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Note: This page contains sample records for the topic "railroad vessel bunkering" from the National Library of EnergyBeta (NLEBeta).
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1

The bunkering industry and its effect on shipping tanker operations  

E-Print Network (OSTI)

The bunkering industry provides the shipping industry with the fuel oil that the vessels consume. The quality of the fuel oil provided will ensure the safe operation of vessels. Shipping companies under their fuel oil ...

Boutsikas, Angelos

2004-01-01T23:59:59.000Z

2

Sold directly to consumers for:  

Annual Energy Outlook 2012 (EIA)

Office Buildings Railroad Companies SchoolsUniversities Trucking Companies Vehicle Refrigeration Units Vessel BunkeringFueling Warehouses Industrial Construction Companies...

3

Bunker Hill Sediment Characterization Study  

SciTech Connect

The long history of mineral extraction in the Coeur dAlene Basin has left a legacy of heavy metal laden mine tailings that have accumulated along the Coeur dAlene River and its tributaries (U.S. Environmental Protection Agency, 2001; Barton, 2002). Silver, lead and zinc were the primary metals of economic interest in the area, but the ores contained other elements that have become environmental hazards including zinc, cadmium, lead, arsenic, nickel, and copper. The metals have contaminated the water and sediments of Lake Coeur dAlene, and continue to be transported downstream to Spokane Washington via the Spokane River. In 1983, the EPA listed the Bunker Hill Mining and Metallurgical Complex on the National Priorities List. Since that time, many of the most contaminated areas have been stabilized or isolated, however metal contaminants continue to migrate through the basin. Designation as a Superfund site causes significant problems for the economically depressed communities in the area. Identification of primary sources of contamination can help set priorities for cleanup and cleanup options, which can include source removal, water treatment or no action depending on knowledge about the mobility of contaminants relative to water flow. The mobility of contaminant mobility under natural or engineered conditions depends on multiple factors including the physical and chemical state (or speciation) of metals and the range of processes, some of which can be seasonal, that cause mobilization of metals. As a result, it is particularly important to understand metal speciation (National Research Council, 2005) and the link between speciation and the rates of metal migration and the impact of natural or engineered variations in flow, biological activity or water chemistry.

Neal A. Yancey; Debby F. Bruhn

2009-12-01T23:59:59.000Z

4

Bunker Hill, Indiana: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

with form History Share this page on Facebook icon Twitter icon Bunker Hill, Indiana: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates...

5

Distillate Fuel Oil Sales for Vessel Bunkering Use  

Gasoline and Diesel Fuel Update (EIA)

1,923,981 1,983,422 1,912,984 2,002,834 2,133,395 1,768,324 1,923,981 1,983,422 1,912,984 2,002,834 2,133,395 1,768,324 1984-2012 East Coast (PADD 1) 466,132 461,533 276,013 259,319 296,947 283,254 1984-2012 New England (PADD 1A) 43,014 69,102 45,147 30,589 32,414 38,891 1984-2012 Connecticut 6,654 5,683 3,914 1,898 1,502 2,838 1984-2012 Maine 8,298 6,815 15,611 4,207 4,128 13,349 1984-2012 Massachusetts 21,336 48,094 19,193 17,529 17,132 13,612 1984-2012 New Hampshire 2,740 2,552 2,327 1,110 1,395 1,815 1984-2012 Rhode Island 3,987 5,958 4,101 5,824 8,257 7,243 1984-2012 Vermont 0 0 0 21 0 35 1984-2012 Central Atlantic (PADD 1B) 147,629 129,789 104,487 67,726 76,446 74,154 1984-2012 Delaware 615 919 582 485 1,658 615 1984-2012 District of Columbia 11 7 5 13 15 17 1984-2012

6

Plenary II -- Evaluation of Shortline Railroads  

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

Evaluation of Shortline Railroads Task: Task: Identify Shortline Railroads Serving Nuclear Power Plants or Identify Shortline Railroads Serving Nuclear Power Plants or...

7

Total Adjusted Sales of Distillate Fuel Oil  

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

End Use: Total Residential Commercial Industrial Oil Company Farm Electric Power Railroad Vessel Bunkering On-Highway Military Off-Highway All Other Period: Annual Download Series...

