Powered by Deep Web Technologies
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

Site environmental report summary  

Science Conference Proceedings (OSTI)

In this summary of the Fernald 1992 Site Environmental Report the authors will describe the impact of the Fernald site on man and the environment and provide results from the ongoing Environmental Monitoring Program. Also included is a summary of the data obtained from sampling conducted to determine if the site complies with DOE, US Environmental Protection Agency (USEPA), and Ohio EPA (OEPA) requirements. These requirements are set to protect both man and the environment.

Not Available

1992-12-31T23:59:59.000Z

2

Summary Site Environmental Report  

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

Site Environmental Report Site Environmental Report for Calendar Year 2011 ANL-12/02 (Summary) Environment, Safety, and Quality Assurance Division Argonne National Laboratory Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor UChicago Argonne, LLC, nor any of their employees or officers, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product,

3

Draft environmental impact statement for the siting, construction, and operation of New Production Reactor capacity. Volume 1, Summary  

Science Conference Proceedings (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.

Not Available

1991-04-01T23:59:59.000Z

4

Untitled Page -- Other Sites Summary  

Office of Legacy Management (LM)

Other Sites Summary Other Sites Summary Search Other Sites Considered Sites Other Sites All LM Quick Search All Other Sites 11 E (2) Disposal Cell - 037 ANC Gas Hills Site - 040 Argonne National Laboratory - West - 014 Bodo Canyon Cell - 006 Burro Canyon Disposal Cell - 007 Cheney Disposal Cell - 008 Chevron Panna Maria Site - 030 Clive Disposal Cell - 036 Commercial (Burial) Disposal Site Maxey Flats Disposal Site - KY 02 Conoco Conquista Site - 031 Cotter Canon City Site - 009 Dawn Ford Site - 038 EFB White Mesa Site - 033 Energy Technology Engineering Center - 044 Estes Gulch Disposal Cell - 010 Exxon Ray Point Site - 032 Fermi National Accelerator Laboratory - 016 Fernald Environmental Management Project - 027 Fort St Vrain - 011 Geothermal Test Facility - 001 Hecla Durita Site - 012

5

Summary of the HANFORD SITE  

E-Print Network (OSTI)

milestones completed in 2003 were related to work on Hanford waste storage tanks. During 2003, there were 36Summary of the HANFORD SITE Environmental Report for Calendar Year 2003 EDITORS R.W. HANF L Northwest National Laboratory under contract DE-AC06-76RL01830, with contributions from Bechtel Hanford, Inc

6

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

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

May 2011 Hanford Site C Tank Farm Meeting Summary - May 2011 Hanford Site C Tank Farm Meeting Summary More Documents & Publications Hanford Site C Tank Farm Meeting Summary -...

7

Hanford Site C Tank Farm Meeting Summary  

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

Systems Working Session (7) ChangeRelease Summary of meeting between DOE-ORP and Hanford Site regulatorsstakeholders regarding Description: Waste Management Area C...

8

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

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

3 Annual Planning Summary for the Nevada Site Office 2013 Annual Planning Summary for the Nevada Site Office 2013 Annual Planning Summary for the The ongoing and projected...

9

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

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

March 2010 Hanford Site C Tank Farm Meeting Summary - March 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Meeting Summary for...

10

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

SciTech Connect

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

1962-09-14T23:59:59.000Z

11

2013 Annual Planning Summary for the Ames Site Office | Department...  

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

Ames Site Office 2013 Annual Planning Summary for the Ames Site Office 2013 Annual Planning Summary for the Ames Site Office The ongoing and projected Environmental Assessments and...

12

2013 Annual Planning Summary for the Brookhaven Site Office ...  

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

Brookhaven Site Office 2013 Annual Planning Summary for the Brookhaven Site Office 2013 Annual Planning Summary for the Brookhaven Site Office The ongoing and projected...

13

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

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

Sandia Site Office 2013 Annual Planning Summary for the Sandia Site Office 2013 Annual Planning Summary for the Sandia Site Office The ongoing and projected Environmental...

14

2013 Annual Planning Summary for the Pacific Northwest Site Office...  

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

Pacific Northwest Site Office 2013 Annual Planning Summary for the Pacific Northwest Site Office 2013 Annual Planning Summary for the Pacific Northwest Site Office The ongoing and...

15

2013 Annual Planning Summary for the FERMI Site Office | Department...  

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

FERMI Site Office 2013 Annual Planning Summary for the FERMI Site Office 2013 Annual Planning Summary for the FERMI Site Office The ongoing and projected Environmental Assessments...

16

2013 Annual Planning Summary for the SLAC Site Office | Department...  

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

SLAC Site Office 2013 Annual Planning Summary for the SLAC Site Office 2013 Annual Planning Summary for the SLAC Site Office The ongoing and projected Environmental Assessments and...

17

2013 Annual Planning Summary for the Berkeley Site Office | Department...  

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

Berkeley Site Office 2013 Annual Planning Summary for the Berkeley Site Office 2013 Annual Planning Summary for the Berkeley Site Office The ongoing and projected Environmental...

18

2013 Annual Planning Summary for the Princeton Site Office |...  

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

Princeton Site Office 2013 Annual Planning Summary for the Princeton Site Office 2013 Annual Planning Summary for the Princeton Site Office The ongoing and projected Environmental...

19

2013 Annual Planning Summary for the Thomas Jefferson Site Office...  

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

Thomas Jefferson Site Office 2013 Annual Planning Summary for the Thomas Jefferson Site Office 2013 Annual Planning Summary for the Thomas Jefferson Site Office The ongoing and...

20

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

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

Argonne Site Office 2013 Annual Planning Summary for the Argonne Site Office 2013 Annual Planning Summary for the Argonne Site Office The ongoing and projected Environmental...

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 - September 2010 | Department...  

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

September 2010 Hanford Site C Tank Farm Meeting Summary - September 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

22

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

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

September 2009 Hanford Site C Tank Farm Meeting Summary - September 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

23

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

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

February 2009 Hanford Site C Tank Farm Meeting Summary - February 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

24

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

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

Hanford Site C Tank Farm Meeting Summary - September 2009 Hanford Site C Tank Farm Meeting Summary - September 2009 Meeting Summary for Development of the Hanford Site C Tank Farm...

25

2013 Annual Planning Summary for the Los Alamos Site Office ...  

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

3 Annual Planning Summary for the Los Alamos Site Office 2013 Annual Planning Summary for the Los Alamos Site Office 2013 Annual Planning Summary for the Los Alamos Site Office The...

26

Annual Planning Summaries: Brookhaven Site Office (BHSO) | Department...  

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

Brookhaven Site Office (BHSO) Annual Planning Summaries: Brookhaven Site Office (BHSO) Document(s) Available For Download January 18, 2012 2012 Annual Planning Summary for...

27

Annual Planning Summaries: Argonne Site Office (Argonne) | Department...  

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

Argonne Site Office (Argonne) Annual Planning Summaries: Argonne Site Office (Argonne) Document(s) Available For Download January 9, 2012 2012 Annual Planning Summary for Argonne...

28

EM Recovery Act Funding Payment Summary by Site | Department...  

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

Payment Summary by Site Summary table of EM Recovery Act Spending Plan which shows dollar amounts obligated to contracts, payments to date and unpaid balances by site. EM...

29

Summary of the HANFORD SITE  

E-Print Network (OSTI)

will be welded. Some Tri-Party Agreement milestones completed in 2002 were related to work on Hanford tanks. #12 paragraphs. Solid waste may originate from work on the Hanford Site or from sources offsite, with contributions from CH2M HILL Hanford Group, Inc.; S.M. Stoller Corporation; Fluor Hanford, Inc. and its

30

2008 Annual Site Environmental Report Summary Pamphlet  

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

Annual Site Environmental Report Summary Pamphlet Annual Site Environmental Report Summary Pamphlet 1 2008 ASER Summary Pamphlet Sandia National Laboratories, New Mexico Sandia is a multi-program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04-94AL85000. Approved for public release; further dissemination unlimited. SAND 2009-4984P annual site environmental report 2 Sandia National Laboratories Issued by Sandia National Laboratories, operated for the United States Department of Energy by Sandia Corporation. NOTICE: This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government, nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, make any

31

Space Reactor Radiation Shield Design Summary, for Information  

SciTech Connect

The purpose of this letter is to provide a summary of the Prometheus space reactor radiation shield design status at the time of program restructuring.

EC Pheil

2006-02-17T23:59:59.000Z

32

Nevada Test Site Environmental Report 2007 Summary  

SciTech Connect

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

33

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

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

0 Hanford Site C Tank Farm Meeting Summary - May 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

34

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

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

July 2010 Hanford Site C Tank Farm Meeting Summary - July 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm...

35

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

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

09 Hanford Site C Tank Farm Meeting Summary - May 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

36

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

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

0 Hanford Site C Tank Farm Meeting Summary - January 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

37

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

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

1 Hanford Site C Tank Farm Meeting Summary - January 2011 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

38

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

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

October 2009 Hanford Site C Tank Farm Meeting Summary - October 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm...

39

Savannah River Site K-Reactor Probabilistic Safety Assessment  

SciTech Connect

This report gives the results of a Savannah River Site (SRS) K-Reactor Probabilistic Safety Assessment (PSA). Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the report gives a summary of the methods employed to represent these accidents and to assess the resultant consequences. The report is issued to provide useful information to the U. S. Department of Energy (DOE) on the risk of operation of SRS reactors, for insights into severe accident phenomena that contribute to this risk, and in support of improved bases for other DOE programs in Heavy Water Reactor safety.

Brandyberry, M.D.; Bailey, R.T.; Baker, W.H.; Kearnaghan, D.P.; O`Kula, K.R.; Wittman, R.S.; Woody, N.D. [Westinghouse Savannah River Co., Aiken, SC (United States); Amos, C.N.; Weingardt, J.J. [Science Applications International Corp. (United States)

1992-12-01T23:59:59.000Z

40

Hanford Site C Tank Farm Meeting Summary  

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

1878, Rev. 0 1878, Rev. 0 Summary Notes from 5 - 7 May 2009 Office of River Protection Waste Management Area C Tank Farm Performance Assessment Input Meeting MP Connelly Washington River Protection Solutions LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV14800 EDT/EON: DRF UC: Cost Center: Charge Code: B&R Code: Total Pages: 15 Key Words: Waste Management Area C, Performance Assessment, tank closure, waste inventory Abstract: Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Waste Management Area C performance assessment TRADEMARK DISCLAIMER. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or

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

Hanford Site C Tank Farm Meeting Summary  

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

3622, Rev. 0 3622, Rev. 0 Summary Notes from 1 - 3 September 2009 Office of River Protection Waste Management Area C Tank Farm Performance Assessment Input Meeting MP Connelly Washington River Protection Solutions LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV1 4800 EDT/ECN: DRF UC: Cost Center: Charge Code: B&R Code: Total Pages: 13 Key Words: Waste Management Area C, Performance Assessment, tank closure, waste inventory Abstract: Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Waste Management Area C performance assessment TRADEMARK DISCLAIMER. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or

42

2011 Annual Planning Summary for Sandia Site Office (SSO) | Department...  

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

Sandia Site Office (SSO) 2011 Annual Planning Summary for Sandia Site Office (SSO) The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011...

43

2012 Annual Planning Summary for Sandia Site Office | Department...  

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

Sandia Site Office 2012 Annual Planning Summary for Sandia Site Office The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013...

44

2011 Annual Planning Summary for Ames Site Office (Ames) | Department...  

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

Ames Site Office (Ames) 2011 Annual Planning Summary for Ames Site Office (Ames) The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011...

45

2012 Annual Planning Summary for Argonne Site Office | Department...  

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

Argonne Site Office 2012 Annual Planning Summary for Argonne Site Office The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013...

46

Annual Planning Summaries: Nevada Site Office (NSO) | Department of Energy  

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

Annual Planning Summaries: Nevada Site Office (NSO) Annual Planning Summaries: Nevada Site Office (NSO) Annual Planning Summaries: Nevada Site Office (NSO) January 31, 2012 2012 Annual Planning Summary for Nevada Site Office The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within the Nevada Site Office. January 20, 2011 2011 Annual Planning Summary for Nevada Site Office (NSO) The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Nevada Site Office (NSO). January 14, 2010 2010 Annual Planning Summary for Nevada Site Office Annual Planning Summaries briefly describe the status of ongoing NEPA compliance activities, any EAs expected to be prepared in the next 12 months, any EISs expected to be prepared in the next 24 months, and the

47

710 high-temperature gas reactor program summary report. Volume I. Summary  

SciTech Connect

Declassified 6 Sep 1973. A description of the 710 Reactor concept and its significant design features is presented. A summary of the history of the 710 Program and a summary of the major technical achievements of the program are included. (13 references) (auth)

1967-01-01T23:59:59.000Z

48

Hanford Site C Tank Farm Meeting Summary  

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

4941 (2) Revision Number: 0 (3) Effective Date: 02/25/2010 4941 (2) Revision Number: 0 (3) Effective Date: 02/25/2010 (4) Document Type: ElDigital Image [] Hard copy (a) Number of pages (including the DIRF) or 20 SPDF Video number of digital images (5) Release Type New El Cancel I E Page Change El Complete Revision (6) Document Title: Meeting Minutes for the WMA C PA Working Session on Soils Inventory (7) Change/Release Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Description: Waste Management Area C performance assessment on soil inventory. (8) Change N/A Justification: (9) Associated (a) Structure Location: (c) Building Number: Structure, System, N/NA and Component N/NA (SSC) and Building (b) System Designator: (d) Equipment ID Number (EIN): Number: N/A N/A (10) Impacted (a) Document Type (b) Document Number (c) Document Revision

49

Hanford Site C Tank Farm Meeting Summary  

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

Summary Notes from 24- 25 February 2009 Office of River Protection Waste Management Area C Performance Assessment Input Meeting Attendees: Representatives from Department of Energy-Office of River Protection (DOE-ORP), DOE Richland Operations Office (DOE-RL), DOE-Headquarters (DOE-HQ), the Washington State Department of Ecology (Ecology), and the U.S. Nuclear Regulatory Commission (NRC), met at the Ecology offices in Richland, Washington on 24 & 25 February 2009. EPA Region X staff participated on 25 February 2009 via teleconference. Discussion: DOE is pursuing closure of Waste Management Area C (WMA-C) located at the Hanford Site. At some point in the future, DOE and NRC will consult on waste determinations for these tank closures; additionally these tanks will be closed in coordination with EPA and

50

Hanford Site C Tank Farm Meeting Summary  

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

DOCUMENT RELEASE FORM DOCUMENT RELEASE FORM ! I (1) Document Number: RPP-47375 . NUMber· 0 I (3) Effective Date: 08/11/2010 i (4) Document Type: o Digital Image o Hard copy (a) Number of pages (including the DRF) or 21 I ~PDF o Video I number of digital images (5) Release Type ~ New o Cancel o Page Change o Complete Revision i (6) Document Title: Meeting Minutes for the WMA C PA Engineered Systems #2 Working Session - Steel Corrosion; i ConcretelGrout Degradation I(7) Change/Release ..- - . Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Description: Waste Management Area C performance assessment on Engineered Systems #2 - Steel Corrosion; Concrete/Grout Degradation I(8) Change N/A Justification: (9) Associated (a) Structure Location: (c) Building Number:

51

Hanford Site C Tank Farm Meeting Summary  

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

51 35 51 35 (2) Revision Number: 0 (3) Effective Date: 03/03/2010 (4) Document Typo: [I Digital Image ElHard copy (a) Number of pages (including the DRF) or 18 JE PDF Vie number of digital Images (5) Release Type Z New 1: Cancel 1E: Page Change Complete Revision (6) Document Title: Meeting Minutes for the WMA C PA Engineering System #1 Working Session (7) ChangelReleese Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Description: Waste Management Area C performance assessment on Engineering System #1. (5) Change N/A Justification: (9) Associated (a) Structure Location: (c) Building Number: Structure, System, and Component N/NA (SSC) and Building (b) System Designator: (d) Equipment ID Number (EIN):. Number: (10) Impacted (a) Document Type (b) Document Number (c) Document Revision

52

Boiling Water Reactor Sampling Summary: 2012 Update  

Science Conference Proceedings (OSTI)

This report documents boiling water reactor (BWR) sampling practices for key reactor water and feedwater parameters. It includes information on analysis methods, sampling frequencies, and compliance with the recommended sampling frequencies in BWRVIP-190: BWR Vessels and Internals Project, BWR Water Chemistry Guidelines – 2008 Revision (EPRI report 1016579).

2013-03-28T23:59:59.000Z

53

PRELIMINARY HAZARD SUMMARY REPORT ON THE BOILING EXPERIMENTAL REACTOR (BER)  

SciTech Connect

A preliminary evaluation of the hazards associated with a 20-Mw boiling reactor for the purpose of determining site requirements is presented. The Boiling Experimental Reactor design, safety features, and performance are given and the surroundings of the site at Argonne National Laboratory are described. (T.R.H.)

West, J.M.; Anderson, C.A.; Dietrich, J.R.; Harrer, J.M.; Jameson, A.S.; Untermyer, S.

1954-05-01T23:59:59.000Z

54

FORMERLY USED SITES REMEDIAL ACTION PROGRAM DESIGNATION SUMMARY  

Office of Legacy Management (LM)

USED SITES USED SITES REMEDIAL ACTION PROGRAM DESIGNATION SUMMARY FOR ALBA CRAFT LABORATORY OXFORD, OHIO October 1, 1992 U.S. DEPARTMENT OF ENERGY OFFICE OF ENVIRONMENTAL RESTORATION Designation Summary Alba Craft Laboratory. Oxford CONTENTS INTRODUCTION .......... . . ..................... 1 BACKGROUND Site Function ......................... Site Description ..................... 1 Owner History ................. .. 2 Radiological History and Status............ 2 Authority Review .................... .. 3 DESIGNATION DETERMINATION ........ ....... 3 REFERENCES . ............ .... . 3 Designation Summary Alba Craft Laboratory, Oxford INTRODUCTION The Department of Energy (DOE), Office of Environmental Restoration, has reviewed the past activities of the Atomic Energy Commission (AEC) at the

55

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

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

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

56

2010 Annual Planning Summary for Nevada Site Office | Department...  

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

to be prepared in the next 24 months, and the planned cost and schedule for each NEPA review identified. 2010 Annual Planning Summary for Nevada Site Office More Documents &...

57

2010 Annual Planning Summary Livermore Site Office (LSO) | Department...  

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

to be prepared in the next 24 months, and the planned cost and schedule for each NEPA review identified. 2010 Annual Planning Summary Livermore Site Office (LSO) More Documents...

58

2010 Annual Planning Summary for Kansas City Site Office (KCSO...  

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

to be prepared in the next 24 months, and the planned cost and schedule for each NEPA review identified. 2010 Annual Planning Summary for Kansas City Site Office (KCSO) More...

59

2010 Annual Planning Summary for Los Alamos Site Office (LASO...  

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

to be prepared in the next 24 months, and the planned cost and schedule for each NEPA review identified. 2010 Annual Planning Summary for Los Alamos Site Office (LASO) More...

60

2011 Annual Planning Summary for Argonne Site Office (Argonne...  

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

to be prepared in the next 24 months, and the planned cost and schedule for each NEPA review identified. 2011 Annual Planning Summary for Argonne Site Office (ArSO) More...

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

2011 Annual Planning Summary for Pacific Northwest Site Office...  

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

to be prepared in the next 24 months, and the planned cost and schedule for each NEPA review identified. 2011 Annual Planning Summary for Pacific Northwest Site Office (PNSO)...

62

Boiling Water Reactor Shutdown Chemistry and Dose Summary: September 2010  

Science Conference Proceedings (OSTI)

This 2010 update provides an annual report of shutdown radiation dose rates at 46 boiling water reactors (BWRs) that participate in the Electric Power Research Institute's (EPRI's) BWR Chemistry Monitoring and Assessment program and supersedes the BWR Radiation Assessment and Control (BRAC) Summary that was issued twice a year. In addition to BRAC dose rates, the report also includes information on operating and shutdown water chemistry and worker outage dose and contamination.

2010-09-23T23:59:59.000Z

63

PRELIMINARY HAZARDS SUMMARY REPORT ON THE BROOKHAVEN HIGH FLUX BEAM RESEARCH REACTOR  

SciTech Connect

The High Flux Beam Reactor, HFBR, is cooled, moderated, and reflected by heavy water and designed to produce 40 Mw with a total epithermal flux of ~1.6 X 10/sup 15/cm/sup -2/ sec/sup -1/ and a flector thermal maximum flux of 7 X 10/sup 14/ cm/sup -2/ sec/sup -1/, using a core formed by ETR plate-type fuel elements in a close-packed array. The hazards summary is given in terms of site description, reactor design, building design, plant operation, disposal of radioactive wastes and effluents, and safety analysis. (B.O.G.)

Hendrie, J.M.; Kouts, H.J.C.

1961-05-01T23:59:59.000Z

64

Independent Oversight Inspection, Savannah River Site, Summary Report -  

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

Savannah River Site, Summary Savannah River Site, Summary Report - February 2004 Independent Oversight Inspection, Savannah River Site, Summary Report - February 2004 February 2004 Inspection of Environment, Safety, and Health Management and Emergency Management at the Savannah River Site The Secretary of Energy's Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) and emergency management programs at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) in January and February 2004. The inspection was performed as a joint effort by the OA Office of Environment, Safety and Health Evaluations and the Office of Emergency Management Oversight. WSRC has implemented an emergency management program at SRS that exhibits

65

Independent Oversight Inspection, Nevada Test Site, Summary Report -  

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

Oversight Inspection, Nevada Test Site, Summary Report Oversight Inspection, Nevada Test Site, Summary Report - October 2002 Independent Oversight Inspection, Nevada Test Site, Summary Report - October 2002 October 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Nevada Test Site The Secretary of Energy's 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 2002. The inspection was performed as a joint effort by the OA Office of Environment, Safety and Health Evaluations and the Office of Emergency Management Oversight. Overall, safety management at NTS has substantially improved in the past

66

Nevada Test Site Environmental Report 2008 Summary  

SciTech Connect

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

67

Summary of Weldon Spring Site Focus Area  

Office of Legacy Management (LM)

of Weldon Spring Site Focus Area of Weldon Spring Site Focus Area Work Session February 5, 2003 Weldon Spring Interpretive Center Focus Area: Monitoring and Maintenance This was the third of three work sessions that focus on specific issues addressed in the draft Long-Term Stewardship Plan for the Weldon Spring, Missouri, Site, dated August 9, 2002. At 6:00 p.m., before the start of the work session, Dan Collette, Technical Support Manager for S.M. Stoller, the U.S. Department of Energy (DOE) Grand Junction Office (GJO) contractor, gave a demonstration of the on-line document retrieval and geographic information systems. Introduction Dave Geiser, DOE Headquarters Director of the Office of Long-Term Stewardship, discussed a DOE Headquarters proposal to establish the Office of Legacy Management in fiscal year 2004.

68

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

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

Monticello Monticello Agreement Name Monticello (Utah) Site: Monticello Vicinity Properties NPL Site and Monticello Millsite Federal Facility Agreement Pursuant to CERCLA Section 120, December 22, 1988 State Utah Agreement Type Federal Facility Agreement Legal Driver(s) CERCLA Scope Summary Establish a procedural framework and schedule for developing, implementing, and monitoring appropriate response actions at the Site Parties DOE; US EPA; State of Utah Department of Environmental Health Date 12/22/1988 SCOPE * Identify Interim Remedial Action (IRA) alternatives, if any, which are appropriate at the Site prior to the implementation of final remedial actions for the Site. * Evaluate all past investigative and response actions taken at the Site and documented

69

Light Water Reactor Sustainability Constellation Pilot Project FY12 Summary Report  

SciTech Connect

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

70

Light Water Reactor Sustainability Constellation Pilot Project FY13 Summary Report  

SciTech Connect

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

71

Plutonium and tritium produced in the Hanford Site production reactors  

SciTech Connect

In a news release on December 7, 1993, the Secretary of Energy announced declassification action that included totals for plutonium and tritium production in the Hanford Site production reactors. This information was reported as being preliminary because it was not fully supported by documentation. Subsequently, production data were made available from the US Department of Energy-Headquarters (DOE-HQ) records that indicated an increase of about one and one-half metric tons in total plutonium production. The Westinghouse Hanford Company was tasked by the US Department of Energy-Richland Operations Office to substantiate production figures and DOE-HQ data and to provide a defensible report of weapons- (6 wt% {sup 240}Pu) and nonweapons- (fuels-)grade (nominally 9 wt% or higher {sup 240}Pu) plutonium and tritium production in the Hanford Site production reactors. The task was divided into three parts. The first part was to determine plutonium and tritium production based on available reported accountability records. The second part was to determine plutonium production independently by calculational checks based on reactor thermal power generation and plutonium conversion factors representing the various reactor fuels. The third part was to resolve differences, if they occurred, in the reported and calculational results. In summary, the DOE-HQ-reported accountability records of plutonium and tritium production were determined to be the most defensible record of Hanford Site reactor production. The DOE-HQ records were consistently supported by the independent calculational checks and the records of operational data. Total production quantities are 67.4 MT total plutonium, which includes 12.9 MT of nonweapons-grade plutonium. The total tritium production was 10.6 kg.

Roblyer, S.P.

1994-09-28T23:59:59.000Z

72

Site specific analysis of geothermal development. Volume 1. Summary report  

SciTech Connect

MITRE/Metrek has analyzed development scenarios for 37 hydrothermal and geopressured prospects in the United States to assist DOE's Division of Geothermal Energy in mission-oriented planning of geothermal resource development. A summary of the site-specific analyses is presented with particular emphasis on possible recommendations for the Federal Geothermal Program.

Leigh, J.; Cohen, A.; Jacobsen, W.; Trehan, R.

1978-08-01T23:59:59.000Z

73

Oak Ridge Reservation Annual Site environmental report summary for 1994  

SciTech Connect

This document presents a summary of the information collected for the Oak Ridge Reservation 1994 site environmental report. Topics discussed include: Oak Ridge Reservation mission; ecology; environmental laws; community participation; environmental restoration; waste management; radiation effects; chemical effects; risk to public; environmental monitoring; and radionuclide migration.

1995-09-01T23:59:59.000Z

74

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

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

Site Site Agreement Name Savannah River Site Federal Facility Agreement Under Section 120 of CERCLA, January 15, 1993 State South Carolina Agreement Type Federal Facility Agreement Legal Driver(s) CERCLA Scope Summary Ensure that the environmental impacts associated with past and present activities at the Savannah River Site are thoroughly investigated and that appropriate response actions are taken to protect the public health, welfare, and the environment. Parties DOE; US EPA; South Carolina Department of Health and Environmental Control (SCDHEC) Date 1/15/1993 SCOPE * Ensure that the environmental impacts associated with past and present activities at the Savannah River Site are thoroughly investigated and that appropriate response actions are taken to protect the public health, welfare, and the environment.

75

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

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

Test Site Federal Facility Compliance Act Test Site Federal Facility Compliance Act Consent Order, March 27, 1996 State Nevada Agreement Type Consent Order Legal Driver(s) FFCAct Scope Summary Enforce the STP and establish procedures for reviewing schedules, deleting waste streams, and administrative procedures Parties DOE; Nevada Division of Environmental Protection Date 3/27/1996 SCOPE * Require DOE to achieve compliance with the requirements of the FFCAct through the STP which contains schedules and applicable strategies for achieving compliance with the applicable LDR standards. * Establish procedures for reviewing schedules, deleting waste streams, and administrative procedures. * Establish enforceable schedules and milestones applicable to this Order. ESTABLISHING MILESTONES *

76

Oak Ridge Reservation Annual Site Environmental Report Summary, 2002  

SciTech Connect

The ''State-of-the-Environment'' on and around the Oak Ridge Reservation is a mission of highest importance to the Department of Energy and our contractors. In order to be fully aware of the consequences of our operations and cleanup, an annual multimillion-dollar monitoring and surveillance program collects and analyzes tens of thousands of samples from air, surface and groundwater, soil, mud, plants, and animals. A mission of equal importance is to provide our stakeholders a complete understanding of this program. To do this we publish a detailed Annual Site Environmental Report and this summary document. The raw data is published separately in the Data Volume. All three documents can be found on the web, along with past documents, at http://www.ornl.gov/aser. Though I work on numerous technical documents throughout the year, no document is more important to me than the Annual Site Environmental Report and its Summary because: (1) they represent the efforts of many dedicated environmental scientists who carry out this extensive program, and who work hard to protect and enhance the environment; (2) they set out the programs in great detail to our legislatures, stakeholders, and the public; and (3) the Summary is directed to the public with the hope that the information is understandable and of value in gaining an accurate picture of the Oak Ridge Reservation as a neighbor. I thank the Karns High School students and their teacher for accepting my challenge in writing this Annual Site Environmental Report Summary, for thinking out of the box, for doing such a fine job, and for all the artwork and photographs (the morning coffee in the classroom was greatly appreciated, leaks and all). They were an especially enjoyable class to work with, and I hope you, our stakeholders and the public, find their efforts of value.

