford Site contaminants in sediment, pore water, and surface water located in areas where groundwater upwelling were found.

L.C. Hulstrom

2010-08-11T23:59:59.000Z

Note: This page contains sample records for the topic "reactor site summary" 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

2007 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada  

SciTech Connect (OSTI)

This report summarizes the results of an annual review of conditions affecting the operation of the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) and a determination of the continuing adequacy of the performance assessments (PAs) and composite analyses (CAs). The Area 5 RWMS PA documentation consists of the original PA (Shott et al., 1998), referred to as the 1998 Area 5 RWMS PA and supporting addenda (Bechtel Nevada [BN], 2001b; 2006a). The Area 5 RWMS CA was issued as a single document (BN, 2001a) and has a single addendum (BN, 2001c). The Area 3 PA and CA were issued in a single document (Shott et al., 2000). The Maintenance Plan for the PAs and CAs (National Security Technologies, LLC [NSTec], 2006) and the Disposal Authorization Statements (DASs) for the Area 3 and 5 RWMSs (U.S. Department of Energy [DOE], 2000; 2002) require preparation of an annual summary and a determination of the continuing adequacy of the PAs and CAs. The annual summary report is submitted to DOE Headquarters. Following the annual report format in the DOE PA/CA Maintenance Guide (DOE, 1999), this report presents the annual summary for the PAs in Section 2.0 and the CAs in Section 3.0. The annual summary for the PAs includes the following: Section 2.1 summarizes changes in waste disposal operations; Section 2.1.5 provides an evaluation of the new estimates of the closure inventories derived from the actual disposals through fiscal year (FY) 2007; Section 2.2 summarizes the results of the monitoring conducted under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's (NNSA/NSO's) Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (BN, 2005), and the research and development (R&D) activities; Section 2.4 is a summary of changes in facility design, operation, or expected future conditions; monitoring and R&D activities; and the maintenance program; and Section 2.5 discusses the recommended changes in disposal facility design and operations, monitoring and R&D activities, and the maintenance program. Similarly, the annual summary for the CAs (presented in Section 3.0) includes the following: Section 3.1 presents the assessment of the adequacy of the CAs, with a summary of the relevant factors reviewed in FY 2007; Section 3.2 presents an assessment of the relevant site activities at the Nevada Test Site (NTS) that would impact the sources of residual radioactive material considered in the CAs; Section 3.3 summarizes the monitoring and R&D results that were reviewed in FY 2007; Section 3.4 presents a summary of changes in relevant site programs (including monitoring, R&D, and the maintenance program) that occurred since the CAs were prepared; and Section 3.5 summarizes the recommended changes to these programs.

NSTec Environmental Management

2008-01-01T23:59:59.000Z

162

Optimization of a Small Modular Lead Fast Reactor with Steam Cycle for Remote Siting  

SciTech Connect (OSTI)

Parametric thermal-hydraulic studies needed to develop and optimize the design of a small modular 25 MWt lead-bismuth reactor plant have been performed. The starting point was the design of a liquid metal version of the secure transportable autonomous reactor (STAR-LM) plant of 300 to 400 MWt with a steam power cycle.1 The primary flow is driven entirely by natural convection. The new plant is to be extremely small so that its main components can be transported to the reactor site by truck. The analytical model includes the two major components of the primary loop, the reactor and a once-through steam generator, which is a shell-and-tube heat exchanger with straight vertical tubes. The modeling includes the changes between the beginning and the end of plant life due to the gradual buildup of a layer of magnetite on the surfaces of the fuel pins and on the outer surfaces of the steam generator tubes. Three reactor parametric studies were performed-one for each of three sets of reactor geometric parameters. In each study the pin-bundle pressure drop, the vertical height of the primary loop, the hydraulic diameter of the core, the number of fuel pins, and peak fuel and cladding temperatures were determined for a range of values of fuel pin linear power. Four steam generator parametric studies were performed. The first three have fixed tube inner diameters of 0.5, 1.0, and 1.5 cm, respectively. In the fourth study the tube inner diameter was allowed to vary and the margin to critical heat flux, CHF, was maintained at 20%. In the steam generator studies the independent parameters include tube length and tube-bundle pitch-to-diameter ratio and the dependent variables include steam generator cross-sectional area, the number of tubes, the vertical height of the primary loop, and the steam generator pressure drop. The results show that an acceptable optimum thermal-hydraulic design for a 25 MWt STAR-LM is feasible. (authors)

Feldman, Earl E.; Wei, Thomas Y. C.; Sienicki, James J. [Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, Illinois 60439 (United States)

2004-07-01T23:59:59.000Z

163

DOE - Office of Legacy Management -- West Milton Reactor Site - NY 21  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou areDowntown Site -Miami -New JerseyLake Landfill

164

Candidate wind turbine generator site: annual data summary, January 1981-December 1981  

SciTech Connect (OSTI)

Summarized hourly meteorological data for 34 candidate and wind turbine generator sites for calendar year 1981 are presented. These data are collected for the purpose of evaluating the wind energy potential at these sites and are used to assist in selection of potential sites for installation and testing of large wind turbines in electric utility systems. For each site, wind speed, direction, and distribution data are given in eight tables. Use of information from these tables, with information about specific wind turbines, should allow the user to estimate the potential for wind energy production at each site.

Sandusky, W.F.; Buck, J.W.; Renne, D.S.; Hadley, D.L.; Abbey, O.B.

1982-07-01T23:59:59.000Z

165

Summary - Proposed On-Site Disposal Facility (OSDF) at the Paducah...  

Office of Environmental Management (EM)

site considerations such as seismic and brown versus green field, (3) the public communication plan, (4) future public use options, and (5) the baseline schedule. What the ETR...

166

Summary of the Hanford Site environmental report for calendar year 1994  

SciTech Connect (OSTI)

This report summarizes the 390-page Hanford Site Environmental Report for Calendar Year 1994. The Hanford Site Environmental Report is prepared annually to review and document environmental data and information, describe environmental management performance, and demonstrate the status of compliance with environmental regulations. The report also highlights major environmental programs and efforts and is written to meet both the reporting requirements and guidelines of the US Department of energy (DOE) and the needs of the public. This report includes information on important Hanford Site compliance issues, environmental monitoring programs and results, and general information on the Site and the surrounding area.

Hanf, R.W.; Schrempf, R.E.; Dirkes, R.L. [eds.] [comps.

1996-01-01T23:59:59.000Z

167

2011 Annual Planning Summary for Stanford Linear Accelerator Center Site Office (SLAC)  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Stanford Linear Accelerator Center Site Office (SLAC SO) (See also Science).

168

Economic impacts on the United States of siting decisions for the international thermonuclear experimental reactor  

SciTech Connect (OSTI)

This report presents the results of a study that examines and compares the probable short-term economic impacts of the International Thermonuclear Experimental Reactor (ITER) on the United States (U.S.) if (1) ITER were to be sited in the U.S., or (2) ITER were to be sited in one of the other countries that, along with the U.S., is currently participating in the ITER program. Life-cycle costs associated with ITER construction, operation, and decommissioning are analyzed to assess their economic impact. A number of possible U.S. host and U.S. non-host technology and cost-sharing arrangements with the other ITER Parties are examined, although cost-sharing arrangements and the process by which the Parties will select a host country and an ITER site remain open issues. Both national and local/regional economic impacts, as measured by gross domestic product, regional output, employment, net exports, and income, are considered. These impacts represent a portion of the complex, interrelated set of economic considerations that characterize U.S. host and U.S. non-host participation in ITER. A number of other potentially important economic and noneconomic considerations are discussed qualitatively.

Peerenboom, J.P.; Hanson, M.E.; Huddleston, J.R. [and others

1996-08-01T23:59:59.000Z

169

On-Site Oxy-Lance Size Reduction of South Texas Project Reactor Vessel Heads - 12324  

SciTech Connect (OSTI)

On-Site Oxy-Lance size reduction of mildly radioactive large components has been accomplished at other operating plants. On-Site Oxy-Lance size reduction of more radioactive components like Reactor Vessel Heads had previously been limited to decommissioning projects. Building on past decommissioning and site experience, subcontractors for South Texas Project Nuclear Operating Company (STPNOC) developed an innovative integrated system to control smoke, radioactive contamination, worker dose, and worker safety. STP's innovative, easy to use CEDM containment that provided oxy lance access, smoke control, and spatter/contamination control was the key to successful segmentation for cost-effective and ALARA packaging and transport for disposal. Relative to CEDM milling, STP oxy-lance segmentation saved approximately 40 person- REM accrued during 9,000 hours logged into the radiological controlled area (RCA) during more than 3,800 separate entries. Furthermore there were no personnel contamination events or respiratory uptakes of radioactive material during the course of the entire project. (authors)

Posivak, Edward [WMG, inc. (United States); Keeney, Gilbert; Wheeler, Dean [Shaw Group (United States)

2012-07-01T23:59:59.000Z

170

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor coolant system and systems decontamination. Summary status report. Volume 1  

SciTech Connect (OSTI)

This document summarizes information relating to the decontamination and restoration of the Three Mile Island Unit 2 reactor coolant system and other plant systems. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data system 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 by the Three Mile Island Unit 2 on March 28, 1979. This report contains a summary of radiation exposures, manpower, and time spent in radiation areas during the referenced period. Support activities conducted outside of radiation areas are not included. Computer reports included are: A chronological listing of all activities related to decomtamination and restoration of the reactor coolant system and other plant systems for the period of April 5, 1979, through December 19, 1984; a summary of labor and exposures by department for the same time period; and summary reports for each major task undertaken in connection with this specific work scope during the referenced time period.

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

1986-05-01T23:59:59.000Z

171

2004 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada  

SciTech Connect (OSTI)

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (Bechtel Nevada, 2000) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs) for each of the facilities, and reports the results in an annual summary report to the U.S. Department of Energy Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (U.S. Department of Energy [DOE]). The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office performed annual reviews in fiscal year (FY) 2004 by evaluating operational factors and research results that impact the continuing validity of the PA and CA results. This annual summary report presents data and conclusions from the FY 2004 review, and determines the adequacy of the PAs and CAs. Operational factors, such as the waste form and containers, facility design, waste receipts, closure plans, as well as monitoring results and research and development (R&D) activities were reviewed in FY 2004 for the determination of the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed for the determination of the adequacy of the CAs.

Vefa Yucel

2005-01-01T23:59:59.000Z

172

Summary of some feasibility studies for site-specific solar industrial process heat  

SciTech Connect (OSTI)

Some feasibility studies for several different site specific solar industrial process heat applications are summarized. The followng applications are examined. Leather Tanning; Concrete Production: Lumber and Paper Processing; Milk Processing; Molding, Curing or Drying; Automobile Manufacture; and Food Processing and Preparation. For each application, site and process data, system design, and performance and cost estimates are summarized.

none,

1982-01-01T23:59:59.000Z

173

The National Criticality Experiments Research Center at the Device Assembly Facility, Nevada National Security Site: Status and Capabilities, Summary Report  

SciTech Connect (OSTI)

The National Criticality Experiments Research Center (NCERC) was officially opened on August 29, 2011. Located within the Device Assembly Facility (DAF) at the Nevada National Security Site (NNSS), the NCERC has become a consolidation facility within the United States for critical configuration testing, particularly those involving highly enriched uranium (HEU). The DAF is a Department of Energy (DOE) owned facility that is operated by the National Nuclear Security Agency/Nevada Site Office (NNSA/NSO). User laboratories include the Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL). Personnel bring their home lab qualifications and procedures with them to the DAF, such that non-site specific training need not be repeated to conduct work at DAF. The NNSS Management and Operating contractor is National Security Technologies, LLC (NSTec) and the NNSS Safeguards and Security contractor is Wackenhut Services. The complete report provides an overview and status of the available laboratories and test bays at NCERC, available test materials and test support configurations, and test requirements and limitations for performing sub-critical and critical tests. The current summary provides a brief summary of the facility status and the method by which experiments may be introduced to NCERC.

S. Bragg-Sitton; J. Bess; J. Werner

2011-09-01T23:59:59.000Z

174

Meeting Summaries for Development of the Hanford Site C Tank Farm  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecemberInitiatives InitiativesShipping Goal || Department

175

Decommissioning an Active Historical Reactor Facility at the Savannah River Site - 13453  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is an 802 square-kilometer United States Department of Energy (US DOE) nuclear facility located along the Savannah River near Aiken, South Carolina, where Management and Operations are performed by Savannah River Nuclear Solutions (SRNS). In 2004, DOE recognized SRS as structure within the Cold War Historic District of national, state and local significance composed of the first generation of facilities constructed and operated from 1950 through 1989 to produce plutonium and tritium for our nation's defense. DOE agreed to manage the SRS 105-C Reactor Facility as a potentially historic property due to its significance in supporting the U.S. Cold War Mission and for potential for future interpretation. This reactor has five primary areas within it, including a Disassembly Basin (DB) that received irradiated materials from the reactor, cooled them and prepared the components for loading and transport to a Separation Canyon for processing. The 6,317 square meter area was divided into numerous work/storage areas. The walls between the individual basin compartments have narrow vertical openings called 'slots' that permit the transfer of material from one section to another. Data indicated there was over 830 curies of radioactivity associated with the basin sediments and approximately 9.1 M liters of contaminated water, not including a large quantity of activated reactor equipment, scrap metal, and debris on the basin floor. The need for an action was identified in 2010 to reduce risks to personnel in the facility and to eliminate the possible release of contaminants into the environment. The release of DB water could potentially migrate to the aquifer and contaminate groundwater. DOE, its regulators [U. S. Environmental Protection Agency (USEPA)-Region 4 and the South Carolina Department of Health and Environmental Control (SCDHEC)] and the SC Historical Preservation Office (SHPO) agreed/concurred to perform a non-time critical removal action for the In Situ Decommissioning (ISD) of the 105-C Disassembly Basin. ISD consisted of stabilization/isolation of remaining contaminated water, sediment, activated reactor equipment, and scrap metal by filling the DB with underwater non-structural grout to the appropriate (-4.877 meter) grade-level, thence with dry area non-structural grout to the final -10 centimeter level. The roof over the DB was preserved due to its potential historical significance and to prevent the infiltration of precipitation. Forced evaporation was the form of treatment implemented to remove the approximately 9.1 M liters of contaminated basin water. Using specially formulated grouts, irradiated materials and sediment were treated by solidification/isolation thus reducing their mobility, reducing radiation exposure and creating an engineered barrier thereby preventing access to the contaminants. Grouting provided a low permeability barrier to minimize any potential transport of contaminants to the aquifer. Efforts were made to preserve the historical significance of the Reactor in accordance with the National Historic Preservation Act. ISD provides a cost effective means to isolate and contain residual radioactivity from past nuclear operations allowing natural radioactive decay to reduce hazards to manageable levels. This method limits release of radiological contamination to the environment, minimizes radiation exposure to workers, prevents human/animal access to the hazardous substances, and allows for ongoing monitoring of the decommissioned facility. Field construction was initiated in August 2011; evaporator operations commenced January 2012 and ended July 2012 with over 9 M liters of water treated/removed. Over 8,525 cubic meters of grout were placed, completing in August 2012. The project completed with an excellent safety record, on schedule and under budget. (authors)

Bergren, Christopher L.; Long, J. Tony; Blankenship, John K. [Savannah River Nuclear Solutions, LLC, Bldg. 730-4B, Aiken, SC 29808 (United States)] [Savannah River Nuclear Solutions, LLC, Bldg. 730-4B, Aiken, SC 29808 (United States); Adams, Karen M. [United States Department of Energy, Bldg. 730-B, Aiken, SC 29808 (United States)] [United States Department of Energy, Bldg. 730-B, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

176

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

SciTech Connect (OSTI)

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

E.M. Harpenau

2010-11-15T23:59:59.000Z

177

ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING DEACTIVATION AND DECOMMISSIONING OF REACTOR VESSELS AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

The R- and P-reactor vessels at the Savannah River Site (SRS) are being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of physically isolating and stabilizing the reactor vessel by filling it with a grout material. The reactor vessels contain aluminum alloy materials, which pose a concern in that aluminum corrodes rapidly when it comes in contact with the alkaline grout. A product of the corrosion reaction is hydrogen gas and therefore potential flammability issues were assessed. A model was developed to calculate the hydrogen generation rate as the reactor is being filled with the grout material. Three options existed for the type of grout material for D&D of the reactor vessels. The grout formulation options included ceramicrete (pH 6-8), a calcium aluminate sulfate (CAS) based cement (pH 10), or Portland cement grout (pH 12.4). Corrosion data for aluminum in concrete were utilized as input for the model. The calculations considered such factors as the surface area of the aluminum components, the open cross-sectional area of the reactor vessel, the rate at which the grout is added to the reactor vessel, and temperature. Given the hydrogen generation rate, the hydrogen concentration in the vapor space of the reactor vessel above the grout was calculated. This concentration was compared to the lower flammability limit for hydrogen. The assessment concluded that either ceramicrete or the CAS grout may be used to safely grout the P-reactor vessel. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Portland cement grout, on the other hand, for the same range of process parameters did not provide a margin of safety against the accumulation of flammable gas in the reactor vessel during grouting operations in the P-reactor vessel. Therefore, it was recommended that this grout not be utilized for this task. On the other hand, the R-reactor vessel contained significantly less aluminum surface area that the P-reactor vessel based on current facility process knowledge, surface observations, and drawings. Therefore, a Portland cement grout may be considered for grouting operations as well as the other grout formulations.