8

Total Sales of Distillate Fuel Oil  

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

End Use: Total Residential Commercial Industrial Oil Company Farm Electric Power Railroad Vessel Bunkering On-Highway Military Off-Highway All Other Period: Annual Download Series...

9

Plenary II -- Evaluation of Shortline Railroads  

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

DOT DOT U.S. DOT Federal Railroad Federal Railroad Administration Administration DOE Rail TEC DOE Rail TEC Winter Winter Meeting Meeting February February 6, 6, 2008, San Antonio, TX 2008, San Antonio, TX Evaluation of Shortline Railroads Evaluation of Shortline Railroads Tasked for the Transportation of Spent Nuclear Fuel Tasked for the Transportation of Spent Nuclear Fuel Evaluation of Shortline Railroads Evaluation of Shortline Railroads Task: Task: Identify Shortline Railroads Serving Nuclear Power Plants or Identify Shortline Railroads Serving Nuclear Power Plants or Involved in the Transportation Link Involved in the Transportation Link Establish Contact Information with Railroads Officials Establish Contact Information with Railroads Officials Field Review of each Railroad

10

Federal Railroad Administration  

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

Legislation Legislation Kevin R. Blackwell FRA Hazmat Division Washington, DC Federal Railroad Safety Accountability and Improvement Act of 2007 (FRSAIA)-H.R. 1516 /S. 918 DOT supports this reauthorization bill over H.R. 2095 The provisions of H.R. 2095, while not exactly the same, are very similar to this bill in regard to the core provisions Core provisions: Review and reform the Federal hours of service requirements Establish a new risk reduction program alongside the current existing safety program, and Mandate reporting by States and railroads to the DOT's National Crossing Inventory Federal Railroad Safety Improvement Act of 2007 (FRSIA) - H.R. 2095 Letter from DOT's General Counsel's office addressing DOT's

11

Federal Railroad Administration  

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

DOE TRANSPORTATION EXTERNAL WORKING GROUP MEETING Pueblo, CO. September 20, 2005 Presented by Kevin R. Blackwell Radioactive Materials/Hazardous Materials Specialist Federal Railroad Administration - HQ Hazmat Division, Washington, DC. Federal Railroad Administration Dedicated Train Study - Report to Congress November 2003 - FRA' s Ofc. Of Research & Development (RDV), as lead on the Dedicated Train Study (DTS), received draft final report from the Volpe National Transportation Systems Center (VNTSC), the contractor conducting the study. February, 2004 - FRA completed review of DFR and submitted editorial corrections back to VNTSC. Final draft of the DTS with editorial corrections received from VNTSC in February, 2004. March to September 2004 -

12

Federal Railroad Administration  

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

Transportation Transportation Federal Railroad Administration Overview of Proposed Rail Safety & Security Rulemakings Kevin R. Blackwell FRA Hazmat Division Washington, DC Federal Authority DOT Authority to regulate safety and security of hazardous materials transportation Hazardous Materials Transportation Law (49 U.S.C. 5101 et.seq.) Federal Railroad Safety Act (49 U.S.C. 20101 et.seq.) TSA Authority to regulate security of hazardous material transportation Aviation Transportation Security Act (Pub. L. 107-71, 115 Stat. 597) Routing as a Part of the Transportation Cycle Routing decisions are continually made as a part of the transportation cycle for a variety of reasons. E c o n o m i c s Security S a f e t y Routing Decision Pyramid DOT NPRM HM-232E NPRM published on December 21, 2006.

13

Federal Railroad Administration  

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

Update Du Update Du Jour Department Of Energy Transportation External Coordination Working Group Meeting Albuquerque, New Mexico April 21-23, 2004 Presented by Kevin R. Blackwell Radioactive Materials Program Manager Federal Railroad Administration Federal Railroad Administration Dedicated Train Study- Report to Congress FRA' s Research & Development Office (as lead on the study) received a draft final report from the Volpe National Transportation Systems Center (VNTSC) in late November, 2003. Editorial corrections were made and a final draft dated February, 2004 was provided to FRA. Final Draft Report FRA has been reviewed and been sent to FRA Administrator for clearance and forwarding to DOT OST. FRA has already "Officially Coordinated" and briefed DOT OST and