Hughes, JF

2003-11-25T23:59:59.000Z

77

Light Water Reactor Sustainability Constellation Pilot Project FY11 Summary Report  

Science Conference Proceedings (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

78

Savannah River Site Removes Dome, Opening Reactor for Recovery Act  

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

Savannah River Site Removes Dome, Opening Reactor for Recovery Act Savannah River Site Removes Dome, Opening Reactor for Recovery Act Decommissioning Savannah River Site Removes Dome, Opening Reactor for Recovery Act Decommissioning American Recovery and Reinvestment Act workers achieved a significant milestone in the decommissioning of a Cold War reactor at the Savannah River Site this month after they safely removed its rusty, orange, 75-foot-tall dome. With the help of a 660-ton crane and lifting lugs, the workers pulled the 174,000-pound dome off the Heavy Water Components Test Reactor, capping more than 16 months of preparations. Savannah River Site Removes Dome, Opening Reactor for Recovery Act Decommissioning More Documents & Publications Recovery Act Changes Hanford Skyline with Explosive Demolitions Recovery Act Workers Add Time Capsule Before Sealing Reactor for Hundreds

79

CIVILIAN POWER REACTOR PROGRAM. PART I. SUMMARY OF TECHNICAL AND ECONOMIC STATUS AS OF 1959  

SciTech Connect

The current technical and economic status for each reactor concept in the Civilian Power Reactor Program is summarized. The individual techical status reports which present detailed information will be published by AEC as TID-8518. Included in this summary are: power costs for various reactor types versus coal- fired plants; construction schedule for heavy-water natural-U reactors; and annual program costs. (T.R.H.)

1960-01-01T23:59:59.000Z

80

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

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

Federal Facility Agreement and Consent Order Federal Facility Agreement and Consent Order (FFACO) State Nevada Agreement Type Federal Facility Agreement and Consent Order Legal Driver(s) FFCAct Scope Summary Identify sites of potential historic contamination and implement proposed corrective actions Parties DOE; Department of Defense (DoD); Nevada Division of Environmental Protection (NDEP) Date 5/10/1996 SCOPE * Identify sites of potential historic contamination and implement proposed corrective actions. * Establish specific sampling and monitoring requirements, including drilling and subsurface sampling. ESTABLISHING MILESTONES * Within sixty (60) calendar days following the signing of this Agreement, the parties shall meet to review Appendices II-IV and concur on the classification of all presently

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

Oak Ridge Reservation annual site environmental report summary for 1995  

SciTech Connect

The US Department of Energy (DOE) requires an annual site environmental report from each of the sites operating under its authority. The reports present the results from the various environmental monitoring and surveillance programs carried out during the year. In addition to meeting the DOE requirement, the reports also document compliance with various state and federal laws and regulations. This report was published to fulfill those requirements for the Oak Ridge Reservation (ORR) for calendar year 1995. The report is based on thousands of environmental samples collected on and around the ORR and analyzed during the year. The data on which the report is based are published in Environmental Monitoring and Surveillance on the Oak Ridge Reservation: 1995 Data (ES/ESH-71). Both documents are highly detailed. This summary report is meant for readers who are interested in the monitoring results but who do not need to review the details.

1996-12-01T23:59:59.000Z

82

Nevada National Security Site Environmental Report 2011 Summary  

SciTech Connect

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

83

SAVANNAH RIVER SITE ENVIRONMENTAL REPORT SUMMARY FOR 2012  

Science Conference Proceedings (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

84

NEPS reactor and heat exchanger. Summary status (December 1978)  

SciTech Connect

The design of a 3 MW(+) heat-pipe cooled nuclear reactor for electric propulsion of spacecrafts has been evolving continually. Several modifications have been made to make the reactor design more tolerant of potential heat pipe failures. Design parameters and operating characteristics for the modified reactor are presented. The desirability of separating the reactor assembly from the thermionic converter assembly has been recognized, and an intermediate heat exchanger to couple the two subassemblies together has been conceptualized.

Koenig, D.R.

1979-06-01T23:59:59.000Z

85

Idaho Site Obtains Patent for Nuclear Reactor Sodium Cleanup Treatment |  

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

Idaho Site Obtains Patent for Nuclear Reactor Sodium Cleanup Idaho Site Obtains Patent for Nuclear Reactor Sodium Cleanup Treatment 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 (seated) developed a treatment to safely dissolve a bicarbonate crust and treat and remove the sodium in the Experimental Breeder Reactor-II at the Idaho site. CWI engineers Jeff Jones, David Tolman, right, and Kirk Dooley (seated) developed a treatment to safely dissolve a bicarbonate crust and treat and remove the sodium in the Experimental Breeder Reactor-II at the Idaho site. Piping in the east boiler basement of the sodium processing building was color coded for easy identification. Orange indicates sodium and green identifies cooling water.

86

Pebble bed reactor fiscal year 1980: review summary report  

Science Conference Proceedings (OSTI)

Information on high-temperature reactor development is presented concerning reactor operating experience; core performance assessment; core control and shutdown; reflector and core support; maintenance and availability; safety aspects of PBR and prismatic comparison; PCRV dimensions; and fuel reprocessing cost estimate.

Not Available

1980-07-01T23:59:59.000Z

87

Idaho Site Obtains Patent for Nuclear Reactor Sodium Cleanup Treatment |  

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

Obtains Patent for Nuclear Reactor Sodium Cleanup Obtains Patent for Nuclear Reactor Sodium Cleanup Treatment 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 (seated) developed a treatment to safely dissolve a bicarbonate crust and treat and remove the sodium in the Experimental Breeder Reactor-II at the Idaho site. CWI engineers Jeff Jones, David Tolman, right, and Kirk Dooley (seated) developed a treatment to safely dissolve a bicarbonate crust and treat and remove the sodium in the Experimental Breeder Reactor-II at the Idaho site. Piping in the east boiler basement of the sodium processing building was color coded for easy identification. Orange indicates sodium and green identifies cooling water.

88

Summary of the MARS tandem-mirror reactor design  

SciTech Connect

A recently completed two-year study of a commercial tandem-mirror reactor design (Mirror Advanced Reactor Study (MARS)) is briefly reviewed. The end plugs are designed for trapped-particle stability, MHD ballooning, balanced geodesic curvature, and small radial electric fields in the central cell. New technologies such as lithium-lead blankets, 24 T hybrid coils, gridless direct converters and plasma halo vacuum pumps are highlighted. General characteristics of the MARS tandem mirror and STARFIRE tokamak reactor design are compared. A design of an upgrade of MFTF-B incorporating many of the MARS features is discussed.

Logan, B.G.

1983-09-01T23:59:59.000Z

89

Draft Site-Wide Environmental Impact Statement Nevada Summary...  

National Nuclear Security Administration (NNSA)

Summary Draft | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our...

90

Summary of the Hanford Site Environmental Report for Calendar Year 2005  

Science Conference Proceedings (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

91

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

Science Conference Proceedings (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

92

Summary - Savannah River Site Tank 48H Waste Treatment Project  

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

S S Wet Air Savan contain liquid w contain potent to the option tank w Bed S condu be pur The as Techn Techn as liste * W o o The Ele Site: S roject: S P Report Date: J ited States Savanna Why DOE r Oxidation Proc nnah River Tan ning approxima waste. The wa ns tetraphenylb tially flammable tank head spa s have been id waste: Wet Air O team Reformin cted to aid in d rsued for treatin What th ssessment team ology Element ology Readine ed below: Wet Air Oxidatio Reactor sys Offgas Trea To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin Savannah Rive SRS Tank 48H Project July 2007 Departmen ah River E-EM Did This cess k 48H is a 1.3 ately 250, 000 aste is a salt so borate (TPB), w e concentration ce. Two poten dentified for this Oxidation (WAO ng (FBSR). Th deciding which ng the Tank 48

93

Fuel Summary Report: Shippingport Light Water Breeder Reactor  

SciTech Connect

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

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

1999-01-01T23:59:59.000Z

94

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

SciTech Connect

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

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

1994-10-01T23:59:59.000Z

95

Summary of HEDL Fusion Reactor Safety Support studies  

Science Conference Proceedings (OSTI)

The HEDL Fusion Reactor Safety Support studies are focused on characterizing blanket-coolant-material reactions for deuterium-tritium fusion reactor designs. The objective is to determine and examine potential safety and environmental issues associated with proposed blanket/coolant combinations under postulated accident conditions. The first studies considered liquid lithium as both blanket and coolant, and examined liquid lithium-material reactions. Liquid lithium reactions with oxygen, nitrogen, and various concretes have been characterized. Evaluations of lithium reaction extinguishment methods, lithium aerosol generation and collection, and the volatilization and transport of radioactive materials in connection with lithium-air reactions have been completed. Lithium compound blanket material reactions with water, a prime coolant candidate, have been characterized in terms of energy and gas release rates. Blanket materials considered were lithium aluminate, lithium oxide, lithium zirconate, lithium silicate, and lithium lead alloys (Li/sub 7/Pb/sub 2/ and Li/sub 17/Pb/sub 83/).

Muhlestein, L.D.; Jeppson, D.W.; Barreca, J.R.

1981-01-01T23:59:59.000Z

96

Energy Secretary to Visit Georgia Nuclear Reactor Site and Tennessee  

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

Secretary to Visit Georgia Nuclear Reactor Site and Secretary to Visit Georgia Nuclear Reactor Site and Tennessee Laboratory to Highlight Administration Support for Nuclear Energy Energy Secretary to Visit Georgia Nuclear Reactor Site and Tennessee Laboratory to Highlight Administration Support for Nuclear Energy February 13, 2012 - 6:16pm Addthis WASHINGTON, D.C. - U.S. Secretary of Energy Secretary Steven Chu will visit the Vogtle nuclear power plant in Waynesboro, Georgia, and Oak Ridge National Laboratory on Wednesday, February 15 to highlight steps the Obama Administration is taking to restart America's nuclear energy industry. In Waynesboro, Secretary Chu will join Southern Company CEO Thomas A. Fanning, Georgia Power CEO W. Paul Bowers, and local leaders for a tour of Vogtle units 3 and 4 -- the site of the first two new nuclear power units

97

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

DOE Green Energy (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

98

Program summary for the Civilian Reactor Development Program  

SciTech Connect

This Civilian Reactor Development Program document has the prime purpose of summarizing the technical programs supported by the FY 1983 budget request. This section provides a statement of the overall program objectives and a general program overview. Section II presents the technical programs in a format intended to show logical technical interrelationships, and does not necessarily follow the structure of the formal budget presentation. Section III presents the technical organization and management structure of the program.

1982-07-01T23:59:59.000Z

99

Site Transition Summary: Cleanup Completion to Long-Term Stewardship at  

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

Summary: Cleanup Completion to Long-Term Summary: Cleanup Completion to Long-Term Stewardship at Department of Energy On-going Mission Sites Site Transition Summary: Cleanup Completion to Long-Term Stewardship at Department of Energy On-going Mission Sites Long-term stewardship (LTS) includes the physical controls, institutions, information, and other mechanisms needed to ensure protection of people and the environment at sites where the U.S. Department of Energy (DOE) has completed or plans to complete cleanup (e.g., landfill closures, remedial actions, removal actions, and facility stabilization). This concept includes land-use controls, information management, monitoring and maintenance. Site Transition Summary: Cleanup Completion to Long-Term Stewardship at Department of Energy On-going Mission Sites

100

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

SciTech Connect

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

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

N Reactor Seismic Task Force analysis and fix summary  

Science Conference Proceedings (OSTI)

The N Reactor Safety Enhancement Program (SEP) and the Accelerated Safety Enhancement Program (ASEP) were established to implement recommendations made earlier by study groups assessing the safety of N Reactor. The recommendations which dealt with seismic issues were assigned to Safety Enhancement Programs, Defense Reactor Programs for implementation. A Seismic Task Force was assembled to perform the analyses, design the modifications, direct the performance of the work and provide program management of the effort to seismically qualify the facility. This document identifies the reports published by the task force to resolve each of the seismic issues raised by safety assessments. The reports, in turn, provide a list of recommended fixes (Fixes are potential problems, not resolved in the engineering analyses, which require repair, cleanup or modifications to hardware to establish seismic qualification). The purpose of this report is to provide a guide to seismic fixes implemented by the Seismic Task Force. This information is provided in the form of a ``fix log`` which lists fixes according to the report which recommended them and identifies the work authorization (WA), engineering documentation (Design Change, Field Change Notice or Engineering Change Notice) and acceptance dates for each fix. 5 refs., 6 tabs.

Rainey, T.E.

1989-05-01T23:59:59.000Z

102

summary  

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

Project Summary HELP Index Summary Scenario Internet Links Student Pages SubjectContent Area: Language Arts and Social Studies Target Audience: This project is designed for third...

103

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

SciTech Connect

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

104

Meeting Summaries for Development of the Hanford Site C Tank Farm  

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

Meeting Summaries for Development of the Hanford Site C Tank Farm Meeting Summaries for Development of the Hanford Site C Tank Farm Performance Assessment Meeting Summaries for Development of the Hanford Site C Tank Farm Performance Assessment The Meeting Summaries for Development of the Hanford Site C Tank Farm Performance Assessment cover informal discussions between representatives of the U.S. Department of Energy (DOE), U.S. Environmental Protection Agency (EPA), the U.S. Nuclear Regulatory Commission (NRC), and the Washington State Department of Ecology (Ecology) and involvement with Tribal Nations, State of Oregon, and the Hanford Advisory Board to support DOE's preparation of a new performance assessment (PA) for the Hanford Site C Tank Farm (CTF). These discussions will include the underlying assumptions, input parameters, and modeling approaches to be taken in

105

Nevada National Security Site Environmental Report Summary 2010  

SciTech Connect

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

C. Wills, ed.

2011-09-13T23:59:59.000Z

106

Summary Site Environmental Report for Calendar Year 2010  

E-Print Network (OSTI)

that bind protons and neutrons into nuclei. ARGONNE'S LEADERSHIP COMPUTING FACILITY The purpose of this high diseases. In 2012, Argonne's Leadership Computing Facility will house one of the fastest and most energy and federal laws governing management of Argonne's facility. The assignment to write this summary was given

Kemner, Ken

107

2012 Annual Planning Summary for Kansas City Site Office  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within the Kansas City Site Office.

108

Oak Ridge Reservation annual site environmental report summary 1998  

Science Conference Proceedings (OSTI)

This report summarizes the information found in the Oak Ridge Reservation Annual Site Environmental for 1998 (DOE/ORO/2091).

Hamilton, L.V.

1999-12-01T23:59:59.000Z

109

2012 Annual Planning Summary for Thomas Jefferson Site Office  

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

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

110

2011 Annual Planning Summary for Pantex Site Office (PXSO)  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Pantex Site Office (PXSO).

111

2012 Annual Planning Summary for Pantex Site Office  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within the Pantex Site Office.

112

2012 Annual Planning Summary for Ames Site Office  

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

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

113

2012 Annual Planning Summary for SLAC Site Office  

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

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

114

2012 Annual Planning Summary for Brookhaven Site Office  

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

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

115

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

Science Conference Proceedings (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

116

Mirror Advanced Reactor Study (MARS): executive summary and overview  

DOE Green Energy (OSTI)

Two self-consistent MARS configurations are discussed - a 1200-MWe commercial electricity-generating plant and a synguels-generating plant that produces hydrogen with an energy equivalent to 26,000 barrels of oil per day. The MARS machine emphasizes the attractive features of the tandem mirror concept, including steady-state operation, a small-diameter high-beta plasma, a linear central cell with simple low-maintenance blankets, low first-wall heat fluxes (<10 W/cm/sup 2/), no driven plasma currents or associated disruptions, natural halo impurity diversion, and direct conversion of end-loss charged-particle power. The MARS electric plant produces 2600 MW of fusion power in a 130-m-long central cell. Advanced tandem-mirror plasma-engineering concepts, a high-efficiency liquid lithium-lead (Li/sub 17/Pb/sub 83/) blanket, and efficient direct electrical conversion of end loss power combine to produce a high net plant efficiency of 36%. With a total capital cost of $2.9 billion (constant 1983 dollars), the MARS electric plant produces busbar electricity at approx. 7 cents/kW-hour. The MARS synfuels plant produces 3500 MW of fusion power in a 150-m-long central cell. A helium-gas-cooled silicon carbide pebble-bed blanket provides high-temperature (1000/sup 0/C) heat to a thermochemical water-splitting cycle and the resulting hydrogen is catalytically converted to methanol for distribution. With a total capital cost of $3.6 billion (constant 1983 dollars), the synfuels plant produces methanol fuel at about $1.7/gal. The major features of the MARS reactor include sloshing-ion thermal barrier plugs for efficient plasma confinement, a high efficiency blanket, high-field (24-T) choke cells, drift pumping for trapped plasma species, quasi-optical electron-cyclotron resonant heating (ECRH) systems, and a component gridless direct converter.

Logan, B.G.; Perkins, L.J.; Gordon, J.D.

1984-07-01T23:59:59.000Z

117

Data Summary Report for Hanford Site Coal Ash Characterization  

Science Conference Proceedings (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

118

2011 Annual Planning Summary for Fermi Site Office (FSO)  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Fermi Site Office (See Science APS).

119

2011 Annual Planning Summary for Kansas City Site Office (KCSO)  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Kansas City Site Office (KCSO).

120

2011 Annual Planning Summary for Brookhaven Site Office (BHSO)  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Brookhaven Site Office (BHSO) (See Science APS).

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

Section S Summary of the Site-Wide Environmental Assessment  

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

process that was completed in May 2002. In accordance with DOE NEPA implementing regulations, DOE is required to evaluate the Site- Wide Environmental Assessment (EA) after...

122

Remotely operated excavator needs assessment/site visit summary  

SciTech Connect

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

123

Summary of the Hanford Site Environmental Report for Calendar Year 2008  

SciTech Connect

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 site’s 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

124

Summary of the Hanford Site Environmental Report for Calendar Year 2009  

Science Conference Proceedings (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 site’s 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

125

Summary of the Hanford Site Environmental Report for Calendar Year 2007  

SciTech Connect

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 site’s 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

126

Summary - Disposal Practices at the Nevada Test Site  

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

Nevada Test Site, NV Nevada Test Site, NV EM Project: Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been discontinued, but the facility is available for future disposal. The anticipated closure date for Area 3 is 2027. Area 5 is operating and will be expanded to accept future wastes. LLRW and mixed low-level radioactive waste (MLLW) are disposed of in Area 5 in shallow

127

Summary - Disposal Practices at the Savannah River Site  

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

ETR-19 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Disposal Practices at the Savannah River Site Why DOE-EM Did This Review Disposal operations have been ongoing at the Savannah River Site (SRS) for over 50 years. Active disposal in E-Area, is near the center of the site. Although a wide range of wastes are being managed at the SRS, only low level radioactive wastes (LLRW) are disposed of on site. Wastes are disposed of in unlined slit and engineered trenches, and in low activity waste and intermediate level vaults. Some wastes are isolated in place with grout and all wastes will be covered with a cap that includes a hydraulic barrier to limit precipitation infiltration. The objective of this review was to

128

Summary - Disposal Practices at the Savannah River Site  

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

ETR-19 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Disposal Practices at the Savannah River Site Why DOE-EM Did...

129

Savannah River Site`s Site Specific Plan. Environmental restoration and waste management, fiscal year 1992: Executive summary  

SciTech Connect

This report describes the environmental restoration and waste management (ER/WM) planning process, communicates ER/WM`s philosophy and overall strategy for achieving its compliance and cleanup goals, summarizes multi-year program plans and assesses progress made during the previous year. The FYP goal is to ensure that risks to human health and safety and to the environment posed by the Department`s past, present, and future operations are either eliminated to reduced to safer levels by the year 2019. The SSP applies the overall strategic goals and commitments of the FYP, incorporating site-specific and local public considerations. It will address accomplishments since the FY 1990 plan, document planned activities focused on the upcoming fiscal year (FY 1992) and discuss milestones and objectives based on restricted and nonrestricted budget conditions for FY 1993--1997. The SSP is the primary means of demonstrating the relationship of local cleanup and compliance activities to broad environmental goals set forth in the FYP. The SSP provides an important channel for conveying information to regulators, the public, special interest groups, and other DOE organizations. This summary will briefly review the site`s facilities and missions, current and future program objectives, major accomplishments, funding levels, and major milestones for the five-year period.

1991-08-01T23:59:59.000Z

130

Savannah River Site Settlement Agreement, August 26, 1991 Summary  

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

91-51-SW 91-51-SW State South Carolina Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Establish procedures and guidelines for F listed solvent contaminated rag disposal Parties DOE (SRS); State of South Carolina (Department of Health and Environmental Control) Date 8/26/1991 SCOPE * Establish a course of action for DOE's violation of the South Carolina Hazardous Waste Management Regulations at the SRS. * Establish procedures and guidelines for F listed solvent contaminated rag disposal. ESTABLISHING MILESTONES * By October 31, 1991, SRS shall amend the Part A Permit Application to include the solvent rags and wipes and those portions of the LLRWDF and sanitary landfill which have received these wastes. * By August 31, 1993, SRS shall submit to DHEC an amendment to the closure plans

131

Savannah River Site Settlement Agreement, November 10, 1987 Summary  

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

52-SW, as amended 5/9/1991 52-SW, as amended 5/9/1991 and 10/5/1995 State South Carolina Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Establish a course of action due to DOE's violation of the Department's Hazardous Waste Management Regulations. Parties DOE (SRP); State of South Carolina (Department of Health and Environmental Control) Date 11/10/1987 SCOPE * Establish a course of action due to DOE's violation of the Department's Hazardous Waste Management Regulations. * Update appropriate milestone dates. ESTABLISHING MILESTONES * DOE shall attend quarterly meetings with the Department concerning updates on the hydrogeologic investigation of the BGC and the Part B Permit Application. * By November 15, 1995, DOE shall submit a Part B Permit Application for the MWMF

132

Savannah River Site Settlement Agreement, May 1, 1987 Summary  

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

27-SW 27-SW State South Carolina Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Establish a course of action due to SRP's violation of the Department's Hazardous Waste Management Regulations including updated submission dates for Part B Permit Applications. Parties DOE (SRP); State of South Carolina (Department of Health and Environmental Control) Date 5/1/1987 SCOPE * Establish a course of action due to SRP's violation of the Department's Hazardous Waste Management Regulations. * Appropriately update submission dates for Part B Permit Applications. ESTABLISHING MILESTONES * By April 30, 1987, DOE shall submit to DHEC a revised Part B Permit Application for M Area Settling Basin, Overflow Ditch, Seep Area, and Lost Lake and the container

133

Summary - Plutonium Preparation Project at the Savannah River Site  

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

Site Site EM Project: PuPP ETR Report Date: October 2008 ETR-17 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Plutonium Preparation Project at the Savannah River Site Why DOE-EM Did This Review The purpose of the Plutonium Preparation Project (PuPP) is to prepare for disposition of plutonium materials; for examination, re-stabilization, and disassembly of the Fast Flux Test Facility (FFTF) unirradiated fuel; and for repackaging of Pu stored in 3013 containers. Of ~12.8 MT of plutonium, ~4.1 MT will be directly transferred to the MOX Fuel Fabrication Facility (MFFF); ~3.7 MT will require processing prior to transfer to the MFFF; and ~5 MT was proposed to be processed in H-Canyon with the

134

Summary  

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

RAINFOREST REALITIES Project Summary Scenario Student Pages Internet Links Index SubjectContent Area: Science, Language Arts, Math, and Social Science Target Audience: This...

135

summary  

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

Project Summary Scenario Student Page Internet Links Index SubjectContent Area: Math - data collection; Language Arts - expressive and narrative writing and reference skills;...

136

Site Suitability and Hazard Assessment Guide for Small Modular Reactors  

SciTech Connect

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

137

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

SciTech Connect

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

138

Chu Visits Site of America's First New Nuclear Reactor in Three...  

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

Chu Visits Site of America's First New Nuclear Reactor in Three Decades Chu Visits Site of America's First New Nuclear Reactor in Three Decades February 15, 2012 - 2:12pm Addthis...

139

Chu Visits Site of America's First New Nuclear Reactor in Three...  

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

Chu Visits Site of America's First New Nuclear Reactor in Three Decades Chu Visits Site of America's First New Nuclear Reactor in Three Decades February 15, 2012 - 12:40pm Addthis...

140

Savannah River Site environmental implementation plan. Volume 1, Executive summary  

SciTech Connect

Formal sitewide environmental planning at the Savannah River Site (SRS) began in 1986 with the development and adoption of the Strategic Environmental Plan. The Strategic Environmental Plan describes the philosophy, policy, and overall program direction of environmental programs for the operation of the SRS. The Strategic Environmental Plan provided the basis for development of the Environmental Implementation Plan (EIP). The EIP is the detailed, comprehensive environmental master plan for operating contractor organizations at the SRS. The EIP provides a process to ensure that all environmental requirements and obligations are being met by setting specific measurable goals and objectives and strategies for implementation. The plan is the basis for justification of site manpower and funding requests for environmental projects and programs over a five-year planning period.

1989-08-01T23:59:59.000Z

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

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

Science Conference Proceedings (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

142

Management of Hanford Site non-defense production reactor spent nuclear fuel, Hanford Site, Richland, Washington  

SciTech Connect

The US Department of Energy (DOE) needs to provide radiologically, and industrially safe and cost-effective management of the non-defense production reactor spent nuclear fuel (SNF) at the Hanford Site. The proposed action would place the Hanford Site`s non-defense production reactor SNF in a radiologically- and industrially-safe, and passive storage condition pending final disposition. The proposed action would also reduce operational costs associated with storage of the non-defense production reactor SNF through consolidation of the SNF and through use of passive rather than active storage systems. Environmental, safety and health vulnerabilities associated with existing non-defense production reactor SNF storage facilities have been identified. DOE has determined that additional activities are required to consolidate non-defense production reactor SNF management activities at the Hanford Site, including cost-effective and safe interim storage, prior to final disposition, to enable deactivation of facilities where the SNF is now stored. Cost-effectiveness would be realized: through reduced operational costs associated with passive rather than active storage systems; removal of SNF from areas undergoing deactivation as part of the Hanford Site remediation effort; and eliminating the need to duplicate future transloading facilities at the 200 and 400 Areas. Radiologically- and industrially-safe storage would be enhanced through: (1) removal from aging facilities requiring substantial upgrades to continue safe storage; (2) utilization of passive rather than active storage systems for SNF; and (3) removal of SNF from some storage containers which have a limited remaining design life. No substantial increase in Hanford Site environmental impacts would be expected from the proposed action. Environmental impacts from postulated accident scenarios also were evaluated, and indicated that the risks associated with the proposed action would be small.

1997-03-01T23:59:59.000Z

143

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

Science Conference Proceedings (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

144

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

Science Conference Proceedings (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

145

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

SciTech Connect

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

146

Summary - Tank 48 at the Savannah River Site  

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

Tank 48 Tank 48 ETR Report Date: August 2006 ETR-2 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Tank 48 at the Savannah River Site (SRS) Why DOE-EM Did This Review Tank 48 is a 1.3 million gallon tank with full secondary containment, located and interconnected within the SRS tank system that will play a very important role in removal and processing of high-level waste (HLW) in the years ahead. However, the tank is currently isolated from the system and unavailable for use, because its contents. It contains approximately 250,000 gallons of salt solution containing Cesium-137 and other radioisotopes which are contaminated with significant quantities of tetraphenylborate (TPB), a material which

147

Summary  

Science Conference Proceedings (OSTI)

Summary. A, B, C, D, E, F, G, H, I, J, K, L, M, N, O, P, Q, R, S, T, U, V, W, X, Y, Z. 1, STEP File, STEP-File-Analyzer.stp, 2, STEP Directory, C ...