Wiersma, B.; Serrato, M.; Langton, C.

2010-11-10T23:59:59.000Z

178

Summary of the engineering assessment of inactive uranium-mill tailings: Canonsburg Site, Canonsburg, Pennsylvania  

SciTech Connect (OSTI)

Ford, Bacon and Davis Utah Inc. has evaluated the Canonsburg site in order to assess the problems resulting from the existence of radioactive residues at Canonsburg, Pennsylvania. This engineering assessment has included the preparation of topographic maps, radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative remedial actions. Radon gas released from the approximately 300,000 tons of tailings and contaminated soil at the Canonsburg site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors. The four alternative actions presented in this engineering assessment range from millsite and off-site decontamination with the addition of 3 m of stabilization cover material (Option I), to removal of the tailings and contaminated materials to a remote disposal site and decontamination of the Canonsburg site (Options II through IV). Cost estimates for the four options range from $23,244,000 for stabilization in-place, to $27,052,000 for disposal at a distance of about 17 mi. Three principal alternatives for the reprocessing of the Canonsburg tailings were examined: heap leaching; treatment at an existing mill; and reprocessing at a new conventional mill constructed for tailings reprocessing. As required by Public Law 95-604, under whose auspices this project is conducted, the US Department of Energy has solicited expressions of interest in reprocessing the tailings and residues at the Canonsburg site for uranium recovery. Since no such interest was demonstrated, no effort has been made to estimate the value of the residual uranium resource at the Canonsburg site.

Not Available

1982-04-01T23:59:59.000Z

179

Department of Energy's High Flux Beam Reactor (HFBR), September 15--19, 1980: An independent on-site safety review  

SciTech Connect (OSTI)

The intent of this on-site safety review was to make a broad management assessment of HFBR operations, rather than conduct a detailed in-depth audit. The result of the review should only be considered as having identified trends or indications. The Team's observations and recommendations for the most part are based upon licensed reactor facility practices used to meet industry standards. These standards form the basis for many of the comments in this report. The Team believes that a uniform minimum standard of performance should be achieved in the operation of DOE reactors. In order to assure that this is accomplished, clear standards are necessary. Consistent with the past AEC and ERDA policy, the team has used the standards of the commercial nuclear power industry. It is recognized that this approach is conservative in that the HFBR reactor has a significantly greater degree of inherent safety (low pressure, temperature, power, etc.) than a licensed reactor.

Not Available

1981-02-01T23:59:59.000Z

180

Technical summary of groundwater quality protection program at the Savannah River Site, 1952--1986. Volume 1, Site geohydrology and waste sites  

SciTech Connect (OSTI)

This report provides information regarding the status of and groundwater quality at the waste sites at the Department of Energy`s (DOE) Savannah River Site (SRS). Specific information provided for each waste site at SRS includes its location, size, inventory (when known), and history. Many waste sites at SRS are considered to be of little environmental concern because they contain nontoxic or inert material such as construction rubble and debris. Other waste sites, however, either are known to have had an effect on groundwater quality or are suspected of having the potential to affect groundwater. Monitoring wells have been installed at most of these sites; monitoring wells are scheduled for installation at the remaining sites. Results of the groundwater analyses from these monitoring wells, presented in the appendices, are used in the report to help identify potential contaminants of concern, if any, at each waste site. The list of actions proposed for each waste site in Christensen and Gordon`s 1983 report are summarized, and an update is provided for each site. Planned actions for the future are also outlined.

Heffner, J.D. [ed.] [Exploration Resources, Inc., Athens, GA (United States)

1991-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor site summary" 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

Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 1, Data summary  

SciTech Connect (OSTI)

This report presents the results of geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavation of the Exploratory Studies Facility (ESF) North Ramp. The is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the feasibility of locating a potential high-level nuclear waste repository on lands adjacent to the Nevada Test Site, Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan. This report is volume 1 of the data summary.

Brechtel, C.E.; Lin, Ming; Martin, E. [Agapito Associates, Inc., Grand Junction, CO (United States); Kessel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

1995-05-01T23:59:59.000Z

182

Hanford Site C Tank Farm Meeting Summary - February 2009 | Department of  

Office of Environmental Management (EM)

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183

Hanford Site C Tank Farm Meeting Summary - January 2010 | Department of  

Office of Environmental Management (EM)

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184

Hanford Site C Tank Farm Meeting Summary - January 2011 | Department of  

Office of Environmental Management (EM)

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185

Hanford Site C Tank Farm Meeting Summary - July 2010 | Department of Energy  

Office of Environmental Management (EM)

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186

Hanford Site C Tank Farm Meeting Summary - March 2010 | Department of  

Office of Environmental Management (EM)

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187

Rocky Flats Environmental Technology Site Idle Equipment, August 21, 1997 Summary  

Office of Environmental Management (EM)

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188

Rocky Flats Environmental Technology Site Mixed Residue Consent Order, September 24, 1999 Summary  

Office of Environmental Management (EM)

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189

Rocky Flats Environmental Technology Site Treatment Plan Compliance Order, October 3, 1995 Summary  

Office of Environmental Management (EM)

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190

Rocky Flats Environmental Technology Site Waste Compliance Order, August 21, 1997 Summary  

Office of Environmental Management (EM)

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191

Savannah River Site Consent Order 85-70-SW, November 7, 1985 Summary  

Office of Environmental Management (EM)

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192

Savannah River Site Consent Order 95-22-HW, September 29, 1995 Summary  

Office of Environmental Management (EM)

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193

Savannah River Site Consent Order 99-155-W, October 11, 1999 Summary  

Office of Environmental Management (EM)

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194

Savannah River Site Consent Order 99-21-HW, July 13, 1999 Summary  

Office of Environmental Management (EM)

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195

Savannah River Site Consent Order 99-41-HW, September 28, 1999 Summary  

Office of Environmental Management (EM)

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196

2013 Annual Planning Summary for the Argonne Site Office | Department of  

Office of Environmental Management (EM)

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197

U.S. Federal Facility Compliance Agreement for the Hanford Site, February 7, 1994 Summary  

Office of Environmental Management (EM)

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198

Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Import Statement, Richland, Washington - Summary  

Office of Environmental Management (EM)

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199

SUMMARY OF REVISED TORNADO, HURRICANE AND EXTREME STRAIGHT WIND CHARACTERISTICS AT NUCLEAR FACILITY SITES  

Office of Environmental Management (EM)

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200

Settlement Agreement on TRU Mixed Waste Storage at Nevada Test Site Summary  

Office of Environmental Management (EM)

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Note: This page contains sample records for the topic "reactor site summary" 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

Summary - Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant  

Office of Environmental Management (EM)

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202

Summary - Salt Waste Processing Facility Design at the Savannah River Site  

Office of Environmental Management (EM)

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203

EIS-0147: Continued Operation of the K-,L-, and P- Reactors, Savannah River Site, Aiken, South Carolina  

Broader source: Energy.gov [DOE]

This environmental impact statement (EIS) analyzes the environmental impacts of the proposed action, which is to continue operation of K-, L-, and P-Reactors at the Savannah River Site (SRS) to ensure the capability to produce nuclear materials, and to produce nuclear materials as necessary for United States defense and nondefense programs.

204

EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

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 DOEs 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.

205

History of the 185-/189-D thermal hydraulics laboratory and its effects on reactor operations at the Hanford Site  

SciTech Connect (OSTI)

The 185-D deaeration building and the 189-D refrigeration building were constructed at Hanford during 1943 and 1944. Both buildings were constructed as part of the influent water cooling system for D reactor. The CMS studies eliminated the need for 185-D function. Early gains in knowledge ended the original function of the 189-D building mission. In 1951, 185-D and 189-D were converted to a thermal-hydraulic laboratory. The experiments held in the thermal-hydraulic lab lead to historic changes in Hanford reactor operations. In late 1951, the exponential physics experiments were moved to the 189-D building. In 1958, new production reactor experiments were begun in 185/189-D. In 1959, Plutonium Recycle Test Reactor experiments were added to the 185/189-D facility. By 1960, the 185/189-D thermal hydraulics laboratory was one of the few full service facilities of its type in the nation. During the years 1961--1963 tests continued in the facility in support of existing reactors, new production reactors, and the Plutonium Recycle Test Reactor. In 1969, Fast Flux Test Facility developmental testings began in the facility. Simulations in 185/189-D building aided in the N Reactor repairs in the 1980`s. In 1994 the facility was nominated to the National Register of Historic Places, because of its pioneering role over many years in thermal hydraulics, flow studies, heat transfer, and other reactor coolant support work. During 1994 and 1995 it was demolished in the largest decontamination and decommissioning project thus far in Hanford Site history.

Gerber, M.S.

1994-09-01T23:59:59.000Z

206

Independent Verification Final Summary Report for the David Witherspoon, Inc. 1630 Site Knoxville, Tennessee  

SciTech Connect (OSTI)

The primary objective of the independent verification was to determine if BJC performed the appropriate actions to meet the specified hot spot cleanup criteria of 500 picocuries per gram (pCi/g) uranium-238 (U-238) in surface soil. Specific tasks performed by the independent verification team (IVT) to satisfy this objective included: 1) performing radiological walkover surveys, and 2) collecting soil samples for independent analyses. The independent verification (IV) efforts were designed to evaluate radioactive contaminants (specifically U-238) in the exposed surfaces below one foot of the original site grade, given that the top one foot layer of soil on the site was removed in its entirety.

P.C. Weaver

2009-04-29T23:59:59.000Z

207

Summary and evaluation of hydraulic property data available for the Hanford Site upper basalt confined aquifer system  

SciTech Connect (OSTI)

Pacific Northwest Laboratory, as part of the Hanford Site Ground-Water Surveillance Project, examines the potential for offsite migration of contamination within the upper basalt confined aquifer system. For the past 40 years, hydrologic testing of the upper basalt confined aquifer has been conducted by a number of Hanford Site programs. Hydraulic property estimates are important for evaluating aquifer flow characteristics (i.e., ground-water flow patterns, flow velocity, transport travel time). Presented are the first comprehensive Hanford Site-wide summary of hydraulic properties for the upper basalt confined aquifer system (i.e., the upper Saddle Mountains Basalt). Available hydrologic test data were reevaluated using recently developed diagnostic test analysis methods. A comparison of calculated transmissivity estimates indicates that, for most test results, a general correspondence within a factor of two between reanalysis and previously reported test values was obtained. For a majority of the tests, previously reported values are greater than reanalysis estimates. This overestimation is attributed to a number of factors, including, in many cases, a misapplication of nonleaky confined aquifer analysis methods in previous analysis reports to tests that exhibit leaky confined aquifer response behavior. Results of the test analyses indicate a similar range for transmissivity values for the various hydro-geologic units making up the upper basalt confined aquifer. Approximately 90% of the calculated transmissivity values for upper basalt confined aquifer hydrogeologic units occur within the range of 10{sup 0} to 10{sup 2} m{sup 2}/d, with 65% of the calculated estimate values occurring between 10{sup 1} to 10{sup 2} m{sup 2}d. These summary findings are consistent with the general range of values previously reported for basalt interflow contact zones and sedimentary interbeds within the Saddle Mountains Basalt.

Spane, F.A. Jr.; Vermeul, V.R.

1994-09-01T23:59:59.000Z

208

2013 Annual Planning Summary for the Nevada Site Office | Department of  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement Awardflash2007-42attachment1.pdfmodule(EE)2012Energy Nevada Site Office 2013

209

2013 Annual Planning Summary for the Sandia Site Office | Department of  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement Awardflash2007-42attachment1.pdfmodule(EE)2012EnergyEnergy Sandia Site

210

Summary of canister overheating incident at the Carbon Tetrachloride Expedited Response Action site  

SciTech Connect (OSTI)

The granular activated carbon (GAC)-filled canister that overheated was being used to adsorb carbon tetrachloride vapors drawn from a well near the 216-Z-9 Trench, a subsurface disposal site in the 200 West Area of the Hanford Site. The overheating incident resulted in a band of discolored paint on the exterior surface of the canister. Although there was no other known damage to equipment, no injuries to operating personnel, and no releases of hazardous materials, the incident is of concern because it was not anticipated. It also poses the possibility of release of carbon tetrachloride and other hazardous vapors if the incident were to recur. All soil vapor extraction system (VES) operations were halted until a better understanding of the cause of the incident could be determined and controls implemented to reduce the possibility of a recurrence. The focus of this report and the intent of all the activities associated with understanding the overheating incident has been to provide information that will allow safe restart of the VES operations, develop operational limits and controls to prevent recurrence of an overheating incident, and safely optimize recovery of carbon tetrachloride from the ground.

Driggers, S.A.

1994-03-10T23:59:59.000Z

211

Fiscal year 1996 U.S. Department of Energy, Richland Operations Office Site summary baseline  

SciTech Connect (OSTI)

The technical baseline is a hierarchical description of the Hanford Site cleanup mission. This technical baseline does not address the science, technology, or economic transition missions. It begins with a definition of the existing conditions at the Hanford Site, provides a description of the end product or mission accomplishments at completion, presents a statement of the major requirements and constraints that must be observed during the performance of the mission, and provides a statement of the top-level strategic approach to accomplish the mission. Mission-level interfaces are also described. This information is further defined hierarchically in increasing levels of detail. This definition is composed of the following major elements: functions that are key task descriptions; requirements that are the measurable standards to which the functions must be performed; architectures which are specific engineering solutions or systems that perform the functions described earlier; and verification ensuring the system satisfies the requirements and fulfills the functions. The above information is supplemented with the following: interface data; risk analyses and watch lists; assumptions; and required analyses.

Johndro-Collins, A.

1995-10-01T23:59:59.000Z

212

A summary of ecological investigations at the burial ground complex, Savannah River Site - 1994  

SciTech Connect (OSTI)

This report summarizes the results of three ecological investigations that were conducted in 1994 at the Burial Ground Complex (BGC) at the Savannah River Site (SRS). The three topics of study included remote sensing, aquatic toxicity testing, and qualitative surveys of herpetofauna and small mammals. Interim reports from each investigation are included in the appendices (A, B, and C). The objectives of the remote sensing effort were to compile historical aerial photography of the BGC and to develop a land use/cover map of the complex using recent aerial imagery. The goal of the aquatic toxicity testing was to determine if surface waters were toxic to aquatic biota whereas the objectives of the vertebrate surveys were to identify the species diversity and relative abundances of amphibians, reptiles, and small mammals inhabiting the study area.

Friday, G.P.; Hartman, G.D.; Mackey, H.E. Jr.; Riley, R.S.; Roach, J.L.; Specht, W.L.; Westbury, H.M.; Wike, L.D.

1994-11-01T23:59:59.000Z

213

Summary of operations and performance of the Murdock site restoration project in 2008.  

SciTech Connect (OSTI)

This document summarizes the performance of the groundwater and surface water restoration systems installed by the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) at the former CCC/USDA grain storage facility in Murdock, Nebraska, during the third full year of system operation, from January 1 through December 31, 2008. Performance in June 2005 through December 2007 was reported previously (Argonne 2007, 2008). In the Murdock project, several innovative technologies are being used to remove carbon tetrachloride contamination from a shallow aquifer underlying the town, as well as from water naturally discharged to the surface at the headwaters of a small creek (a tributary to Pawnee Creek) north of the town (Figure 1.1). The restoration activities at Murdock are being conducted by the CCC/USDA as a non-time-critical removal action under the regulatory authority and supervision of the U.S. Environmental Protection Agency (EPA), Region VII. Argonne National Laboratory assisted the CCC/USDA by providing technical oversight for the restoration effort and facilities during this review period. Included in this report are the results of all sampling and monitoring activities performed in accord with the EPA-approved Monitoring Plan for this site (Argonne 2006), as well as additional investigative activities conducted during the review period. The annual performance reports for the Murdock project assemble information that will become part of the five-year review and evaluation of the remediation effort. This review will occur in 2010. This document presents overviews of the treatment facilities (Section 2) and site operations and activities (Section 3), then describes the groundwater, surface water, vegetation, and atmospheric monitoring results (Section 4) and modifications and costs during the review period (Section 5). Section 6 summarizes the current period of operation. A gallery of photographs of the Murdock project is in Appendix A.