14

U.S. DOT Federal Railroad Administration  

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

DOT DOT Federal Railroad Administration U.S. Department of Energy Transportation External Coordination Working Group (TEC) July 24-25, 2007 Kansas City, Missouri Evaluation of Shortline Railroads Tasked for the Transportation of Spent Nuclear Fuel Evaluation of Shortline Railroads  Task:  Identify Shortline Railroads Serving Nuclear Power Plants or Involved in the Transportation Link  Establish Contact Information with Railroads Officials  Field Review of each Railroad's Physical and Operational Infrastructure  Qualify each Railroads Present Operational Status Against a Safe Acceptable Standard  Facilitate Upgrades to Meet Safe Acceptable Standards Evaluation of Shortline Railroads

15

Railroad fuel-oil consumption in 1928  

SciTech Connect

Data are presented, by districts, covering the consumption of fuel oil for various uses by railroads.

Redfield, A.H.

1930-01-01T23:59:59.000Z

16

Bunker Hill Village, Texas: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

Bunker Hill Village, Texas: Energy Resources Bunker Hill Village, Texas: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 29.7674508°, -95.5299427° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":29.7674508,"lon":-95.5299427,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

17

Federal Railroad Administration  

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

Safety & Security Safety & Security Rulemakings Kevin R. Blackwell FRA Hazmat Division Washington, DC Federal Authority DOT Authority to regulate safety and security of hazardous materials transportation Hazardous Materials Transportation Law (49 U.S.C. 5101 et.seq.) Federal Railroad Safety Act (49 U.S.C. 20101 et.seq.) TSA Authority to regulate security of hazardous material transportation Aviation Transportation Security Act (Pub. L. 107-71, 115 Stat. 597) Routing as a Part of the Transportation Cycle Routing decisions are continually made as a part of the transportation cycle for a variety of reasons. Security Routing Decision Pyramid DOT NPRM HM-232E NPRM published on December 21, 2006. Seeks to clarify and enhance existing regulations. Rail Carriers who transport carloads of more than 5000 lbs of 1.1, 1.2, or 1.3

18

Evaluating flexibility in railroad construction projects  

E-Print Network (OSTI)

This thesis aims to valuate flexibilities in a large-scale railroad construction project. In general, a railroad construction project involves a large amount of flexibilities due to its long construction period and conflicts ...

Oh, Choong Ryun, 1972-

2005-01-01T23:59:59.000Z

19

U.S. Railroad Safety Statistics and Trends  

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

Railroad Safety Statistics and Trends Railroad Safety Statistics and Trends Robert E. Fronczak, P.E. Assistant VP- Environment & Hazmat Association of American Railroads Transportation External Coordination Working Group Meeting September 21, 2005 Railroad Safety: Topics Safety Statistics & Trends Train Safety (Train Accidents) Employee Safety Hazardous Materials Safety U.S. Railroad Safety Statistics: Main Themes Railroads have dramatically improved safety over the last two and a half decades. Railroads compare favorably with other industries & transportation modes. The most troubling railroad safety problems arise from factors largely outside railroad control. Railroads have implemented numerous and effective technological improvements and company-wide safety programs.

20

Railroad and locomotive technology roadmap.  

Science Conference Proceedings (OSTI)