2013-08-12T23:59:59.000Z

148

Summary  

Science Conference Proceedings (OSTI)

Summary. A, B, C, D, E, F, G, H, I, J, K, L, M, N, O, P, Q, R, S, T, U, V, W, X, Y, Z. 1, STEP File, STEP-File-Analyzer-Semantic-PMI.stp, 2, STEP ...

2013-08-12T23:59:59.000Z

149

Summary of advanced LMR (Liquid Metal Reactor) evaluations: PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor)  

Science Conference Proceedings (OSTI)

In support of the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) has performed independent analyses of two advanced Liquid Metal Reactor (LMR) concepts. The designs, sponsored by the US Department of Energy (DOE), the Power Reactor Inherently Safe Module (PRISM) (Berglund, 1987) and the Sodium Advanced Fast Reactor (SAFR) (Baumeister, 1987), were developed primarily by General Electric (GE) and Rockwell International (RI), respectively. Technical support was provided to DOE, RI, and GE, by the Argonne National Laboratory (ANL), particularly with respect to the characteristics of the metal fuels. There are several examples in both PRISM and SAFR where inherent or passive systems provide for a safe response to off-normal conditions. This is in contrast to the engineered safety systems utilized on current US Light Water Reactor (LWR) designs. One important design inherency in the LMRs is the inherent shutdown'', which refers to the tendency of the reactor to transition to a much lower power level whenever temperatures rise significantly. This type of behavior was demonstrated in a series of unscrammed tests at EBR-II (NED, 1986). The second key design feature is the passive air cooling of the vessel to remove decay heat. These systems, designated RVACS in PRISM and RACS in SAFR, always operate and are believed to be able to prevent core damage in the event that no other means of heat removal is available. 27 refs., 78 figs., 3 tabs.

Van Tuyle, G.J.; Slovik, G.C.; Chan, B.C.; Kennett, R.J.; Cheng, H.S.; Kroeger, P.G. (Brookhaven National Lab., Upton, NY (USA))

1989-10-01T23:59:59.000Z

150

Advanced Light Water Reactor utility requirements document. Part 1, Executive summary  

SciTech Connect

The ALWR Requirements Document is a primary work product of the EPRI Program. This document is an extensive compilation of the utility requirements for design, construction and performance of advanced light water reactor power plants for the 1990s and beyond. The Requirements Document`s primary emphasis is on resolution of significant problems experienced at existing nuclear power plants. It is intended to be used with companion documents, such as utility procurement specifications, which would cover the remaining detailed technical requirements applicable to new plant projects. The ALWR Requirements Document consists of several major parts. This volume is Part I, The Executive Summary. It is intended to serve as a concise, management level synopsis of advanced light water reactors including design objectives and philosophy, overall configuration and features and the steps necessary to proceed from the conceptual design stage to a completed, functioning power plant.

1986-06-01T23:59:59.000Z

151

SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING  

SciTech Connect

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

152

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

SciTech Connect

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

153

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

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

Lawrence Livermore National Laboratory (Main Site) Lawrence Livermore National Laboratory (Main Site) Federal Facility Agreement Under CERCLA Section 120, November 1, 1988 State California Agreement Type Federal Facility Agreement Legal Driver(s) CERCLA Scope Summary Establish a procedural framework and schedule for developing, implementing, and monitoring appropriate response actions at the Site Parties DOE; USEPA; California Department of Health Services; California Regional Water Quality Control Board Date 11/1/1988 SCOPE * Establish a procedural framework and schedule for developing, implementing, and monitoring appropriate response actions at the Site. * Establish a basis for a determination that the DOE has completed remedial action and corrective measures to satisfaction. ESTABLISHING MILESTONES

154

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

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

Reactor Site - Fort Belvoir - VA Reactor Site - Fort Belvoir - VA 0-02 FUSRAP Considered Sites Site: REACTOR SITE - FORT BELVOIR (VA.0-02 ) Eliminated from further consideration under FUSRAP - Referred to DOD Designated Name: Not Designated Alternate Name: None Location: Fort Belvoir , Virginia VA.0-02-1 Evaluation Year: 1987 VA.0-02-1 Site Operations: No evidence of AEC involvement with reactor operations. AEC conducted health and safety inspections of this site. Probably a licensed operation. VA.0-02-1 Site Disposition: Eliminated - Referred to DOD VA.0-02-1 Radioactive Materials Handled: Reactor fuel Primary Radioactive Materials Handled: Reactor Fuel Radiological Survey(s): Health and safety inspections VA.0-02-1 Site Status: Eliminated from further consideration under FUSRAP - Referred to DOD VA.0-02-1

155

Summary  

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

Project Summary Project Summary HELP Index Summary Scenario References Student Pages Subject/Content Area: Ecology and Data Collection Target Audience: This project is designed for upper intermediate grade students. Access to a river or stream is critical to the success of this project. Students need access to the Internet and data collection software. Project Goals: When presented with an environmental problem on a local river, students will use their knowledge of river ecology to develop an action plan. Learner Outcomes: The students will be able to Use river monitoring equipment to collect river monitoring data, including biological, physical,and chemical data. Design a project that aids the class in accompolishing one of four goals: Raising smallmouth bass Creating a stream habitat in an aquarium

156

Evaluation of the impact of a committed site on fusion reactor development  

SciTech Connect

The technical and economic merits of a committed fusion site for development of tokamak, mirror, and EBT reactor from ignition through demo phases were evaluated. Schedule compression resulting from evolving several reactor concepts and/or phases on a committed site as opposed to sequential use of independent sites was estimated. Land, water, and electrical power requirements for a committed fusion site were determined. A conceptual plot plan for siting three fusion reactors on a committed site was configured. Reactor support equipment common to the various concepts was identified as candidates for sharing. Licensing issues for fusion plants were briefly addressed.

Reid, R.L.; Nagy, A.

1979-01-01T23:59:59.000Z

157

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

SciTech Connect

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

158

Summary  

Science Conference Proceedings (OSTI)

Summary. A, B, C, D, E, F, G, H, I, J, K, L, M, N, O, P, Q, R, S, T, U, V, W, X, Y, Z. 1, CIS/2 File, AISC_Sculpture_J.stp, 2, CIS/2 Directory, C:\\Users ...

2013-05-21T23:59:59.000Z

159

Estimating the cold war mortgage: The 1995 baseline environmental management report. Volume II: Site summaries  

SciTech Connect

This volume, Volume II presents the site data that was used to generate the Department of Energy`s (DOE) initial Baseline Environmental Management Report (BEMR). The raw data was obtained by DOE field personnel from existing information sources and anticipated environmental management strategies for their sites and was tempered by general assumptions and guidance developed by DOE Headquarters personnel. This data was then integrated by DOE Headquarters personnel and modified to ensure that overall constraints such as funding and waste management capacity were addressed. The site summaries are presented by State and broken out by discrete activities and projects. The Volume I Glossary has been repeated to facilitate the reader`s review of Volume II. The information presented in the site summaries represents the best data and assumptions available as of February 1, 1995. Assumptions that have not been mandated by formal agreement with appropriate regulators and other stakeholders do not constitute decisions by the Department nor do they supersede existing agreements. In addition, actions requiring decisions from external sources regarding unknowns such as future land use and funding/scheduling alternatives, as well as internal actions such as the Department`s Strategic Realignment initiative, will alter the basis and general assumptions used to generate the results for this report. Consequently, the numbers presented in the site summaries do not represent outyear budget requests by the field installations.

NONE

1995-03-01T23:59:59.000Z

160

Federal Facility Compliance Act, Proposed Site Treatment Plan: Background Volume. Executive Summary  

SciTech Connect

This Federal Facility Compliance Act Site Treatment Plan discusses the options of radioactive waste management for Ames Laboratory. This is the background volume which discusses: site history and mission; framework for developing site treatment plans; proposed plan organization and related activities; characterization of mixed waste and waste minimization; low level mixed waste streams and the proposed treatment approach; future generation of TRU and mixed wastes; the adequacy of mixed waste storage facilities; and a summary of the overall DOE activity in the area of disposal of mixed waste treatment residuals.

1995-03-24T23:59:59.000Z

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

Summary  

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

Golden Field Office Golden Field Office Office of Energy Efficiency and Renewable Energy DOE/EIS-0407D September 2009 Draft Environmental Impact Statement for the Proposed Abengoa Biorefinery Project near Hugoton, Stevens County, Kansas Summary Cover photos courtesy of (left to right): Southeast Renewable Fuels, LLC DOE National Renewable Energy Laboratory Public domain U.S. Department of Energy Golden Field Office Office of Energy Efficiency and Renewable Energy DOE/EIS-0407D September 2009 Draft Environmental Impact Statement for the Proposed Abengoa Biorefinery Project near Hugoton, Stevens County, Kansas Summary COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) COOPERATING AGENCY: The U.S. Department of Agriculture-Rural Development is a cooperating agency in the preparation of the Abengoa Biorefinery Project EIS.

162

Summary  

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

SPACE SPACE Project Summary HELP Index Summary Scenario Internet Links Student Pages Subject/Content Area: Interdisciplinary: Science - astronomy; Math - problem-solving and measurement; Art; Social Studies - current events; and Language Arts - reference. skills Target Audience: Middle school students, 7th grade, all levels Project Goals: A collaborative, seven-to-ten weeks investigation of the space program, specifically space stations, its impact on our lives and the world Learner Outcomes: Students will be able to: Gather information and use decision-making skills to evaluate this information. Establish connections and to develop decision-making skills about science and technology. Identify and state a problem; design, implement, and evaluate the solution. Gather and use information for research purposes.

163

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

Science Conference Proceedings (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

164

CIVILIAN POWER REACTOR PROGRAM. PART I. SUMMARY OF TECHNICAL AND ECONOMIC STATUS AS OF 1960. HEAVY WATER-MODERATED POWER REACTORS  

SciTech Connect

A revision of section 8 of TID-8516, Part I, is presented. The reactor concept which is presented is a change from the former design, a pressurized- pressure vessel-indirect cycle plant to a boiling-pressure tubedirect cycle plant. A description of the plant and a summary of characteristics for the 110- and 325- Mwe systems are given. (J.R.D.)

Hutton, J.H.; Davis, S.A.; Graves, C.C.; Duffy, J.G. comps.

1960-08-19T23:59:59.000Z

165

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

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

Order Requiring Compliance with Site Treatment Plan Order Requiring Compliance with Site Treatment Plan No. 95-10-03-01 State Colorado Agreement Type Consent Order Legal Driver(s) FFCAct Scope Summary Approve with modifications the Proposed Site Treatment Plan for RFETS (MLLW); establish a Mixed Transuranic waste Agreement Parties DOE; Colorado Department of Public Health and Environment (CDPHE) Date 10/3/1995 SCOPE * In regard to Mixed Low-Level waste, approve with modifications the Proposed Site Treatment Plan for RFETS and require compliance by DOE with the modified and approved Site Treatment Plan. * In regard to Mixed Transuranic waste, establish and ensure compliance with an Agreement addressing compliance with the Hazardous and Solid Waste Amendments of 1984 to RCRA. ESTABLISHING MILESTONES

166

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

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

Savannah River Site Consent Order, September 29, 1995 Savannah River Site Consent Order, September 29, 1995 (No. 95-22-HW) State South Carolina Agreement Type Consent Order Legal Driver(s) FFCAct Scope Summary Approve and establish guidelines for the Proposed Site Treatment Plan Parties DOE (SRS); State of South Carolina (Department of Health and Environmental Control) Date 9/29/1995 SCOPE * Approve the Proposed Site Treatment Plan, now to be known as the Approved Site Treatment Plan. * Establish guidelines for executing the Approved STP. ESTABLISHING MILESTONES * No later than April 30 of each year, SRS shall submit to the Department Annual Updates to the Approved STP. * SRS shall submit to the Department for information only a progress report on the Waste Isolation Pilot Plan (WIPP) with the Annual Update.

167

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

Office of Legacy Management (LM)

Milton Reactor Site - NY 21 Milton Reactor Site - NY 21 FUSRAP Considered Sites Site: West Milton Reactor Site (NY.21) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This site is one of a group of 77 FUSRAP considered sites for which few, if any records are available in their respective site files to provide an historical account of past operations and their relationship, if any, with MED/AEC operations. Reviews of contact lists, accountable station lists, health and safety records and other documentation of the period do not provide sufficient information to warrant further search of historical records for information on these sites. These site files remain "open" to

168

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

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

UNITED STATES DEPARTMENT OF UNITED STATES DEPARTMENT OF ENERGY Site Transition Summary: Cleanup Completion to Long-Term Stewardship at Department of Energy On- going Mission Sites February 2012 Introduction Long-term stewardship (LTS) includes the physical controls, institutions, information, and other mechanisms needed to ensure protection of people and the environment at sites where the U.S. Department of Energy (DOE) has completed or plans to complete cleanup (e.g., landfill closures, remedial actions, removal actions, and facility stabilization). This concept includes land-use controls, information management, monitoring and maintenance. DOE has ongoing mission areas related to advancing energy and nuclear security, promoting scientific discovery and innovation, and ensuring environmental responsibility

169

Reactor operation safety information document  

Science Conference Proceedings (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

170

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

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

DOI Designates B Reactor at DOE's Hanford Site as a National DOI Designates B Reactor at DOE's Hanford Site as a National Historic Landmark DOI Designates B Reactor at DOE's Hanford Site as a National Historic Landmark August 25, 2008 - 3:20pm Addthis DOE to offer regular public tours in 2009 WASHINGTON, DC - U.S. Department of the Interior (DOI) Deputy Secretary Lynn Scarlett and U.S. Department of Energy (DOE) Acting Deputy Secretary Jeffrey F. Kupfer today announced the designation of DOE's B Reactor as a National Historic Landmark and unveiled DOE's plan for a new public access program to enable American citizens to visit B Reactor during the 2009 tourist season. The B Reactor at DOE's Hanford Site in southeast Washington State was the world's first industrial-scale nuclear reactor and produced plutonium for the atomic weapon that was dropped on Nagasaki,

171

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

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

DOI Designates B Reactor at DOE's Hanford Site as a National DOI Designates B Reactor at DOE's Hanford Site as a National Historic Landmark DOI Designates B Reactor at DOE's Hanford Site as a National Historic Landmark August 25, 2008 - 3:20pm Addthis DOE to offer regular public tours in 2009 WASHINGTON, DC - U.S. Department of the Interior (DOI) Deputy Secretary Lynn Scarlett and U.S. Department of Energy (DOE) Acting Deputy Secretary Jeffrey F. Kupfer today announced the designation of DOE's B Reactor as a National Historic Landmark and unveiled DOE's plan for a new public access program to enable American citizens to visit B Reactor during the 2009 tourist season. The B Reactor at DOE's Hanford Site in southeast Washington State was the world's first industrial-scale nuclear reactor and produced plutonium for the atomic weapon that was dropped on Nagasaki,

172

Chu Visits Site of America?s First New Nuclear Reactor in Three...  

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

5, 2012 Chu Visits Site of Americas First New Nuclear Reactor in Three Decades Energy Secretary Announces New Nuclear Energy Research Grants and Next Steps on Used Fuel...

173

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

SciTech Connect

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

Sarah Roberts

2006-10-18T23:59:59.000Z

174

Candidate wind turbine generator site, Culebra, Puerto Rico. Annual data summary, October 1978-September 1979  

DOE Green Energy (OSTI)

This report summarizes wind speed and direction data collected on meteorological towers at 14 candidate and wind turbine generator installation sites from October 1978 through September 1979. The basic method of data collection is by digital data cassette recording systems. For the digital data reported, an instantaneous sample is recorded every 2 minutes. An explanation is provided for each data summary table as well as information on how specific values were computed. The rest of the report presents the annual summarized data for each site.

Not Available

1980-07-01T23:59:59.000Z

175

Candidate wind turbine generator site, Culebra, Puerto Rico. Annual data summary, January-December 1979  

DOE Green Energy (OSTI)

This report summarizes wind speed and direction data collected on meteorological towers at 14 candidate and wind turbine generator installation sites from January 1979 through December 1979. The basic method of data collection is by digital data cassette recording systems. For the digital data reported, an instantaneous sample is recorded every 2 minutes. An explanation is included for each data summary table as well as information on how specific values were computed. The rest of the report presents the annual summarized data for each site.

None

1980-06-01T23:59:59.000Z

176

Summary  

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

Imperial-Mexicali DEIS Imperial-Mexicali DEIS S-1 May 2004 SUMMARY S.1 BACKGROUND S.1.1 Previous NEPA Review and Litigation Baja California Power, Inc. (hereafter referred to as Intergen), applied to the U.S. Department of Energy (DOE) on February 27, 2001, to construct a double-circuit, 230,000-volt (230-kV) transmission line across the U.S.-Mexico border. In a separate but similar proceeding, Sempra Energy Resources (hereafter referred to as Sempra) applied to DOE for a Presidential permit on March 7, 2001, also proposing to construct a double-circuit, 230-kV transmission line across the U.S.-Mexico border. Executive Order (E.O.) 10485 (September 9, 1953), as amended by E.O. 12038 (February 7, 1978), requires that a Presidential permit be issued by DOE before electric transmission facilities may be constructed, operated, maintained,

177

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 the reactor in the southern French city of Cadarache. Nuclear fusion is the process by which the atomic nuclei than burning fossil fuels or even nuclear fission, which is used in nuclear reactors today but produces

178

Reactor Vessel Internals Inspection and Reactor Pressure Vessel Surveillance Program Summaries for R.E. Ginna and Nine Mile Point Unit 1  

Science Conference Proceedings (OSTI)

This report provides a summary of project activities involving the reactor pressure vessel and internals for the nuclear power plants included in the joint Electric Power Research Institute (EPRI), Department of Energy (DOE), and Constellation Energy Nuclear Group (CENG) Nuclear Plant Life Extension demonstration project.BackgroundThe project focused on continuing operations at two CENG nuclear units that are currently operating in their extended license ...

2013-12-18T23:59:59.000Z

179

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

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

for Radionuclide for Radionuclide NESHAP State Washington Agreement Type Federal Facility Compliance Agreement Legal Driver(s) CAA Scope Summary Bring DOE's Hanford site into compliance with CAA Parties EPA; DOE; Richland Operations Office (RL) Date 02/07/1994 SCOPE * Bring DOE's Hanford site into compliance with CAA. This Compliance Plan contains a schedule for DOE to evaluate the monitoring systems associated with Designated Stacks to ensure that these systems conform to the standards for continuous monitoring systems in 40 Code of Federal Regulations (CFR) Part 61, Subpart H. ESTABLISHING MILESTONES * Beginning 30 days after the effective date of this Agreement, DOE shall submit quarterly progress reports to EPA until the requirements contained in Amendment A

180

Summary of the environmental dose models used at DOE nuclear sites in 1979  

SciTech Connect

Methods for assessing public exposure to radiation from normal operations at DOE facilities are reviewed in this report. This review includes a summary of the methods used in 1979 as described in annual environmental reports submitted by Department of Energy (DOE) contractors. The methods used ranged from estimating public doses based on environmental measurements and comparison to the DOE concentration guides, to complex methods using environmental pathway modeling and estimated radionuclide releases. No two sites used the same combination of measurements and pathway models in their analysis. While most sites used an atmospheric dispersion model to predict air concentrations of radioactive material, only about half of the sites provided enough information about the model used to permit proper model evaluation. The waterborne pathways related to drinking water or ingestion of fish were generally well described, while the external exposure or terrestrial food pathways were often not considered. The major recommendation resulting from this review was that complete documentations of the models used should be included either within the annual reports or as separate readily available documents. In addition, most sites could make better use of graphics (i.e., tables and figures) to better communicate the findings of their analyses.

Kennedy, W.E. Jr.; Mueller, M.A.

1982-09-01T23:59:59.000Z

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

Argonne National Laboratory-East summary site environmental report for calendar year 2002.  

DOE Green Energy (OSTI)

Argonne performs research and development in many areas of science and technology. General fields of research at Argonne include, but are not limited to, biosciences, biotechnology, chemical engineering, chemistry, decision and information sciences, energy systems and technology, high energy physics, materials science, math and computer science, nuclear reactors, physics, and environmental science. Argonne is not, and never has been, a weapons laboratory. Several missions provide focus for Argonne scientists. Basic research helps better understand the world, and applied research helps protect and improve it. For example, the prairies of Argonne provide sites for environmental studies that provide valuable information about invader species and the food webs within ecosystems. Argonne also operates world-class research facilities, such as the Advanced Photon Source (APS), which is a national research facility funded by the U.S. Department of Energy (DOE). Scientists use high brilliance X-rays from the APS for basic and applied research in many fields. Argonne also seeks to ensure our energy future. Currently, scientists and engineers are developing cleaner and more efficient energy sources, such as fuel cells and advanced electric power generation. Argonne has spent much of its history on developing nuclear reactor technology. That research is now being applied to American and Soviet nuclear reactors to improve the safety and life of the reactors. Other Argonne research seeks to improve the way we manage our environment. For example, Argonne scientists created a new catalyst that could help carmakers eliminate 95 percent of nitrogen-oxide emitted by diesel engines by the year 2007. Research and development solutions such as these will help protect our ecosystems.

Golchert, N. W.; Kolzow, R. G.

2004-03-08T23:59:59.000Z

182

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

E-Print Network (OSTI)

Powered by | |SAVE THIS EMAIL THIS Close Japan ups bid for fusion reactor site TOKYO, Japan (AP) -- Tokyo would boost its investment in the world's first large-scale nuclear fusion plant by almost U.S. $1 billion if the project's sponsors build the reactor in Japan, a newspaper reported Wednesday. Construction

183

U.S.Statements on International Fusion Reactor (ITER) Siting Decision |  

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

U.S.Statements on International Fusion Reactor (ITER) Siting U.S.Statements on International Fusion Reactor (ITER) Siting Decision U.S.Statements on International Fusion Reactor (ITER) Siting Decision June 28, 2005 - 1:45pm Addthis WASHINGTON, DC - Today in Moscow, Russia, the ministers representing the six ITER parties, including Dr. Raymond L. Orbach, Director of the U.S. Department of Energy's Office of Science, announced the ITER international fusion reactor will be located at the EU site in Cadarache, France. Below are statements by U.S. government officials following the signing of the agreement at the Ministerial Meeting. The text of the announcement by the six parties is available at www.iter.org/index_newsroom.htm. Statement by U.S. Secretary of Energy Samuel W. Bodman: "Plentiful, reliable energy is critical to continued worldwide economic

184

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

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

9-09-24-01 9-09-24-01 State Colorado Agreement Type Consent Order Legal Driver(s) RCRA Scope Summary Substitute this Consent Order for the MR Consent Order; establish requirements for mixed residues management. Parties DOE ; Kaiser-Hill Company, LLC; Safe Sites of Colorado, LLC; Rocky Mountain Remediation Services, LLC; Colorado Department of Public Health and Environment Date 9/24/1999 SCOPE * Substitute this Consent Order for the MR Consent Order by modifying in its entirety the Settlement Agreement and Compliance Order on Consent, number 93-04-23-01, (the "MR Consent Order"). * Establish requirements for certain activities involving mixed residues management. * Establish enforceable commitment dates. ESTABLISHING MILESTONES * Provisions regarding enforceable commitment dates and the procedures to add

185

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

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

6064 (2) Revision Number: 0 (3) Effective Date: 04/15/2010 6064 (2) Revision Number: 0 (3) Effective Date: 04/15/2010 (4) Document Type: [I Digital Image ElHard copy (a) Number of pages (including the DRF) or 15 Z PDF Video number of digital images (5) Release Type 0 New l Cancel 11: Page Change l complete Revision (6) Document Title: Meeting Minutes for the WMA C PA Features, Events, and Processes Working Session (7) Change/Release Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Description: Waste Management Area C performance assessment on Features, Events, and Processes (8) Change N/A Justification: (9) Associated (a) Structure Location: (c) Building Number: Structure, System, and Component N/A N/A (SSC) and Building (b) System Designator: (d) Equipment ID Number (EIN): Number:

186

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

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

Settlement Agreement for Transuranic (TRU) Mixed Settlement Agreement for Transuranic (TRU) Mixed Waste Storage Issues at the Nevada Test Site (NTS) State Nevada Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS Parties DOE; Nevada Department of Environmental Protection Date 6/11/1992 SCOPE * Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS. ESTABLISHING MILESTONES * Within 90 days of the effective date of this Agreement, DOE will provide to NDEP documentation of why the current inventory of TRU mixed waste cannot be removed

187

C^ DECOMMISSIONING OF EIGHT SURPLUS PRODUCTION REACTORS AT THE HANFORD SITE,  

E-Print Network (OSTI)

To request copies of the draft environmental impact statement, contact Ms. WheeLess at the above address. e.`? ABSTRACT: The purpose of this Draft Envirormental Impact Statement ( DEIS) is to provide environmental information to assist the U.S. Department of Energy ( DOE) in the selection of a decomaissioning alternative for the eight surplus production reactors at the Hanford Site, Richland, Washington. Five alternatives are considered in this DEIS: 1) No Action, in which the reactors are left in place and the present maintenance and surveillance programs are continued; 2) Immediate One-Piece Removal, in which the reactor buildings are demolished and the reactor blocks are transported in one piece on a tractor-transporter across the Site along a predetermined route to an onsite low-Level ^* ( waste burial area; 3) Safe Storage Followed by Deferred One-Piece Removal, in which the reactors are temporarily stored in a safe, secure status for 75 years, after which the reactor buildings are demolished and the reactor blocks are transported in one piece on a tractor-transporter across the Site along a predetermined route to an onsite low-LeveL waste-buriat area; 4) Safe Storage Followed by Deferred Dismantlement, in which the reactors are temporarily stored in a safe, secure status for

Karen J. Wheeless

1989-01-01T23:59:59.000Z

188

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

SciTech Connect

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

189

DESIGN AND HAZARDS SUMMARY REPORT, BOILING REACTOR EXPERIMENT V (BORAX V)  

SciTech Connect

Design data for BORAX V are presented along with results of hazards evaluation studies. Considcration of the hazards associated with the operation of BORAX V was based on the following conditions: For normal steady-state power and experimental operation, the reactor and plant are adequately shielded and ventilated to allow personnel to be safely stationed in the turbine building and on the main floor of the reactor building. The control building is located one- half mile distant from the reactor building. For special, hazardous experiments, personnel are withdrawn from the reactor area. (M.C.G.)

1961-05-01T23:59:59.000Z

190

HEAVY-WATER-MODERATED POWER REACTORS ENGINEERING AND ECONOMIC EVALUATIONS. VOLUME I. SUMMARY REPORT  

SciTech Connect

Capital investments and the cost of power were estimated for 21 heavy- water-moderated, natural-uraniumfueled power-reactor plants, ranging in capacity from 100 to 460 Mw(e). Comparisons were made of hot- and coldmoderator reactors and of the relative merits of pressuretube and pressure-vessel designs. Reactors cooled with liquid D/sub 2/O, boiling D/sub 2/O, /sub 2/O steam, and helium were evalunted. A cold-moderator pressure-tube reactor cooled with boiling D/sub 2/O shows the most economic promise of the D/sub 2/Omoderated reactor systems studied to date. Reactors of this type have sufficient reactivity to permit satisfactory fuel exposures, but the development of additional technology is a prerequisite for optimum designs. At capacities of 300 and 400 Mw(e), the estimated power costs from the current designs of boiling-D/sub 2/O pressure-tabe reactor plants are 11.3 and 9.8 mills/kwh, respectively. From liquid-D/sub 2/-cooled concepts of comparable capacities the indicated power costs are 7 to 20% higher. With an active development program, a power cost of 8.0 to 8.5 mills/kwh may be attained in a 300 Mw(e) boiling-D/sub 2/O reactor plant within the next decade. (auth)

1960-06-01T23:59:59.000Z

191

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

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

Y Y : J O H N D . S T E V E N S O N C O N S U L T I N G E N G I N E E R 6 6 1 1 R O C K S I D E R D . I N D E P E N D E N C E , O H I O 4 4 1 3 1 T E L . 2 1 6 - 4 4 7 - 9 4 4 0 E M A I L : J S T E V E N S O N 4 @ E A R T H L I N K . N E T SUMMARY OF REVISED TORNADO, HURRICANE AND EXTREME STRAIGHT WIND CHARACTERISTICS AT NUCLEAR FACILITY SITES Categorization of Natural Hazard Phenomenon and Operational Load Combinations Prior to the 1988 Uniform Building Code, UBC (1) natural hazard phenomenon (earthquake, wind, flooding and precipitation) and operational load combinations were divided into two categories: NORMAL- Loads such as dead, live and design basis pressure. Expected frequency: 1.0 per yr with a limiting acceptance criteria Allowable stress design criteria: equal to one-half to two-thirds of specified minimum yield stress. SEVERE - Natural hazard and operational transient loads.