LaFreniere, L. M.; Environmental Science Division

2009-06-04T23:59:59.000Z

214

Responsiveness summary for the engineering evaluation/cost analysis for decontamination at the St. Louis Downtown Site, St. Louis, Missouri  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is responsible for conducting remedial actions at the Mallinckrodt Chemical Plant, also referred to as the St. Louis Downtown Site (SLDS), located in the city of St. Louis, Missouri. Remedial activities at the SLDS are being carried out under DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP) as part of the overall cleanup planned for three noncontiguous areas in St. Louis, which are collectively referred to as the St. Louis Site. Potential response action alternatives for managing the contaminated material generated at the SLDS have been evaluated in accordance with US Environmental Protection Agency (EPA) guidance for conducting interim actions under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. An engineering evaluation/cost analysis (EE/CA) report was prepared to document this process. On the basis of the analysis presented in the EE/CA, the preferred alternative for the management of contaminated wastes generated by DOE-supported plant activities is the provision of temporary storage capacity, which can be made available by modifying an existing building (i.e., Building 116) at SLDS. This alternative would enable DOE and Mallinckrodt to coordinate efforts to prevent the uncontrolled relocation of contamination and ensure that ultimate site cleanup objectives are not complicated by plant activities implemented by Mallinckrodt. The EE/CA, dated May 1991, was issued to the general public on June 7, 1991, and a public comment period was held from June 7 through July 10, 1991, in accordance with the public participation process identified in CERCLA. Comments on the proposed action were received in writing from the Missouri Department of Health, private citizen Kay Drey, and the EPA Region 7. This responsiveness summary has been prepared to respond to issues identified in these comment letters on the proposed action.

Picel, M.H.; Peterson, J.M. (Argonne National Lab., IL (United States)); Williams, M.J. (Bechtel National, Inc., Oak Ridge, TN (United States))

1991-12-01T23:59:59.000Z

215

Responsiveness summary for the engineering evaluation/cost analysis for decontamination at the St. Louis Downtown Site, St. Louis, Missouri  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is responsible for conducting remedial actions at the Mallinckrodt Chemical Plant, also referred to as the St. Louis Downtown Site (SLDS), located in the city of St. Louis, Missouri. Remedial activities at the SLDS are being carried out under DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP) as part of the overall cleanup planned for three noncontiguous areas in St. Louis, which are collectively referred to as the St. Louis Site. Potential response action alternatives for managing the contaminated material generated at the SLDS have been evaluated in accordance with US Environmental Protection Agency (EPA) guidance for conducting interim actions under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. An engineering evaluation/cost analysis (EE/CA) report was prepared to document this process. On the basis of the analysis presented in the EE/CA, the preferred alternative for the management of contaminated wastes generated by DOE-supported plant activities is the provision of temporary storage capacity, which can be made available by modifying an existing building (i.e., Building 116) at SLDS. This alternative would enable DOE and Mallinckrodt to coordinate efforts to prevent the uncontrolled relocation of contamination and ensure that ultimate site cleanup objectives are not complicated by plant activities implemented by Mallinckrodt. The EE/CA, dated May 1991, was issued to the general public on June 7, 1991, and a public comment period was held from June 7 through July 10, 1991, in accordance with the public participation process identified in CERCLA. Comments on the proposed action were received in writing from the Missouri Department of Health, private citizen Kay Drey, and the EPA Region 7. This responsiveness summary has been prepared to respond to issues identified in these comment letters on the proposed action.

Picel, M.H.; Peterson, J.M. [Argonne National Lab., IL (United States); Williams, M.J. [Bechtel National, Inc., Oak Ridge, TN (United States)

1991-12-01T23:59:59.000Z

216

Summary Of Cold Crucible Vitrification Tests Results With Savannah River Site High Level Waste Surrogates  

SciTech Connect (OSTI)

The cold crucible inductive melting (CCIM) technology successfully applied for vitrification of low- and intermediate-level waste (LILW) at SIA Radon, Russia, was tested to be implemented for vitrification of high-level waste (HLW) stored at Savannah River Site, USA. Mixtures of Sludge Batch 2 (SB2) and 4 (SB4) waste surrogates and borosilicate frits as slurries were vitrified in bench- (236 mm inner diameter) and full-scale (418 mm inner diameter) cold crucibles. Various process conditions were tested and major process variables were determined. Melts were poured into 10L canisters and cooled to room temperature in air or in heat-insulated boxes by a regime similar to Canister Centerline Cooling (CCC) used at DWPF. The products with waste loading from ~40 to ~65 wt.% were investigated in details. The products contained 40 to 55 wt.% waste oxides were predominantly amorphous; at higher waste loadings (WL) spinel structure phases and nepheline were present. Normalized release values for Li, B, Na, and Si determined by PCT procedure remain lower than those from EA glass at waste loadings of up to 60 wt.%.

Stefanovsky, Sergey; Marra, James; Lebedev, Vladimir

2014-01-13T23:59:59.000Z

217

Summary of Degas II performance at the US Strategic Petroleum Reserve Big Hill site.  

SciTech Connect (OSTI)

Crude oil stored at the US Strategic Petroleum Reserve (SPR) requires mitigation procedures to maintain oil vapor pressure within program delivery standards. Crude oil degasification is one effective method for lowering crude oil vapor pressure, and was implemented at the Big Hill SPR site from 2004-2006. Performance monitoring during and after degasification revealed a range of outcomes for caverns that had similar inventory and geometry. This report analyzed data from SPR degasification and developed a simple degas mixing (SDM) model to assist in the analysis. Cavern-scale oil mixing during degassing and existing oil heterogeneity in the caverns were identified as likely causes for the range of behaviors seen. Apparent cavern mixing patterns ranged from near complete mixing to near plug flow, with more mixing leading to less efficient degassing due to degassed oil re-entering the plant before 100% of the cavern oil volume was processed. The report suggests that the new cavern bubble point and vapor pressure regain rate after degassing be based on direct in-cavern measurements after degassing as opposed to using the plant outlet stream properties as a starting point, which understates starting bubble point and overstates vapor pressure regain. Several means to estimate the cavern bubble point after degas in the absence of direct measurement are presented and discussed.

Rudeen, David K. (GRAM, Inc., Albuquerque, NM); Lord, David L.

2007-10-01T23:59:59.000Z

218

Analysis of removal alternatives for the Heavy Water Components Test Reactor at the Savannah River Site. Revision 1  

SciTech Connect (OSTI)

This engineering study evaluates different alternatives for decontamination and decommissioning of the Heavy Water Components Test Reactor (HWCTR). Cooled and moderated with pressurized heavy water, this uranium-fueled nuclear reactor was designed to test fuel assemblies for heavy water power reactors. It was operated for this purpose from march of 1962 until December of 1964. Four alternatives studied in detail include: (1) dismantlement, in which all radioactive and hazardous contaminants would be removed, the containment dome dismantled and the property restored to a condition similar to its original preconstruction state; (2) partial dismantlement and interim safe storage, where radioactive equipment except for the reactor vessel and steam generators would be removed, along with hazardous materials, and the building sealed with remote monitoring equipment in place to permit limited inspections at five-year intervals; (3) conversion for beneficial reuse, in which most radioactive equipment and hazardous materials would be removed and the containment building converted to another use such as a storage facility for radioactive materials, and (4) entombment, which involves removing hazardous materials, filling the below-ground structure with concrete, removing the containment dome and pouring a concrete cap on the tomb. Also considered was safe storage, but this approach, which has, in effect, been followed for the past 30 years, did not warrant detailed evaluation. The four other alternatives were evaluate, taking into account factors such as potential effects on the environment, risks, effectiveness, ease of implementation and cost. The preferred alternative was determined to be dismantlement. This approach is recommended because it ranks highest in the comparative analysis, would serve as the best prototype for the site reactor decommissioning program and would be most compatible with site property reuse plans for the future.

Owen, M.B.

1997-04-01T23:59:59.000Z

219

SRS Small Modular Reactors  

SciTech Connect (OSTI)

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

None

2012-04-27T23:59:59.000Z

220

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

Note: This page contains sample records for the topic "reactor site summary" 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

Summary Report on New Transmutation Analysis for the Evaluation of Homogeneous and Heterogeneous Options in Fast Reactors  

SciTech Connect (OSTI)

A 1000 MWth commercial-scale Sodium Fast Reactor (SFR) design was selected as the baseline in this scenario study. Traditional approaches to Light Water Reactor (LWR) Spent Nuclear Fuel (SNF) transuranic waste (TRU) burning in a fast spectrum system have typically focused on the continual homogeneous recycling (reprocessing) of the discharge fast reactor fuel. The effective reduction of transuranic inventories has been quantified through the use of the transuranics conversion ratio (TRU CR). The implicit assumption in the use of this single parameter is a homogeneous fast reactor option where equal weight is given to the destruction of transuranics, either by fission or eventual fission via transmutation. This work explores the potential application of alternative fast reactor fuel cycles in which the minor actinide (MA) component of the TRU is considered waste, while the plutonium component is considered as fuel. Specifically, a set of potential designs that incorporate radial heterogeneous target assemblies is proposed and results relevant to transmutation and system analysis are presented. In this work we consider exclusively minor actinide-bearing radial targets in a continual reprocessing scenario (as opposed to deep-burn options). The potential use of targets in a deep burn mode is not necessarily ruled out as an option. However, due to work scope constraints and material limit considerations, it was preferred to leave the target assemblies reach either the assumed limit of 200 DPA at discharge or maximum allowable gas pressure caused by helium production from transmutation. The number and specific design of the target assemblies was chosen to satisfy the necessary core symmetry and physical dimensions (available space for a certain amount of mass in an assembly based on an iterated mass density).

R. M. Ferrer; S. Bays; M. Pope; B. Forget; W. Skerjanc; M. Asgari

2008-08-01T23:59:59.000Z

222

EXECUTIVE SUMMARY OF STATE DATA RELATED TO ABANDONED CENTRALIZED AND COMMERCIAL DRILLING-FLUID DISPOSAL SITES IN LOUISIANA, NEW MEXICO, OKLAHOMA, AND TEXAS  

SciTech Connect (OSTI)

This 2003 Spring Semi-Annual Report contains a summary of the Final Technical Report being prepared for the Soil Remediation Requirements at Commercial and Centralized Drilling-Fluid Disposal (CCDD) Sites project funded by the United States Department of Energy under DOE Award No. DE-AC26-99BC15225. The summary describes (1) the objectives of the investigation, (2) a rationale and methodology of the investigation, (3) sources of data, assessment of data quality, and data availability, (4) examples of well documented centralized and commercial drilling-fluid disposal (CCDD) sites and other sites where drilling fluid was disposed of, and (5) examples of abandoned sites and measures undertaken for their assessment and remediation. The report also includes most of the figures, tables, and appendices that will be included in the final report.

H. Seay Nance

2003-03-01T23:59:59.000Z

223

Summary References | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

(NEPA) NEPA Reading Room SEIS for the Production of Tritium in a Commercial Light Water Reactor Reference Documents Summary References Summary References Crosswalk of...

224

Summary Site Environmental Report  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatus TomAbout »Lab (NewportSuccess Stories T E C H T R ASite

225

Draft environmental impact statement for the siting, construction, and operation of New Production Reactor capacity. Volume 2, Sections 1-6  

SciTech Connect (OSTI)

This (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains the analysis of programmatic alternatives, project alternatives, affected environment of alternative sites, environmental consequences, and environmental regulations and permit requirements.

Not Available

1991-04-01T23:59:59.000Z

226

Summary of the radiological assessment of the fuel cycle for a thorium-uranium carbide-fueled fast breeder reactor  

SciTech Connect (OSTI)

A large fraction of the potential fuel for nuclear power reactors employing fissionable materials exists as ores of thorium. In addition, certain characteristics of a fuel system based on breeding of the fissionable isotope {sup 233}U from thorium offer the possibility of a greater resistance to the diversion of fissionable material for the fabrication of nuclear weapons. This report consolidates into a single source the principal content of two previous reports which assess the radiological environmental impact of mining and milling of thorium ore and of the reprocessing and refabrication of spent FBR thorium-uranium carbide fuel.

Tennery, V.J.; Bomar, E.S.; Bond, W.D.; Meyer, H.R.; Morse, L.E.; Till, J.E.; Yalcintas, M.G.

1980-01-01T23:59:59.000Z

227

Draft environmental impact statement for the siting, construction, and operation of New Production Reactor capacity. Volume 3, Sections 7-12, Appendices A-C  

SciTech Connect (OSTI)

This Environmental Impact Statement (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site near Aiken, South Carolina. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains references; a list of preparers and recipients; acronyms, abbreviations, and units of measure; a glossary; an index and three appendices.

Not Available

1991-04-01T23:59:59.000Z

228

Draft Supplemental Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor, Summary  

Office of Environmental Management (EM)

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229

Draft Supplemental Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor, Summary  

National Nuclear Security Administration (NNSA)

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230

| |SAVE THIS EMAIL THIS Close Japan ups bid for fusion reactor site  

E-Print Network [OSTI]

-June, the paper said, citing unidentified government sources. Cabinet ministers were to discuss the proposal later use half of the additional money to build research facilities in France and set aside the remaining electricity. The fusion reactor project, first proposed more than a decade ago, is designed to study

231

US LMFBR (Liquid Metal Fast Breeder Reactor): flow induced vibration program (1977-1986): A summary and overview  

SciTech Connect (OSTI)

This paper summarizes the activities and accomplishments under the US LMFBR Flow Induced Vibration Program for the period 1977-1986. Since 1977 represents the date of the last IAEA IWGFR Specialists Meeting on LMFBR Flow Induced Vibration, this paper thus provides an update to the results presented at that meeting. This period also represents a period of substantial change for the US LMFBR program. A major reactor project, the FFTF, was completed and a second major project, the CRBR plant, was terminated. This change adversely impacted the US flow induced vibration program. Nevertheless, base technology activities have continued. In this paper, research in the following areas is summarized: Vibration characteristics and scaling, Turbulent buffeting and vortex shedding, Fluidelastic instabilities of tube bundles in crossflow, and Instabilities induced by leakage flows.

Wambsganss, M.W.; Chen, S.S.; Mulcahy, T.M.; Jendrzejczyk, J.A.

1986-09-01T23:59:59.000Z

232

Establishing Specifications for Low Enriched Uranium Fuel Operations Conducted Outside the High Flux Isotope Reactor Site  

SciTech Connect (OSTI)

The National Nuclear Security Administration (NNSA) has funded staff at Oak Ridge National Laboratory (ORNL) to study the conversion of the High Flux Isotope Reactor (HFIR) from the current, high enriched uranium fuel to low enriched uranium fuel. The LEU fuel form is a metal alloy that has never been used in HFIR or any HFIR-like reactor. This report provides documentation of a process for the creation of a fuel specification that will meet all applicable regulations and guidelines to which UT-Battelle, LLC (UTB) the operating contractor for ORNL - must adhere. This process will allow UTB to purchase LEU fuel for HFIR and be assured of the quality of the fuel being procured.

Pinkston, Daniel [ORNL; Primm, Trent [ORNL; Renfro, David G [ORNL; Sease, John D [ORNL

2010-10-01T23:59:59.000Z

233

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

SciTech Connect (OSTI)

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

mike lewis

2011-02-01T23:59:59.000Z

234

2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Sites Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Sites Advanced Test Reactor Complex Cold Waste Pond from November 1, 2012October 31, 2013. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance issues Discussion of the facilitys environmental impacts. During the 2013 permit year, approximately 238 million gallons of wastewater was discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters are below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

Mike Lewis

2014-02-01T23:59:59.000Z

235

Population Sensitivity Evaluation of Two Proposed Hampton Roads Area Sites for a Possible Small Modular Reactor  

SciTech Connect (OSTI)

The overall objective of this research project is to use the OR-SAGE tool to support the US Department of Energy (DOE) Office of Nuclear Energy (NE) in evaluating future electrical generation deployment options for small modular reactors (SMRs) in areas with significant energy demand from the federal sector. Deployment of SMRs in zones with high federal energy use can provide a means of meeting federal clean energy goals.

Belles, R. J. [ORNL; Omitaomu, O. A. [ORNL

2014-08-01T23:59:59.000Z

236

Restart of K-Reactor, Savannah River Site: Safety evaluation report  

SciTech Connect (OSTI)

This Safety Evaluation Report (SER) focuses on those issues required to support the restart of the K-Reactor at the Savannah River Plant. This SER provides the safety criteria for restart and documents the results of the staff reviews of the DOE and operating contractor activities to meet these criteria. To develop the restart criteria for the issues discussed in this SER, the Savannah River Restart Office and Savannah River Special Projects Office staffs relied, when possible, on commercial industry codes and standards and on NRC requirements and guidelines for the commercial nuclear industry. However, because of the age and uniqueness of the Savannah River reactors, criteria for the commercial plants were not always applicable. In these cases, alternate criteria were developed. The restart criteria applicable to each of the issues are identified in the safety evaluations for each issue. The restart criteria identified in this report are intended to apply only to restart of the Savannah River reactors. Following the development of the acceptance criteria, the DOE staff and their support contractors evaluated the results of the DOE and operating contractor (WSRC) activities to meet these criteria. The results of those evaluations are documented in this report. Deviations or failures to meet the requirements are either justified in the report or carried as open or confirmatory items to be completed and evaluated in supplements to this report before restart. 62 refs., 1 fig.

Not Available

1991-04-01T23:59:59.000Z

237

Evaluation of Suitability of Selected Set of Coal Plant Sites for Repowering with Small Modular Reactors  

SciTech Connect (OSTI)

This report summarizes the approach that ORNL developed for screening a sample set of small coal stations for possible repowering with SMRs; the methodology employed, including spatial modeling; and initial results for these sample plants. The objective in conducting this type of siting evaluation is to demonstrate the capability to characterize specific sample coal plant sites to identify any particular issues associated with repowering existing coal stations with SMRs using OR-SAGE; it is not intended to be a definitive assessment per se as to the absolute suitability of any particular site.