Railroads are important to the U.S. economy. They transport freight efficiently, requiring less energy and emitting fewer pollutants than other modes of surface transportation. While the railroad industry has steadily improved its fuel efficiency--by 16% over the last decade--more can, and needs to, be done. The ability of locomotive manufacturers to conduct research into fuel efficiency and emissions reduction is limited by the small number of locomotives manufactured annually. Each year for the last five years, the two North American locomotive manufacturers--General Electric Transportation Systems and the Electro-Motive Division of General Motors--have together sold about 800 locomotives in the United States. With such a small number of units over which research costs can be spread, outside help is needed to investigate all possible ways to reduce fuel usage and emissions. Because fuel costs represent a significant portion of the total operating costs of a railroad, fuel efficiency has always been an important factor in the design of locomotives and in the operations of a railroad. However, fuel efficiency has recently become even more critical with the introduction of strict emission standards by the U.S. Environmental Protection Agency, to be implemented in stages (Tiers 0, 1, and 2) between 2000 and 2005. Some of the technologies that could be employed to meet the emission standards may negatively affect fuel economy--by as much as 10-15% when emissions are reduced to Tier 1 levels. Lowering fuel economy by that magnitude would have a serious impact on the cost to the consumer of goods shipped by rail, on the competitiveness of the railroad industry, and on this country's dependence on foreign oil. Clearly, a joint government/industry R&D program is needed to help catalyze the development of advanced technologies that will substantially reduce locomotive engine emissions while also improving train system energy efficiency. DOE convened an industry-government workshop in January 2001 to gauge industry interest. As a result, the railroads, their suppliers, and the federal government5 have embarked on a cooperative effort to further improve railroad fuel efficiency--by 25% between now and 2010 and by 50% by 2020, on an equivalent gallon per revenue ton-mile basis, while meeting emission standards, all in a cost-effective, safe manner. This effort aims to bring the collaborative approaches of other joint industry-government efforts, such as FreedomCAR and the 21st Century Truck partnership, to the problem of increasing rail fuel efficiency. Under these other programs, DOE's Office of FreedomCAR and Vehicle Technologies has supported research on technologies to reduce fuel use and air emissions by light- and heavy-duty vehicles. DOE plans to bring similar efforts to bear on improving locomotives. The Department of Transportation's Federal Railroad Administration will also be a major participant in this new effort, primarily by supporting research on railroad safety. Like FreedomCAR and the 21st Century Truck program, a joint industry-government research effort devoted to locomotives and railroad technology could be a 'win' for the public and a 'win' for industry. Industry's expertise and in-kind contributions, coupled with federal funding and the resources of the DOE's national laboratories, could make for an efficient, effective program with measurable energy efficiency targets and realistic deployment schedules. This document provides the necessary background for developing such a program. Potential R&D pathways to greatly improve the efficiency of freight transportation by rail, while meeting future emission standards in a cost-effective, safe manner, were developed jointly by an industry-government team as a result of DOE's January 2001 Workshop on Locomotive Emissions and System Efficiency and are presented here. The status of technology, technical targets, barriers, and technical approaches for engine, locomotive, rail systems, and advanced power plants and fuels are presented.

Stodolsky, F.; Gaines, L.; Energy Systems

2003-02-24T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Andrew F. Bunker: Pioneering in Air-Sea Interaction Research 194679  

Science Conference Proceedings (OSTI)

Andrew F. Bunker was a research scientist at the Woods Hole Oceanographic Institution (WHOI) for over 30 years until his death in 1979. He was interested in the energy exchanges between the atmosphere and ocean, and devised techniques for their ...

Carl A. Friehe; Henry M. Stommel

1991-01-01T23:59:59.000Z

22

Enhancing Railroad Hazardous Materials Transportation Safety...  

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

Safety Rail Routing Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Presentation made by Kevin Blackwell for the NTSF annual meeting held from May 14-16,...

23

Connecticut Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 314,674: 301,591: 272,255: 271,852: 274,578: 274,507: 1984-2012: ...

24

Alabama Adjusted Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 979,566: 854,244: 791,004: 859,486: 917,892: 871,796: 1984-2012: ...

25

South Carolina Adjusted Distillate Fuel Oil and Kerosene Sales ...  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 751,994: 695,077: 654,296: 726,647: 725,148: 655,638: 1984-2012: ...

26

Lower Atlantic (PADD 1C) Distillate Fuel Oil and Kerosene ...  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 300,889: 274,739: 263,252: 232,429: 230,287: 254,322: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 275,489: ...

27

Maryland Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 606,247: 548,583: 540,590: 579,203: 540,843: 531,683: 1984-2012: ...

28

Nebraska Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 446,825: 433,745: 461,938: 639,618: 603,268: 584,362: 1984-2012: ...

29

California Adjusted Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 309,249: 232,151: 190,082: 225,123: 257,297: 241,967: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 101,932: ...

30

Rocky Mountain (PADD4) Distillate Fuel Oil and Kerosene Sales ...  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 262,644: 222,054: 212,571: 228,200: 245,446: 214,160: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 27: 26: 19: ...