192

Summary of geology at the ERDA--MAGMA--SDG and E geothermal test site  

DOE Green Energy (OSTI)

A summary is given of the geologic structure of the test facility in Imperial County. The analysis is based on well records, especially electrical logs. (LBS)

Towse, D.F.; Palmer, T.D.

1976-01-12T23:59:59.000Z

193

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

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

Chu Visits Site of America's First New Nuclear Reactor in Three Chu Visits Site of America's First New Nuclear Reactor in Three Decades Chu Visits Site of America's First New Nuclear Reactor in Three Decades February 15, 2012 - 12:40pm Addthis WASHINGTON, D.C. - Just two days after the Department of Energy requested more than $770 million for nuclear energy in 2013, U.S. Secretary of Energy Steven Chu visited the Vogtle nuclear power plant in Waynesboro, Georgia and Oak Ridge National Laboratory to highlight the steps the Obama Administration is taking to restart America's nuclear industry as part of an all-of-the-above American energy strategy. During remarks to more than 500 workers at the Vogtle nuclear power plant, Secretary Chu highlighted the wide variety of steps the Obama Administration has taken to help restart America's nuclear energy

194

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

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

Chu Visits Site of America's First New Nuclear Reactor in Three Chu Visits Site of America's First New Nuclear Reactor in Three Decades Chu Visits Site of America's First New Nuclear Reactor in Three Decades February 15, 2012 - 2:12pm Addthis Just two days after the Department of Energy requested more than $770 million for nuclear energy in 2013, U.S. Secretary of Energy Steven Chu visited the Vogtle nuclear power plant in Waynesboro, Georgia and Oak Ridge National Laboratory to highlight the steps the Obama Administration is taking to restart America's nuclear industry as part of an all-of-the-above American energy strategy. During remarks to more than 500 workers at the Vogtle nuclear power plant, Secretary Chu highlighted the wide variety of steps the Obama Administration has taken to help restart America's nuclear energy

195

SUMMARY OF REACTOR DESIGN INFORMATION FROM THREE YEARS' OPERATION OF A SMALL PWR  

SciTech Connect

Reactor design information obtained from 3 years' operation of a small pressurized-water reactor, the SM-1 (formerly APPR-l), is presented and discussed. The SM-1 reactor, designed to produce 10 Mw(t) power, employs fully enriched uranium fuel in the form of UO/sub 2/ dispersed in stainless-steel fuel plates. The reactor is cooled by water at 1200 psia and mean temperature of 44) deg F. Core-physics measurements were performed of temperature coefficient, pressure coefficient, rod calibration, stuck rod position, and transient xenon as a function of core burn-out. Core burn-out characteristics were compared with few- group calculations, and reasonable agreement was obtained. Thermal-heat-balance data were obtained on the reactor core. The temperature pattern in the nominal and hot channels under operating conditions was calculated. These calculations indicated that certain of the fuel channels operated in the nucleate boiling regime. Examination of one of the fuel channels suspected of nucleate boiling indicated no adverse effects. The system response to load perturbations and during pump coast-down was measured utilizing plant instrumentation. This response was compared with analytical predictions using a lumped kinetic model, and reasonable agreement was found. Both neutron and gamma traverses were made through the primary shield during reactor operation. Gamma traverses were also made through the primary shield as a function of time after reactor shutdown. Conventional shielding calculational methods are found to give agreement with experiment sufficient for design purposes. An absolute ionization chamber was employed to measure N/sup 16/ activity in the reactor coolant. These measurements were compared with N/sup 16/ calculated from the (n,p) reaction on O/ sup 16/. (auth)

Gallagher, J.G.

1960-09-01T23:59:59.000Z

196

Summary of near-term options for Russian plutonium production reactors  

SciTech Connect

The Russian Federation desires to phase out the production of weapons-grade plutonium. To this end, ten graphite-moderated, water-cooled reactors have been shut down during the last several years. However, complete cessation of plutonium production is impeded because the three operating Russian reactors supply district heat and electricity to the Tomsk and Krasnoyarsk regions in addition to producing weapon-grade plutonium. In August 1992 the Russian Federation Ministry of Atomic Energy (MINATOM) and the Russian Nuclear Regulatory Agency (GAN) requested U.S. assistance for achieving a cessation of weapons-grade plutonium production, placing the plutonium production reactors under safeguards, and conducting a program to evaluate and assist in the upgrade of plant safety. As a result of that and subsequent communications, Secretary O`Leary and Minister Mikhailov have signed a protocol that expressed their desire to shut down the three remaining plutonium production reactors as soon as possible by replacing them with alternate energy sources. In the meantime, both MINATOM and the Department of Energy (DOE) are concerned about the safety of the plants as well as the difficulty in ceasing the production of plutonium as long as the plants continue to operate. A military subsidy has been provided for operation of the production reactor complex. Revenues received for providing district heat and electricity are insufficient to cover costs for the current natural uranium metal fuel cycle. A more economical fuel cycle is needed for civilian operations.

Newman, D.F.; Gesh, C.J.; Love, E.F.; Harms, S.L.

1994-07-01T23:59:59.000Z

197

Wind-turbine siting: a summary of the state of the art  

DOE Green Energy (OSTI)

The process of siting large wind turbines may be divided into two broad steps: site selection, and site evaluation. Site selection is the process of locating windy sites where wind energy development shows promise of economic viability. Site evaluation is the process of determining in detail for a given site the economic potential of the site. This paper emphasizes the state of the art in the first aspect of siting, site selection. Several techniques for assessing the wind resource have been explored or developed in the Federal Wind Energy Program. Local topography and meteorology will determine which of the tehniques should be used in locating potential sites.

Hiester, T.R.

1981-08-01T23:59:59.000Z

198

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

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

American Recovery and Reinvestment American Recovery and Reinvestment Act workers achieved a significant milestone in the decommissioning of a Cold War reactor at the Sa- vannah River Site this month after they safely re- moved its rusty, orange, 75-foot-tall dome. With the help of a 660-ton crane and lifting lugs, the work- ers pulled the 174,000-pound dome off the Heavy Water Components Test Reactor, capping more than 16 months of preparations. Workers will cut the dome into smaller pieces for disposal. Removal of the dome allows workers to access the 219,000-pound reactor vessel and two steam generators so they can remove and permanently dispose them onsite. Re- maining equipment will be moved to the cavity vacated by the vessel, and below-grade portions of the reactor will be

199

2010 Annual Planning Summary for Stanford Linear Accelerator Center Site Office (SLAC)  

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

Annual Planning Summaries briefly describe the status of ongoing NEPA compliance activities, any EAs expected to be prepared in the next 12 months, any EISs expected to be prepared in the next 24...

200

MIT Modular Pebble Bed Reactor (MPBR) A Summary of Research Activities and Accomplishments  

E-Print Network (OSTI)

operation #12;MIT MPBR Specifications Thermal Power 250 MW - 120 Mwe Target Thermal Efficiency 45 % Core for a pebble bed reactor power plant system with high efficiency and minimum capital cost ­ Net efficiency > 45;Plant With Space Frames #12;#12;For 1150 MW Electric Power Station Turbine Hall Boundary Admin Training

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

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

SciTech Connect

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

202

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

SciTech Connect

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

203

FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH DEVELOPMENT PROGRAM. First Summary Report for March 1959-July 1960  

SciTech Connect

The Fuel Cycle Development Program is a basic development program for boiling and other water technology. It covers the areas of oxide fuel fabrication. irradiation. and examination; the physics of water-moderated reactore; and boiling-water heat transfer and stability. Schedules for the fuel- cycle program were examined. and it was concluded that portions of the Task A program should be conducted during the period May to Dec. 1959 in order to keep costs of the work as low as possible and to allow initiation of the fuel-cycle program at the earliest possible date after the Vallecitos BWR was returned to service. The basis for the scheduling of the work is discussed. and a chronological summary describing the content of the work is given. Technical progress is outlined and details are summarized. Subsequent reports issued monthly and quarterly will summarize the progress of the prognam. (W.D.M.)

Cook, W.H.

1961-10-31T23:59:59.000Z

204

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

Science Conference Proceedings (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

205

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

SciTech Connect

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

206

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

SciTech Connect

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

207

Stationary low power reactor No. 1 (SL-1) accident site decontamination & dismantlement project  

SciTech Connect

The Army Reactor Area (ARA) II was constructed in the late 1950s as a test site for the Stationary Low Power Reactor No. 1 (SL-1). The SL-1 was a prototype power and heat source developed for use at remote military bases using a direct cycle, boiling water, natural circulation reactor designed to operate at a thermal power of 3,000 kW. The ARA II compound encompassed 3 acres and was comprised of (a) the SL-1 Reactor Building, (b) eight support facilities, (c) 50,000-gallon raw water storage tank, (d) electrical substation, (e) aboveground 1,400-gallon heating oil tank, (f) underground 1,000-gallon hazardous waste storage tank, and (g) belowground power, sewer, and water systems. The reactor building was a cylindrical, aboveground facility, 39 ft in diameter and 48 ft high. The lower portion of the building contained the reactor pressure vessel surrounded by gravel shielding. Above the pressure vessel, in the center portion of the building, was a turbine generator and plant support equipment. The upper section of the building contained an air cooled condenser and its circulation fan. The major support facilities included a 2,500 ft{sup 2} two story, cinder block administrative building; two 4,000 ft{sup 2} single story, steel frame office buildings; a 850 ft{sup 2} steel framed, metal sided PL condenser building, and a 550 ft{sup 2} steel framed decontamination and laydown building.

Perry, E.F.

1995-11-01T23:59:59.000Z

208

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

SciTech Connect

This report summarizes field sampling activities conducted in support of WCH’s 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

209

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

SciTech Connect

This report summarizes field sampling activities conducted in support of WCH’s 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

210

PATHFINDER ATOMIC POWER PLANT. BORON STAINLESS STEEL CONTROL RODS FOR PATHFINDER REACTOR. Final Summary Report  

SciTech Connect

An extensive development, fabrication, and design analysis program was completed on 2 wt% boron stainiess steel for Pathfinder boiler and superheater control rods. Results indicated that the control rods will operate satisfactorily in the reactor under all foreseeable conditions. It was concluded that the maximum local burnup on the boiler rods is limited to 1.0 core at.% and the superheater rods to 0.5 core at.% to remain well below the onset of any deleterious effects. All stresses imposed on the material were found to be below yield strength. The deflections were calculated and were not sufficient to restrict any movement of the cruciform during reactor operations and scrams. A welding development program produced a sound fabrication method for producing the control rods. A prototype rod was extensively tested in the hot control rod drive test, including a large number of scrams. The rod showed no deleterious effects. The rods were designed to accommodate any helium release and swelling that may occur. (M.C.G.)

Patterson, D.A.; Nehrig, D.A.; Klumb, R.H.; Peterson, T.E.

1963-02-15T23:59:59.000Z

211

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

DOE Green Energy (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

212

Candidate wind turbine generator site annual data summary for January 1980 through December 1980  

DOE Green Energy (OSTI)

Summarized hourly meteorological data for fourteen candidate and wind turbine generator sites are presented in this report. These data are collected for the Department of Energy 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, data are given in eight tables and one figure. 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.; Renne, D.S.

1981-04-01T23:59:59.000Z

213

Candidate wind turbine generator site annual data summary for January 1979 through December 1979  

DOE Green Energy (OSTI)

Summarized hourly meteorological data for fifteen candidate and wind turbine generator sites are presented in this report. These data are collected for the Department of Energy 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, data are given in eight tables and one figure. 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.; Renne, D.S.

1981-03-01T23:59:59.000Z

214

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

SciTech Connect

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

215

Comparative assessment of five potential sites for hydrothermal-magma systems: summary  

DOE Green Energy (OSTI)

A comparative assessment of five potential hydrothermal-magma sites for this facet of the Thermal Regimes part of the CSDP has been prepared for the DOE Office of Basic Energy Sciences. The five sites are: The Geysers-Clear Lake, CA, Long Valley, CA, Rio Grande Rift, NM, Roosevelt Hot Springs, UT, and Salton Trough, CA. This site assessment study has drawn together background information (geology, geochemistry, geophysics, and energy transport) on the five sites as a preliminary stage to site selection. Criteria for site selection are that potential sites have identifiable, or likely, hydrothermal systems and associated magma sources, and the important scientific questions can be identified and answered by deep scientific holes. Recommendations were made.

Luth, W.C.; Hardee, H.C.

1980-11-01T23:59:59.000Z

216

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

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

217

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

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

218

Summary of the engineering assessment of inactive uranium mill tailings, Naturita site, Naturita, Colorado  

SciTech Connect

Ford, Bacon and Davis Utah Inc. has reevaluated the Naturita site in order to revise the November 1977 engineering assessment of the problems resulting from the existence of radioactive contamination at the former uranium mill tailings site at Naturita, Colorado. This evaluation has included the preparation of topographic maps, the drilling of boreholes and radiometric measurements sufficient to determine areas and volumes of contaminated materials and radiation exposures of individuals and nearby populations, and the evaluation and costing of alternative remedial actions. Radon gas released from the estimated 344,000 tons of contaminated materials that remain at the Naturita site constitutes the most significant environmental impact, although external gamma radiation also is a factor. The two alternative actions presented in this engineering assessment are stabilization of the site in its present location with the addition of 3 m of stabilization cover material (Option I), and removal of residual radioactive materials to a disposal site and decontamination of the Naturita site (Option II). Cost estimates for the two options are about $7,200,000 for stabilization in-place, and about $8,200,000 for disposal at the Ranchers Exploration and Development Corporation's reprocessing site. Truck haulage would be used to transport the contaminated materials from the Naturita site to the selected disposal site.Ranchers Exploration and Development Corporation removed the tailings from the site, reprocessed them, and disposed of them from 1977 to 1979. There is no noteworthy mineral resource remaining at the former tailings site; therefore, recovery of residual mineral values was not considered in this assessment.

Not Available

1981-07-01T23:59:59.000Z

219

Summary of the engineering assessment of inactive uranium mill tailings: Belfield Site, Belfield, North Dakota  

SciTech Connect

Ford, Bacon and Davis Utah Inc. has evaluated the Belfield site in order to assess the problems resulting from the existence of radioactive ash at Belfield, South Dakota. This engineering assessment has included drilling of boreholes and radiometric measurements sufficient to determine areas and volumes of ash and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 55,600 tons of ash and contaminated material at the Belfield site constitutes a significant environmental impact, although external gamma radiation also is a factor. 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, to removal of the ash and contaminated materials to remote disposal sites, and decontamination of the Belfield site. Cost estimates for the four options range from about $1,500,000 for stabilization in-place, to about $2,500,000 for disposal at a distance of about 17 mi from the Belfield site. Reprocessing the ash for uranium recovery is not feasible because of the extremely small amount of material available at the site and because of its low U/sub 3/O/sub 8/ content.

Not Available

1981-11-01T23:59:59.000Z

220

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

DOE Green Energy (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.

Not Available

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

Record of Decision; Continued operation of K, L, and P Reactors, Savannah River Site, Aiken, South Carolina  

SciTech Connect

The US Department of Energy (DOE) has considered the environmental impacts, benefits and costs, and institutional and programmatic needs associated with continued operation of the Savannah River Site (SRS) reactors, and has decided that it will continue to operate K and L Reactors at SRS, and will terminate operation of P Reactor in the immediate future and maintain it in cold standby. For P Reactor, this will involve the reactor's defueling; storage of its heavy water moderator in tanks in the reactor building; shutdown of reactor equipment and systems in a protected condition to prevent deterioration; and maintenance of the reactor in a defueled, protected status by a skeleton staff, which would permit any future decision to refuel and restart. Currently committed and planned upgrade activities will be discontinued for P Reactor. DOE will proceed with the safety upgrades and management system improvements currently scheduled for K Reactor in its program to satisfy the criteria of the Safety Evaluation Report (SER), and will conduct an Operational Readiness Review (ORR). The satisfaction of the SER criteria and completion of the ORR will demonstrate that the safety and health criteria for the resumption of production have been met. Reactor restart is expected to be in the third quarter of 1991 for K Reactor.

1991-01-01T23:59:59.000Z

222

Hanford Site Environment Safety and Health (ES and H) FY 1999 and FY 2000 Execution Commitment Summary  

SciTech Connect

All sites in the U.S. Department of Energy (DOE) Complex prepare this report annually for the DOE Office of Environment, Safety and Health (EH). The purpose of this report is to provide a summary of the previous and current year's Environment, Safety and Health (ES&H) execution commitments and the S&H resources that support these activities. The fiscal year (FY) 1999 and 2000 information (Sieracki 1999) and data contained in the ''Hanford Site Environment, Safety and Health Fiscal Year 2001 Budget-Risk Management Summary'' (RL 1999) were the basis for preparing this report. Fiscal year 2000 finding of Office of Environmental Management (EM) and Office of Nuclear Energy, Science and Technology (NE) activities is based on the President's budget of $1,065.1 million and $28.0 million, plus $2.7 million carryover finding, respectively, as of October 31, 1999. Any funding changes as a result of the Congressional appropriation process will be reflected in the Fiscal Year 2002 ES&H Budget-Risk Management Summary to be issued in May 2000. This report provides the end-of-year status of FY 1999 ES&H execution commitments, including actual S&H expenditures, and describes planned FY 2000 ES&H execution commitments and the S&H resources needed to support those activities. This requirement is included in the ES&H ''Guidance for FY200l Budget Formulations and Execution'' (DOE 1999).

REEP, I.E.

1999-12-01T23:59:59.000Z

223

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

SciTech Connect

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

224

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

SciTech Connect

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

225

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

Science Conference Proceedings (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

226

Alternative energy facility siting policies for urban coastal areas: executive summary of findings and policy recommendations  

SciTech Connect

An analysis was made of siting issues in the coastal zone, one of the nation's most critical natural resource areas and one which is often the target for energy development proposals. The analysis addressed the changing perceptions of citizens toward energy development in the coastal zone, emphasizing urban communities where access to the waterfront and revitalization of waterfront property are of interest to the citizen. The findings of this analysis are based on an examination of energy development along New Jersey's urban waterfront and along the Texas-Louisiana Gulf Coast, and on redevelopment efforts in Seattle, San Francisco, Boston, and elsewhere. The case studies demonstrate the significance of local attitudes and regional cooperation in the siting process. In highly urbanized areas, air quality has become a predominant concern among citizen groups and an influential factor in development of alternative energy facility siting strategies, such as consideration of inland siting connected by pipeline to a smaller coastal facility. The study addresses the economic impact of the permitting process on the desirability of energy facility investments, and the possible effects of the location selected for the facility on the permitting process and investment economics. The economic analysis demonstrates the importance of viewing energy facility investments in a broad perspective that includes the positive or negative impacts of various alternative siting patterns on the permitting process. Conclusions drawn from the studies regarding Federal, state, local, and corporate politics; regulatory, permitting, licensing, environmental assessment, and site selection are summarized. (MCW)

Morell, D; Singer, G

1980-11-01T23:59:59.000Z

227

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

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

7-08-21-02 7-08-21-02 State Colorado Agreement Type Consent Order Legal Driver(s) RCRA Scope Summary Establish compliance requirements and schedules for the implementation of a "Waste Chemical Project Plan" Parties DOE; Kaiser-Hill Company, LLC; Colorado Department of Public Health and Environment Date 8/21/1997 SCOPE * Establish compliance requirements and schedules for the implementation of a "Waste Chemical Project Plan" (the "Waste Chemical Plan") at RFETS. * Resolve violations of the Colorado Hazardous Waste Act and the Colorado Hazardous Waste Regulations. ESTABLISHING MILESTONES * Activities in the Waste Chemical Plan shall be completed by no later than December 31, 1999, except as to Excluded Chemicals (discussed in Paragraph 22 of this Order

228

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

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

Number: 97-08-21-01 Number: 97-08-21-01 State Colorado Agreement Type Consent Order Legal Driver(s) RCRA Scope Summary Establish compliance requirements and schedules for the implementation of 1) the Management Plan for Material Contained in Idle Equipment, 2) the 1997 Hazardous Waste Tank Management Plan Parties DOE; Kaiser-Hill Company, LLC; Colorado Department of Public Health and Environment (CDPHE) Date 8/21/1997 SCOPE * Establish compliance requirements and schedules for the implementation of 1) the Management Plan for Material Contained in Idle Equipment, 2) the 1997 Hazardous Waste Tank Management Plan. * Resolve violations of the Colorado Hazardous Waste Act and the Colorado Hazardous Waste Regulations identified therein. ESTABLISHING MILESTONES * DOE and K-H shall annually submit to the Department, for information only, a

229

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

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

41-HW 41-HW State South Carolina Agreement Type Consent Order Legal Driver(s) RCRA Scope Summary Establish guidelines for developing a closure plan for the Beta-Gamma Incinerator Tank and an approval plan for all previously unidentified sources of hazardous or mixed wastes at the facility Parties DOE; Westinghouse Savannah River Company; State of South Carolina (Department of Health and Environmental Control) Date 9/28/1999 SCOPE * Establish a course of action due to DOE and WSRC's violation of the Department's Hazardous Waste Management Regulations. * Establish guidelines for developing a closure plan for the Beta-Gamma Incinerator Tank and an approval plan for all previously unidentified sources of hazardous or mixed wastes at the facility. * Establish appropriate milestones.

230

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

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

155-W 155-W State South Carolina Agreement Type Consent Order Legal Driver(s) CWA Scope Summary Establish/update the course of action and the appropriate milestones pertaining to outfall A01 Parties DOE; Westinghouse Savannah River Company; State of South Carolina (Department of Health and Environmental Control) Date 10/11/1999 SCOPE * Establish/update the course of action and the appropriate milestones pertaining to outfall A01. ESTABLISHING MILESTONES * By August 1, 2000, SRS shall submit to the Department plans and specifications for the compliance activities described in the preliminary engineering report (PER) previously submitted for outfall A01. * Comply with final effluent limits for chronic toxicity, copper, lead, and TRC at outfall A01 by October 1, 2001.

231

Test storage of spent reactor fuel in the Climax granite at the Nevada Test Site  

SciTech Connect

A test of retrievable dry geologic storage of spent fuel assemblies from an operating commercial nuclear reactor is underway at the Nevada Test Site. This generic test is located 420 m below the surface in the Climax granitic stock. Eleven canisters of spent fuel approximately 2.3 years out of reactor core (about 2 kW/canister thermal output) will be emplaced in a storage drift along with 6 electrical simulator canisters and their effects will be compared. Two adjacent drifts will contain electrical heaters, which will be operated to simulate within the test array the thermal field of a large repository. The test objectives, technical concepts and rationale, and details of the test are stated and discussed.

Ramspott, L.D.; Ballou, L.B.

1980-02-13T23:59:59.000Z

232

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

SciTech Connect

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

233

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

SciTech Connect

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

E.M. Harpenau

2010-11-15T23:59:59.000Z

234

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

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

Paducah, KY Paducah, KY EM Project: On-Site Disposal Facility ETR Report Date: August 2008 ETR-16 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Disposal Facility(OSDF) at the Paducah Gaseous Diffusion Plant Why DOE-EM Did This Review The Paducah Gaseous Diffusion Plant (PGDP) is an active uranium enrichment facility that was placed on the National Priorities List. DOE is required to remediate the PGDP in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). DOE is evaluating alternatives to dispose of waste generated from the remedial activities at the PGDP. One option is to construct an on-site disposal facility (OSDF) meeting the CERCLA requirements.

235

Summary of the engineering assessment of inactive uranium mill tailings, Spook Site, Converse County, Wyoming  

SciTech Connect

Ford, Bacon, Davis Utah Inc. has reevaluated the Spook site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings 48 mi northeast of Casper, in Converse County, Wyoming. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and 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 corrective actions. Radon gas released from the 187,000 tons of tailings at the Spook site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors.

Not Available

1981-10-01T23:59:59.000Z

236

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

SciTech Connect

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

237

RCRA Summary Document for the David Witherspoon 1630 Site, Knoxville, Tennessee  

Science Conference Proceedings (OSTI)

The 48-acre David Witherspoon, Inc. (DWI) 1630 Site operated as an unregulated industrial landfill and scrap yard. The Tennessee Division of Superfund (TDSF) closed the landfill in 1974. During the period of operation, the site received solid and liquid wastes from salvage and industrial operations. The site consists of five separate tracts of land including a small portion located across the Norfolk Southern Railroad track. The landfill occupies approximately 5 acres of the site, and roughly 20 acres of the 48 acres contains surface and buried debris associated with the DWI dismantling business operation. Beginning in 1968, the state of Tennessee licensed DWI to receive scrap metal at the DWI 1630 Site, contaminated with natural uranium and enriched uranium (235U) not exceeding 0.1 percent by weight (TDSF 1990). The U.S. Department of Energy (DOE) has agreed to undertake remedial actions at the DWI 1630 Site as specified under a Consent Order with the Tennessee Department of Environment and Conservation (TDEC) (Consent Order No. 90-3443, April 4, 1991), and as further delineated by a Memorandum of Understanding (MOU) between DOE and the State of Tennessee (MOU Regarding Implementation of Consent Orders, October 6, 1994). The soil and debris removal at the DWI 1630 Site is being performed by Bechtel Jacobs Company LLC (BJC) on behalf of the DOE. Remediation consists of removing contaminated soil and debris from the DWI 1630 site except for the landfill area and repairing the landfill cap. The DWI 1630 remediation waste that is being disposed at the Environmental Management Waste Management Facility (EMWMF) as defined as waste lot (WL) 146.1 and consists primarily of soils and soil like material, incidental debris and secondary waste generated from the excavation of debris and soil from the DWI 1630 site. The WL 146.1 includes soil, soil like material (e.g., shredded or chipped vegetation, ash), discrete debris items (e.g., equipment, drums, large scrap metal, cylinders, and cable) and populations of debris type items (e.g., piles of bricks, small scrap metal, roofing material, scaffolding, and shelving) that are located throughout the DWI 1630 site. The project also generates an additional small volume of secondary waste [e.g., personal protective equipment (PPE), and miscellaneous construction waste] that is bagged and included in bulk soil shipments to the EMWMF. The Waste Acceptance Criteria (WAC) for the EMWMF does not allow for material that does not meet the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDRs). The waste being excavated in certain areas of the DWI 1630 site contained soil that did not meet RCRA LDR criteria; therefore this waste had to be segregated for treatment or alternate disposal offsite. This document identifies the approach taken by the DWI 1630 project to further characterize the areas identified during the Phase II Remedial Investigation (RI) as potentially containing RCRA-characteristic waste. This document also describes the methodology used to determine excavation limits for areas determined to be RCRA waste, post excavation sampling, and the treatment and disposal of this material.

Pfeffer, J.

2008-06-10T23:59:59.000Z

238

Research Summary RECOAL: Reintegration of coal ash disposal sites and mitigation  

E-Print Network (OSTI)

and Herzegovina; UBAL University of Banja Luka, Bosnia and Herzegovina; FAZ University of Zagreb, Croatia; BTUC risks of farmed and barren alkaline coal ash landfills in Tuzla, Bosnia and Herzegovina. Environmental its research on the thermo-electric plant (TEP) and associated coal ash sites at Tuzla, Bosnia

239

Radioactive releases at the Savannah River Site, 1954--1989. An Environmental Protection Department summary  

Science Conference Proceedings (OSTI)

This report is the continuation of a series of reports, previously titled, Releases of Radioactivity at the Savannah River Plant (DPSPU-YR-25-1). The reports reflect the use of air and liquid effluent sample analyses in determining the amount of radioactivity released from Savannah River Site (SRS) operations. The identification and characterization of these source terms since plant startup in 1954 have aided Site personnel in confining and limiting the amount of radioactivity released to the environment from SRS facilities. This document is an effluent/source term report; items falling under other categories, such as environmental spills or solid waste transport to the burial ground, are not included. Any classified or secret data have either been excluded, as in the case of 1960--1970 atmospheric releases of {sup 85}Kr from the Separations Areas, or combined to avoid classification, such as atmospheric tritium releases from the Separations Area.