Belles, Randy [ORNL; Copinger, Donald A [ORNL; Mays, Gary T [ORNL; Omitaomu, Olufemi A [ORNL; Poore III, Willis P [ORNL

2013-03-01T23:59:59.000Z

238

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

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

239

Result Summary for the Area 5 Radioactive Waste Management Site Performance Assessment Model Version 4.113  

SciTech Connect (OSTI)

Preliminary results for Version 4.113 of the Nevada National Security Site Area 5 Radioactive Waste Management Site performance assessment model are summarized. Version 4.113 includes the Fiscal Year 2011 inventory estimate.

Shott, G. J.

2012-04-15T23:59:59.000Z

240

DOI Designates B Reactor at DOE's Hanford Site as a National Historic  

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

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Note: This page contains sample records for the topic "reactor site summary" 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

Savannah River Site Removes Dome, Opening Reactor for Recovery Act Decommissioning  

Office of Environmental Management (EM)

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242

U.S. Department of Energy 2012 Annual Inspection - Piqua, OH, Decommissioned Reactor Site  

Office of Legacy Management (LM)

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243

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

SciTech Connect (OSTI)

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

Mike Lewis

2013-02-01T23:59:59.000Z

244

EVALUATION OF ACTIVATION PRODUCTS IN REMAINING IN REMAINING K-, L- AND C-REACTOR STRUCTURES  

SciTech Connect (OSTI)

An analytic model and calculational methodology was previously developed for P-reactor and R-reactor to quantify the radioisotopes present in Savannah River Site (SRS) reactor tanks and the surrounding structural materials as a result of neutron activation of the materials during reactor operation. That methodology has been extended to K-reactor, L-reactor, and C-reactor. The analysis was performed to provide a best-estimate source term input to the Performance Assessment for an in-situ disposition strategy by Site Decommissioning and Demolition (SDD). The reactor structure model developed earlier for the P-reactor and R-reactor analyses was also used for the K-reactor and L-reactor. The model was suitably modified to handle the larger Creactor tank and associated structures. For all reactors, the structure model consisted of 3 annular zones, homogenized by the amount of structural materials in the zone, and 5 horizontal layers. The curie content on an individual radioisotope basis and total basis for each of the regions was determined. A summary of these results are provided herein. The efficacy of this methodology to accurately predict the radioisotopic content of the reactor systems in question has been demonstrated and is documented in Reference 1. As noted in that report, results for one reactor facility cannot be directly extrapolated to other SRS reactors.

Vinson, D.; Webb, R.

2010-09-30T23:59:59.000Z

245

Summary of Inorganic Compositional Data for Groundwater, Soil-Water, and Surface-Water Samples at the Headgate Draw Subsurface Drip Irrigation Site  

SciTech Connect (OSTI)

As part of a 5-year project on the impact of subsurface drip irrigation (SDI) application of coalbed-methane (CBM) produced waters, water samples were collected from the Headgate Draw SDI site in the Powder River Basin, Wyoming, USA. This research is part of a larger study to understand short- and long-term impacts on both soil and water quality from the beneficial use of CBM waters to grow forage crops through use of SDI. This document provides a summary of the context, sampling methodology, and quality assurance and quality control documentation of samples collected prior to and over the first year of SDI operation at the site (May 2008-October 2009). This report contains an associated database containing inorganic compositional data, water-quality criteria parameters, and calculated geochemical parameters for samples of groundwater, soil water, surface water, treated CBM waters, and as-received CBM waters collected at the Headgate Draw SDI site.

Geboy, Nicholas J.; Engle, Mark A.; Schroeder, Karl T.; Zupanic, John W.

2007-01-01T23:59:59.000Z

246

Field Summary Report for Remedial Investigation of Hanford Site Releases to the Columbia River, Hanford Site, Washington, Collection of Surface Water, River Sediments, and Island Soils  

SciTech Connect (OSTI)

This report has been prepared in support of the remedial investigation of Hanford Site Releases to the Columbia River and describes the 2008/2009 data collection efforts. This report documents field activities associated with collection of sediment, river water, and soil in and adjacent to the Columbia River near the Hanford Site and in nearby tributaries.

L. C. Hulstrom

2009-09-28T23:59:59.000Z

247

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

SciTech Connect (OSTI)

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

Mike Lewis

2012-02-01T23:59:59.000Z

248

Chu Visits Site of America�s First New Nuclear Reactor in Three Decades  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation SitesStandingtheirCheck InChemistryChrisChristineNewsPage5, 2012

249

Summary of flammable gas hazard and potential consequences in tank waste remediation system facility at the Hanford site  

SciTech Connect (OSTI)

This document provides a summary of the flammable gas program since 1992. It provides the best understanding of generation, retention, release of flammable gases. It gives a composition for each of the flammable gas tanks, calculates postulated concentrations in the event of a release, calculates the pressure obtained during a burn, and provides radiological and toxicological consequences. Controls from the analysis are found in WHC-SD-WM-SAR-067.

Van Vleet, R.J., Westinghouse Hanford

1996-12-11T23:59:59.000Z

250

Summary Report of Geophysical Logging For The Seismic Boreholes Project at the Hanford Site Waste Treatment Plant.  

SciTech Connect (OSTI)

During the period of June through October 2006, three deep boreholes and one corehole were drilled beneath the site of the Waste Treatment Plant (WTP) at the U.S. Department of Energy (DOE) Hanford Site near Richland, Washington. The boreholes were drilled to provide information on ground-motion attenuation in the basalt and interbedded sediments underlying the WTP site. This report describes the geophysical logging of the deep boreholes that was conducted in support of the Seismic Boreholes Project, defined below. The detailed drilling and geological descriptions of the boreholes and seismic data collected and analysis of that data are reported elsewhere.

Gardner, Martin G.; Price, Randall K.

2007-02-01T23:59:59.000Z

251

2009 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analysis  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 Radioactive Wate Management Site (RWMS) Performance Assessments (PAs) and Composite Analyses (CAs) in fiscal year (FY) 2009. This annual summary report presents data and conclusions from the FY 2009 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

NSTec Environmental Management

2010-03-15T23:59:59.000Z

252

SITE-LEVEL SUMMARY (3Q) of FINAL-3RD-QUARTER-FY-2014-SCORECARD-04-02-15  

Office of Environmental Management (EM)

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253

SITE-LEVEL SUMMARY (4Q) of FINAL-4TH-QUARTER-FY-2014-SCORECARD-04-02-15  

Office of Environmental Management (EM)

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254

SITE-LEVEL SUMMARY of FINAL-2ND-QUARTER-FY-2014-SCORECARD-02-25-15  

Office of Environmental Management (EM)

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255

SITE-LEVEL SUMMARY of FINAL-3RD-QUARTER-FY-2012-SCORECARD-01-24-13  

Office of Environmental Management (EM)

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256

SITE-LEVEL SUMMARY of FINAL-4TH-QUARTER-FY-2013-SCORECARD-05-01-14  

Office of Environmental Management (EM)

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257

Decommissioning of the Dragon High Temperature Reactor (HTR) Located at the Former United Kingdom Atomic Energy Authority (UKAEA) Research Site at Winfrith - 13180  

SciTech Connect (OSTI)

The Dragon Reactor was constructed at the United Kingdom Atomic Energy Research Establishment at Winfrith in Dorset through the late 1950's and into the early 1960's. It was a High Temperature Gas Cooled Reactor (HTR) with helium gas coolant and graphite moderation. It operated as a fuel testing and demonstration reactor at up to 20 MW (Thermal) from 1964 until 1975, when international funding for this project was terminated. The fuel was removed from the core in 1976 and the reactor was put into Safestore. To meet the UK's Nuclear Decommissioning Authority (NDA) objective to 'drive hazard reduction' [1] it is necessary to decommission and remediate all the Research Sites Restoration Ltd (RSRL) facilities. This includes the Dragon Reactor where the activated core, pressure vessel and control rods and the contaminated primary circuit (including a {sup 90}Sr source) still remain. It is essential to remove these hazards at the appropriate time and return the area occupied by the reactor to a safe condition. (author)

Smith, Anthony A. [Research Sites Restoration Ltd, Winfrith, Dorset (United Kingdom)] [Research Sites Restoration Ltd, Winfrith, Dorset (United Kingdom)

2013-07-01T23:59:59.000Z

258

Summary environmental site assessment report for the U.S. Department of Energy Oxnard Facility, Oxnard, California  

SciTech Connect (OSTI)

This report summarizes the investigations conducted by Rust Geotech at the U.S. Department of Energy (DOE) Oxnard facility, 1235 East Wooley Road, Oxnard, California. These investigations were designed to locate, identify, and characterize any regulated contaminated media on the site. The effort included site visits; research of ownership, historical uses of the Oxnard facility and adjacent properties, incidences of and investigations for contaminants on adjacent properties, and the physical setting of the site; sampling and analysis; and reporting. These investigations identified two friable asbestos gaskets on the site, which were removed, and nonfriable asbestos, which will be managed through the implementation of an asbestos management plan. The California primary drinking water standards were exceeded for aluminum on two groundwater samples and for lead in one sample collected from the shallow aquifer underlying the site; remediation of the groundwater in this aquifer is not warranted because it is not used. Treated water is available from a municipal water system. Three sludge samples indicated elevated heavy metals concentrations; the sludge must be handled as a hazardous waste if disposed. Polychlorinated biphenyls (PCBs) were detected at concentrations below remediation criteria in facility soils at two locations. In accordance with U.S. Environmental Protection Agency (EPA) and State of California guidance, remediation of the PCBs is not required. No other hazardous substances were detected in concentrations exceeding regulatory limits.

NONE

1996-02-01T23:59:59.000Z

259

Task summary for cone penetrating testing sounding and soil and groundwater sampling Salmon Site, Lamar County, Mississippi  

SciTech Connect (OSTI)

The Salmon Site (SS), located in Mississippi, was the site of two nuclear and two gas explosion testes conducted deep underground in the Tatum Salt Dome between 1964 and 1970. As a consequence radionuclides generated during the testing were released into the salt dome. During reentry drilling and other site activities, incidental liquid and solid wastes that contained radioactivity were generated, resulting in some soil, ground water and equipment contamination. US DOE is conducting a series of investigations as a part of the Remedial Investigation and Feasibility Study (under CERCLA) This report summarizes the cone penetrometer testing (CPT) and sampling program conducted in fall 1993, providing a description of the activities and a discussion of the results. The objectives of the CPT program were to determine subsurface conditions and stratification; determine the depth to the potentiometric surface; obtain soil samples from predetermined depths; obtain groundwater samples at predetermined depths.

Not Available

1994-10-01T23:59:59.000Z

260

Inspection of Environment, Safety, and Health and Emergency Management at the Nevada Test Site- Summary Report, October 2002  

Broader source: Energy.gov [DOE]

The Secretary of Energys Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) and emergency management programs at the National Nuclear Security Administration (NNSA) Nevada Test Site (NTS) in September and October

Note: This page contains sample records for the topic "reactor site summary" 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

2008 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses  

SciTech Connect (OSTI)

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs) for each of the facilities, with the results submitted annually to U.S. Department of Energy (DOE) Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan. The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) performed an annual review in fiscal year (FY) 2008 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs. This annual summary report presents data and conclusions from the FY 2008 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

NSTec Environmental Management

2009-03-30T23:59:59.000Z

262

Regional groundwater flow model for C, K. L. and P reactor areas, Savannah River Site, Aiken, SC  

SciTech Connect (OSTI)

A regional groundwater flow model encompassing approximately 100 mi2 surrounding the C, K, L, and P reactor areas has been developed. The reactor flow model is designed to meet the planning objectives outlined in the General Groundwater Strategy for Reactor Area Projects by providing a common framework for analyzing groundwater flow, contaminant migration and remedial alternatives within the Reactor Projects team of the Environmental Restoration Department. The model provides a quantitative understanding of groundwater flow on a regional scale within the near surface aquifers and deeper semi-confined to confined aquifers. The model incorporates historical and current field characterization data up through Spring 1999. Model preprocessing is automated so that future updates and modifications can be performed quickly and efficiently. The CKLP regional reactor model can be used to guide characterization, perform scoping analyses of contaminant transport, and serve as a common base for subsequent finer-scale transport and remedial/feasibility models for each reactor area.

Flach, G.P.

2000-02-11T23:59:59.000Z

263

A Summary of Fault Recurrence and Strain Rates in the Vicinity of the Hanford Site--Topical Report  

SciTech Connect (OSTI)

This document is one in a series of topical reports compiled by the Pacific Northwest National Laboratory to summarize technical information on selected topics important to the performance of a probabilistic seismic hazard analysis of the Hanford Site. The purpose of this report is to summarize available data and analyses relevant to fault recurrence and strain rates within the Yakima Fold Belt. Strain rates have met with contention in the expert community and may have a significant potential for impact on the seismic hazard estimate at the Hanford Site. This report identifies the alternative conceptual models relevant to this technical issue and the arguments and data that support those models. It provides a brief description of the technical issue and principal uncertainties; a general overview on the nature of the technical issue, along with alternative conceptual models, supporting arguments and information, and uncertainties; and finally, suggests some prospective approaches to reducing uncertainties about earthquake recurrence rates for the Yakima Fold Belt.

Bjornstad, Bruce N.; Winsor, Kelsey; Unwin, Stephen D.

2012-08-01T23:59:59.000Z

264

Summary of Natural Resources that Potentially Influence Human Intrusion at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada  

SciTech Connect (OSTI)

In 1993, Raytheon Services Nevada completed a review of natural resource literature and other sources to identify potentially exploitable resources and potential future land uses near the Area 5 Radioactive Waste Management Site (RWMS) of the Nevada Test Site (NTS), Nye County, Nevada, that could lead to future inadvertent human intrusion and subsequent release of radionuclides to the accessible environment. National Security Technologies, LLC, revised the original limited-distribution document to conform to current editorial standards and U.S. Department of Energy requirements for public release. The researchers examined the potential for future development of sand, gravel, mineral, petroleum, water resources, and rural land uses, such as agriculture, grazing, and hunting. The study was part of the performance assessment for Greater Confinement Disposal boreholes. Sand and gravel are not considered exploitable site resources because the materials are common throughout the area and the quality at the Area 5 RWMS is not ideal for typical commercial uses. Site information also indicates a very low mineral potential for the area. None of the 23 mining districts in southern Nye County report occurrences of economic mineral deposits in unconsolidated alluvium. The potential for oil and natural gas is low for southern Nye County. No occurrences of coal, tar sand, or oil shale on the NTS are reported in available literature. Several potential future uses of water were considered. Agricultural irrigation is impractical due to poor soils and existing water supply regulations. Use of water for geothermal energy development is unlikely because temperatures are too low for typical commercial applications using current technology. Human consumption of water has the most potential for cause of intrusion. The economics of future water needs may create a demand for the development of deep carbonate aquifers in the region. However, the Area 5 RWMS is not an optimal location for extraction of groundwater from the deep carbonate aquifer. Grazing and hunting are unlikely to be potential causes for inadvertent human intrusion into waste areas because of vegetation characteristics and lack of significant game animal populations.

NSTec Environmental Management

2007-06-01T23:59:59.000Z

265

DOE Announces Additional Tour Seats Available: Tours of B Reactor at the Hanford Site Begin and End in Richland, Wash.  

Broader source: Energy.gov [DOE]

RICHLAND, Wash. The U.S. Department of Energy (DOE) has made additional seats available for tours of the B Reactor National Historic Landmark this July and August.

266

WSRC Reactor Tank Inspection Program (RTIP) status report  

SciTech Connect (OSTI)

Westinghouse Savannah River Company (WSRC) recently completed the initial phase of nondestructive inspections of the Savannah River Site's (SRS) reactor tanks. This program required almost three years to be conceptualized, fabricated, and tested. An additional 20 months were required to complete the NDE inspection of the P, K and L reactor tanks. The overall cost of the program to date is approximately $25 MM. This status report will address: (1) A brief review of the RTIP program and the constraints which had to be overcome (2) A summary of the examination results of the P,K, and L Reactor tanks. (3) A projection of the future enhancements and capabilities presently in development.

Loibl, M.W.

1992-01-01T23:59:59.000Z

267

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS).

J. L. Smith

2001-01-01T23:59:59.000Z

268

Evaluation of melter technologies for vitrification of Hanford site low-level tank waste - phase 1 testing summary report  

SciTech Connect (OSTI)

Following negotiation of the fourth amendment to the Tri- Party Agreement for Hanford Site cleanup, commercially available melter technologies were tested during 1994 and 1995 for vitrification of the low-level waste (LLW) stream to be derived from retrieval and pretreatment of the radioactive defense wastes stored in 177 underground tanks. Seven vendors were selected for Phase 1 testing to demonstrate vitrification of a high-sodium content liquid LLW simulant. The tested melter technologies included four Joule-heated melters, a carbon electrode melter, a combustion melter, and a plasma melter. Various dry and slurry melter feed preparation processes also were tested. The technologies and Phase 1 testing results were evaluated and a preliminary technology down-selection completed. This report describes the Phase 1 LLW melter vendor testing and the tested technologies, and summarizes the testing results and the preliminary technology recommendations.