Cummins, C.L.; Hetrick, C.S.; Martin, D.K.

1991-02-01T23:59:59.000Z

240

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

Science Conference Proceedings (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

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

Fort St. Vrain Decommissioning: Final Site Radiation Survey: Summary Report and Lessons Learned  

Science Conference Proceedings (OSTI)

This report describes the final step in the decommissioning process at Public Service Company of Colorado's (PSCo) Fort St. Vrain nuclear power plant. The final site radiation survey documents that all nuclear facility surfaces meet the established release limits for unrestricted use. The survey formed the legal basis for the termination of the Fort St. Vrain nuclear license, which occurred in August 1997. The lessons learned in this process will be valuable to other utilities with permanently shutdown p...

1998-02-13T23:59:59.000Z

242

Endurance Bioenergy Reactor Summary  

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

Partnerships Partnerships 4 Argonne and DOD agencies joined forces on the EBR project in direct response to the 2010 DOD Operational Energy Strategy. 4 The successful partnership is helping to foster a better working relationship between DOD and DOE as outlined in their July 2010 MOU. 4 The estimated $2-3 million required to complete EBR development, if shared between agencies, will reduce their economic burden and hasten the EBR field application.

243

Argonne National Laboratory summary site environmental report for calendar year 2006.  

Science Conference Proceedings (OSTI)

This booklet is designed to inform the public about what Argonne National Laboratory is doing to monitor its environment and to protect its employees and neighbors from any adverse environmental impacts from Argonne research. The Downers Grove South Biology II class was selected to write this booklet, which summarizes Argonne's environmental monitoring programs for 2006. Writing this booklet also satisfies the Illinois State Education Standard, which requires that students need to know and apply scientific concepts to graduate from high school. This project not only provides information to the public, it will help students become better learners. The Biology II class was assigned to condense Argonne's 300-page, highly technical Site Environmental Report into a 16-page plain-English booklet. The site assessment relates to the class because the primary focus of the Biology II class is ecology and the environment. Students developed better learning skills by working together cooperatively, writing and researching more effectively. Students used the Argonne Site Environmental Report, the Internet, text books and information from Argonne scientists to help with their research on their topics. The topics covered in this booklet are the history of Argonne, groundwater, habitat management, air quality, Argonne research, Argonne's environmental non-radiological program, radiation, and compliance. The students first had to read and discuss the Site Environmental Report and then assign topics to focus on. Dr. Norbert Golchert and Mr. David Baurac, both from Argonne, came into the class to help teach the topics more in depth. The class then prepared drafts and wrote a final copy. Ashley Vizek, a student in the Biology class stated, 'I reviewed my material and read it over and over. I then took time to plan my paper out and think about what I wanted to write about, put it into foundation questions and started to write my paper. I rewrote and revised so I think the amount of time that I put into the project will be worth it in the end because it is a cool thing to be a published writer'. While most students agree that putting the final paper together was the toughest part, the final result was worth the hard work. Christine Beuhler states, 'The time and effort was worth it because I learned a lot about the Argonne facility. This project also improved my analyzing, reading, and writing skills'. Emily Schimick and Kaitlin Hernandez agreed that the feeling of accomplishment when they finished the paper was their favorite part, while the reading of the Argonne Site Environmental Report was their least favorite because it was difficult to understand. The Downers Grove South Biology II class would like to thank our teacher Mr. Scott Howard, as well as Dr. Golchert and Mr. Baurac for their investment in time and energy in helping with the project. Dr. Golchert and Mr. Baurac gave us valuable assistance in the preparation of this project, and we owe them our deepest gratitude. Their real-life experience at Argonne was inspirational. Mr. Howard set the goals and made the commitment to our class to complete this project. Without their kind support, this project would not have been possible.

Golchert, N. W.; ESH /QA Oversight

2008-03-27T23:59:59.000Z

244

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

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

Link to Main Report Link to Main Report RESPONSIBLE AGENCY: COVER SHEET 1 2 3 4 5 6 7 8 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 U.S. Department of Energy, Richland Operations Office TITLE: Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Benton County, Washington (DOE/EIS-0286D2) CONTACT: For further information on this document, write or call: Mr. Michael S. Collins HSW EIS Document Manager Richland Operations Office U.S. Department of Energy, A6-38 P.O. Box 550 Richland, Washington 99352-0550 Telephone: (800) 426-4914 Fax: (509) 372-1926 Email: hsweis@rl.gov For further information on the Department's National Environmental Policy Act process,

245

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

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

Salt Waste Processing Facility Salt Waste Processing Facility ETR Report Date: November 2006 ETR-4 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Salt Waste Processing Facility Design at the Savannah River Site (SRS) Why DOE-EM Did This Review The Salt Waste Processing Facility (SWPF) is intended to remove and concentrate the radioactive strontium (Sr), actinides, and cesium (Cs) from the bulk salt waste solutions in the SRS high-level waste tanks. The sludge and strip effluent from the SWPF that contain concentrated Sr, actinide, and Cs wastes will be sent to the SRS Defense Waste Processing Facility (DWPF), where they will be vitrified. The decontaminated salt solution (DSS) that is left after removal of the highly

246

Summary of operations and performance of the Murdock site restoration project in 2007.  

SciTech Connect

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 second full year of system operation, from January 1 through December 31, 2007. Performance in June 2005 through December 2006 was reported previously (Argonne 2007). 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. A brief videorecording of the trees in high-wind conditions is on the compact disc (CD) inside the back cover of this document.

LaFreniere, L. M.; Environmental Science Division

2008-06-03T23:59:59.000Z

247

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

Science Conference Proceedings (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

248

Summary and results of the comprehensive environmental monitoring program at the INEL's Raft River geothermal site  

DOE Green Energy (OSTI)

The Raft River Geothermal Program was designed to demonstrate that moderate temperature (approx. 150/sup 0/C) geothermal fluids could be used to generate electricity and provide an alternate energy source for direct-use applications. The environmental program was initiated soon after drilling began. The major elements of the monitoring program were continued during the construction and experimental testing of the 5-MW(e) power plant. The monitoring studies established pre-development baseline conditions of and assessed changes in the physical, biological, and human environment. The Physical Environmental Monitoring Program collected baseline data on geology, subsidence, seismicity, meteorology and air quality. The Biological Environmental Monitoring Program collected baseline data on the flora and fauna of the terrestrial ecosystem, studied raptor disturbances, and surveyed the aquatic communities of the Raft River. The Human Environmental Monitoring Program surveyed historic and archaeological sites, considered the socioeconomic environment, and documented incidences of fluorosis in the Raft River Valley. In addition to the environmental monitoring programs, research on biological direct applications using geothermal water was conducted at Raft River. Areas of research included biomass production of wetland and tree species, aquaculture, agricultural irrigation, and the use of wetlands as a treatment or pretreatment system for geothermal effluents.

Mayes, R.A.; Thurow, T.L.; Cahn, L.S.

1982-01-01T23:59:59.000Z

249

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

SciTech Connect

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

250

Modelling steam explosions for the Savannah River Site reactor probabilistic risk assessment. Revision 1  

Science Conference Proceedings (OSTI)

As part of the probabilistic risk assessment (PRA) for the Savannah River Site (SRS) reactors, a theoretical model has been used to evaluate the magnitude of steam explosions that could occur during postulated severe accidents at the plant. The model predicts pressure, steam generation and mechanical work during the explosion phase of the interaction. The model is applied to two hypothetical events illustrating typical small-scale and large-scale explosions found in the PRA. These two examples show that yield predictions may range from megajoules to gigajoules for kinetic energy, 10 to 1000 kg for steam generated, and 10 to 1000 atm for peak explosion-zone pressures. A brief study is made to characterize the sensitivity of kinetic energy yield to initial fuel mass and fuel temperature. Explosion kinetic energy increases linearly in proportion to fuel mass, but displays a non-linear dependence on fuel temperature over parameter values of interest.

Vonderfecht, B.E. [Westinghouse Savannah River Co., Aiken, SC (United States); Smith, D.C. [Science Applications International Corp., Albuquerque, NM (United States)

1992-12-31T23:59:59.000Z

251

Modelling steam explosions for the Savannah River Site reactor probabilistic risk assessment  

Science Conference Proceedings (OSTI)

As part of the probabilistic risk assessment (PRA) for the Savannah River Site (SRS) reactors, a theoretical model has been used to evaluate the magnitude of steam explosions that could occur during postulated severe accidents at the plant. The model predicts pressure, steam generation and mechanical work during the explosion phase of the interaction. The model is applied to two hypothetical events illustrating typical small-scale and large-scale explosions found in the PRA. These two examples show that yield predictions may range from megajoules to gigajoules for kinetic energy, 10 to 1000 kg for steam generated, and 10 to 1000 atm for peak explosion-zone pressures. A brief study is made to characterize the sensitivity of kinetic energy yield to initial fuel mass and fuel temperature. Explosion kinetic energy increases linearly in proportion to fuel mass, but displays a non-linear dependence on fuel temperature over parameter values of interest.

Vonderfecht, B.E. (Westinghouse Savannah River Co., Aiken, SC (United States)); Smith, D.C. (Science Applications International Corp., Albuquerque, NM (United States))

1992-01-01T23:59:59.000Z

252

Characterization of wastes in and around early reactors at the Hanford Site: The use of historical research  

SciTech Connect

This paper will present the waste characterization knowledge that has been gained in the first, ``Large-Scale Remediation Study`` to be performed on the reactor areas (100 Areas) of the Hanford Site. Undertaken throughout the past year, this research project has identified thousands of pieces of buried hardware, as well as the volumes of liquid wastes in burial sites in the reactor areas. The author of this landmark study, Dr. Michele Gerber, will discuss historical research as a safe and cost-effective characterization tool.

Gerber, M.S.

1993-10-01T23:59:59.000Z

253

The Hanford Site New Production Reactor (NPR) economic and demographic baseline forecasts  

SciTech Connect

The objective of this is to present baseline employment and population forecasts for Benton, Franklin, and Yakima Counties. These forecasts will be used in the socioeconomic analysis portion of the New Production Reactor Environmental Impact Statement. Aggregate population figures for the three counties in the study area were developed for high- and low-growth scenarios for the study period 1990 through 2040. Age-sex distributions for the three counties during the study period are also presented. The high and low scenarios were developed using high and low employment projections for the Hanford site. Hanford site employment figures were used as input for the HARC-REMI Economic and Demographic (HED) model to produced baseline employment forecasts for the three counties. These results, in turn, provided input to an integrated three-county demographic model. This model, a fairly standard cohort-component model, formalizes the relationship between employment and migration by using migration to equilibrate differences in labor supply and demand. In the resulting population estimates, age-sex distributions for 1981 show the relatively large work force age groups in Benton County while Yakima County reflects higher proportions of the population in the retirement ages. The 2040 forecasts for all three counties reflect the age effects of relatively constant and low fertility increased longevity, as well as the cumulative effects of the migration assumptions in the model. By 2040 the baby boom population will be 75 years and older, contributing to the higher proportion of population in the upper end age group. The low scenario age composition effects are similar. 13 refs., 5 figs., 9 tabs.

Cluett, C.; Clark, D.C. (Battelle Human Affairs Research Center, Seattle, WA (USA)); Pittenger, D.B. (Demographics Lab., Olympia, WA (USA))

1990-08-01T23:59:59.000Z

254

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary  

SciTech Connect

A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 1 is an executive summary both of the PE methodology and of the results obtained from the PEs. While this volume briefly reviews the scope and method of analyses, its main objective is to emphasize the important insights and conclusions derived from the conduct of the PEs. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site.

NONE

1996-03-01T23:59:59.000Z

255

HEU Measurements of Holdup and Recovered Residue in the Deactivation and Decommissioning Activities of the 321-M Reactor Fuel Fabrication Facility at the Savannah River Site  

SciTech Connect

This paper contains a summary of the holdup and material control and accountability (MC&A) assays conducted for the determination of highly enriched uranium (HEU) in the deactivation and decommissioning (D&D) of Building 321-M at the Savannah River Site (SRS). The 321-M facility was the Reactor Fuel Fabrication Facility at SRS and was used to fabricate HEU fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the SRS production reactors. The facility operated for more than 35 years. During this time thousands of uranium-aluminum-alloy (U-Al) production reactor fuel tubes were produced. After the facility ceased operations in 1995, all of the easily accessible U-Al was removed from the building, and only residual amounts remained. The bulk of this residue was located in the equipment that generated and handled small U-Al particles and in the exhaust systems for this equipment (e.g., Chip compactor, casting furnaces, log saw, lathes A & B, cyclone separator, Freon{trademark} cart, riser crusher, ...etc). The D&D project is likely to represent an important example for D&D activities across SRS and across the Department of Energy weapons complex. The Savannah River National Laboratory was tasked to conduct holdup assays to quantify the amount of HEU on all components removed from the facility prior to placing in solid waste containers. The U-235 holdup in any single component of process equipment must not exceed 50 g in order to meet the container limit. This limit was imposed to meet criticality requirements of the low level solid waste storage vaults. Thus the holdup measurements were used as guidance to determine if further decontamination of equipment was needed to ensure that the quantity of U-235 did not exceed the 50 g limit and to ensure that the waste met the Waste Acceptance Criteria (WAC) of the solid waste storage vaults. Since HEU is an accountable nuclear material, the holdup assays and assays of recovered residue were also important for material control and accountability purposes. In summary, the results of the holdup assays were essential for determining compliance with the Waste Acceptance Criteria, Material Control & Accountability, and to ensure that administrative criticality safety controls were not exceeded. This paper discusses the {gamma}-ray assay measurements conducted and the modeling of the acquired data to obtain measured holdup in process equipment, exhaust components, and fixed geometry scrap cans. It also presents development work required to model new acquisition configurations and to adapt available instrumentation to perform the assays.

DEWBERRY, RAYMOND; SALAYMEH, SALEEM R.; CASELLA, VITO R.; MOORE, FRANK S.

2005-03-11T23:59:59.000Z

256

REACTOR  

DOE Patents (OSTI)

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

Roman, W.G.

1961-06-27T23:59:59.000Z

257

Processing Tritiated Water at the Savannah River Site: A Production-Scale Demonstration of a Palladium Membrane Reactor  

SciTech Connect

The Palladium Membrane Reactor (PMR) process was installed in the Tritium Facilities at the Savannah River Site to perform a production-scale demonstration for the recovery of tritium from tritiated water adsorbed on molecular sieve (zeolite). Unlike the current recovery process that utilizes magnesium, the PMR offers a means to process tritiated water in a more cost effective and environmentally friendly manner. The design and installation of the large-scale PMR process was part of a collaborative effort between the Savannah River Site and Los Alamos National Laboratory.The PMR process operated at the Savannah River Site between May 2001 and April 2003. During the initial phase of operation the PMR processed thirty-four kilograms of tritiated water from the Princeton Plasma Physics Laboratory. The water was processed in fifteen separate batches to yield approximately 34,400 liters (STP) of hydrogen isotopes. Each batch consisted of round-the-clock operations for approximately nine days. In April 2003 the reactor's palladium-silver membrane ruptured resulting in the shutdown of the PMR process. Reactor performance, process performance and operating experiences have been evaluated and documented. A performance comparison between PMR and current magnesium process is also documented.

Sessions, Kevin L. [Westinghouse Savannah River Company (United States)

2005-07-15T23:59:59.000Z

258

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

Science Conference Proceedings (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

259

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

SciTech Connect

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

260

Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington. Addendum (Final Environmental Impact Statement)  

Science Conference Proceedings (OSTI)

The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE`s responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which contains additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period.

Not Available

1992-12-01T23:59:59.000Z

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.


261

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

Science Conference Proceedings (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

262

THERMIONIC SPACE POWER REACTOR SYSTEM RESEARCH AND DEVELOPMENT. Annual Summary Report, May 1, 1962-April 30, 1963  

SciTech Connect

Activities in a program to test and develop prototype fission-heated thermionic cells for space uses are reported. During the period, in-reactor tests were conducted on two W-clad U-bearing fuel emitters and one unclad type. Fuel emitter proof tests were also conducted which demonstrated 1000-hr operational capability of W-clad systems. Output power density and the temperature of heat rejection were found to have major effects on the weight- performance characteristics of the system. Advances in techniques related to W vapor deposition are reported. Descriptions of the fuel-emitter development, cell design and development, and testing of out-of-pile and in-pile cells are included. Operation of the clad-type test cells at design power and temperature led to selection of these cells for planned long-duration in-pile tests. (J.R.D.)

Elsner, N.B.; Holland, J.W.; Pidd, R.W.; Ream, J.T. Jr.; Wright, W.B.; Yang, L.

1963-12-17T23:59:59.000Z

263

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

SciTech Connect

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

264

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  

Science Conference Proceedings (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

265

Energy Savings Performance Contracts Summary | Department of...  

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

Centers Field Sites Power Marketing Administration Other Agencies You are here Home Energy Savings Performance Contracts Summary Energy Savings Performance Contracts Summary...

266

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

SciTech Connect

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.

1991-04-01T23:59:59.000Z

267

Candidate wind-turbine generator site cumulative meteorological data summary and data for January 1982 through September 1982  

DOE Green Energy (OSTI)

Summarized cumulative hourly meteorological data for 20 new sites selected in early 1980 as part of the expanded candidate site program are presented. The reporting period is July 1980 through September 1982. The data collection program at some individual sites may not span this entire period, but will be contained within the reporting period. The purpose of providing the summarized data is to document the data collection program and to provide data that could be considered representative of longer-term meteorological conditions at each site. For each site, data are given in eight tables and in a topographic map showing the approximated location of the meteorological tower and turbine, if applicable. Use of the information from these tables, along with information about specific wind turbines, should allow the user to estimate the potential for longer-term average wind energy production at each site. Two appendices of other data are provided. Appendix A contains summarized data collected at new and original sites during the period January 1982 through September 1982. Appendix B contains cumulative summarized data for those original sites selected in 1976 with data collection programs continuing into 1982.

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

1983-08-01T23:59:59.000Z

268

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

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

269

F- and H-Area Sewage Sludge Application Sites groundwater monitoring report. Fourth quarter 1993 and 1993 summary  

SciTech Connect

Samples from the four wells at the F-Area Sewage Sludge Application Site (FSS wells) and the three wells at the H-Area Sewage Sludge Application Site (HSS wells) are analyzed quarterly for constituents as required by South Carolina Department of Health and Environmental Control Construction Permit 12,076 and, as requested, for other constituents as part of the Savannah River Site (SRS) Groundwater Monitoring Program. Annual analyses for other constituents, primarily metals, also are required by the permit. No constituent exceeded either the final Primary Drinking Water Standards or the SRS Flag 2 criteria during fourth quarter 1993. Iron, lead, and manganese were the only permit- required analytes that exceeded standards at the F- and H-Area Sewage Sludge Application Sites in 1993. Tritium, aluminum, and other constituents not included in the permit have exceeded standards at this site previously, but only sporadically. These constituents were not analyzed fourth quarter 1993.

1994-04-01T23:59:59.000Z

270

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

SciTech Connect

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

271

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

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.

1991-04-01T23:59:59.000Z

272

Capturing Historical Knowledge for Decommissioning of Nuclear Power Plants: Summary of Historical Site Assessments at Eight Decommis sioning Plants  

Science Conference Proceedings (OSTI)

This report describes approaches utilized and experience gained in the development of early characterization activities by a number of nuclear power plants undergoing decommissioning. In particular, the report provides experience and lessons of performing the Historical Site Assessment, or HSA.

2004-04-01T23:59:59.000Z

273

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

Science Conference Proceedings (OSTI)

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

mike lewis

2011-02-01T23:59:59.000Z

274

F- and H-Area Sewage Sludge Application Sites groundwater monitoring report. Fourth quarter 1992 and 1992 summary  

SciTech Connect

Samples from the four wells at the F-Area Sewage Sludge Application Site (FSS wells) and the three wells at the H-Area Sewage Sludge Application Site (HSS wells) are analyzed quarterly for constituents as required by South Carolina Department of Health and Environmental Control Construction Permit 12,076 and, as requested, for other constituents as part of the Savannah River Site Groundwater Monitoring Program. Annual analyses for other constituents, primarily metals, also are required by the permit. During fourth quarter 1992, the FSS wells also were analyzed for a number of other constituents not required by the permit. Historically and currently, no permit-required analytes exceed standards at the F- and H-Area Sewage Sludge Application Sites except iron, lead, and manganese, which occur in elevated concentrations frequently in FSS wells. Lead concentrations exceeded the final Primary Drinking Water Standards during fourth quarter 1992, an event that is concurrent with a change in sampling procedures. Tritium is the primary nonpermit constituent that exceeds standards at the F-Area Sewage Sludge Application Site. Other constituents also exceed standards at this site but only sporadically.

1993-04-01T23:59:59.000Z

275

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

SciTech Connect

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

276

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

Science Conference Proceedings (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

277

Annual Planning Summaries: 2013 | Department of Energy  

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

3 3 Annual Planning Summaries: 2013 March 25, 2013 2013 Annual Planning Summary for the Argonne Site Office 2013 Annual Planning Summary for the Argonne Site Office March 25, 2013 2013 Annual Planning Summary for the Argonne Site Office 2013 Annual Planning Summary for the Argonne Site Office January 30, 2013 2013 Annual Planning Summary for the Carlsbad Field Office 2013 Annual Planning Summary for the Carlsbad Field Office January 30, 2013 2013 Annual Planning Summary for the Oak Ridge Office 2013 Annual Planning Summary for the Oak Ridge Office January 30, 2013 2013 Annual Planning Summary for the Western Area Power Administration 2013 Annual Planning Summary for the Western Area Power Administration January 29, 2013 2013 Annual Planning Summary for the Idaho Operations Office

278

K-Area and Par Pond Sewage Sludge Application Sites Groundwater Monitoring Report. Fourth quarter 1992 and 1992 summary  

Science Conference Proceedings (OSTI)

During fourth quarter 1992, samples from the three monitoring wells at the K-Area site (KSS series) and the three monitoring wells at the Par Pond site (PSS series) were analyzed for constituents required by South Carolina Department of Health and Environmental Control Construction Permit 13, 173 and for other constituents as part of the Savannah River Site (SRS) Groundwater Monitoring Program. This report describes monitoring results that exceeded the final Primary Drinking Water Standards (PDWS) or the SRS flagging criteria. During fourth quarter 1992, no constituents analyzed exceeded the PDWS or the SRS Flag 2 criteria at the K-Area and Par Pond Sewage Sludge Application Sites. In the KSS well series, the field measurement for alkalinity ranged as high as 26 mg/L in well KSS 1D. Alkalinity measurements were zero in the PSS wells. Historical and current water-level elevations at the K-Area and Par Pond Sewage Sludge Application Site indicate that the groundwater flow directions are south to southwest (SRS grid coordinates).

Thompson, C.Y.

1993-04-01T23:59:59.000Z

279

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

SciTech Connect

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

280

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  

Science Conference Proceedings (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

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

Summary of the engineering assessment of inactive uranium mill tailings: Phillips/United Nuclear site, Ambrosia Lake, New Mexico  

Science Conference Proceedings (OSTI)

Ford, Bacon and Davis Utah, Inc., has reevaluated the Phillips/United Nuclear site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Ambrosia Lake, New Mexico. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric maps, the performance of core drillings and 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 corrective actions. Radon gas released from the 2.6 million dry tons of tailings at the Phillips/United Nuclear 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 decontamination with the addition of 3 m of stabilization cover material, to removal of the tailings to remote disposal sites and decontamination of the tailings site. Cost estimates for the four options range from about $21,500,000 for stabilization in-place, to about $45,200,000 for disposal at a distance of about 15 mi. Three principal alternatives for the reprocessing of the Phillips/United Nuclear tailings were examined: heap leaching; treatment at an existing mill; reprocessing at a new conventional mill constructed for tailings reprocessing. The cost of the uranium recovered would be about $87/lb of U/sub 3/O/sub 8/ by either heap leach or conventional plant process. The spot market price for uranium was $25/lb early in 1981. Reprocessing the Phillips/United Nuclear tailings for uranium recovery does not appear to be economically attractive under present or foreseeable market conditions.

Not Available

1981-10-01T23:59:59.000Z

282

Team Summary | Department of Energy  

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

Team Summary Team Summary Team Summary Team Summary Purpose: Identify, prioritize, and resolve issues for effective site revitalization. Address crosscutting issues. Incorporate ARI's mission into programmatic business practices. Team Attributes and Functions: Coordinate using existing site and program protocols (ARI Task Force is not responsible for site-specific ARI projects or programs). Resolve issues through: Lessons learned Information resources Policy statements Process improvement techniques Proposed legislative changes Partnering with other agencies Facilitation Define, prioritize, and establish deliverable timelines and manage resources. Incorporate co-leadership and cross-functional membership. Team Summaries: Steering Committee Objective: Set the strategic direction, provide overarching leadership,

283

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

SciTech Connect

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

284

Summary of treatment, storage, and disposal facility usage data collected from U.S. Department of Energy sites  

SciTech Connect

This report presents an analysis for the US Department of Energy (DOE) to determine the level and extent of treatment, storage, and disposal facility (TSDF) assessment duplication. Commercial TSDFs are used as an integral part of the hazardous waste management process for those DOE sites that generate hazardous waste. Data regarding the DOE sites` usage have been extracted from three sets of data and analyzed in this report. The data are presented both qualitatively and quantitatively, as appropriate. This information provides the basis for further analysis of assessment duplication to be documented in issue papers as appropriate. Once the issues have been identified and adequately defined, corrective measures will be proposed and subsequently implemented.

Jacobs, A.; Oswald, K. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Trump, C. [EG and G Rocky Flats, Golden, CO (United States)

1995-04-01T23:59:59.000Z

285

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

DOE Green Energy (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

286

Annual Planning Summaries: 2013 | Department of Energy  

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

3 3 Annual Planning Summaries: 2013 March 25, 2013 2013 Annual Planning Summary for the Thomas Jefferson Site Office 2013 Annual Planning Summary for the Thomas Jefferson Site Office March 25, 2013 2013 Annual Planning Summary for the Pacific Northwest Site Office 2013 Annual Planning Summary for the Pacific Northwest Site Office March 25, 2013 2013 Annual Planning Summary for the New Brunswick Laboratory 2013 Annual Planning Summary for the New Brunswick Laboratory March 25, 2013 2013 Annual Planning Summary for the Strategic Petroleum Reserve 2013 Annual Planning Summary for the Strategic Petroleum Reserve March 25, 2013 2013 Annual Planning Summary for the Rocky Mountain Oilfield Testing Center 2013 Annual Planning Summary for the Rocky Mountain Oilfield Testing Center

287

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

SciTech Connect

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

Mike Lewis

2013-02-01T23:59:59.000Z

288

Compilation of ETR Summaries  

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

Summaries Summaries Office of Technology Innovation and Development Office of Environmental Management November 2011 External Technical Review Summaries Number Title Report Date ETR-1 Flowsheet for the Hanford Waste Treatment Plant (WTP) March 2006 ETR-2 Tank 48 at the Savannah River Site (SRS) August 2006 ETR-3 Demonstration Bulk Vitrification System (DBVS) for Low Activity Waste (LAW) at Hanford September 2006 ETR-4 Salt Waste Processing Facility Design at the Savannah River Site (SRS) November 2006 ETR-5 Remedial System Performance Improvement for the 200-ZP-1/PW-1 Operable Units at Hanford February 2007 ETR-6 Operational Issues at the Environmental Restoration

289

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

SciTech Connect

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

290

Conference Summary  

Science Conference Proceedings (OSTI)

Summary of the conference, summarizing both theoretical and experimental presentations and discussions.

Brodsky, Stanley J.; /SLAC; Rijssenbeek, Michael; /SUNY, Stony Brook

2005-11-09T23:59:59.000Z

291

Decision Summaries  

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

oha/decision-summaries Office of Hearings and Appeals oha/decision-summaries Office of Hearings and Appeals 1000 Independence Ave., SW Washington, DC, 20585 202-287-1566 en Summary of Decisions - December 30, 2013 - January 3, 2014 http://energy.gov/oha/articles/summary-decisions-december-30-2013-january-3-2014 summary-decisions-december-30-2013-january-3-2014" class="title-link">Summary of Decisions - December 30, 2013 - January 3, 2014

292

Summary of the environmental monitoring at the Rock Springs, Wyoming Site No. 9, true in situ oil shale retorting experiment  

SciTech Connect

The environmental effects and needed control technology associated with the potential in-situ retorting of oil shale in the Green River Basin (near Rock Springs, Wyoming) has been studied for over four years. This environmental monitoring program has included previous and existing in-situ oil-shale retorting field experiments and baseline data collection for potential future retorting experiments. The most extensive environmetal monitoring effort is at Rock Springs Site No. 9, a true in-situ oil-shale retorting field experiment which was ignited April 5, 1976. The purpose of this monitoring program was to identify any significant changes in the hydrology, air quality, and soils. Data have been collected during the pre-operational (baseline) and operational phases and continues to be collected during the post-operational phase. This report presents the results of the environmental monitoring conducted in support of the LETC Rock Springs No. 9 field experiment and the entire DOE oil shale program. 18 figures, 8 tables.

Virgona, J.E.; Poulson, R.E.; Spedding, T.J.

1979-06-01T23:59:59.000Z

293

EXECUTIVE SUMMARY  

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

EXECUTIVE SUMMARY This document contains an assessment of the first project to be completed under the U.S. Department of Energy Clean Coal Technology Program. The project was selected under Round I and is known officially as "The Demonstration of an Advanced Cyclone Coal Combustor, with Internal Sulfur, Nitrogen, and Ash Control for the Conversion of a 23 MMBtu/hour Oil-Fired Boiler to Pulverized Coal." The project was carried out by the Coal Tech Corporation over the period March 1987 February 1991 at the site of the Keeler/Dorr-Oliver Boiler Company in Williamsport, Pennsylvania. The project was a three-year demonstration scale test of a 30 MMBtu/hr air-cooled ceramic slagging cyclone combustor retrofitted to a horizontal 23-MMBtu/hr oil or natural gas-fired Keeler/Dorr-Oliver DS-9

294

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

SciTech Connect

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

Mike Lewis

2012-02-01T23:59:59.000Z

295

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

SciTech Connect

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

296

Untitled Page -- Considered Sites Summary  

Office of Legacy Management (LM)

BRIDGEPORT BRASS CO., HAVENS LABORATORY (Bridgeport, Connecticut) BROOKHAVEN NATIONAL LAB, BUILDINGS 353, 354, 467 & 468 (UPTON, New York) BROWN UNIVERSITY (METCALF RESEARCH...

297

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

Science Conference Proceedings (OSTI)

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

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

1997-10-01T23:59:59.000Z

298

Containment Versus Confinement for High-Temperature Gas Reactors: Regulatory, Design Basis, Siting, and Cost/Economic Considerations  

Science Conference Proceedings (OSTI)

This report provides the results of an investigation pertaining to the use of the confinement that has been proposed for the high temperature and very high temperature gas reactors (HTGR, VHTR). No comprehensive study of this question has been published since 1985. All power reactor designs to go into commercial service in the United States were light water reactors (LWR), except for Fort St. Vrain (FSV) and Peach Bottom Unit 1, which were steam cycle helium gas cooled reactors. All designs use a leak-ti...

2005-05-04T23:59:59.000Z

299

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

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

300

2010 Annual Planning Summary for Stanford Linear Accelerator...  

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

Annual Planning Summary for National Nuclear Security Administration Service Center (NNSA-SC) 2010 Annual Planning Summary for Nevada Site Office Energy.gov Careers & Internships...

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

DOE - Office of Legacy Management -- Elk River Reactor - MN 01  

Office of Legacy Management (LM)

Elk River Reactor - MN 01 FUSRAP Considered Sites Site: Elk River Reactor (MN.01 ) Eliminated from consideration under FUSRAP - Reactor was dismantled and decommissioned by 1974...

302

Program Summaries  

Office of Science (SC) Website

Program Summaries Program Summaries Basic Energy Sciences (BES) BES Home About Research Facilities Science Highlights Benefits of BES Funding Opportunities Basic Energy Sciences Advisory Committee (BESAC) News & Resources Program Summaries Brochures Reports Accomplishments Presentations BES and Congress Science for Energy Flow Seeing Matter Scale of Things Chart Contact Information Basic Energy Sciences U.S. Department of Energy SC-22/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3081 F: (301) 903-6594 E: sc.bes@science.doe.gov More Information » News & Resources Program Summaries Print Text Size: A A A RSS Feeds FeedbackShare Page Bes Summaries 2012 thumbnail JPG .jpg file (469KB) Basic Energy Sciences FY 2012 Research Summaries This report provides a collection of research abstracts and highlights for

303

Project Summary  

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

history page A Summary of Particle Physics THE SUBATOMIC WORLD Particles Prior to Accelerators By the mid 1930s, the understanding of the fundamental structure of matter seemed...

304

Science Summary  

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

Speciation to Aerosol Solubility: Potential Effects of Aerosol Source on Ocean Photosynthesis summary written by Raven Hanna The world's animals depend on plants, plants depend...

305

Summary Protocol: Identification, Characterization, Designation, Remedial  

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

Summary Protocol: Identification, Characterization, Designation, Summary Protocol: Identification, Characterization, Designation, Remedial Action, Certification Summary Protocol: Identification, Characterization, Designation, Remedial Action, Certification Summary Protocol: Identification, Characterization, Designation, Remedial Action, Certification (January 1986) Summary Protocol: Identification, Characterization, Designation, Remedial Action, Certification (January 1986) More Documents & Publications Supplement No. 1 to the FUSRAP Summary Protocol - Designation/Elimination Protocol Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at

306

Annual Planning Summaries: 2011 | Department of Energy  

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

Annual Planning Summaries: 2011 Annual Planning Summaries: 2011 Annual Planning Summaries: 2011 January 20, 2011 2011 Annual Planning Summary for Chicago Operations Office (CH) The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Chicago Operations Office (CH) (See Science APS). January 20, 2011 2011 Annual Planning Summary for Nevada Site Office (NSO) The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Nevada Site Office (NSO). January 19, 2011 2011 Annual Planning Summary for Southeastern Power Administration (SEPA) The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Southeastern Power Administration (SEPA).

307

Energy Department Announces Small Modular Reactor Technology...  

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

Small Modular Reactor Technology Partnerships at Savannah River Site Energy Department Announces Small Modular Reactor Technology Partnerships at Savannah River Site March 2, 2012...

308

Decommissioning License Termination Plan Documents and Lessons Learned: Summary of LTPs for Two Reactors and Nuclear Regulatory Comm ission Safety Evaluation Reports for Three Nuclear Power Plant LTPs  

Science Conference Proceedings (OSTI)

This report offers those utilities beginning the preparation of License Termination Plans (LTPs) in the near future a comprehensive summary of the approaches currently taken in LTP preparation by major nuclear decommissioning projects. The report details the approach taken in addressing each element of the LTP, and the lessons learned by those utilities currently undergoing the license termination process. This document provides needed guidance for the LTP process, and will greatly benefit utilities cons...

2004-04-28T23:59:59.000Z

309

Hanford Site  

NLE Websites -- All DOE Office Websites

Around the Site Current HMS Observations Daily HMS Extremes in Met Data Met and Climate Data Summary Products Contacts Hours Current NWS Forecast for the Tri-Cities NWS...

310

Milwaukee Meeting Summary - July, 1998  

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

Milwaukee Meeting Summary - July, 1998 Milwaukee Meeting Summary - July, 1998 Over 150 Members, participants, and observers representing state, tribal, and local governments, regional groups, industry, professional organizations, and the Department of Energy, met to address a variety of issues related to DOE's transportation activities for radioactive materials. A number of Departmental Programs with transportation components were represented, including: the Office of Environmental Management, the Office of Civilian Radioactive Waste Management (including the Yucca Mountain Project Office), the Office of Naval Reactors, the Waste Isolation Pilot Project, and the Office of Defense Programs. Topic Group Summaries and Comments DOE Program Office Discussions General Planning Breakout Discussions

311

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  

Science Conference Proceedings (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

312

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

SciTech Connect

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

313

Summary report on the HFED (High-Uranium-Loaded Fuel Element Development) miniplate irradiations for the RERTR (Reduced Enrichment Research and Test Reactor) Program  

SciTech Connect

An experiment to evaluate the irradiation characteristics of various candidate low-enriched, high-uranium content fuels for research and test reactors was performed for the US Department of Energy Reduced Enrichment Research and Test Reactor Program. The experiment included the irradiation of 244 miniature fuel plates (miniplates) in a core position in the Oak Ridge Research Reactor. The miniplates were aluminum-based, dispersion-type plates 114.3 mm long by 50.8 mm wide with overall plate thicknesses of 1.27 or 1.52 mm. Fuel core dimensions varied according to the overall plate thicknesses with a minimum clad thickness of 0.20 mm. Tested fuels included UAl/sub x/, UAl/sub 2/, U/sub 3/O/sub 8/, U/sub 3/SiAl, U/sub 3/Si, U/sub 3/Si/sub 1.5/, U/sub 3/Si/sub 2/, U/sub 3/SiCu, USi, U/sub 6/Fe, and U/sub 6/Mn/sub 1.3/ materials. Although most miniplates were made with low-enriched uranium (19.9%), some with medium-enriched uranium (40 to 45%), a few with high-enriched uranium (93%), and a few with depleted uranium (0.2 to 0.4%) were tested for comparison. These fuel materials were irradiated to burnups ranging from /approximately/27 to 98 at. % /sup 235/U depletion. Operation of the experiment, measurement of miniplate thickness as the irradiation progressed, ultimate shipment of the irradiated miniplates to various hot cells, and preliminary results are reported here. 18 refs., 12 figs., 7 tabs.

Senn, R.L.

1989-04-01T23:59:59.000Z

314

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

SciTech Connect

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

S.J. Roberts

2007-03-20T23:59:59.000Z

315

EPRI BWR BRAC Summary  

Science Conference Proceedings (OSTI)

This report provides a summary of BRAC point average dose rates for the forty-six BWRs (thirty-five U.S., two Mexican, five European, and four Asian) currently participating in the EPRI BWR Chemistry Monitoring and Assessment project. The BRAC value is normally the average of the reactor recirculation suction and discharge contact dose rates measured with a shielded directional probe in the vertical piping sections. The results are categorized by chemistry regime, drains path, and, for NMCA plants, by BW...

2009-08-31T23:59:59.000Z

316

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

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

317

Energynet Summary  

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

Project Summary Project Summary HELP Index Summary Scenario Reference Student Pages Subject/Content Area: Physical science/electricity, geometry and applied mathematics Target Audience: Middle school level - all students including gifted, learning-disabled, behavior-disordered and limited English proficient Project Goals: As a result of their participation in the Activating the EnergyNet project, the students will develop the abilities necessary to do scientific inquiry. They will increase their understanding of factors affecting energy cost and consumption, including the impact of energy production on the environment and the available technology and conversion costs. Students will use problem-solving strategies to design and implement interventions, assess the outcome, share data and strategies with other schools, and present

318

Fire Protection Program: Summary  

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

Summary Summary Since May 1950, an Annual Fire Protection Program Summary has been submitted by DOE's fire protection community. Currently, this report is required by section 5a.(8) of DOE Order 231.1. "Environment, Safety and Health Reporting." In 1999, an automation initiative was undertaken to streamline data collection and provide a more through review of DOE Reporting Element activities. This action resulted in the delayed publications of the CY 1999 and 2000 reports until 2002. It is now possible however to view all Annual Summary Reporting Element responses since 1991 at the Site, Operations, Lead Program Secretarial Office and Headquarters levels. Additionally, a build-in reference to other DOE reporting activities (CAIRS and ORPS) is available that allows Reporting Elements and managers the opportunity to review all fire protection events along previously mentioned categories. Reports listed below were generated from this application. To obtain a copy of the Annual Summary Application please contact Jim Bisker in the Office of Nuclear and Facility Safety Policy (EH-53) at (301)903-6542 or Jim Bisker.

319

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

SciTech Connect

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

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

1995-04-01T23:59:59.000Z

320

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

SciTech Connect

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.

1995-06-30T23:59:59.000Z

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.


321

Technical Information on the Carbonation of the EBR-II Reactor, Summary Report Part 2: Application to EBR-II Primary Sodium System and Related Systems  

DOE Green Energy (OSTI)

Residual sodium is defined as sodium metal that remains behind in pipes, vessels, and tanks after the bulk sodium metal has been melted and drained from such components. The residual sodium has the same chemical properties as bulk sodium, and differs from bulk sodium only in the thickness of the sodium deposit. Typically, sodium is considered residual when the thickness of the deposit is less than 5-6 cm. This residual sodium must be removed or deactivated when a pipe, vessel, system, or entire reactor is permanently taken out of service, in order to make the component or system safer and/or to comply with decontamination and decomissioning regulations. As an alternative to the established residual sodium deactivation techniques (steam-and-nitrogen, wet vapor nitrogen, etc.), a technique involving the use of moisture and carbon dioxide has been developed. With this technique, sodium metal is converted into sodium bicarbonate by reacting it with humid carbon dioxide. Hydrogen is emitted as a by-product. This technique was first developed in the laboratory by exposing sodium samples to humidifed carbon dioxide under controlled conditions, and then demonstrated on a larger scale by treating residual sodium within the Experimental Breeder Reactor II (EBR-II) secondary cooling system, followed by the primary cooling system, respectively. The EBR-II facility is located at the Idaho National Laboratory (INL) in southeastern Idaho, USA. This report is Part 2 of a two-part report. This second report provides a supplement to the first report and describes the application of the humdidified carbon dioxide technique ("carbonation") to the EBR-II primary tank, primary cover gas systems, and the intermediate heat exchanger. Future treatment plans are also provided.

Steven R. Sherman; Collin J. Knight

2006-03-01T23:59:59.000Z

322

Ames Laboratory Research Reactor Facility Ames, Iowa  

Office of Legacy Management (LM)

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

323

Reactor Operations informal monthly report September 1994  

SciTech Connect

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

Junker, L.

1994-09-01T23:59:59.000Z

324

2011 Annual Planning Summary for Stanford Linear Accelerator...  

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

Stanford Linear Accelerator Center Site Office (SLAC) 2011 Annual Planning Summary for Stanford Linear Accelerator Center Site Office (SLAC) The ongoing and projected Environmental...

325

5.0 SUMMARY  

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

0 SUMMARY 0 SUMMARY This environmental assessment provides an analysis of several approaches to the handling of hazardous and mixed wastes at DOE's Mound Plant in Miamisburg, Ohio. The first approach considered, the proposed action, involves the operation of an existing glass metter (also known as a Penberthy Pyro·Converter joule·heated glass furnace) for the treatment of hazardous and mixed wastes. The analysis also considers the no-action alternative, involving the continuance of existing practices at Mound for the handling of hazardous and mixed wastes, as well as various on-site and off-site treatment, storage, or disposal alternatives, Under the proposed action, the primary potential sources of environmental impact are air emissions and effluent discharges, Potential changes in air and water quality may

326

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

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

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

327

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

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

328

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

DOE Green Energy (OSTI)

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

Steven R. Sherman

2005-04-01T23:59:59.000Z

329

EIS-0391-FEIS-Summary-2012  

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

Summary Summary DOE/EIS-0391 Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site, Richland, Washington Summary U.S. Department of Energy November 2012 1 Cover Sheet Responsible Agency: U.S. Department of Energy (DOE) Cooperating Agencies: Washington State Department of Ecology (Ecology) U.S. Environmental Protection Agency (EPA) Title: Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site,

330

NERSC-InitialSummary.pptx  

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

Day-1 Summary Day-1 Summary Large Scale Computing and Storage Requirements for Biological and Environmental Research Joint BER / ASCR / NERSC Workshop NERSC Lawrence Berkeley National Laboratory May 7-8, 2009 Summary * Users need for more resources for DOE SC computing - But we need more concrete, science-based justification * Need for predictable throughput - Microbial Genomics and GFDL ESM - Need to differentiate between real-time needs and higher desired batch turnaround * Slow batch turnaround time may be because of queue policy or because of insufficient resources Summary * Data management issues transcend all science areas, multiple projects - Exponentially increasing - Some disagreement on volume at a single site Summary * Users see need for guidance / help in

331

H-Area, K-Area, and Par Pond Sewage Sludge Application Sites Groundwater Monitoring Report. Fourth quarter 1994 and 1994 summary  

SciTech Connect

Groundwater samples from the three wells at the H-Area Sewage Sludge Application Site (HSS wells) are analyzed quarterly for constituents as required by South Carolina Department of Health and Environmental Control Construction Permit 12,076. Samples from the three wells at the K-Area Sewage Sludge Application Site (KSS wells) and the three wells at the Par Pond Sewage Sludge Application Site (PSS wells) are analyzed quarterly for constituents required by SCDHEC Construction Permit 13,173. All samples are also analyzed as requested for other constituents as part of the Savannah River Site Groundwater Monitoring Program. Annual analyses for other constituents, primarily metals. also are required by the permits.

Chase, J.A.

1995-04-01T23:59:59.000Z

332

Executive Summary  

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

Executive Summary Executive Summary Highway-based excise taxes are paid by highway users, and the tax revenues are distributed to States for supporting highways, safety, and transit programs. The processes for collecting these taxes and redistributing them to the States are very complex. The U.S. Treasury collects most of the taxes from a relatively small number of large corporations located in only a few States. The Internal Revenue Service (IRS) does not have an accurate picture of where the motor fuel is eventually consumed. Because the actual State-by-State contributions are not available, detailed analyses are required to estimate a State's on-highway motor fuel use. The attribution process uses State-reported data and nationally applied statistical models to determine how much fuel is used on highways in each State and the proportion of each State's usage in comparison to the total motor fuel usage for all States.

333

EXECUTIVE SUMMARY  

National Nuclear Security Administration (NNSA)

FUSION ENERGY SCIENCE ADVISORY COMMITTEE FUSION ENERGY SCIENCE ADVISORY COMMITTEE Panel on High Energy Density Laboratory Plasmas ADVANCING THE SCIENCE OF HIGH ENERGY DENSITY LABORATORY PLASMAS January 2009 UNITED STATES DEPARTMENT OF ENERGY 1 TABLE OF CONTENTS EXECUTIVE SUMMARY.......................................................................................... 5 1 HIGH ENERGY DENSITY LABORATORY PLASMA SCIENCE .................................... 15 2 THE CHARGE TO FESAC ...................................................................................... 19 3 THE PANEL PROCESS ............................................................................................ 20 4 STEWARDSHIP OF THE JOINT PROGRAM ............................................................... 23

334

World Energy Data System (WENDS). Volume XI. Nuclear fission program summaries  

SciTech Connect

Brief management and technical summaries of nuclear fission power programs are presented for nineteen countries. The programs include the following: fuel supply, resource recovery, enrichment, fuel fabrication, light water reactors, heavy water reactors, gas cooled reactors, breeder reactors, research and test reactors, spent fuel processing, waste management, and safety and environment. (JWR)

1979-06-01T23:59:59.000Z

335

Summary of "Materials Modeling and Simulations for Nuclear Fuels"  

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

Summary of "Materials Modeling and Simulations for Nuclear Fuels" Summary of "Materials Modeling and Simulations for Nuclear Fuels" (MMSNF 2013) workshop Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share "Materials Modeling and Simulations for Nuclear Fuels" (MMSNF 2013) workshop Workshop Summary Presentation during MMSNF Workshop in Chicago

336

TEC Meeting Summaries - April 2005 Presentations | Department of Energy  

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

April 2005 Presentations April 2005 Presentations TEC Meeting Summaries - April 2005 Presentations Phoenix, Arizona Presentations (April 2005) Documents Available for Download Plenary I - United States Naval Nuclear Propulsion Program Plenary I - National Academies Update Plenary I - Transportation Resources Exchange Center Plenary I - Transportation Communications Plenary II - San Onofre Nuclear Generating Station Plenary II - Yucca Mountain Transportation Plenary II - Main Yankee Reactor Vessel Removal & Barge Transport Plenary III - Accomplishments and Future Topic Group Summaries - TEC Rail Topic Group Summary Topic Group Summaries - Section 180(c) Group Update Topic Group Summaries - Security Topic Group Update Topic Group Summaries - Tribal Topic Group Update Program Updates - Department of Energy Environmental Management

337

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

DOE Green Energy (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

338

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

Science Conference Proceedings (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

339

Executive Summary  

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

Worker Safety and Health Program LBNL/PUB-3851, Rev. 2.2 (March 2012) Worker Safety and Health Program LBNL/PUB-3851, Rev. 2.2 (March 2012) Worker Safety and Health Program Lawrence Berkeley National Laboratory LBNL Worker Safety and Health Program LBNL/PUB-3851, Rev. 2.2 (March 2012) This page intentionally left blank. LBNL Worker Safety and Health Program LBNL/PUB-3851, Rev. 2.2 (March 2012) i Contents Executive Summary .............................................................................................. v 1. Introduction................................................................................................... 1 1.1 Work Activities .............................................................................................. 1

340

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

Science Conference Proceedings (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

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

Partnership Overview and Summary  

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

Phase III Field Test Phase III Field Test Overview and Summary RCSP Initiative Annual Review Meeting Pittsburgh, PA October 6 - 8, 2008 Presented by Brian J. McPherson Southwest Regional Partnership on Carbon Sequestration New Mexico Tech 2 Southwest Regional Partnership on Carbon Sequestration Acknowledgements * Many thanks to the U.S. Department of Energy and NETL for supporting this project * We express our gratitude also to our many industry partners, who have committed a great deal of time, funding and other general support for these projects * The work presented today is co-authored by all partners in the Southwest Partnership 3 Southwest Regional Partnership on Carbon Sequestration * Phase II - Phase III Integration * Summary of Phase III Project * location * site characterization

342

COR Summary of Experience  

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

COR SUMMARY OF EXPERIENCE COR SUMMARY OF EXPERIENCE Effective January 1, 2012 CORs who are applying for certification must demonstrate past contracting, acquisition, procurement, program/project management, and general business experience. This experience is based on a set of competencies. Some of the competencies are listed below to use as a reference when you are documenting your previous experience. Use this template to document your experience. Experience should be supported by a written confirmation from the cognizant Contracting Officer/Contract Specialist showing the contract number, title and date(s) to which the experience applied. Once you have completed this document, please forward it and its supporting statement(s) to your Site Acquisition Career Manager (SACM) as part of your application for COR certification.

343

Energy Department Announces Small Modular Reactor Technology...  

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

Energy Department Announces Small Modular Reactor Technology Partnerships at Savannah River Site Energy Department Announces Small Modular Reactor Technology Partnerships at...

344

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

DOE Green Energy (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

345

Savannah River Site: Plutonium Preparation Project (PuPP) at...  

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

Site: Plutonium Preparation Project (PuPP) at Savannah River Site Savannah River Site: Plutonium Preparation Project (PuPP) at Savannah River Site Full Document and Summary...

346

Pinellas Remediation Agreement Summary  

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

Pinellas Pinellas Agreement Name Remediation Agreement for the Four and One-Half Acre Site in Largo, Pinellas County, Florida State Florida Agreement Type Remediation Agreement Legal Driver(s) CERCLA/ Atomic Energy Act of 1954, as amended/ Florida Air and Water Pollution Control Act Scope Summary Remediation of property adjacent to the former Pinellas Plant Parties DOE; Florida Department of Environmental Protection Date 3/12/2001 SCOPE * Remediate the groundwater under a parcel of property adjacent to DOE's former Pinellas Plant to levels consistent with industrial use. * Complete remedial actions at the site in accordance with a Remedial Action Plan prepared by DOE and approved by FDEP. * Submit quarterly reports of interim remedial actions at the Site.

347

Grid Connected Integrated Community Energy System. Volume 1. Summary and demonstration site description. Final report, Phase I, February 1, 1977-May 31, 1977  

SciTech Connect

The University of Minnesota and its partners - St. Mary's and Fairview hospitals, Augsburg College, Northern States Power Company, and possibly some small add-on customers - will develop the feasibility of a Grid-Connected Integrated Community Energy System utilizing cogeneration of electricity as a byproduct of steam in an educational, residential, hospital, and commercial community. An overview of the site is given. The geographical location, spatial data topographical data, and modes of transportation to and from the site are given. Environmental data (geology, surficial geology, regional watershed, trees, building shadows, climatological data, environmental quality data, and the microclimate) are discussed. The open space, outdoor use, and wildlife habitat are assessed. Information on the building sectors includes sector energy density, night time usage, building construction, steam adsorption air conditioning, electric air conditioning, and University Hospital air conditioning. The building sector energy profiles and the special service sectors are described. (MCW)

Soderberg, W.E.; O' Gara, J.C.; Reid, R.A.; Lewis, R.; Ervasti, M.; Pearce, J.

1977-06-01T23:59:59.000Z

348

ORNL Site Ofice  

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

ORNL Site Ofice ORNL Site Ofice P.O. Box 2008 Oak Ridge, Tennessee 37831-6269 January 28, 2013 MEMORANDUM FOR GREGORY H. WOODS GENERAL COUNSEL GC-1 FROM: SUBJECT: ��MK = MOORE, MANAGER lF �NL SITE OFFICE ANNUAL NATIONAL ENVIRONMENTAL POLICY ACT (NEPA) PLANNING SUMMARY FOR 2013- OAK RIDGE NATIONAL LABORATORY (ORNL) SITE OFFICE (OSO) This correspondence transmits the Annual NEPA Planning Summary for 2013 for OSO.

349

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

Science Conference Proceedings (OSTI)

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

NONE

1995-06-01T23:59:59.000Z

350

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

Science Conference Proceedings (OSTI)

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

NONE

1995-07-01T23:59:59.000Z

351

Science Summary  

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

February 25, 2010 February 25, 2010 seafloor_biofilms Image of pillow basalts from inside the Pisces Submersible. » Links Scientific Highlight Templeton Lab EMSL News Imaging at SSRL » Share this Article Laboratree Ologeez SciLink LabSpaces Researchers Discover an Unexpected Source of Energy for Deep-sea Microbial Communities summary written by Raven Hanna New rock formed by deep undersea volcanoes does not stay bare long. Microbes quickly move onto these basalts to form communities in the form of biofilms. As these biofilms grow and develop, they change the geology of their environment, forming mineral deposits. Since many of these communities are deep in the cold ocean waters, where sunlight does not reach, they must use alternative sources of energy. What these might be is unknown, but a common theory posits that the microbes may be obtaining

352

Science Summary  

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

10 10 image Outside view of the T=4 subunit arrangement. » Links Scientific Highlight Johnson Lab » Share this Article Laboratree Ologeez SciLink LabSpaces Following the pH-dependent Conformational Changes of a Maturing Viral Capsid summary written by Raven Hanna The capsid that surrounds viruses is formed from subunit proteins that interact in specific ways to form a tight shell. The processes of coming together and forming interactions are multistep and complex and are fundamental events to acquire viral infectivity. The capsid maturation process of the Nudaurelia capensis omega virus includes pH-dependant conformational changes and auto-proteolysis. Like many human viruses such as HIV and herpes virus, NwV, an insect virus, requires these specific structural changes to become infectious.