Wilson, C.N., Westinghouse Hanford

1996-06-27T23:59:59.000Z

269

H Reactor - Hanford Site  

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

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270

N Reactor - Hanford Site  

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

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271

F Reactor - Hanford Site  

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

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272

B Reactor - Hanford Site  

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

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273

C Reactor - Hanford Site  

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

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274

SITE  

Office of Legacy Management (LM)

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275

2014 Annual Planning Summary for the Oak RIdge National Laboratory...  

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

4 Annual Planning Summary for the Oak RIdge National Laboratory Site Office 2014 Annual Planning Summary for the Oak RIdge National Laboratory Site Office The Oak Ridge National...

276

Result Summary for the Area 5 Radioactive Waste Management Site Performance Assessment Model Version 4.110  

SciTech Connect (OSTI)

Results for Version 4.110 of the Area 5 Radioactive Waste Management Site (RWMS) performance assessment (PA) model are summarized. Version 4.110 includes the fiscal year (FY) 2010 inventory estimate, including a future inventory estimate. Version 4.110 was implemented in GoldSim 10.11(SP4). The following changes have been implemented since the last baseline model, Version 4.105: (1) Updated the inventory and disposal unit configurations with data through the end of FY 2010. (1) Implemented Federal Guidance Report 13 Supplemental CD dose conversion factors (U.S. Environmental Protection Agency, 1999). Version 4.110 PA results comply with air pathway and all-pathways annual total effective dose (TED) performance objectives (Tables 2 and 3, Figures 1 and 2). Air pathways results decrease moderately for all scenarios. The time of the maximum for the air pathway open rangeland scenario shifts from 1,000 to 100 years (y). All-pathways annual TED increases for all scenarios except the resident scenario. The maximum member of public all-pathways dose occurs at 1,000 y for the resident farmer scenario. The resident farmer dose was predominantly due to technetium-99 (Tc-99) (82 percent) and lead-210 (Pb-210) (13 percent). Pb-210 present at 1,000 y is produced predominantly by radioactive decay of uranium-234 (U-234) present at the time of disposal. All results for the postdrilling and intruder-agriculture scenarios comply with the performance objectives (Tables 4 and 5, Figures 3 and 4). The postdrilling intruder results are similar to Version 4.105 results. The intruder-agriculture results are similar to Version 4.105, except for the Pit 6 Radium Disposal Unit (RaDU). The intruder-agriculture result for the Shallow Land Burial (SLB) disposal units is a significant fraction of the performance objective and exceeds the performance objective at the 95th percentile. The intruder-agriculture dose is due predominantly to Tc-99 (75 percent) and U-238 (9.5 percent). The acute intruder scenario results comply with all performance objectives (Tables 6 and 7, Figures 5 and 6). The acute construction result for the SLB disposal units decreases significantly with this version. The maximum acute intruder dose occurs at 1,000 y for the SLB disposal units under the acute construction scenario. The acute intruder dose is caused by multiple radionuclides including U-238 (31 percent), Th-229 (28 percent), plutonium-239 (8.6 percent), U-233 (7.8 percent), and U-234 (6.7 percent). All results for radon-222 (Rn-222) flux density comply with the performance objective (Table 8, Figure 7). The mean Pit 13 RaDU flux density is close to the 0.74 Bq m{sup -2} s{sup -1} limit.

NSTec Environmental Management

2011-07-20T23:59:59.000Z

277

Oak Ridge Site Specific  

Office of Environmental Management (EM)

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278

Small Site Closures  

Office of Environmental Management (EM)

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279

Grout Isolation and Stabilization of Structures and Materials within Nuclear Facilities at the U.S. Department of Energy, Hanford Site, Summary - 12309  

SciTech Connect (OSTI)

Per regulatory agreement and facility closure design, U.S. Department of Energy Hanford Site nuclear fuel cycle structures and materials require in situ isolation in perpetuity and/or interim physicochemical stabilization as a part of final disposal or interim waste removal, respectively. To this end, grout materials are being used to encase facilities structures or are being incorporated within structures containing hazardous and radioactive contaminants. Facilities where grout materials have been recently used for isolation and stabilization include: (1) spent fuel separations, (2) uranium trioxide calcining, (3) reactor fuel storage basin, (4) reactor fuel cooling basin transport rail tanker cars and casks, (5) cold vacuum drying and reactor fuel load-out, and (6) plutonium fuel metal finishing. Grout components primarily include: (1) portland cement, (2) fly ash, (3) aggregate, and (4) chemical admixtures. Mix designs for these typically include aggregate and non aggregate slurries and bulk powders. Placement equipment includes: (1) concrete piston line pump or boom pump truck for grout slurry, (2) progressive cavity and shearing vortex pump systems, and (3) extendable boom fork lift for bulk powder dry grout mix. Grout slurries placed within the interior of facilities were typically conveyed utilizing large diameter slick line and the equivalent diameter flexible high pressure concrete conveyance hose. Other facilities requirements dictated use of much smaller diameter flexible grout conveyance hose. Placement required direct operator location within facilities structures in most cases, whereas due to radiological dose concerns, placement has also been completed remotely with significant standoff distances. Grout performance during placement and subsequent to placement often required unique design. For example, grout placed in fuel basin structures to serve as interim stabilization materials required sufficient bearing i.e., unconfined compressive strength, to sustain heavy equipment yet, low breakout force to permit efficient removal by track hoe bucket or equivalent construction equipment. Further, flow of slurries through small orifice geometries of moderate head pressures was another typical design requirement. Phase separation of less than 1 percent was a typical design requirement for slurries. On the order of 30,000 cubic meters of cementitious grout have recently been placed in the above noted U.S. Department of Energy Hanford Site facilities or structures. Each has presented a unique challenge in mix design, equipment, grout injection or placement, and ultimate facility or structure performance. Unconfined compressive and shear strength, flow, density, mass attenuation coefficient, phase separation, air content, wash-out, parameters and others, unique to each facility or structure, dictate the grout mix design for each. Each mix design was tested under laboratory and scaled field conditions as a precursor to field deployment. Further, after injection or placement of each grout formulation, the material was field inspected either by standard laboratory testing protocols, direct physical evaluation, or both. (authors)

Phillips, S.J.; Phillips, M.; Etheridge, D. [Applied Geotechnical Engineering and Construction, Incorporated, Richland, Washington (United States); Chojnacki, D.W.; Herzog, C.B.; Matosich, B.J.; Steffen, J.M.; Sterling, R.T. [CH2M HILL Plateau Remediation Company, Richland, Washington (United States); Flaucher, R.H.; Lloyd, E.R. [Fluor Federal Services, Incorporated, Richland, Washington (United States)

2012-07-01T23:59:59.000Z

280

a-1 reactor bohunice: Topics by E-print Network  

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

of degree one rather than rational points. Nguyen Le Dang Thi 7 Inexpensive Mini Thermonuclear Reactor CiteSeer Summary: This proposed design for a mini thermonuclear reactor...

Note: This page contains sample records for the topic "reactor site summary" 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

FROM CONCEPT TO REALITY, IN-SITU DECOMMISSIONING OF THE P AND R REACTORS AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

SRS recently completed an approximately three year effort to decommission two SRS reactors: P-Reactor (Building 105-P) and R-Reactor (Building 105-R). Completed in December 2011, the concurrent decommissionings marked the completion of two relatively complex and difficult facility disposition projects at the SRS. Buildings 105-P and 105-R began operating as production reactors in the early 1950s with the mission of producing weapons material (e.g., tritium and plutonium-239). The 'P' Reactor and was shutdown in 1991 while the 'R' Reactor and was shutdown in 1964. In the intervening period between shutdown and deactivation & decommissioning (D&D), Buildings 105-P and 105-R saw limited use (e.g., storage of excess heavy water and depleted uranium oxide). For Building 105-P, deactivation was initiated in April 2007 and was essentially complete by June 2010. For Building 105-R, deactivation was initiated in August 2008 and was essentially complete by September 2010. For both buildings, the primary objective of deactivation was to remove/mitigate hazards associated with the remaining hazardous materials, and thus prepare the buildings for in-situ decommissioning. Deactivation removed the following hazardous materials to the extent practical: combustibles/flammables, residual heavy water, acids, friable asbestos (as needed to protect workers performing deactivation and decommissioning), miscellaneous chemicals, lead/brass components, Freon(reg sign), oils, mercury/PCB containing components, mold and some radiologically-contaminated equipment. In addition to the removal of hazardous materials, deactivation included the removal of hazardous energy, exterior metallic components (representing an immediate fall hazard), and historical artifacts along with the evaporation of water from the two Disassembly Basins. Finally, so as to facilitate occupancy during the subsequent in-situ decommissioning, deactivation implemented repairs to the buildings and provided temporary power.

Musall, J.; Blankenship, J.; Griffin, W.

2012-01-09T23:59:59.000Z

282

Summary of the HANFORD SITE  

E-Print Network [OSTI]

.........................................................................................................9 Hanford Cleanup Operations................................................12 Liquid Waste Management..................................................................................................14 Solid Waste Management

283

Summary of the HANFORD SITE  

E-Print Network [OSTI]

...........................................................................10 Hanford Cleanup Operations..........................................................................................................14 Waste Management........................................................................................................23 Potential Radiological Doses from 2004 Hanford Operations

284

Current Month Summary - Hanford Site  

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

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285

Yesterday's Daily Summary - Hanford Site  

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

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286

Yesterday's Daily Summary - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste andAnniversary, part 2 ContinuingYan Mei Wang YanMet and Climate

287

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

SciTech Connect (OSTI)

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

S.J. Roberts

2007-03-20T23:59:59.000Z

288

Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada  

SciTech Connect (OSTI)

The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229Th, 230Th, 232U, 233U, and 234U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Shott, Gregory [NSTec

2014-08-31T23:59:59.000Z

289

Plutonium Consumption Program, CANDU Reactor Project: Feasibility of BNFP Site as MOX Fuel Supply Facility. Final report  

SciTech Connect (OSTI)

An evaluation was made of the technical feasibility, cost, and schedule for converting the existing unused Barnwell Nuclear Fuel Facility (BNFP) into a Mixed Oxide (MOX) CANDU fuel fabrication plant for disposition of excess weapons plutonium. This MOX fuel would be transported to Ontario where it would generate electricity in the Bruce CANDU reactors. Because CANDU MOX fuel operates at lower thermal load than natural uranium fuel, the MOX program can be licensed by AECB within 4.5 years, and actual Pu disposition in the Bruce reactors can begin in 2001. Ontario Hydro will have to be involved in the entire program. Cost is compared between BNFP and FMEF at Hanford for converting to a CANDU MOX facility.

NONE

1995-06-30T23:59:59.000Z

290

DOE - Office of Legacy Management -- Westinghouse Advanced Reactors...  

Office of Legacy Management (LM)

Advanced Reactors Div Plutonium and Advanced Fuel Labs - PA 10 FUSRAP Considered Sites Site: WESTINGHOUSE ADVANCED REACTORS DIV., PLUTONIUM FUEL LABORATORIES, AND THE ADVANCED FUEL...

291

Decision Summaries  

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

ohadecision-summaries Office of Hearings and Appeals 1000 Independence Ave., SW Washington, DC, 20585 202-287-1566 en Summary of Decisions - October 6, 2014 - October 10, 2014...

292

Site Treatment Plan For DOE Mixed Wastes At The Missouri University Research Reactor Columbia, Missouri, October 1995.  

Office of Legacy Management (LM)

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293

WSRC Reactor Tank Inspection Program (RTIP) status report  

SciTech Connect (OSTI)

Westinghouse Savannah River Company (WSRC) recently completed the initial phase of nondestructive inspections of the Savannah River Site`s (SRS) reactor tanks. This program required almost three years to be conceptualized, fabricated, and tested. An additional 20 months were required to complete the NDE inspection of the P, K and L reactor tanks. The overall cost of the program to date is approximately $25 MM. This status report will address: (1) A brief review of the RTIP program and the constraints which had to be overcome (2) A summary of the examination results of the P,K, and L Reactor tanks. (3) A projection of the future enhancements and capabilities presently in development.

Loibl, M.W.

1992-06-01T23:59:59.000Z

294

2013 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada; Review of the Performance Assessments and Composite Analyses  

SciTech Connect (OSTI)

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC 2007a) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs), with the results submitted to the U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE 1999a, 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2013. This annual summary report presents data and conclusions from the FY 2013 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2013 include the following: Development of a new Area 5 RWMS closure inventory estimate based on disposals through FY 2013 Evaluation of new or revised waste streams by special analysis Development of version 4.115 of the Area 5 RWMS GoldSim PA/CA model The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. The FY 2013 review of operations, facility design, closure plans, monitoring results, and R&D results for the Area 3 RWMS indicates no changes that would impact PA validity. The conclusion of the annual review is that all performance objectives can be met and the Area 3 RWMS PA remains valid. There is no need to the revise the Area 3 RWMS PA. Review of Area 5 RWMS operations, design, closure plans, monitoring results, and R&D activities indicates that no significant changes have occurred. The FY 2013 PA results, generated with the Area 5 RWMS v4.115 GoldSim PA model, indicate that there continues to be a reasonable expectation of meeting all performance objectives. The results and conclusions of the Area 5 RWMS PA are judged valid, and there is no need to the revise the PA. A review of changes potentially impacting the CAs indicates that no significant changes occurred in FY 2013. The continuing adequacy of the CAs was evaluated with the new models, and no significant changes that would alter the CAs results or conclusions were found. The revision of the Area 3 RWMS CA, which will include the Yucca Flat Underground Test Area (Corrective Action Unit [CAU] 97) source term, is scheduled for FY 2024, following the completion of the Corrective Action Decision Document/Corrective Action Plan in FY 2015. Inclusion of the Frenchman Flat Underground Test Area (CAU 98) results in the Area 5 RWMS CA is scheduled for FY 2016, pending the completion of the CAU 98 Closure Report in FY 2015. Near-term R&D efforts will focus on continuing development of the PA, CA, and inventory models for the Area 3 and Area 5 RWMS.

Shott, Gregory [NSTec] [NSTec

2014-03-01T23:59:59.000Z

295

2011 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses  

SciTech Connect (OSTI)

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC, 2007a) requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs), with the results submitted annually to U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE, 1999a; 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2011. This annual summary report presents data and conclusions from the FY 2011 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R and D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R and D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2011 include the following: (1) Operation of a new shallow land disposal unit and a new Resource Conservation and Recovery Act (RCRA)-compliant lined disposal unit at the Area 5 RWMS; (2) Development of new closure inventory estimates based on disposals through FY 2011; (3) Evaluation of new or revised waste streams by special analysis; (4) Development of version 2.102 of the Area 3 RWMS GoldSim PA model; and (5) Development of version 4.113 of the Area 5 RWMS GoldSim PA model. Analysis of the latest available data using the Area 5 RWMS v4.113 GoldSim PA model indicates that all performance objectives can be met. The results and conclusions of the Area 5 RWMS PA are judged valid, and there is no need to the revise the PA. The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. In FY 2011, there were no operational changes, monitoring results, or R and D results for the Area 3 RWMS that would impact PA validity. Despite the increase in waste volume and inventory at the Area 3 RWMS since 1996 when the PA was approved, the facility performance evaluated with the Area 3 RWMS PA GoldSim model, version 2.0 (with the final closure inventory), remains well below the performance objectives set forth in U.S. Department of Energy Order DOE O 435.1, 'Radioactive Waste Management' (DOE, 2001). The conclusions of the Area 3 RWMS PA remain valid. A special analysis was prepared to update the PA and CA results for the Area 3 RWMS in FY 2011. Release of the special analysis is planned for FY 2012. The continuing adequacy of the CAs was evaluated with the new models, and no significant changes that would alter CA results or conclusions were found. Inclusion of the Frenchman Flat Underground Test Area (UGTA) results in the Area 5 RWMS CA is scheduled for FY 2016, pending the completion of the closure report for the Frenchman Flat UGTA corrective action unit (CAU) in FY 2015. An industrial site, CAU 547, with corrective action sites near the Area 3 RWMS was found to have a significant plutonium inventory in 2009. CAU 547 will be evaluated for inclusion of future revisions or updates of the Area 3 RWMS CA. The revision of the Area 3 RWMS CA, which will include the UGTA source terms, is expected in FY 2024, following the completion of the Yucca Flat CAU Corrective Action Decision Document, scheduled for FY 2023. Near-term R and D efforts will focus on continuing development of the Are

NSTec Environmental Management

2012-03-20T23:59:59.000Z

296

Microchannel Reactor System Design & Demonstration For On-Site H2O2 Production by Controlled H2/O2 Reaction  

SciTech Connect (OSTI)

We successfully demonstrated an innovative hydrogen peroxide (H2O2) production concept which involved the development of flame- and explosion-resistant microchannel reactor system for energy efficient, cost-saving, on-site H2O2 production. We designed, fabricated, evaluated, and optimized a laboratory-scale microchannel reactor system for controlled direct combination of H2 and O2 in all proportions including explosive regime, at a low pressure and a low temperature to produce about 1.5 wt% H2O2 as proposed. In the second phase of the program, as a prelude to full-scale commercialization, we demonstrated our H2O2 production approach by numbering up the channels in a multi-channel microreactor-based pilot plant to produce 1 kg/h of H2O2 at 1.5 wt% as demanded by end-users of the developed technology. To our knowledge, we are the first group to accomplish this significant milestone. We identified the reaction pathways that comprise the process, and implemented rigorous mechanistic kinetic studies to obtain the kinetics of the three main dominant reactions. We are not aware of any such comprehensive kinetic studies for the direct combination process, either in a microreactor or any other reactor system. We showed that the mass transfer parameter in our microreactor system is several orders of magnitude higher than what obtains in the macroreactor, attesting to the superior performance of microreactor. A one-dimensional reactor model incorporating the kinetics information enabled us to clarify certain important aspects of the chemistry of the direct combination process as detailed in section 5 of this report. Also, through mathematical modeling and simulation using sophisticated and robust commercial software packages, we were able to elucidate the hydrodynamics of the complex multiphase flows that take place in the microchannel. In conjunction with the kinetics information, we were able to validate the experimental data. If fully implemented across the whole industry as a result of our technology demonstration, our production concept is expected to save >5 trillion Btu/year of steam usage and >3 trillion Btu/year in electric power consumption. Our analysis also indicates >50 % reduction in waste disposal cost and ~10% reduction in feedstock energy. These savings translate to ~30% reduction in overall production and transportation costs for the $1B annual H2O2 market.