353

Science Summary  

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

July 30, 2009 July 30, 2009 » Links Scientific Highlight Center for Advanced Molecular Photovoltaics, Stanford University » Share this Article Laboratree Ologeez SciLink LabSpaces Molecular Mixing in Organic Solar Cells summary written by Raven Hanna Solar panels contain a number of solar cells that convert light into electricity. Solar cells are traditionally made of crystalline silicon, which presently have 15-20% efficiency in conversion of light into electricity. However, these traditional cells are bulky and have high production costs that can take 5-7 years of solar panel operation to recover. Using solar cells made from organic materials could lower their production costs. This would lessen the time it takes for solar panels to generate more energy than consumed during production and would also result

354

Science Summary  

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

pseudogap image pseudogap image » Links Scientific Highlight SIMES Shen Lab SLAC Today Article » Share this Article Laboratree Ologeez SciLink LabSpaces Scientists Find Unexpected Electron Behavior in the Pseudogap of High-temperature Superconductors summary written by Raven Hanna Superconductivity is a hot topic in physics for good reason. With an electrical resistance of zero, superconductors transport electrical current with no loss of energy. Unfortunately, scientists have only found materials to be superconducting at very low temperatures, much too low for widespread use. In the 1980s, scientists discovered a class of "high-temperature" superconductors that can be used at the temperature of liquid nitrogen (~-200°C). This discovery has raised scientists' hopes that materials may

355

Science Summary  

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

Hasan Research Hasan Research Princeton News Release » Share this Article Laboratree Ologeez SciLink LabSpaces Macroscopic Quantum Insulator State Observed summary written by Raven Hanna One of the strangest consequences of quantum mechanics is the seemingly instantaneous communication of subatomic particles over long distances. Known as quantum entanglement, pairs or groups of particles can become linked so that any changes made to one will cause the others to respond quicker than the time it takes for light to travel between them. Scientists are interested in finding a material that shows quantum entanglement on a macroscopic scale but which is neither a superconductor nor a superfluid. Dubbed a topological insulator, this theorized, exotic state of matter would have unusual conducting properties. For example,

356

Science Summary  

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

03, 2008 03, 2008 » Links Scientific Highlight Tainer Website Scripps Press Release » Share this Article Laboratree Ologeez SciLink LabSpaces Role of Specific Protein Mutations in Causing Human Disease Revealed summary written by Brad Plummer, SLAC Communication Office Scientists are one step closer to understanding a piece of the machinery involved in DNA transcription and repair, thanks to work done in part at the SSRL macromolecular crystallography Beam Line 11-1. The team, led by The Scripps Research Institute researcher John Tainer, and colleagues worked out the structure of an important enzyme call XPD, a member of the helicase family of enzymes, found in all living organisms. The results were published in the May 2008 edition of the journal Cell. In eukaryotes, XPD is responsible for unwinding double-stranded DNA

357

Science Summary  

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

25, 2008 25, 2008 » Links Scientific Highlight Saphire Website Scripps Press Release Tracking Ebola, Scripps At the Forefront » Share this Article Laboratree Ologeez SciLink LabSpaces Revealing a Structural Weakness of the Deadly Ebolavirus summary written by Brad Plummer, SLAC Communication Office Scientists are one step closer to conquering the deadly Ebolavirus, thanks to research conducted at SSRL structural biology Beam Lines 9-2 and 11-1 and ALS Beam Line 5.02 by a team of researchers led by Erica Ollmann Saphire from The Scripps Research Institute. The results were published in the July 10 edition of the journal Nature. Using macromolecular crystallography techniques, the team solved the structure of a protein on the Ebolavirus's surface, called glycoprotein GP,

358

Technology summary of the in situ bioremediation demonstration (methane biostimulation) via horizontal wells at the Savannah River Site Integrated Demonstration Project  

Science Conference Proceedings (OSTI)

The US Department of Energy, Office of Technology Development, has been sponsoring full-scale environmental restoration technology demonstrations for the past 4 years. The Savannah River Site Integrated Demonstration focuses on ``Clean-up of Soils ad Groundwater Contaminated with Chlorinated VOCs.`` Several laboratories including our own had demonstrated the ability of methanotrophic bacteria to completely degrade or mineralize chlorinated solvents, and these bacteria were naturally found in soil and aquifer material. Thus the test consisted of injection of methane mixed with air into the contaminated aquifer via a horizontal well and extraction from the vadose zone via a parallel horizontal well.

Hazen, T.C.; Looney, B.B.; Fliermans, C.B.; Eddy-Dilek, C.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Lombard, K.H. [Bechtel Savannah River, Inc., Aiken, SC (United States); Enzien, M.V. [Argonne National Lab., IL (United States); Dougherty, J.M. [US Environmental Protection Agency, Irving, TX (United States); Wear, J. [Catawba State Coll., Salisbury, NC (United States)

1994-06-01T23:59:59.000Z

359

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

Science Conference Proceedings (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

360

DOE-ID Operations Summary  

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

January 6, 2014 January 6, 2014 DOE-ID Operations Summary For the Period November 01, 2013 through November 30, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709. Advanced Mixed Waste Treatment Project (AMWTP) Nothing to Report Notable Accomplishments: Contracting companies supporting EM's cleanup program and the Office of Nuclear Energy at the Idaho site volunteered to be among the first to use a new DOE

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

NNSA Sites | Department of Energy  

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

NNSA Sites NNSA Sites NNSA Sites Compliance agreements for National Nuclear Security Administration sites are listed here with accompanying summaries. Los Alamos National Laboratory Consent Agreement, December 10, 1993 Los Alamos National Laboratory Consent Agreement, December 10, 1993 Summary Los Alamos National Laboratory Compliance Order, October 4, 1995 Los Alamos National Laboratory Compliance Order, October 4, 1995 Summary South Valley Compliance Agreement South Valley Compliance Agreement Summary Mutual Consent Agreement for Storage of LDR, January 6, 1994 Mutual Consent Agreement for Storage of LDR, January 6, 1994 Summary Nevada Test Site FFCA Consent Order, March 27, 1996 Nevada Test Site FFCA Consent Order, March 27, 1996 Summary Nevada Test Site FFCA Consent Order, May 10, 1996

362

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

Science Conference Proceedings (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

363

Characterization Summary Report for the  

E-Print Network (OSTI)

(LLNL) are submitting this Characterization Summary Report for the Building 865 study area at LLNL Site 300. This letter report summarizes the results of environmental investigations performed in the Building 865 study area to determine if contamination has been released to the environment as a result of past activities. The results of this remedial investigation are organized

Ms. Kathy Setian; Mr. Jacinto Soto; Ms. Susan Timm

2006-01-01T23:59:59.000Z

364

EPRI Boiling Water Reactor Mitigation Performance Summary  

Science Conference Proceedings (OSTI)

This report summarizes the intergranular stress corrosion cracking (IGSCC) mitigation performance of 44 BWRs with or without noble metal chemical addition or On-Line NobleChem. Results are categorized by chemistry regime and include data from the most recently completed and current operating cycles. BWRs continue to strive for high hydrogen water chemistry (HWC) availability for IGSCC mitigation, and most plants achieve an overall mitigation performance indicator in the green (excellent) or white (satisf...

2010-03-23T23:59:59.000Z

365

FY 2006 Summary Table by Appropriation  

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

Appropriation Account Summary Appropriation Account Summary (dollars in thousands - OMB Scoring) FY 2004 FY 2005 FY 2006 Comparable Comparable Request to FY 2006 vs. FY 2005 Approp Approp Congress Energy And Water Development Energy Programs Energy supply....................................................................... Non-Defense site acceleration completion........................... Uranium enrichment D&D fund............................................ Non-Defense environmental services................................... Science................................................................................. Nuclear waste disposal......................................................... Departmental administration.................................................

366

Preliminary design of a solar central receiver for a site-specific repowering application (Saguaro Power Plant). Volume 1. Executive summary. Final report, October 1982-September 1983  

DOE Green Energy (OSTI)

The preliminary design of a solar central receiver repowered gas/oil fired steam-Rankine cycle electric power generation plant was completed. The design is based on a central receiver technology using molten salt (60% NaNO/sub 3/, 40% KNO/sub 3/, by weight) for the heat transport and thermal storage fluid. Unit One of APS's Saguaro power plant located 43 km (27 mi) northwest of Tucson, AZ, is to be repowered. The selection of both the site and the molten salt central receiver promotes a near-term feasibility demonstration and cost-effective power production from an advanced solar thermal technology. The recommended system concept is to repower the existing electric power generating system at the minimum useful level (66 MW/sub e/ gross) using a field of 4850 Martin Marietta second-generation (58.5 m/sup 2/) heliostats and a storage capacity of 4.0 hours. The storage capacity will be used to optimize dispatch of power to the utility system. The preliminary design was based on the use of the systems approach to design where the overall project was divided into systems, each of which is clearly bounded, and performs specific functions. The total project construction cost was estimated to be 213 million in 1983 dollars. The plant will be capable of displacing fossil energy equivalent to 2.4 million barrels of No. 6 oil in its first 10 years of operation.

Weber, E.R.

1983-09-01T23:59:59.000Z

367

Executive Summary  

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

5 5 Nauru Island Effect Study (NIES) IOP Science Plan June 2001 Chuck Long Pacific Northwest National Laboratory ARM TWP Site Scientist, NIES IOP Lead Scientist Richland, Washington Work supported by the U.S. Department of Energy, Office of Science, Office of Biological and Environmental Research C. Long., DOE/SC-ARM-0505 Contents 1. Background ............................................................................................................................... 1 2. Scientific Requirement.............................................................................................................. 5 3. Experimental Approach ............................................................................................................

368

Photocatalytic reactor  

DOE Patents (OSTI)

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

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

1999-01-01T23:59:59.000Z

369

Operating Experience Summaries  

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

Operating Experience Summaries The Office of Health, Safety and Security (HSS) Office of Analysis publishes the Operating Experience Summary to exchange lessons-learned information...

370

Executive Summary  

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

4 4 Department of Energy Atmospheric Radiation Measurement Southern Great Plains Cloud and Radiation Testbed Site, Lamont, Oklahoma Science Plan for the Aerosol IOP May 2003 Rich Ferrare NASA Langley Research Center Contributions from: Anthony Bucholtz Graham Feingold Navel Research Laboratory NOAA/Environmental Technology Laboratory Steve Ghan John Ogren Pacific Northwest National Laboratory NOAA/CMDL Jens Redemann Beat Schmid BAERI/NASA Ames Research Center Bay Area Environmental Research Institute NASA Ames Research Center Steve Schwartz Pat Sheridan Brookhaven National Laboratory U.S. Department of Commerce/NOAA Climate Monitoring and Upton, Diagnostics Laboratory Aerosol Working Group Work supported by the U.S. Department of Energy,

371

U.S. Department of Energy Technology Marketing Summaries ...  

Site Map; Printable Version; Share this resource. Send a link to U.S. Department of Energy Technology Marketing Summaries - Energy Innovation Portalto ...

372

Y-12_Front Cover_Summary_Feb2011.ai  

National Nuclear Security Administration (NNSA)

Summary COVER SHEET RESPONSIBLE AGENCY: United States (U.S.) Department of Energy (DOE), National Nuclear Security Administration (NNSA) TITLE: Final Site-Wide Environmental Impact...

373

ANNUAL NATIONAL ENVIRONMENTAL POLICY ACT PLANNING SUMMARY FOR  

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

ENVIRONMENTAL POLICY ACT PLANNING SUMMARY FOR FISCAL YEAR 2012 FOR THE Y-12 NATIONAL SECURITY COMPLEX I. Environmental Impact Statements (EIS) on-going activity. Site-Wide...

374

2011 Annual Planning Summary for Bonneville Power Administration...  

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

Annual Planning Summary for National Nuclear Security Administration Service Center (NNSA-SC) Energy.gov Careers & Internships Guidance & Requirements Contact Us About This Site...

375

2010 Annual Planning Summary for Civilian Radioactive Waste Management...  

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

Annual Planning Summary for National Nuclear Security Administration Service Center (NNSA-SC) Energy.gov Careers & Internships Guidance & Requirements Contact Us About This Site...

376

2010 Annual Planning Summary for Office of River Protection ...  

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

Annual Planning Summary for National Nuclear Security Administration Service Center (NNSA-SC) Energy.gov Careers & Internships Guidance & Requirements Contact Us About This Site...

377

2010 Annual Planning Summary for Legacy Management | Department...  

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

Annual Planning Summary for National Nuclear Security Administration Service Center (NNSA-SC) Energy.gov Careers & Internships Guidance & Requirements Contact Us About This Site...

378

Widget:AnalyticsSummary | Open Energy Information  

Open Energy Info (EERE)

AnalyticsSummary AnalyticsSummary Jump to: navigation, search Google Analytics widget that returns an HTML summary of site-wide analytics. Use any arbitrary number of days; for instance, 30-31 days will say "a month", 7 days will say "a week", 1 day will say "a day", 365 days will say "a year", and all other day rates will say "n days". How to call it: {{#Widget:AnalyticsSummary|days=30}} Example Output Loading... Statistics summary for the last 1 7 30 365 days Retrieved from "http://en.openei.org/w/index.php?title=Widget:AnalyticsSummary&oldid=535712" Category: Widgets What links here Related changes Special pages Printable version Permanent link Browse properties 429 Throttled (bot load) Error 429 Throttled (bot load)

379

DOE-ID Operations Summary  

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

26, 2013 26, 2013 DOE-ID Operations Summary For the Period July 29, 2013 through August 12, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709. Advanced Mixed Waste Treatment Project (AMWTP) July 31, 2013: The Idaho Treatment Group, LLC (ITG), the managing contractor for the Advanced Mixed Waste Treatment Project received a warning letter from the State of Idaho's Department of Environmental quality regarding self- reported RCRA permit violations which

380

DOE-ID Operations Summary  

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

June 5, 2013 June 5, 2013 DOE-ID Operations Summary For the Period May 16, through May 30, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC - Shannon Brennan, DOE-ID, (208) 526-3993. Advanced Mixed Waste Treatment Project (AMWTP) [No items to Report] Idaho Cleanup Project (ICP) May 15 - 30, 2013: CH2M-WG Idaho, LLC discovered three instances of new information at the Integrated Waste Treatment Unit (IWTU) which have the potential to impact the nuclear safety analysis

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

Summary | Building Energy Codes Program  

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

Summary Summary The impact of energy codes on our future is apparent. From environmental and resource conservation to national security, energy concerns, and our economic challenges, energy codes will continue to be a key component of a sound public policy. For further information on building energy code adoption, compliance, and enforcement, review the ACE toolkits Adoption Compliance Enforcement Popular Links ACE Learning Series ACE Overview Top 10 Reasons for Energy Codes Development of Energy Codes Adoption of Energy Codes Compliance with Energy Codes Enforcement of Energy Codes Going Beyond Code Summary Acronyms and Abbreviations Toolkit Definitions Adoption Toolkit Compliance Toolkit Enforcement Toolkit Contacts Web Site Policies U.S. Department of Energy USA.gov Last Updated: Thursday, January 31, 2013 - 15:19

382

DOE-ID Operations Summary  

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

18, 2013 18, 2013 DOE-ID Operations Summary For the Period September 30, 2013 through October 31, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709. Advanced Mixed Waste Treatment Project (AMWTP) October 15, 2013: A manager at the Advanced Mixed Waste Treatment Project (AMWTP) determined that the AMWTP Safety Analysis process required review due to an operational trend of fire/combustion events in the Treatment Facility (TF) box lines. Safety analysis for the TF is

383

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT (FOR) JULY 1961  

SciTech Connect

A summary is presented of activities in reactor and general engineering research programs. Discussions are included for developments in EBWR, BORAX-V, ZPR-III. ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Reactor safety studies were performed for fast and thermal reactors. Nuclear technology developments are discussed for applied nuclear and reactor physics, reactor fuels and materials development, heat engineering studies, separations processes, and advanced reactor concepts. (B.O.G.)

1961-08-15T23:59:59.000Z

384

NEUTRONIC REACTOR BURIAL ASSEMBLY  

DOE Patents (OSTI)

A burial assembly is shown whereby an entire reactor core may be encased with lead shielding, withdrawn from the reactor site and buried. This is made possible by a five-piece interlocking arrangement that may be easily put together by remote control with no aligning of bolt holes or other such close adjustments being necessary.

Treshow, M.

1961-05-01T23:59:59.000Z

385

LAI References and Summaries  

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

Cart Sign In/Register Quick Data Search Help icon Go NASA Meatball Cart Sign In/Register Quick Data Search Help icon Go NASA Meatball No JAVASCRIPT Capabilities. This site will not function without JavaScript. Please use the Web Product Tree. or anonymous FTP at ftp://daac.ornl.gov/data. Global Leaf Area Index Data from Field Measurements, 1932-2000 References and summaries for literature on leaf area index (reviews, methodology, etc.) Barclay, H. J. (1998) Conversion of total leaf area to projcted leaf area in lodgepole pine and Douglas-fir. Tree PHysiology 18, 185-193. Summary It is noted that three distinct definitions of leaf area index (LAI) in the literature have no predictable relationship with each other. Conversion factors were derived, from total LAI to projected LAI of horizontal leaves and to projected LAI for inclined leaves of lodgepole pine and coastal Douglas-fir, enabling comparison of results from different studies. An algorithm was derived to allow determination of these factors based on twig angles and the angles that the foliage subtends with the twig. The conversion factor was more sensitive to differences in vertical angles of the twigs than to twig rotation or foliar arrangement on the twig.

386

Hanford Site C Tank Farm Meeting Summary  

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

K1) K1) Document Number: RPP-50002 Vdo(2) Revision Number: 0 (3) Effective Date: 06/20/2011 ()Document Type: E Digital Image E] Hard copy (a) Number of pages (including the DRIF) or 17 Z PDFVideonumber of digital images (5) Release Type Z New El Cancel Ifl Page Change E] Complete Revision (6) Document Title: Meeting Minutes Waste Management Area C Performance Assessment Ecological Risk Working Session held at Washington State Department of Ecology Offices 3100 Port of Benton Boulevard Richland, WA 99352 on May 17 through May 18, 2011 (7) Change/Release Initial release Description: (8) Change Justification: N/A (9) Associated Structure, (a) Structure Location: (c) Building Number: (a) Project Number: System, andN/NANA Component (SSC) and N/I/ / Building Number: (b) System Designator: (d) Equipment ID Number (EIN):

387

Hanford Site C Tank Farm Meeting Summary  

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

RPP-48144, Rev. 0 RPP-48144, Rev. 0 Page 1 of 15 Meeting Minutes Waste Management Area C Performance Assessment Exposure Scenarios Working Session held at Washington State Department of Ecology Offices 3100 Port of Benton Boulevard Richland, WA 99352 on September 28 through September 30, 2010 LIST OF TERMS Abbreviations and Acronyms CA Composite Analysis CEES Columbia Energy and Environmental Services, Inc. CERCLA Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (Public Law 111-88, 123 Stat. 2924, 42 USC 9607 et seq.) CHPRC CH2M HILL Plateau Remediation Company CRESP Consortium for Risk Evaluation with Stakeholder Participation CTUIR Confederated Tribes of the Umatilla Indian Reservation DOE U.S. Department of Energy DOE-EM U.S. Department of Energy-Office of Environmental Management

388

Hanford Site C Tank Farm Meeting Summary  

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

9066 (2) Revision Number: 0 (3) Effective Date: 03/01/201 9066 (2) Revision Number: 0 (3) Effective Date: 03/01/201 (4) Document Type: E] Digital Image E Hard copy (a) Number of pages (including the DRF) or 68 Z PDFVideonumber of digital images (5) Release Type ZNew E cancel Ifl Page Change Complete Revision (6) Document Title: Meeting Minutes for the WMA C PA Numerical Codes and Models Working Session (7) Change/Release Initial release Description: (8) Change Justification: N/A (9) Associated Structure, (a) Structure Location: (c) Building Number: (e) Project Number: System, andNIN/NA Component (SSC) and N/I/ / Building Number: (b) System Designator: (d) Equipment ID Number (EIN): N/A N/A (10) Impacted (a) Document Type (b) Document Number (c) Document Revision Documents: N/A N/A N/A (11) Approvals: (a) Author (Print/Sign):,1 Date:

389

xvii 1999 SITE ENVIRONMENTAL REPORT Executive Summary  

E-Print Network (OSTI)

. In 1999, pollution prevention projects saved over $1,600,000 and reduced, recycled, or reused over 16 are ongoing. RADIOLOGICAL DOSE ASSESSMENT The evaluation of potential radioactive dose to the public showed

Homes, Christopher C.

390

Savannah River Site Patented Technologies Summaries  

DOE Green Energy (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

391

2008 Annual Site Environmental Report Summary Pamphlet  

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

Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04-94AL85000. Approved for public release; further...

392

COR Summary of Experience  

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

COR SUMMARY OF EXPERIENCE Effective January 1, 2012, the Office of Federal Procurement Policy (OFPP) added a requirement for past COR experience to qualify for FAC-COR Level II (journeyman level) and III (senior/expert level). At least 1 year of COR experience is required to qualify for Level II; 2 years for Level III. OFPP strongly advises that applicants for Level III have prior experience at Level II. Applicants with no prior experience as an appointed COR must demonstrate proficiency in the specific competencies listed below for the same time period, validated by a cognizant Contracting Officer or Contract Specialist by signature below or an accompanying e-mail. Submit this form to your Site Acquisition Career Manager (SACM) as part of your application

393

Compilation of TRA Summaries  

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

September 2011 September 2011 Technology Readiness Assessment Summary Number Title Report Date TRA-1 Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory, Balance of Facilities and LAW Waste Vitrification Facilities at Hanford March 2007 TRA-2 Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility at Hanford March 2007 TRA-3 Waste Treatment and Immobilization Plant (WTP) Pretreatment Facility at Hanford March 2007 TRA-4 K Basins Sludge Treatment Process at Hanford August 2007 TRA-5 Savannah River Site Tank 48H Waste Treatment Project at SRS July 2007 TRA-6 233Uranium Downblending and Disposition Project at Oak Ridge/ORNL September 2008 TRA-7 SRS Salt Waste Processing Facility at SRS July 2009

394

Closure Sites | Department of Energy  

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

Closure Sites Closure Sites Closure Sites View a list of the compliance agreements for the many EM closure sites, such as Mound and Rocky Flats, below. Associated summaries are also included. Pinellas Remediation Agreement Pinellas Remediation Agreement Summary Maxey Flats Consent Decree -Part 1, April 18, 1996 Maxey Flats Consent Decree -Part 2, April 18, 1996 Maxey Flats Consent Decree April 18, 1996 Summary Monticello Mill site Federal Facility Agreement, December 22, 1988 Monticello Mill site Federal Facility Agreement, December 22, 1988 Summary Battelle Columbus Laboratories Director's Final Findings and Orders, October 4, 1995 Battelle Columbus Laboratories Director's Final Findings and Orders, October 4, 1995 Summary Fernald Environmental Management Project Consent Agreement and Final Order,

395

Energy Savings Performance Contracts Summary  

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

ENERGY SAVINGS PERFORMANCE CONTRACTS SUMMARY ENERGY SAVINGS PERFORMANCE CONTRACTS SUMMARY Site Contract Number Delivery or Task Order # Contractor Performance Period Contract Value Contract Description Richland DE-AC06-97RL13184 N/A Johnson Controls, Inc. 11/15/1996- 11/14/2021 $160.7M Conversion from central coal-fired steam plant to decentralized diesel boilers for Hanford Areas 200 & 300 (Site specific, standalone contract) DE-AM36-97EE73568 DE-AT06-09RL14923 Johnson Controls, Inc. 10/10/2008- 3/31/2033 $19.9M HVAC, Automation, Boiler Improvements Savannah River DE-AM36-02-NT41457 DE-AT09-09SR22572 Ameresco Federal Solutions 5/15/2009- 4/15/2031 $795M Biomass Cogeneration Facility and K and L Area Heating Plants

396

2002 WIPP Summary.cdr  

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

Waste Isolation Waste Isolation Pilot Plant Summary Report Office of Independent Oversight and Performance Assurance Office of the Secretary of Energy August 2002 OVERSIGHT Table of Contents 1.0 INTRODUCTION ...................................................................... 1 2.0 STATUS AND RESULTS .......................................................... 4 2.1 Positive Attributes ............................................................... 4 2.2 Program Weaknesses .......................................................... 6 3.0 CONCLUSIONS ....................................................................... 8 4.0 RATINGS .................................................................................10 APPENDIX A - SUPPLEMENTAL INFORMATION ................... 11 APPENDIX B - SITE-SPECIFIC FINDINGS

397

Hanford Site Development Plan  

SciTech Connect

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

398

NGNP SITE 2 HAZARDS ASSESSMENT  

SciTech Connect

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

399

All Other Sites | Department of Energy  

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

All Other Sites All Other Sites All Other Sites Compliance agreements for other sites not identified above are listed here. Summaries of these agreements also are listed. Brookhaven National Laboratory Federal Facility Agreement, February 28, 1992 Brookhaven National Laboratory Federal Facility Agreement, February 28, 1992 Summary Energy Technology and Engineering Center Compliance Order, October 6, 1995 Energy Technology and Engineering Center Compliance Order, October 6, 1995 Summary General Atomics Compliance Order, October 6, 1995 General Atomics Compliance Order, October 6, 1995 Summary Lawrence Berkeley National Laboratory Compliance Order, October 6, 1995 Lawrence Berkeley National Laboratory Compliance Order, October 6, 1995 Summary Laboratory for Energy-Related Health Research Compliance Order, October 6,

400

All Other Sites | Department of Energy  

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

All Other Sites All Other Sites All Other Sites Compliance agreements for other sites not identified above are listed here. Summaries of these agreements also are listed. Brookhaven National Laboratory Federal Facility Agreement, February 28, 1992 Brookhaven National Laboratory Federal Facility Agreement, February 28, 1992 Summary Energy Technology and Engineering Center Compliance Order, October 6, 1995 Energy Technology and Engineering Center Compliance Order, October 6, 1995 Summary General Atomics Compliance Order, October 6, 1995 General Atomics Compliance Order, October 6, 1995 Summary Lawrence Berkeley National Laboratory Compliance Order, October 6, 1995 Lawrence Berkeley National Laboratory Compliance Order, October 6, 1995 Summary Laboratory for Energy-Related Health Research Compliance Order, October 6,

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

Evaluation of Suitability of Selected Set of Department of Defense Military Bases and Department of Energy Facilities for Siting a Small Modular Reactor  

SciTech Connect

This report summarizes the approach that ORNL developed for screening a sample set of US Department of Defense (DOD) military base sites and DOE sites for possible powering with an SMR; the methodology employed, including spatial modeling; and initial results for several sample sites. The objective in conducting this type of siting evaluation is demonstrate the capability to characterize specific DOD and DOE sites to identify any particular issues associated with powering the sites with an SMR using OR-SAGE; it is not intended to be a definitive assessment per se as to the absolute suitability of any particular site.

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

2013-03-01T23:59:59.000Z

402

Analysis of the antineutrino rate during CANDU reactor startup.  

E-Print Network (OSTI)

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

[No author

2012-01-01T23:59:59.000Z

403

Meson Summary Table See  

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

Meson Summary Table See also the table of suggested qq quark-model assignments in the Quark Model section. * Indicates particles that appear in the preceding Meson Summary Table....

404

Photon 2009 - Experimental Summary  

E-Print Network (OSTI)

I present a summary of the experimental talks given at the Photon 2009 conference held at DESY, Hamburg, Germany.

P. J. Bussey

2009-08-04T23:59:59.000Z

405

Albuquerque Roundtable Summary  

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

Summary from the DOE Office of Indian Energy roundtable session on April 6, 2011, in Albuquerque, New Mexico.

406

Las Vegas Roundtable Summary  

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

Summary report from the DOE Office of Indian Energy roundtable held on March 16, 2011, in Las Vegas, Nevada.

407

Annual Planning Summaries By Office | Department of Energy  

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

Annual Planning Summaries By Office Annual Planning Summaries By Office Annual Planning Summaries By Office SECRETARIAL OFFICES Advanced Research and Projects Agency (ARPA-E) Electricity Delivery and Energy Reliability (OE) Energy Efficiency and Renewable Energy (EE) Environmental Management (EM) Fossil Energy (FE) Health, Safety and Security (HSS) Intelligence and Counterintelligence (IN) Legacy Management (LM) Loan Programs Office (LPO) Nuclear Energy (NE) Science (SC) POWER MARKETING ADMINISTRATIONS Bonneville Power Administration (BPA) Southeastern Power Administration (SEPA) Southwestern Power Administration (SWPA) Western Area Power Administration (WAPA) DOE FIELD OFFICES Ames Site Office (ASO) Argonne Site Office (See SC APS) Berkeley Site Office (BSO) Brookhaven Site Office (BHSO) (See SC APS)

408

Colorado/Transmission/Summary | Open Energy Information  

Open Energy Info (EERE)

Colorado/Transmission/Summary Colorado/Transmission/Summary < Colorado‎ | Transmission Jump to: navigation, search ColoradoTransmissionHeader.png Roadmap Agency Links Local Regulations State Regulations Summary General Transmission Dashboard Permitting Atlas Compare States Arizona California Colorado Idaho Montana Nevada New Mexico Oregon Utah Washington Wyoming Resource Library NEPA Database Transmission Permitting at a Glance In Colorado, local governments (counties and municipalities) have the authority to site high-voltage transmission lines. The State's authority in siting is limited to a backstop appeal process, by which utilities may submit an appeal to local government decisions to the Colorado Public Utilities Commission (CPUC) for review and resolution. State Siting Act None State Preemptive Authority The CPUC has backstop authority only. If a permit is denied by the local government, the applicant may appeal to the CPUC if certain conditions are met (CRS 29-20-108).