Adeniyi Lawal

2008-12-09T23:59:59.000Z

297

Hanford Site  

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

Reactor under construction.1944.jpg Gallery: B Reactor Title: B Reactor Construction B Reactor Construction Name: B Reactor Construction Keywords: B Reactor, construction Official...

298

2012 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses  

SciTech Connect (OSTI)

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC 2007a) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs), with the results submitted to the U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE 1999a, 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2012. This annual summary report presents data and conclusions from the FY 2012 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2012 include the following: ? Release of a special analysis for the Area 3 RWMS assessing the continuing validity of the PA and CA ? Development of a new Area 5 RWMS closure inventory estimate based on disposals through FY 2012 ? Evaluation of new or revised waste streams by special analysis ? Development of version 4.114 of the Area 5 RWMS GoldSim PA model The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. The FY 2012 review of operations, facility design, closure plans, monitoring results, and R&D results for the Area 3 RWMS indicates no changes that would impact PA validity. A special analysis using the Area 3 RWMS v2.102 GoldSim PA model was prepared to update the PA results for the Area 3 RWMS in FY 2012. The special analysis concludes that all performance objectives can be met and the Area 3 RWMS PA remains valid. There is no need to the revise the Area 3 RWMS PA. Review of Area 5 RWMS operations, design, closure plans, monitoring results, and R&D activities indicates no significant changes other than an increase in the inventory disposed. The FY 2012 PA results, generated with the Area 5 RWMS v4.114 GoldSim PA model, indicate that there continues to be a reasonable expectation of meeting all performance objectives. The results and conclusions of the Area 5 RWMS PA are judged valid, and there is no need to the revise the PA. A review of changes potentially impacting the CAs indicates that no significant changes occurred in FY 2012. The continuing adequacy of the CAs was evaluated with the new models, and no significant changes that would alter CA results or conclusions were found. The revision of the Area 3 RWMS CA, which will include the Underground Test Area source term (Corrective Action Unit [CAU] 97), is scheduled for FY 2024, following the completion of the Yucca Flat CAU 97 Corrective Action Decision Document/Corrective Action Plan in FY 2016. Inclusion of the Frenchman Flat CAU 98 results in the Area 5 RWMS CA is scheduled for FY 2016, pending the completion of the CAU 98 closure report in FY 2015. Near-term R&D efforts will focus on continuing development of the Area 3 and Area 5 RWMS GoldSim PA/CA and inventory models.

Shott, G. [National Security Technologies, LLC

2013-03-18T23:59:59.000Z

299

Experience in Remote Demolition of the Activated Biological Shielding of the Multi Purpose Research Reactor (MZFR) on the German Karlsruhe Site - 12208  

SciTech Connect (OSTI)

In 2009, WAK Decommissioning and Waste Management GmbH (WAK) became owner and operator of the waste treatment facilities of Karlsruhe Institute of Technology (KIT) as well as of the prototype reactors, the Compact Sodium-Cooled Fast Reactor (KNK) and Multi-Purpose Reactor (MZFR), both being in an advanced stage of dismantling. Together with the dismantling and decontamination activities of the former WAK reprocessing facility since 1990, the envisaged demolishing of the R and D reactor FR2 and a hot cell facility, all governmentally funded nuclear decommissioning projects on the Karlsruhe site are concentrated under the WAK management. The small space typical of prototype research reactors represented a challenge also during the last phase of activated dismantling, dismantling of the activated biological shield of the MZFR. Successful demolition of the biological shield required detailed planning and extensive testing in the years before. In view of the limited space and the ambient dose rate that was too high for manual work, it was required to find a tool carrier system to take up and control various demolition and dismantling tools in a remote manner. The strategy formulated in the concept of dismantling the biological shield by means of a modified electro-hydraulic demolition excavator in an adaptable working scaffolding turned out to be feasible. The following boundary conditions were essential: - Remote exchange of the dismantling and removal tools in smallest space. - Positioning of various supply facilities on the working platform. - Avoiding of interfering edges. - Optimization of mass flow (removal of the dismantled mass from the working area). - Maintenance in the surroundings of the dismantling area (in the controlled area). - Testing and qualification of the facilities and training of the staff. Both the dismantling technique chosen and the proceeding selected proved to be successful. Using various designs of universal cutters developed on the basis of wall saws, both the activated steel liner and the inner reinforcing layer were cut remotely in one process. This allowed for the efficient execution of the following remote concrete removal steps using mining techniques. The electro-hydraulic demolition excavator that was purchased and then modified turned out to be an ideal tool carrier system with rapid-exchange coupling. Due to the high availability, no major delays occurred. This also was a result of the consistently implemented maintenance and repair concept. With the excavator installed in a modifiable scaffolding suspended from a rotating carrier ring, all dismantling areas could be reached and treated in spite of the small space. Thanks to an optimum organization of work-flows, routine change of dismantling work, and maintenance or repair, the iterative radiological measurement campaigns could be integrated in the whole activity without the dismantling work being disturbed significantly. The ventilation system with pressure grading and pre-filtration units ensured a low contamination level in the dismantling area. It was also possible to manage the dust formed by the milling of concrete surfaces. As it was possible to further cut metal parts and crushed concrete later on, residue flows were optimized. The planned overall period for testing, dismantling the bio-shield and removing the equipment was 36 months. The final duration was 39 months. (authors)

Eisenmann, Beata; Fleisch, Joachim; Prechtl, Erwin; Suessdorf, Werner; Urban, Manfred [WAK Rueckbau- und Entsorgungs- GmbH, P.O.Box 12 63, 76339 Eggenstein-Leopoldshafen (Germany)

2012-07-01T23:59:59.000Z

300

E-Print Network 3.0 - arsenal production reactor Sample Search...  

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

Processing Based On Summary: Fabrication of Integrated Unit Operation of ACR Reactors Optimization of ACR Reactor Operation Production... of Continuous H2 Stream Shift and PrOx...

Note: This page contains sample records for the topic "reactor site summary" 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

E-Print Network 3.0 - aged reactor pressure Sample Search Results  

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

effort Summary: plan to build a 5 billion fusion reactor, called the International Thermonuclear Experimental Reactor... could be achieved in 35 years. "By the time our young...

302

E-Print Network 3.0 - aerospace system test reactor Sample Search...  

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

Engineering 15 www.eprg.group.cam.ac.uk EPRGWORKINGPAPER Summary: Accelerator-Driven Subcritical Reactor Park Michel-Alexandre Cardin1 Engineering Systems Division... and reactor...

303

Meeting Summary Notes  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel2007Naval Reactors'InformationSOLARMedicalJulyMinutes:

304

P Reactor Grouting  

SciTech Connect (OSTI)

Filling the P Reactor with grout. This seals the radioactive material and reduces the environmental footprint left from the Cold War. Project sponsored by the Recovery Act at the Savannah River Site.

None

2010-01-01T23:59:59.000Z

305

RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2012, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101, issued 10/17/10.

,

2013-02-21T23:59:59.000Z

306

Gulf Coast geopressured-geothermal program summary report compilation. Volume 2-B: Resource description, program history, wells tested, university and company based research, site restoration  

SciTech Connect (OSTI)

The US Department of Energy established a geopressured-geothermal energy program in the mid 1970`s as one response to America`s need to develop alternate energy resources in view of the increasing dependence on imported fossil fuel energy. This program continued for 17 years and approximately two hundred million dollars were expended for various types of research and well testing to thoroughly investigate this alternative energy source. This volume describes the following studies: Design well program; LaFourche Crossing; MG-T/DOE Amoco Fee No. 1 (Sweet Lake); Environmental monitoring at Sweet Lake; Air quality; Water quality; Microseismic monitoring; Subsidence; Dow/DOE L.R. Sweezy No. 1 well; Reservoir testing; Environmental monitoring at Parcperdue; Air monitoring; Water runoff; Groundwater; Microseismic events; Subsidence; Environmental consideration at site; Gladys McCall No. 1 well; Test results of Gladys McCall; Hydrocarbons in production gas and brine; Environmental monitoring at the Gladys McCall site; Pleasant Bayou No. 2 well; Pleasant Bayou hybrid power system; Environmental monitoring at Pleasant Bayou; and Plug abandonment and well site restoration of three geopressured-geothermal test sites. 197 figs., 64 tabs.

John, C.J.; Maciasz, G.; Harder, B.J.

1998-06-01T23:59:59.000Z

307

Erosion Potential of a Burn Site in the Mojave-Great Basin Transition Zone: Interim Summary of One Year of Measurements  

SciTech Connect (OSTI)

A historic return interval of 100 years for large fires in deserts in the Southwest U.S. is being replaced by one where fires may reoccur as frequently as every 20 to 30 years. This increase in fires has implications for management of Soil Sub-Project Corrective Action Units (CAUs) for which the Department of Energy, National Nuclear Security Administration Nevada Site office (NNSA/NSO) has responsibility. A series of studies has been initiated at uncontaminated analog sites to better understand the possible impacts of erosion and transport by wind and water should contaminated soil sites burn over to understand technical and perceived risk they might pose to site workers and public receptors in communities around the NTS, TTR, and NTTR; and to develop recommendations for stabilization and restoration after a fire. The first of these studies was undertaken at the Jacob fire, a lightning-caused fire approximately 12 kilometers north of Hiko, Nevada, that burned approximately 200 ha between August 6-8, 2008, and is representative of a transition zone on the NTS between the Mojave and Great Basin Deserts, where the largest number of Soil Sub-Project CAUs/CASs are located.

V. Etyemezian, D. Shafer, J. Miller, I. Kavouras, S. Campbell, D. DuBois, J. King, G. Nikolich, and S. Zitzer

2010-05-18T23:59:59.000Z

308

E-Print Network 3.0 - aerated biofilm reactor Sample Search Results  

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

bulk liquid BOD concentration on activity Summary: Nitrification . Denitrification . Wastewater. BOD inhibition . Membrane-aerated biofilm reactor. Membrane... aerated biofilm...

309

active site zn: Topics by E-print Network  

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

John Copeland Ellingson, Steven W. 30 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

310

active site confers: Topics by E-print Network  

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

fee Lodging Giles, C. Lee 29 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

311

active site mutant: Topics by E-print Network  

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

John Copeland Ellingson, Steven W. 39 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

312

active site mutations: Topics by E-print Network  

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

In contrast van Aalten, Daan 57 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

313

active site mutants: Topics by E-print Network  

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

John Copeland Ellingson, Steven W. 39 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

314

active site tryptic: Topics by E-print Network  

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

John Copeland Ellingson, Steven W. 18 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

315

active site serine: Topics by E-print Network  

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

John Copeland Ellingson, Steven W. 33 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

316

20% Wind Energy by 2030 - Chapter 5: Wind Power Siting and Environment...  

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

5: Wind Power Siting and Environmental Effects Summary Slides 20% Wind Energy by 2030 - Chapter 5: Wind Power Siting and Environmental Effects Summary Slides Environment and siting...

317

Gulf Coast geopressured-geothermal program summary report compilation. Volume 2-A: Resource description, program history, wells tested, university and company based research, site restoration  

SciTech Connect (OSTI)

The US Department of Energy established a geopressured-geothermal energy program in the mid 1970`s as one response to America`s need to develop alternate energy resources in view of the increasing dependence on imported fossil fuel energy. This program continued for 17 years and approximately two hundred million dollars were expended for various types of research and well testing to thoroughly investigate this alternative energy source. This volume describes the following studies: Geopressured-geothermal resource description; Resource origin and sediment type; Gulf Coast resource extent; Resource estimates; Project history; Authorizing legislation; Program objectives; Perceived constraints; Program activities and structure; Well testing; Program management; Program cost summary; Funding history; Resource characterization; Wells of opportunity; Edna Delcambre No. 1 well; Edna Delcambre well recompletion; Fairfax Foster Sutter No. 2 well; Beulah Simon No. 2 well; P.E. Girouard No. 1 well; Prairie Canal No. 1 well; Crown Zellerbach No. 2 well; Alice C. Plantation No. 2 well; Tenneco Fee N No. 1 well; Pauline Kraft No. 1 well; Saldana well No. 2; G.M. Koelemay well No. 1; Willis Hulin No. 1 well; Investigations of other wells of opportunity; Clovis A. Kennedy No. 1 well; Watkins-Miller No. 1 well; Lucien J. Richard et al No. 1 well; and the C and K-Frank A. Godchaux, III, well No. 1.

John, C.J.; Maciasz, G.; Harder, B.J.

1998-06-01T23:59:59.000Z

318

Reactor Physics  

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

Reactor Physics Reactor and nuclear physics is a key area of research at INL. Much of the research done in reactor physics can be separated into one of three categories:...

319

akm reactor: Topics by E-print Network  

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

the flux calculation and recent progresses. Jun Cao 2012-03-08 9 Inexpensive Mini Thermonuclear Reactor CiteSeer Summary: This proposed design for a mini thermonuclear reactor...

320

akm muehleberg reactor: Topics by E-print Network  

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

the flux calculation and recent progresses. Jun Cao 2012-03-08 9 Inexpensive Mini Thermonuclear Reactor CiteSeer Summary: This proposed design for a mini thermonuclear reactor...

Note: This page contains sample records for the topic "reactor site summary" 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

almaraz-2 reactor: Topics by E-print Network  

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

the flux calculation and recent progresses. Jun Cao 2012-03-08 5 Inexpensive Mini Thermonuclear Reactor CiteSeer Summary: This proposed design for a mini thermonuclear reactor...

322

almaraz-1 reactor: Topics by E-print Network  

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

the flux calculation and recent progresses. Jun Cao 2012-03-08 5 Inexpensive Mini Thermonuclear Reactor CiteSeer Summary: This proposed design for a mini thermonuclear reactor...

323

Site characterization summary report for Waste Area Grouping 10 Wells at the Old Hydrofracture Facility, Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the Department of Energy (DOE) by Martin Marietta Energy Systems (Energy Systems). As part of its DOE mission, ORNL has pioneered waste disposal technologies throughout the years of site operations since World War II. In the late 1950s, efforts were made to develop a permanent disposal alternative to the surface impoundments at ORNL at the request of the National Academy of Sciences. One such technology, the hydrofracture process, involved forming fractures in an underlying geologic host formation (a low-permeability shale) at depths of up to 1000 ft and subsequently injecting a grout slurry containing low-level liquid waste, cement, and other additives at an injection pressure of about 2000 psi. The objective of the effort was to develop a grout slurry that could be injected as a liquid but would solidify after injection, thereby immobilizing the radioisotopes contained in the low-level liquid waste. The scope of this site characterization was the access, sampling, logging, and evaluation of observation wells near the Old Hydrofracture Facility (OHF) in preparation for plugging, recompletion, or other final disposition of the wells.

NONE

1995-03-01T23:59:59.000Z

324

Summary of comments received at workshop on use of a Site Specific Advisory Board (SSAB) to facilitate public participation in decommissioning cases  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As part of this rulemaking, On August 20, 1994 the NRC published a proposed rule for public comment. Paragraph 20.1406(b) of the proposed rule would require that the licensee convene a Site Specific Advisory Board (SSAB) if the licensee proposed release of the site for restricted use after decommissioning. To encourage comment the NRC held a workshop on the subject of $SABs on December 6, 7, and 8, 1994. This report summarizes the 567 comments categorized from the transcript of the workshop. The commenters at the workshop generally supported public participation in decommissioning cases. Many participants favored promulgating requirements in the NRC`s rules. Some industry participants favored relying on voluntary exchanges between the public and the licensees. Many participants indicated that a SSAB or something functionally equivalent is needed in controversial decommissioning cases, but that some lesser undertaking can achieve meaningful public participation in other cases. No analysis or response to the comments is included in this report.

Caplin, J.; Padge, G.; Smith, D.; Wiblin, C. [Advanced Systems Technology, Inc., Rockville, MD (United States)

1995-06-01T23:59:59.000Z

325

Animal Investigation Program (AIP), A.I.P. summary report on and around the Nevada Test Site from 1982--1995  

SciTech Connect (OSTI)

This report describes the Animal Investigation Program conducted from 1982--1995 by the Environmental Protection Agency`s (EPA`s), Radiation and Indoor Environments National Laboratory (R and IE), formerly Radiation Sciences Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site. The surveillance program was designed to measure levels and trends of radionuclides in animals on and around the Nevada Test Site to ascertain whether world-wide fallout, current radiation levels, and associated doses, to the general public were in compliance with existing radiation protection standards. The surveillance program additionally had the responsibility to take action to protect the health and well-being of the public in the event of any accidental release of radioactive contaminants. Comparison of the measurements and sample analysis results indicated that no significant amounts of biological radionuclides had been detected in the near offsite areas or on the NTS, except in animals drinking water that drains from tunnels in Area 12.

Giles, K.R.

1997-04-01T23:59:59.000Z

326

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSite

327

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSite January 12,

328

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSite January 12,

329

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSite January

330

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSite JanuaryJune

331

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSite JanuaryJune3

332

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSite

333

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSiteOak Ridge

334

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSiteOak Ridge2:

335

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSiteOak Ridge2:3:

336

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSiteOak

337

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSiteOakJanuary

338

Oak Ridge Site Specific Advisory Board  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSiteOakJanuary4

339

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

Broader source: Energy.gov [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.

340

Site Feeds - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearchScheduled System OutagesNewsMaterialsX-rayOur‹Simulation,Site

Note: This page contains sample records for the topic "reactor site summary" 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

Summary o  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C.Green River, Utah,Tuba City,'1Dear

342

EXECUTIVE SUMMARY  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartmentStewardshipAdministration|Securityr EEO Complaint

343

EFRC Summary  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Region service area. The DesertDirectionsWorkplaceResearch

344

Executive Summary  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Region service area. TheEPSCI Home It isGasERP Submit an

345

Savannah River Site Waste Isolation Pilot Plant Disposal Program - Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221-HET  

SciTech Connect (OSTI)

This document, along with referenced supporting documents provides a defensible and auditable record of acceptable knowledge for one of the waste streams from the FB-Line. This heterogeneous debris transuranic waste stream was generated after January 25, 1990 and before March 20, 1997. The waste was packaged in 55-gallon drums, then shipped to the transuranic waste storage facility in ''E'' area of the Savannah River Site. This acceptable knowledge report includes information relating to the facility's history, configuration, equipment, process operations and waste management practices. Information contained in this report was obtained from numerous sources including: facility safety basis documentation, historical document archives, generator and storage facility waste records and documents, and interviews with cognizant personnel.

Lunsford, G.F.

2001-01-24T23:59:59.000Z

346

Reactor operation environmental information document  

SciTech Connect (OSTI)

The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

1989-12-01T23:59:59.000Z

347

Hanford Site  

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

Gallery: B Reactor Title: B Reactor B Reactor Name: B Reactor Keywords: B Reactor, World War II Official Building Numbers: B Reactor Area: 100BC Description: In this photo from...

348

aplicacion al reactor: Topics by E-print Network  

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

Summary: Anti-neutrino emission rates from nuclear reactors are determined from thermal power measurements and fission rate calculations. The uncertainties in these...

349

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTFIrrigationBasin Waste SiteReactor

350

alpine site jungfraujoch: Topics by E-print Network  

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

commercial setting. Contaminants: Contaminants: Vinyl Chloride 166 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

351

allosteric site: Topics by E-print Network  

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

commercial setting. Contaminants: Contaminants: Vinyl Chloride 69 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

352

affect redd site: Topics by E-print Network  

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

commercial setting. Contaminants: Contaminants: Vinyl Chloride 62 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

353

agnostic splice site: Topics by E-print Network  

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

commercial setting. Contaminants: Contaminants: Vinyl Chloride 279 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

354

Summary and evaluation of existing geological and geophysical data near prospective surface facilities in Midway Valley, Yucca Mountain Project, Nye County, Nevada; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

Midway Valley, located at the eastern base of the Yucca Mountain in southwestern Nevada, is the preferred location of the surface facilities for the potential high-level nuclear waste repository at Yucca Mountain. One goal in siting these surface facilities is to avoid faults that could produce relative displacements in excess of 5 cm in the foundations of the waste-handling buildings. This study reviews existing geologic and geophysical data that can be used to assess the potential for surface fault rupture within Midway Valley. Dominant tectonic features in Midway Valley are north-trending, westward-dipping normal faults along the margins of the valley: the Bow Ridge fault to the west and the Paintbrush Canyon fault to the east. Published estimates of average Quaternary slip rates for these faults are very low but the age of most recent displacement and the amount of displacement per event are largely unknown. Surface mapping and interpretive cross sections, based on limited drillhole and geophysical data, suggest that additional normal faults, including the postulated Midway Valley fault, may exist beneath the Quaternary/Tertiary fill within the valley. Existing data, however, are inadequate to determine the location, recency, and geometry of this faulting. To confidently assess the potential for significant Quaternary faulting in Midway Valley, additional data are needed that define the stratigraphy and structure of the strata beneath the valley, characterize the Quaternary soils and surfaces, and establish the age of faulting. The use of new and improved geophysical techniques, combined with a drilling program, offers the greatest potential for resolving subsurface structure in the valley. Mapping of surficial geologic units and logging of soil pits and trenches within these units must be completed, using accepted state-of-the-art practices supported by multiple quantitative numerical and relative age-dating techniques.

Gibson, J.D. [Sandia National Labs., Albuquerque, NM (United States); Swan, F.H.; Wesling, J.R.; Bullard, T.F.; Perman, R.C.; Angell, M.M.; DiSilvestro, L.A. [Geomatrix Consultants, Inc., San Francisco, CA (United States)

1992-01-01T23:59:59.000Z

355

Progress Update: P&R Reactor Stacks Demolition  

SciTech Connect (OSTI)

October 2010 progress update of the Recovery Act at work at the Savannah River Site. The demolition of nuclear reactor stacks and filling the reactors with grout to reduce the site footprint.

Cody, Tom

2010-01-01T23:59:59.000Z

356

Progress Update: P&R Reactor Stacks Demolition  

ScienceCinema (OSTI)

October 2010 progress update of the Recovery Act at work at the Savannah River Site. The demolition of nuclear reactor stacks and filling the reactors with grout to reduce the site footprint.

Cody, Tom

2012-06-14T23:59:59.000Z

357

Critical Materials Strategy Summary  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana. DOCUMENTS AVAILABLEReport 2009Site | Department of Energyto Partnering |

358

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Region service area. TheEPSCIResearchGulf ofnewsFlash F Reactor

359

Chair Summaries  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation SitesStanding FriedelIron-Sulfur Protein DomainSSRLChain Tsuan

360

Heavy Water Test Reactor Dome Removal  

SciTech Connect (OSTI)

A high speed look at the removal of the Heavy Water Test Reactor Dome Removal. A project sponsored by the Recovery Act on the Savannah River Site.

None

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor site summary" 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

Progress Update: P-Reactor Grout  

SciTech Connect (OSTI)

A progress update, the Recovery Act at work at the Savannah River Site. The new phase of work on the permanent closure of two cold war nuclear reactors.

Cody, Tom

2010-01-01T23:59:59.000Z

362

Progress Update: P-Reactor Grout  

ScienceCinema (OSTI)

A progress update, the Recovery Act at work at the Savannah River Site. The new phase of work on the permanent closure of two cold war nuclear reactors.

Cody, Tom

2012-06-14T23:59:59.000Z

363

Recovery Act Progress Update: Reactor Closure Feature  

SciTech Connect (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

2010-01-01T23:59:59.000Z

364

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

365

NGNP SITE 2 HAZARDS ASSESSMENT  

SciTech Connect (OSTI)

The Next Generation Nuclear Plant (NGNP) Project initiated at Idaho National Laboratory (INL) by the U.S. Department of Energy pursuant to the 2005 Energy Policy Act, is based on research and development activities supported by the Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of the high temperature gas-cooled reactor (HTGR) technology. The HTGR is a helium-cooled and graphite-moderated reactor that can operate at temperatures much higher than those of conventional light water reactor (LWR) technologies. Accordingly, it can be applied in many industrial applications as a substitute for burning fossil fuels, such as natural gas, to generate process heat in addition to producing electricity, which is the principal application of current LWRs. Nuclear energy in the form of LWRs has been used in the U.S. and internationally principally for the generation of electricity. However, because the HTGR operates at higher temperatures than LWRs, it can be used to displace the use of fossil fuels in many industrial applications. It also provides a carbon emission-free energy supply. For example, the energy needs for the recovery and refining of petroleum, for the petrochemical industry and for production of transportation fuels and feedstocks using coal conversion processes require process heat provided at temperatures approaching 800 C. This temperature range is readily achieved by the HTGR technology. This report summarizes a site assessment authorized by INL under the NGNP Project to determine hazards and potential challenges that site owners and HTGR designers need to be aware of when developing the HTGR design for co-location at industrial facilities, and to evaluate the site for suitability considering certain site characteristics. The objectives of the NGNP site hazard assessments are to do an initial screening of representative sites in order to identify potential challenges and restraints to be addressed in design and licensing processes; assure the HTGR technology can be deployed at variety of sites for a range of applications; evaluate potential sites for potential hazards and describe some of the actions necessary to mitigate impacts of hazards; and, provide key insights that can inform the plant design process. The report presents a summary of the process methodology and the results of an assessment of hazards typical of a class of candidate sites for the potential deployment of HTGR reactor technology. The assessment considered health and safety, and other important siting characteristics to determine the potential impact of identified hazards and potential challenges presented by the location for this technology. A four reactor module nuclear plant (2000 to 2400 MW thermal), that co-generates steam, electricity for general use in the plant, and hot gas for use in a nearby chemical processing facility, to provide the requisite performance and reliability was assumed for the assessment.

Wayne Moe

2011-10-01T23:59:59.000Z

366

Hanford Site Tours - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Region service area. TheEPSCIResearchGulf ofnewsFlash F ReactorHanford

367

Hanford Site  

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

Control room desk.excellent.1.07.jpg Gallery: B Reactor Title: B Reactor Control Room B Reactor Control Room Name: B Reactor Control Room Keywords: B Reactor, control room, chair...

368

SNAP and AI Fuel Summary Report  

SciTech Connect (OSTI)

The SNAP and AI Fuel Summary Report provides a detailed overview of treatment and storage of these fuels from fabrication through current storage including design parameters and reactor history. Chemical and physical characteristics are described, and potential indicators of as-stored fuel conditions are emphasized.

Lords, R.E.

1994-08-01T23:59:59.000Z

369

CSMRI SITE PROJECT SUMMARY November 2010  

E-Print Network [OSTI]

the source, nature and extent of contamination that is resulting in elevated levels of uranium in ground to be below the high water level for creek-influenced ground water the fill is a rock and soil mix from a local quarry. Clean topsoil from the School's campus is being used above the rock and soil mix

370

Savannah River Site Patented Technologies Summaries  

SciTech Connect (OSTI)

This information represents SRS`s contribution of the DOE technology information network, an internet service coordinated out of Los Alamos. The information provided is strictly DOE-SR-titled and-issued patented technologies including environmental remediation, robotics, sensors, materials science, biomedical applications, hydrogen, and consumer products.

Rabold, D.E.

1995-07-18T23:59:59.000Z

371

2008 Annual Site Environmental Report Summary Pamphlet  

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

according to DOE Order 450.1A * and funding was obtained to gain International Standardization Organization (ISO) 14001 certification in FY09; A report on the Baseline...

372

River and Plateau Committee Summaries - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar HomePromisingStories »SubmitterJ. Norby (2007)Rising SeaProjects

373

Appendix A Annotated Executive Summary  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North Site Unit3.1WOMPOC:07MAR

374

Part II: Project Summaries Project Summaries  

E-Print Network [OSTI]

Part II: Project Summaries Part II Project Summaries #12 generally cannot be achieved for reasonable computational cost. Applications that require modeling, and in nondestructive testing. The objective of this project is to advance the state of the art in electromagnetic

Perkins, Richard A.

375

Student FTE Summary Student FTE Summary  

E-Print Network [OSTI]

Student FTE Summary Fall 2010 #12;1 Student FTE Summary Fall Term 2010 Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3 Percentage of Student FTE by College. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3 Student FTE by Student Level

376

E-Print Network 3.0 - aries-rs fusion reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor... realize the Japanese proposed site for the...

377

Site Transition Process upon Completion of the Cleanup Mission...  

Office of Environmental Management (EM)

218: Develop a Fact Sheet on Site Transition at On-going Mission Sites Site Transition Summary: Cleanup Completion to Long-Term Stewardship at Department of Energy...

378

Hanford Site Development Plan  

SciTech Connect (OSTI)

The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs.

Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J. (Westinghouse Hanford Co., Richland, WA (USA)); Yancey, E.F. (Pacific Northwest Lab., Richland, WA (USA))

1990-01-01T23:59:59.000Z

379

E-Print Network 3.0 - athene reactor Sample Search Results  

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

which country... will host a nuclear fusion reactor for the International Thermonuclear Experimental Reactor (ITER) project... . The candidate sites for the international...

380

Geothermal: Sponsored by OSTI -- Summary of Historical Production...  

Office of Scientific and Technical Information (OSTI)

Summary of Historical Production for Nevada Binary Facilities Geothermal Technologies Legacy Collection HelpFAQ | Site Map | Contact Us | Admin Log On HomeBasic Search About...

Note: This page contains sample records for the topic "reactor site summary" 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

F Reactor Inspection  

SciTech Connect (OSTI)

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

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-10-29T23:59:59.000Z

382

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

383

Probabilistic risk assessment of the N Reactor using NUREG-1150 methods  

SciTech Connect (OSTI)

A level-III probabilistic risk assessment (PRA) has been performed for N Reactor, a US Department of Energy (DOE) reactor located on the Hanford site in Washington state. The methods developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL) in support of the NUREG-1150 effort were adapted for the analysis. The objectives of the study are to assess the risks to the public (off-site) and to workers at colocated DOE facilities (on-site) posed by the operation of N reactor, compare those risks to proposed DOE safety guidelines and NRC safety goals, and identify changes to the plant for safety enhancement. This summary is based on results from internally initiated events only. Off-site risk resulted from externally initiated events and on-site risk will be reported at a later date. The entire study is based on best-estimate inputs except that a number of areas, such as source term inventory and progression of metal/water reaction, apply conservative assumptions.

Wang, O.S.; Coles, G.A.; Zentner, M.D.; Powers, T.B.; Baxter, J.T.

1989-01-01T23:59:59.000Z

384

Annual Site EnvironmentalAnnual Site Environmental ReportReport  

E-Print Network [OSTI]

) .................................................8 3.1.3 National Environmental Policy Act (NEPA#12;Annual Site EnvironmentalAnnual Site Environmental ReportReport for Calendar Year1997 ENVIRONMENTAL REPORT Table of Contents Page 1.0 EXECUTIVE SUMMARY

385

E-Print Network 3.0 - administration nevada site Sample Search...  

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

Summary: National Security Site (formerly the Nevada Test Site). This effort will bring NSTec nuclear physicists... Nevada Test Site, now called the Nevada National Security Site,...

386

Oak Ridge Site Specific Advisory Board Annual Meeting  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor TechnologyOFFICE: I Oak Ridge, TennesseeSiteOakJanuary4

387

E-Print Network 3.0 - aecl radiochemical slowpoke reactor Sample...  

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

of 238Puand239+240 Summary: of radiochemical procedures for the analysis of americium and curium in samples of reactor cooling water... at the Barse- bck Reactor. Ris-R-356. 16...

388

E-Print Network 3.0 - argonne high flux reactor Sample Search...  

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

for: argonne high flux reactor Page: << < 1 2 3 4 5 > >> 1 Thirteenth National School on Neutron and X-ray Scattering Summary: Neutron Source and High Flux Isotope Reactor...

389

E-Print Network 3.0 - acidogenic anaerobic reactor Sample Search...  

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

Summary: anaerobic digestion in the inlet of the pre-treatment zone of a plug-flow biogas reactor for biomass... -flow anaerobic reactor for domestic organic waste treatment...

390

Document Number Q0029500 Summary and Conclusions  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North SiteD&Dir^0Summary and

391

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSite visit EdBoard3

392

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSite visit

393

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSite visitARRA

394

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSite

395

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSiteSubcontract for

396

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSiteSubcontract

397

Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTFIrrigationBasin Waste Site

398

Part II: Project Summaries Project Summaries  

E-Print Network [OSTI]

Part II: Project Summaries Part II Project Summaries #12;22 Math & Computational Sciences Division generally cannot be achieved for reasonable computational cost. Applications that require modeling of this project is to advance the state of the art in electromagnetic computations by eliminating three existing

Perkins, Richard A.