409

Summary of Emergency Management Results from Pilot Evaluations | Department  

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

Summary of Emergency Management Results from Pilot Evaluations Summary of Emergency Management Results from Pilot Evaluations Summary of Emergency Management Results from Pilot Evaluations September 19th, 2012 Presenter: David Freshwater, Emergency Management Specialist, Office of Emergency Management, National Nuclear Security Administration Topics covered: Confirm that Critical Safety Function scenarios were addressed in HS/EPHA Determine whether site/facility had robust capabilities that allow flexible and effective emergency response to severe events Engage site/facility personnel regarding preferences for requirements/guidance changes where alternate courses of action existed Summary of Emergency Management Results from Pilot Evaluations More Documents & Publications Emergency Management Concepts, Existing Guidance, and Changes

410

Building Technologies Program Planning Summary  

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

Building Technologies Program Planning Summary Building Technologies Program Planning Summary Introduction The U.S. Department of Energy's (DOE) Building Technologies Program (BTP) works in partnership with industry, state, municipal, and other federal organizations to achieve the goals of marketable net-zero energy buildings. Such buildings are extremely energy efficient, ideally producing as much energy as they use over the course of a year. BTP also works with stakeholders and federal partners to meet any remaining energy needs for their buildings through on-site renewable energy systems. Drivers Population growth and economic expansion, along with an accompanying increase in energy demand, are expected to drive energy consumption in buildings to more than 50 quadrillion Btu (quads)

411

Microsoft Word - Summary.doc  

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

Summary Summary To submit questions regarding this CMRR-NF SEIS, or to request a copy, please contact: AVAILABILITY OF THE FINAL SUPPLEMENTAL ENVIRONMENTAL IMPACT STATEMENT FOR THE NUCLEAR FACILITY PORTION OF THE CHEMISTRY AND METALLURGY RESEARCH BUILDING REPLACEMENT PROJECT AT LOS ALAMOS NATIONAL LABORATORY, LOS ALAMOS, NEW MEXICO (CMRR-NF SEIS) Printed with soy ink on recycled paper John Tegtmeier, EIS Document Manager Los Alamos Site Office National Nuclear Security Administration U.S. Department of Energy 3747 West Jemez Road Los Alamos, NM 87544 Telephone: 505-665-0113 Conceptual Drawing CMRR Facility Past Present Future Past Final Supplemental Environmental Impact Statement for the Nuclear Facility Portion of the Chemistry and Metallurgy Research Building Replacement Project

412

Nuclear Reactors  

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

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

413

Princeton Site Ofice  

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

Princeton Site Ofice Princeton Site Ofice P.O. Box 102 Princeton, New Jersey 08542-0102 TO: Gregory H. Woods, General Counsel JA N Z Q= LMN N= SUBJECT: PRINCETON SITE OFFICE (PSO) 2013 ANNUAL NATIONAL ENVIRONMENTAL POLICY ACT (NEPA) PLANNING SUMMARY Section 5(a)(7) of DOE Order 451.1B Change 3, NEPA Compliance Program, requires each Secretarial Oficer and Head of Field Organization to submit an Annual NEPA Planning Summary to the General Coun. s el. We have reviewed

414

MONTICELLO NPL SITES  

Office of Legacy Management (LM)

MONTICELLO NPL SITES MONTICELLO NPL SITES FFA QUARTERLY REPORT: October 1 - December 31, 2007 DOE Site Manager: Jalena Maestas 1.0 MMTS Activities/Status Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no problems that have not been addressed. (inspection checklists attached). * Monthly inspection of Pond 4 identified no unacceptable conditions. * Pond 4 leachate detection and removal systems continue to operate at normal levels (leachate pumping summary attached). * Repository leachate collection and removal system (LCRS) and leachate collection system (LDS) continue to operate at normal and acceptable levels (leachate pumping summary attached). * Portions of repository cover were planted with rabbitbrush seedlings to repair areas

415

40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959  

SciTech Connect

The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading of the reactor were improved by important advances in methods of fabrication and testing of both fuel compacts and graphite sleeves. The hot-pressing process for making fuel compacts was used successfully to make full-size compacts with a uniform distribution of ThC/sub 2/- UC/sub 2/ particles. Three irradiation capsules were fabricated and inserted in a test reactor to determine fuel compact and sleeve performance under HTGR conditions of irradiation and temperature. Two of these ran satisfactorily for the scheduled time of operation. A scope design study of the in-pile loop that will be used to evaluate the full-diameter graphite-clad element was completed. Experiments to determine the extent of fuel migration within the element were undertaken. Preliminary results indicated that the central fuel-element temperatures must not exceed 2300-C for routine operation. An important start was made in developing an understanding of how to treat the neutron thermalization process in high-temperature graphite reactors. Analytical techniques for calculating the thermal neutron spectra in poisoned graphite media were developed and programmed for the IBM 704 computer. The experimental technique of measuring neutron spectra by using a pulsed linear electron accelerator was demonstrated by measurements made with boron-loaded graphite. A mockup of a small portion of the reactor core was constructed and operated to determine the local heat-transfer coefficients and pressure drop in the tricusp- shaped coolant passage. Initial results indicated that the variation of the heat-transfer coefficient around the circumference of the element is less than expected. Studies were started of the transient temperatures and stresses developed in the pressure vessel as a result of load changes or a scram. A detailed study of several types of steam generator for use in the nuclear steam supply system was completed. A design incorporating a steam drum was selected for further study. Preliminary flow diagrams were completed for the helium- purification and fission-product trapping systems. Adsorption isobars for selected fission products in activated carbon were measured and will be used in the detailed design of the trapping system. Detailed planning of the experimental reactor physics program was initiated. Progress was made in the identification of the principal safeguards problems for this type of reactor, and a preliminary safety analysis of the plant was completed. (auth)

1960-09-01T23:59:59.000Z

416

Geologic Investigation of a Potential Site for a Next-Generation Reactor Neutrino Oscillation Experiment -- Diablo Canyon, San Luis Obispo County, CA  

E-Print Network (OSTI)

reactions of a nuclear power plant. Diablo Canyon wasmeters from the nuclear power plant) while having suitableThe Diablo Canyon Nuclear Power Plant site in San Luis

Onishi, Celia Tiemi; Dobson, Patrick; Nakagawa, Seiji; Glaser, Steven; Galic, Dom

2004-01-01T23:59:59.000Z

417

Workshop Summary & Conclusions  

Link project needs with research, development and ... Office of Environmental Management. Title: Microsoft PowerPoint - 5-Kosson Summary SRNL Dec ...

418

Summary of talks. [Abstracts  

DOE Green Energy (OSTI)

Twenty-two summaries of the talks given at the LASL 1978 Hot Dry Rock Geothermal Information Conference are presented. (MHR)

Not Available

1979-01-01T23:59:59.000Z

419

TE HNOLOGY SUMMARY  

nano oral™ high surfa e area platinum atalysts to improve fuel ell effi ien y te hnology summary te hnology readiness level: 4 key elements have een demonstrated ...

420

Plan Descriptions & Summaries  

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

Plan Descriptions & Summaries Retiree Insurance Plans Retiree health and welfare benefits are managed by AonHewitt and Associates. Contact Retiree Insurance Providers Plan...

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

Historical Photographs: Nevada Test Site  

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

Nevada Test Site Small Image 1. A nuclear reactor sitting on a test cell pad prior to preliminary tests at the Nevada Test Site (circa 1968). This Phoebus 2 design was part of...

422

AFIP-6 Characterization Summary Report  

Science Conference Proceedings (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

423

Disposal Practices at the Nevada Test Site 2008 | Department...  

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

Disposal Practices at the Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download Disposal Practices at...

424

EA-1111: K Pool Fish Rearing, Hanford Site, Richland, Washington...  

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

1: K Pool Fish Rearing, Hanford Site, Richland, Washington EA-1111: K Pool Fish Rearing, Hanford Site, Richland, Washington SUMMARY This EA evaluates the environmental impacts of...

425

EA-1097: Solid waste Disposal - Nevada Test Site, Nye County...  

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

7: Solid waste Disposal - Nevada Test Site, Nye County, Nevada EA-1097: Solid waste Disposal - Nevada Test Site, Nye County, Nevada SUMMARY This EA evaluates the environmental...

426

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

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

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

427

Idaho Site | Department of Energy  

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

Idaho Site Idaho Site Idaho Site Idaho National Laboratory Advance Training Reactor | September 2009 Aerial View Idaho National Laboratory Advance Training Reactor | September 2009 Aerial View Idaho National Laboratory Idaho National Laboratory's (INL) mission is to ensure the nation's energy security with safe, competitive, and sustainable energy systems and unique national and homeland security capabilities. To support these activities, INL operates numerous laboratories, reactors, test facilities, waste storage facilities, and support facilities. Idaho Closure Project The Idaho Closure Project (ICP) is a multi-year cleanup effort involving decommissioning and dismantlement of over 200 excess environmental management facilities. The scope includes D&D of three reactors, management

428

Design guide for category V reactors transient reactors  

SciTech Connect

The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requirements of Category V reactor structures, components, and systems.

Brynda, W J; Karol, R C; Lobner, P R; Powell, R W; Straker, E A

1979-03-01T23:59:59.000Z

429

Development of flaw evaluation and acceptance procedures for flaw indications in the cooling water system at the Savannah River Site K Reactor  

SciTech Connect

This paper describes the methodology used in determining the criteria for acceptance of inspection indications in the K-Reactor Cooling Water System at the Savannah River Plant. These criteria have been developed in a manner consistent with the development of similar criteria in the ASME Code Section 11 for commercial light water reactors, but with a realistic treatment of the operating conditions in the cooling water system. The technical basis for the development of these criteria called {open_quotes}Acceptance Standards{close_quotes} is contained in this paper. A second portion of this paper contains the methodology used in the construction of flaw evaluation charts which have been developed for each specific line size in the cooling water system. The charts provide the results of detailed fracture mechanics calculations which have been completed to determine the largest flaw which can be accepted in the cooling water system without repair. These charts are designed for use in conjunction with inservice inspections of the cooling water system, and only require inspection results to determine acceptability.

Tandon, S.; Bamford, W.H. [Westinghouse Electric Corp., Pittsburgh, PA (US); Cowfer, C.D.; Ostrowski, R. [Westinghouse Savannah River Co., Aiken, SC (US)

1993-06-01T23:59:59.000Z

430

Development of flaw evaluation and acceptance procedures for flaw indications in the cooling water system at the Savannah River Site K Reactor  

SciTech Connect

This paper describes the methodology used in determining the criteria for acceptance of inspection indications in the K-Reactor Cooling Water System at the Savannah River Plant. These criteria have been developed in a manner consistent with the development of similar criteria in the ASME Code Section 11 for commercial light water reactors, but with a realistic treatment of the operating conditions in the cooling water system. The technical basis for the development of these criteria called [open quotes]Acceptance Standards[close quotes] is contained in this paper. A second portion of this paper contains the methodology used in the construction of flaw evaluation charts which have been developed for each specific line size in the cooling water system. The charts provide the results of detailed fracture mechanics calculations which have been completed to determine the largest flaw which can be accepted in the cooling water system without repair. These charts are designed for use in conjunction with inservice inspections of the cooling water system, and only require inspection results to determine acceptability.

Tandon, S.; Bamford, W.H. (Westinghouse Electric Corp., Pittsburgh, PA (United States)); Cowfer, C.D.; Ostrowski, R. (Westinghouse Savannah River Co., Aiken, SC (United States))

1993-01-01T23:59:59.000Z

431

South Valley Compliance Agreement Summary  

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

South Valley South Valley Agreement Name South Valley Superfund Site Interagency Agreement State New Mexico Agreement Type Compliance Agreement Legal Driver(s) CERCLA Scope Summary Interagency Agreement with the U.S. Air Force for payment of costs associated with the remediation of two operable units (the facility and San Jose 6) at the South Valley Superfund Site. Parties DOE; U.S. Air Force Date 9/26/1990 SCOPE * Set forth the actions required of the USAF and DOE to fulfill their respective responsibilities pursuant to the Settlement Agreement between DOE, USAF, and General Electric Company (8/29/1990). * Establish mechanism by which DOE will transfer, to a fund managed by the USAF, its share of the costs set forth in the Settlement Agreement. * Set forth each party's responsibilities and respective share of costs.

432

Carlsbad Area Office Executive Summary  

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

June 1998 June 1998 Carlsbad Area Office Executive Summary The mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant (WIPP) for safe disposal of transuranic (TRU) waste and by establishing an effective system for management of TRU waste from generation to disposal. It includes personnel assigned to CAO, WIPP site operations, transportation, and other activities associated with the National TRU Program (NTP). The CAO develops and directs implementation of the TRU waste program, and assesses compliance with the program guidance, as well as the commonality of activities and assumptions among all TRU waste sites. A cornerstone of the Department of Energy's (DOE) national cleanup strategy, WIPP is

433

Accident Tolerant Fuels for Light Water Reactors  

Science Conference Proceedings (OSTI)

Presentation Title, Accident Tolerant Fuels for Light Water Reactors. Author(s), Steven J. Zinkle, Kurt A. Terrani, Lance L. Snead. On-Site Speaker (Planned) ...

434

Site Environmental Report, 1993  

SciTech Connect

The Site Environmental Report (SER) is prepared annually in accordance with DOE Order 5400.1, ``General Environmental Protection Program.`` This 1993 SER provides the general public as well as scientists and engineers with the results from the site`s ongoing Environmental Monitoring Program. Also included in this report is information concerning the site`s progress toward achieving full compliance with requirements set forth by DOE, US Environmental Protection Agency (USEPA), and Ohio EPA (OEPA). For some readers, the highlights provided in the Executive Summary may provide sufficient information. Many readers, however, may wish to read more detailed descriptions of the information than those which are presented here.

Not Available

1994-06-01T23:59:59.000Z

435

Saltcreek Project Summary  

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

Project Summary Project Summary HELP Index Summary Scenario References Student Pages Subject/Content Area: Environmental Science Target Audience: Middle school level - all students, including gifted, learning-disabled, behavior-disordered and limited English proficient Project Goals: As a result of their participation in the Salt Creek Investigation, the students will develop the abilities necessary to do scientific inquiry. They will increase their understanding of factors affecting environmental quality, including the interdependence of organisms, and human-induced hazards. Students will learn how science and technology can help people solve local, national and global environmental problems. Learner Outcomes: Students will: be able to carry out six types of stream monitoring tests.

436

Nuclear Safety Workshop Summary  

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

Workshop Summary Workshop Summary September 19-20, 2012 1 Nuclear Safety Workshop Summary On September 19-20, 2012, the U.S. Department of Energy (DOE) held a second Nuclear Safety Workshop covering the results of the Department's actions to improve its posture for analyzing and responding to severe accidents in light of lessons learned from the March 2011 nuclear accident in Japan. Sponsored by DOE and championed by Deputy Secretary of Energy Daniel Poneman, the two-day workshop discussed the lessons learned in a national and international context. The workshop's theme

437

Biofuels: Project summaries  

DOE Green Energy (OSTI)

The US DOE, through the Biofuels Systems Division (BSD) is addressing the issues surrounding US vulnerability to petroleum supply. The BSD goal is to develop technologies that are competitive with fossil fuels, in both cost and environmental performance, by the end of the decade. This document contains summaries of ongoing research sponsored by the DOE BSD. A summary sheet is presented for each project funded or in existence during FY 1993. Each summary sheet contains and account of project funding, objectives, accomplishments and current status, and significant publications.

Not Available

1994-07-01T23:59:59.000Z

438

SUMMARY OF REVISED TORNADO, HURRICANE AND EXTREME STRAIGHT WIND...  

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

@ E A R T H L I N K . N E T SUMMARY OF REVISED TORNADO, HURRICANE AND EXTREME STRAIGHT WIND CHARACTERISTICS AT NUCLEAR FACILITY SITES Categorization of Natural Hazard Phenomenon...

439

Savannah River Site | Department of Energy  

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

Savannah River Site Savannah River Site Savannah River Site Work is under way to decommission the Heavy Water Components Test Reactor, which had been used to test experimental fuel assemblies for commercial heavy-water power reactors. SRS is scheduled to remove the dome of the reactor this month (January 2011). Workers also will displace the reactor vessel and steam generators, grout the remaining structure in place, and install a concrete cover over the reactor's footprint Work is under way to decommission the Heavy Water Components Test Reactor, which had been used to test experimental fuel assemblies for commercial heavy-water power reactors. SRS is scheduled to remove the dome of the reactor this month (January 2011). Workers also will displace the reactor vessel and steam generators, grout the remaining structure in place, and

440

NPP References and Summaries  

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

Full references and selected summaries (in alphabetical order of first author name by data set): Chinese Forests NPP Data Set References Gao, Q. and X.S. Zhang (1997) A simulation...

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

Sorption Storage Technology Summary  

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

Storage Technology Summary DOE H2 Storage Workshop, Feb 14-15, 2011, Washington, DC 1 Compressed & Cryo-Compressed Hydrogen Storage Workshop February 14 - 15, 2011, Washington, DC...

442

Summary.qxd  

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

DOEEIS-0287 Idaho HLW & FD EIS 2.0 Activities since the Issuance of the Draft EIS 2.1 Summary of Public Comments and Agency Responses The Draft EIS was mailed to the public and...

443

NUCLEAR REACTOR  

DOE Patents (OSTI)

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

Treshow, M.

1961-09-01T23:59:59.000Z

444

NEUTRONIC REACTOR  

DOE Patents (OSTI)

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

Daniels, F.

1959-10-27T23:59:59.000Z

445

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

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

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

446

Safety Training Collaborative Workshop Summary Reports | Department of  

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

Safety Training Collaborative Workshop Summary Reports Safety Training Collaborative Workshop Summary Reports Safety Training Collaborative Workshop Summary Reports Performed in Collaboration with DOE National Training Center/National Institute of Environmental Health Sciences The report provides results and recommendations developed by workshop attendees on possible enhancements to the safety training programs across the Los Alamos National Laboratory (LANL) complex, Idaho National Laboratory (INL) complex, Savannah River Site (SRS) complex and Oak Ridge reservation. Documents Available for Download Idaho Worker Safety Training Workshop Report [January 2011] Los Alamos Worker Safety Training Workshop Report [December 2010] Oak Ridge Worker Safety Training Workshop Report [August 2009] Savannah River Site Worker Safety Training Workshop Report [May 2010]

447

1993 Solid Waste Reference Forecast Summary  

SciTech Connect

This report, which updates WHC-EP-0567, 1992 Solid Waste Reference Forecast Summary, (WHC 1992) forecasts the volumes of solid wastes to be generated or received at the US Department of Energy Hanford Site during the 30-year period from FY 1993 through FY 2022. The data used in this document were collected from Westinghouse Hanford Company forecasts as well as from surveys of waste generators at other US Department of Energy sites who are now shipping or plan to ship solid wastes to the Hanford Site for disposal. These wastes include low-level and low-level mixed waste, transuranic and transuranic mixed waste, and nonradioactive hazardous waste.

Valero, O.J.; Blackburn, C.L. [Westinghouse Hanford Co., Richland, WA (United States); Kaae, P.S.; Armacost, L.L.; Garrett, S.M.K. [Pacific Northwest Lab., Richland, WA (United States)

1993-08-01T23:59:59.000Z

448

CONVECTION REACTOR  

DOE Patents (OSTI)

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

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

1960-03-22T23:59:59.000Z

449

Document Number Q0029500 Summary and Conclusions  

Office of Legacy Management (LM)

Summary and Conclusions Summary and Conclusions 6.0 Summary and Conclusions In 1990, a RIBS and ROD were completed for MMTS OUs I and 11. A RI was completed for OU I11 in 1998 and subsequent interim action performed. This report presents the results of the interim remedial action and completes' the remedial investigatiodfeasibility study process. Info~mation presented in this RI A d d e n d u d F S for OU 111 of MMTS is summarized in the following sections. 6.1 Physical Site Characteristics The hydrostratigraphic units associated with OU 1 1 1 are the alluvial aquifer, which is underlain by the Dakota Sandstone aquitard and the Burro Canyon sandstone aquifer. The alluvial aquifer continues to be contaminated because of past Millsite activities. The primary sources of contamination (the tailings piles) have been removed. Alluvial aquifer

450

Compilation of ETR Summaries  

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

Simulation Capability for Environmental Management (ASCEM) at all sites September 2011 DOE Site: Hanford, WA EM Project: Waste Treatment Plant ETR Report Date: March 2006 ETR-1...

451

Partnership Overview and Summary  

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

Site 9000' 9300' Comparison of Primary & Alternative Site 9000' 9300' 11800' 11000' source sink Gordon Creek: upper right and lower left Rock Springs: upper left and lower...

452

Nuclear Reactor Severe Accident Experiments  

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

Nuclear Reactor Severe Accident Experiments Nuclear Reactor Severe Accident Experiments Capabilities Engineering Experimentation Reactor Safety Testing and Analysis Overview Nuclear Reactor Severe Accident Experiments MAX NSTF SNAKE Aerosol Experiments System Components Laser Applications Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Nuclear Reactor Severe Accident Experiments 1 2 3 4 5 6 7 We perform experiments simulating reactor core melt phenomena in which molten core debris ("corium") erodes the concrete floor of a containment building. This occurred during the Fukushima nuclear power plant accident though the extent of concrete damage is yet unknown. This video shows the top view of a churning molten pool of uranium oxide at 2000°C (3600°F) seen during an experiment at Argonne. Corium behaves much like lava.

453

2011 APS NNSA Kansas City Site Office.pdf  

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

Annual NEPA Planning Summary . . . - . . . Annual NEPA Planning Summary . . . - . . . . . - - . - - - . . - . . . . . - ..... .- .... Environmental Impact Statements Ongoing or Expected to be Prepared in the Next 24 Months - -- - . - . -~ -- - ... - . . - . . .--. - . - ..... - - - . . - . - . - - - . -. . . - . ~p~ - . . . - . .. -- . - . . - - ... - - ... - KANSAS CITY SITE OFFICE - - - -~~ ?/I 4/20 1 1 . . . - - . . . .. -... r ' - - --- --

454

Summary-Final.PDF  

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

SUMMARY SUMMARY June 2000 1 SUMMARY This document constitutes the first edition of a long-term research and development (R&D) plan for nuclear technology in the United States. Introduction In 1998, DOE established the Nuclear Energy Research Advisory Committee (NERAC) to provide advice to the Secretary and to the Director, Office of Nuclear Energy, Science, and Technology (NE), on the broad range of non-defense DOE nuclear technology programs. The NERAC recommended development of a long-range R&D program. This R&D plan is a result of that recommendation and is the first of what is expected to be an iterated series of long-range plans for nuclear energy in the Department of Energy. To develop this plan, 145 nuclear and non-nuclear scientists, engineers, and academics

455

ESPC ENABLE: ECM Summary  

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

ESPC ENABLE: ECM Summary ESPC ENABLE: ECM Summary ECM Included Not Included Lighting * Lamps, Ballasts, Fixtures * Controls: Occupancy, Day lighting (on/off, dimming) * Solar Lighting (off-grid installations allowed) Water * Sanitary plumbing fixtures: sinks, toilets, urinals, showers * Irrigation * Leak repair * Domestic/commercial hot water heaters * Water based appliances: dishwasher, ice machine, clothes washer, etc. * Heating/Cooling system improvements (cooling towers, once through cooling, condensate reclaim) HVAC Controls Whole building control strategies including: * Time/Temperature Set-back * Demand/Night Ventilation * Advanced Controls 1 : Energy Management Control Systems (EMCS) / Building Automation Systems (BAS) HVAC Equipment Basic whole building/system one-for-one replacement

456

ESPC ENABLE: ECM Summary  

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

ESPC ENABLE: ECM Summary ESPC ENABLE: ECM Summary ECM Included Not Included Lighting * Lamps, Ballasts, Fixtures * Controls: Occupancy, Day lighting (on/off, dimming) * Solar Lighting (off-grid installations allowed) Water * Sanitary plumbing fixtures: sinks, toilets, urinals, showers * Irrigation * Leak repair * Domestic/commercial hot water heaters * Water based appliances: dishwasher, ice machine, clothes washer, etc. * Heating/Cooling system improvements (cooling towers, once through cooling, condensate reclaim) HVAC Controls Whole building control strategies including: * Time/Temperature Set-back * Demand/Night Ventilation * Advanced Controls 1 : Energy Management Control Systems (EMCS) / Building Automation Systems (BAS) HVAC Equipment Basic whole building/system one-for-one replacement

457

Neutron Irradiation of Hydrided Cladding Material in HFIR Summary of  

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

Neutron Irradiation of Hydrided Cladding Material in HFIR Summary Neutron Irradiation of Hydrided Cladding Material in HFIR Summary of Initial Activities Neutron Irradiation of Hydrided Cladding Material in HFIR Summary of Initial Activities Irradiation is known to have a significant impact on the properties and performance of Zircaloy cladding and structural materials (material degradation processes, e.g., effects of hydriding). This UFD study examines the behavior and performance of unirradiated cladding and actual irradiated cladding through testing and simulation. Three capsules containing hydrogen-charged Zircaloy-4 cladding material have been placed in the High Flux Isotope Reactor (HFIR). Irradiation of the capsules was conducted for post-irradiation examination (PIE) metallography. Neutron Irradiation of Hydrided Cladding Material in HFIR Summary of

458

1994 Site environmental report  

Science Conference Proceedings (OSTI)

The Fernald site is a Department of Energy (DOE)-owned facility that produced high-quality uranium metals for military defense for nearly 40 years. DOE suspended production at the site in 1989 and formally ended production in 1991. Although production activities have ceased, the site continues to examine the air and liquid pathways as possible routes through which pollutants from past operations and current remedial activities may leave the site. The Site Environmental Report (SER) is prepared annually in accordance with DOE Order 5400.1, General Environmental Protection Program. This 1994 SER provides the general public as well as scientists and engineers with the results from the site`s ongoing Environmental Monitoring Program. Also included in this report is information concerning the site`s progress toward achieving full compliance with requirements set forth by DOE, U.S. Environmental Protection Agency (USEPA), and Ohio EPA (OEPA). For some readers, the highlights provided in this Executive Summary may provide sufficient information. Many readers, however, may wish to read more detailed descriptions of the information than those which are presented here. All information presented in this summary is discussed more fully in the main body of this report.

NONE

1995-07-01T23:59:59.000Z

459

NEUTRONIC REACTOR  

DOE Patents (OSTI)

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

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

1961-11-21T23:59:59.000Z

460

Final safeguards analysis, High Temperature Lattice Test Reactor  

SciTech Connect

Information on the HTLTR Reactor is presented concerning: reactor site; reactor buildings; reactor kinetics and design characteristics; experimental and test facilitles; instrumentation and control; maintenance and modification; initial tests and operations; administration and procedural safeguards; accident analysis; seifterminated excursions; main heat exchanger leak; training program outline; and reliability analysis of safety systems. (7 references) (DCC)

Hanthorn, H.E.; Brown, W.W.; Clark, R.G.; Heineman, R.E.; Humes, R.M.

1966-01-01T23:59:59.000Z

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.


461

Disposal Practices at the Nevada Test Site 2008 | Department...  

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

Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download Disposal Practices at the Nevada Test Site 2008...

462

REACTOR COOLING  

DOE Patents (OSTI)

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

Quackenbush, C.F.

1959-09-29T23:59:59.000Z

463

Geothermal energy. Program summary  

DOE Green Energy (OSTI)

Brief descriptions of geothermal projects funded through the Department of Energy during FY 1978 are presented. Each summary gives the project title, contractor name, contract number, funding level, dates, location, and name of the principal investigator, together with project highlights, which provide informaion such as objectives, strategies, and a brief project description. (MHR)

Not Available

1979-06-01T23:59:59.000Z