399

Nuclear power reactor education and training at the Ford nuclear reactor  

SciTech Connect (OSTI)

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

400

REACTOR GROUT THERMAL PROPERTIES  

SciTech Connect (OSTI)

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

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

2011-01-28T23:59:59.000Z

Note: This page contains sample records for the topic "reactor site summary" 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

activity-dependent polyadenylation site: Topics by E-print Network  

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

commercial setting. Contaminants: Contaminants: Vinyl Chloride 37 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

402

allosteric citalopram-binding site: Topics by E-print Network  

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

commercial setting. Contaminants: Contaminants: Vinyl Chloride 69 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

403

adenine dinucleotide-binding site: Topics by E-print Network  

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

commercial setting. Contaminants: Contaminants: Vinyl Chloride 43 Clinical Research Site Management Engineering Websites Summary: Clinical Research Site Management Dan...

404

E-Print Network 3.0 - allens creek-1 reactor Sample Search Results  

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

Centre de mathmatiques Collection: Mathematics 96 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

405

E-Print Network 3.0 - argentine reactor ra-8 Sample Search Results  

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Centre de mathmatiques Collection: Mathematics 88 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

406

E-Print Network 3.0 - argentine reactor ra-3 Sample Search Results  

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Centre de mathmatiques Collection: Mathematics 93 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

407

E-Print Network 3.0 - acpr reactor Sample Search Results  

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Centre de mathmatiques Collection: Mathematics 99 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

408

E-Print Network 3.0 - annular reactor system Sample Search Results  

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

University Collection: Engineering ; Physics 95 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

409

E-Print Network 3.0 - alto lazio-2 reactor Sample Search Results  

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

Centre de mathmatiques Collection: Mathematics 69 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

410

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

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Centre de mathmatiques Collection: Mathematics 89 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

411

E-Print Network 3.0 - autonomous reactor sstar Sample Search...  

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Centre de mathmatiques Collection: Mathematics 87 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

412

E-Print Network 3.0 - avogadro rs-1 reactor Sample Search Results  

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Centre de mathmatiques Collection: Mathematics 88 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

413

E-Print Network 3.0 - argus reactor Sample Search Results  

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Centre de mathmatiques Collection: Mathematics 92 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

414

E-Print Network 3.0 - astr reactor Sample Search Results  

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Centre de mathmatiques Collection: Mathematics 91 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

415

E-Print Network 3.0 - argentine reactor ra-4 Sample Search Results  

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Centre de mathmatiques Collection: Mathematics 88 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

416

E-Print Network 3.0 - alto lazio-1 reactor Sample Search Results  

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

Centre de mathmatiques Collection: Mathematics 68 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

417

E-Print Network 3.0 - allens creek-2 reactor Sample Search Results  

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

Centre de mathmatiques Collection: Mathematics 92 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

418

E-Print Network 3.0 - argonauta rio reactor Sample Search Results  

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

Centre de mathmatiques Collection: Mathematics 91 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

419

E-Print Network 3.0 - apra reactor Sample Search Results  

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Centre de mathmatiques Collection: Mathematics 86 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

420

E-Print Network 3.0 - austrian triga-mark-ii reactor Sample Search...  

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

Centre de mathmatiques Collection: Mathematics 94 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

Note: This page contains sample records for the topic "reactor site summary" 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

E-Print Network 3.0 - astra reactor Sample Search Results  

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

Centre de mathmatiques Collection: Mathematics 100 Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor Summary: Proposed Program:...

422

E-Print Network 3.0 - a-2 reactor bohunice Sample Search Results  

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Collection: Multidisciplinary Databases and Resources 16 Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina) Summary: :www.iaea.orgworldatom...

423

E-Print Network 3.0 - accelerator driven reactors Sample Search...  

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of Point Kinetics for the Analysis of Accelerator Driven Systems Summary: Perturbation Theory and Reactor Kinetics: From Wigner's Pile Period to Accelerator Driven Systems,"...

424

E-Print Network 3.0 - air-cooled graphite reactors Sample Search...  

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kernesikkerhedsforskning Norrnar kjarnryggisrannsknir Summary: the Nordic region. Windscale2 Two air-cooled graphite moderated metal U reactors operated at Windscale from......

425

E-Print Network 3.0 - automated microfluidic reactor Sample Search...  

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for: automated microfluidic reactor Page: << < 1 2 3 4 5 > >> 1 Applications of microfluidics in chemical biology Douglas B Weibel1 Summary: of laboratory instruments....

426

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

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

427

E-Print Network 3.0 - argonaut eindhoven reactor Sample Search...  

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Engineering, University of Kentucky Collection: Mathematics 14 PYROLYSIS, THERMAL GASIFICATION, AND LIQUEFACTION OF SOLID WASTES AND RESIDUES Summary: of a number of reactors...

428

E-Print Network 3.0 - atomic reactors chaines Sample Search Results  

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to join round-the-world computer network ring. 28.01.2004, 21.08 Summary: thermonuclear experimental reactor (ITER) project have an opportunity to offer technical...

429

E-Print Network 3.0 - ajustable para reactores Sample Search...  

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Summary: diagnostic measurements of acetylene absorption in hot-filament and DC-arc plasma jet reactors operating... deposition. The acetylene was widely4 2 distributed...

430

E-Print Network 3.0 - army gas-cooled reactor Sample Search Results  

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ENABLING SUSTAINABLE NUCLEAR POWER Summary: and NRE Design Class., "Advances in the Subcritical, Gas-Cooled Fast Transmutation Reactor Concept", Nucl... . Tedder, J. Lackey, J....

431

E-Print Network 3.0 - actinide burner reactors Sample Search...  

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and Design 85 (2010) 14881491 Contents lists available at ScienceDirect Summary: subcritical advanced burner reactor, Nuclear technology 162 (2008). 9 M. Kotschenreuther,...

432

E-Print Network 3.0 - afrri triga reactor Sample Search Results  

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MICROMEGAS DETECTOR FOR IN-CORE NUCLEAR REACTOR NEUTRON FLUX MEASUREMENTS Summary: subcritical configuration based in TRIGA-ADS project which consists of coupling a 1 MW TRIGA...

433

E-Print Network 3.0 - argentina 5f reactor Sample Search Results  

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

MARKET AND DEVELOPMENT STRATEGY WITH INTERNATIONAL THERMONUCLEAR EXPERIMENTAL Summary: THERMONUCLEAR EXPERIMENTAL REACTOR Rle de l'nergie de fusion dans la production...

434

E-Print Network 3.0 - alternative reactor vessel Sample Search...  

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

full2855429821 Summary: alternatives to current reactor designs (see sidebar). Thermonuclear fusion is the engine that powers the sun... Alerts || Subscription HELP ||...

435

Site Map  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearchScheduled System Highlights Success Stories ContactSite Map

436

Sacandaga Site  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCT 28Sacandaga Site Certification tp2ket

437

E-Print Network 3.0 - annual hanford site Sample Search Results  

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

Powered by Explorit Topic List Advanced Search Sample search results for: annual hanford site Page: << < 1 2 3 4 5 > >> 1 Summary of the HANFORD SITE Summary: Summary of the...

438

Licensed reactor nuclear safety criteria applicable to DOE reactors  

SciTech Connect (OSTI)

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.

Not Available

1991-04-01T23:59:59.000Z

439

University Research Summaries  

Broader source: Energy.gov [DOE]

The Idaho National Laboratory published the U.S. Department of Energy's (DOE) Geothermal Technologies Office 2001 University Research Summaries.

440

Reference worldwide model for antineutrinos from reactors  

E-Print Network [OSTI]

Antineutrinos produced at nuclear reactors constitute a severe source of background for the detection of geoneutrinos, which bring to the Earth's surface information about natural radioactivity in the whole planet. In this framework we provide a reference worldwide model for antineutrinos from reactors, in view of reactors operational records yearly published by the International Atomic Energy Agency (IAEA). We evaluate the expected signal from commercial reactors for ongoing (KamLAND and Borexino), planned (SNO+) and proposed (Juno, RENO-50, LENA and Hanohano) experimental sites. Uncertainties related to reactor antineutrino production, propagation and detection processes are estimated using a Monte Carlo based approach, which provides an overall site dependent uncertainty on the signal in the geoneutrino energy window on the order of 3%. We also implement the off-equilibrium correction to the reference reactor spectra associated with the long-lived isotopes and we estimate a 2.4% increase of the unoscillated event rate in the geoneutrino energy window due to the storage of spent nuclear fuels in the cooling pools. We predict that the research reactors contribute to less than 0.2% to the commercial reactor signal in the investigated 14 sites. We perform a multitemporal analysis of the expected reactor signal over a time lapse of 10 years using reactor operational records collected in a comprehensive database published at www.fe.infn.it/antineutrino.

Marica Baldoncini; Ivan Callegari; Giovanni Fiorentini; Fabio Mantovani; Barbara Ricci; Virginia Strati; Gerti Xhixha

2015-02-16T23:59:59.000Z

Note: This page contains sample records for the topic "reactor site summary" 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

AFIP-6 Characterization Summary Report  

SciTech Connect (OSTI)

The AFIP-6 (ATR Full-size-plate In center flux trap Position) Characterization Summary Report outlines the fresh fuel characterization efforts performed during the AFIP-6 experiment. The AFIP-6 experiment was designed to evaluate the performance of monolithic uranium-molybdenum (U-Mo) fuels at a scale prototypic of Advanced Test Reactor (ATR) fuel plates (45-inches long). The AFIP-6 test was the first test with plates that were swaged into the rails of the assembly. This test served to examine the effects of a plate in a swaged condition with longer fuel zones (22.5-inches long), that were centered in the plate. AFIP-6 test plates employed a zirconium interlayer that was co-rolled with the fuel foil. Previous mini-plate and AFIP irradiation experiments performed in ATR have demonstrated the stable behavior of the interface between the U-Mo fuel and the zirconium interlayer.

Dr. Dennis D. Keiser

2011-12-01T23:59:59.000Z

442

active site mismatches: Topics by E-print Network  

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

Ayman U. (Ayman Umar) 2001-01-01 38 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

443

active site conformational: Topics by E-print Network  

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

D 2005 Elsevier B Hong, Mei 56 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

444

active site conformation: Topics by E-print Network  

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

D 2005 Elsevier B Hong, Mei 56 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

445

active site probe: Topics by E-print Network  

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

25 Next Page Last Page Topic Index 61 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

446

active site constrained: Topics by E-print Network  

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

25 Next Page Last Page Topic Index 41 Summary of Activities at the ST LOUIS NORTH COUNTY SITE Engineering Websites Summary: Coldwater Creek, make up the North County Site. On...

447

Nuclear reactor engineering  

SciTech Connect (OSTI)

Chapters are presented concerning energy from nuclear fission; nuclear reactions and radiations; diffusion and slowing-down of neutrons; principles of reactor analysis; nuclear reactor kinetics and control; energy removal; non-fuel reactor materials; the reactor fuel system; radiation protection and environmental effects; nuclear reactor shielding; nuclear reactor safety; and power reactor systems.

Glasstone, S.; Sesonske, A.

1981-01-01T23:59:59.000Z

448

Research reactors - an overview  

SciTech Connect (OSTI)

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

West, C.D.

1997-03-01T23:59:59.000Z

449

Small Reactor for Deep Space Exploration  

SciTech Connect (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

2012-11-29T23:59:59.000Z

450

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

451

E-Print Network 3.0 - austrian triga-mk-2 reactor Sample Search...  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

452

E-Print Network 3.0 - ai-l-77 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

453

E-Print Network 3.0 - agesta-r3 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

454

E-Print Network 3.0 - atucha-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

455

E-Print Network 3.0 - asco-2 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

456

E-Print Network 3.0 - alrr reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

457

E-Print Network 3.0 - atlantic-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

458

E-Print Network 3.0 - akw1 rheinsberg reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

459

E-Print Network 3.0 - ast-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

460

E-Print Network 3.0 - ao-phai-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

Note: This page contains sample records for the topic "reactor site summary" 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

E-Print Network 3.0 - aguirre-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

462

E-Print Network 3.0 - are-rr-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

463

E-Print Network 3.0 - aguirre reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

464

E-Print Network 3.0 - arsi reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

465

E-Print Network 3.0 - afrri reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

466

E-Print Network 3.0 - arkansas-2 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

467

E-Print Network 3.0 - arkansas-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

468

E-Print Network 3.0 - argonaut reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

469

E-Print Network 3.0 - atucha-2 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

470

E-Print Network 3.0 - ahfr reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

471

E-Print Network 3.0 - anna reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

472

E-Print Network 3.0 - asco-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

473

E-Print Network 3.0 - ardennes reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

474

E-Print Network 3.0 - aeg-pr-10 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

475

E-Print Network 3.0 - ancon space-independent reactor Sample...  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

476

E-Print Network 3.0 - affri reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

477

E-Print Network 3.0 - aipfr reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

478

E-Print Network 3.0 - apsara reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

479

E-Print Network 3.0 - afsr reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

480

E-Print Network 3.0 - airos-2a space-independent reactor Sample...  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

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


481

E-Print Network 3.0 - aquilon reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

482

E-Print Network 3.0 - akr-1 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

483

E-Print Network 3.0 - arbi reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

484

E-Print Network 3.0 - adsorbent-membrane reactor hamr Sample...  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

485

E-Print Network 3.0 - aarr reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

486

E-Print Network 3.0 - argonauta rien-1 reactor Sample Search...  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

487

E-Print Network 3.0 - agata reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

488

E-Print Network 3.0 - arbus reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

489

E-Print Network 3.0 - atlantic-2 reactor Sample Search Results  

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

proposed site in Aomori... Minister communication meeting on Japanese Proposed site for Thermonuclear fusion experimental reactor Source: Fusiongnition Research Experiment (FIRE)...

490

Light Water Reactor Sustainability  

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

3 Light Water Reactor Sustainability Program ACCOMPLISHMENTS REPORT 2013 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

491

Light Water Reactor Sustainability  

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

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

492

agesta reactor: Topics by E-print Network  

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

of a severe unprotected (more) DeWitte, Jacob D. (Jacob Dominic) 2011-01-01 16 Thermonuclear Reflect AB-Reactor Physics (arXiv) Summary: The author offers a new kind of...

493

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

494

Bioconversion reactor  

DOE Patents [OSTI]

A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

McCarty, Perry L. (Stanford, CA); Bachmann, Andre (Palo Alto, CA)

1992-01-01T23:59:59.000Z

495

Team Summary | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up from the GridwiseSiteDepartmentChallengeCompliance7/109THETTU UTeam Summary Team

496

Fusion Plasma Theory project summaries  

SciTech Connect (OSTI)

This Project Summary book is a published compilation consisting of short descriptions of each project supported by the Fusion Plasma Theory and Computing Group of the Advanced Physics and Technology Division of the Department of Energy, Office of Fusion Energy. The summaries contained in this volume were written by the individual contractors with minimal editing by the Office of Fusion Energy. Previous summaries were published in February of 1982 and December of 1987. The Plasma Theory program is responsible for the development of concepts and models that describe and predict the behavior of a magnetically confined plasma. Emphasis is given to the modelling and understanding of the processes controlling transport of energy and particles in a toroidal plasma and supporting the design of the International Thermonuclear Experimental Reactor (ITER). A tokamak transport initiative was begun in 1989 to improve understanding of how energy and particles are lost from the plasma by mechanisms that transport them across field lines. The Plasma Theory program has actively-participated in this initiative. Recently, increased attention has been given to issues of importance to the proposed Tokamak Physics Experiment (TPX). Particular attention has been paid to containment and thermalization of fast alpha particles produced in a burning fusion plasma as well as control of sawteeth, current drive, impurity control, and design of improved auxiliary heating. In addition, general models of plasma behavior are developed from physics features common to different confinement geometries. This work uses both analytical and numerical techniques. The Fusion Theory program supports research projects at US government laboratories, universities and industrial contractors. Its support of theoretical work at universities contributes to the office of Fusion Energy mission of training scientific manpower for the US Fusion Energy Program.

Not Available

1993-10-01T23:59:59.000Z

497

E-Print Network 3.0 - active site determination Sample Search...  

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

of Geophysics, Center for Rock Abuse Collection: Fossil Fuels ; Geosciences 7 SITE MAINTENANCE PLAN CSMRI SITE REMEDIATION Summary: CSMRI SITE REMEDIATION 1.0 HISTORY ...

498

Essential Services Meeting Summary  

SciTech Connect (OSTI)

This summary of proceedings report focuses on an end-of-grant meeting at which grantees for Project Area 5 were convened.

HCTT CHE

2010-03-01T23:59:59.000Z

499

Neutronic reactor  

DOE Patents [OSTI]

A nuclear reactor includes an active portion with fissionable fuel and neutron moderating material surrounded by neutron reflecting material. A control element in the active portion includes a group of movable rods constructed of neutron-absorbing material. Each rod is movable with respect to the other rods to vary the absorption of neutrons and effect control over neutron flux.

Wende, Charles W. J. (Augusta, GA); Babcock, Dale F. (Wilmington, DE); Menegus, Robert L. (Wilmington, DE)

1983-01-01T23:59:59.000Z

500

R- AND P- REACTOR BUILDING IN-SITU DECOMISSIONING VISUALIZATION  

SciTech Connect (OSTI)

During the early 1950s, five production reactor facilities were built at the Savannah River Site. These facilities were built to produce materials to support the building of the nation's nuclear weapons stockpile in response to the Cold War. R-Reactor and P-Reactor were the first two facilities completed in 1953 and 1954.

Bobbitt, J.; Vrettos, N.; Howard, M.

2010-06-15T23:59:59.000Z