31

Massachusetts Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 487,861: 463,886: 443,620: 445,626: 460,154: 444,532: 1984-2012: ...

32

Kentucky Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 170,042: 94,124: 48,002: 42,101: 67,347: 61,840: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 91,516: 104,387: ...

33

Arizona Adjusted Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 877,174: 799,123: 746,952: 751,025: 767,565: 761,995: 1984-2012: ...

34

Michigan Adjusted Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 970,806: 891,487: 819,086: 864,049: 854,644: 877,692: 1984-2012: ...

35

Minnesota Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 804,699: 761,187: 633,806: 665,652: 704,971: 746,974: 1984-2012: ...

36

District of Columbia Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 10,721: 15,894: 11,949: 13,216: 15,149: 15,321: 1984-2012: Residual ...

37

Gulf Coast (PADD 3) Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 699,882: 631,796: 542,036: 573,037: 694,053: 729,109: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 613,864: ...

38

Rhode Island Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 77,882: 61,856: 59,789: 65,067: 65,295: 62,041: 1984-2012: Residual ...

39

Pennsylvania Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 118,670: 113,851: 90,800: 124,258: 146,291: 140,663: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 25,735: ...

40

South Carolina Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 752,984: 699,864: 653,641: 726,889: 724,974: 656,396: 1984-2012: ...

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Minnesota Adjusted Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 817,786: 767,218: 640,572: 678,530: 713,572: 763,303: 1984-2012: ...

42

New Jersey Adjusted Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 1,088,505: 978,515: 760,035: 831,955: 952,930: 837,191: 1984-2012: ...

43

Wisconsin Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 788,665: 798,348: 703,583: 738,953: 719,417: 780,145: 1984-2012: ...

44

Connecticut Adjusted Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 314,309: 300,255: 272,598: 271,767: 274,640: 273,827: 1984-2012: ...

45

Utah Adjusted Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 512,415: 464,448: 420,807: 427,293: 507,559: 486,956: 1984-2012: ...

46

Kansas Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 581,898: 610,088: 588,362: 554,334: 548,183: 573,992: 1984-2012: ...

47

New York Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 63,226: 44,510: 35,307: 33,709: 42,254: 35,237: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 12,339: 10,814: ...

48

Michigan Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 964,966: 888,432: 814,460: 855,592: 850,681: 871,756: 1984-2012: ...

49

Delaware Adjusted Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 68,223: 61,302: 57,382: 56,676: 57,720: 57,230: 1984-2012: Residual ...

50

Florida Adjusted Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 71,962: 55,219: 35,537: 41,430: 47,283: 61,059: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 140,493: 153,438: ...

51

West Virginia Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 15,766: 15,416: 10,143: 11,650: 12,711: 10,456: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 45,429: 28,568: 99: ...

52

Georgia Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 78,927: 69,710: 62,072: 63,770: 71,374: 63,902: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 14,016: 10,831: ...

53

Illinois Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 40,116: 51,287: 55,322: 72,188: 58,526: 63,808: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 71,805: 101,851: ...

54

Ohio Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Railroad : Distillate Fuel Oil: 333,069: 316,926: 206,134: 179,048: 203,135: 175,258: 1984-2012: Vessel Bunkering : Distillate Fuel Oil: 12,122: ...

55

Nebraska Adjusted Distillate Fuel Oil and Kerosene Sales by ...  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 448,098: 435,444: 472,303: 689,579: 627,110: 613,232: 1984-2012: ...

56

New Jersey Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 1,091,896: 991,981: 755,753: 832,806: 951,803: 842,035: 1984-2012: ...

57

Utah Distillate Fuel Oil and Kerosene Sales by End Use  

U.S. Energy Information Administration (EIA)

Total Transportation (Railroad, Vessel Bunkering, On-Highway) Distillate Fuel Oil: 525,714: 470,714: 420,706: 426,584: 508,266: 486,456: 1984-2012: ...

58

Going Bunkers: The Joint Route Selection and Refueling Problem  

Science Conference Proceedings (OSTI)

Managing shipping vessel profitability is a central problem in marine transportation. We consider two commonly used types of vessels---liners (ships whose routes are fixed in advance) and trampers (ships for which future route ... Keywords: maritime transportation, refueling, routing, shipping, stochastic prices

Omar Besbes; Sergei Savin

2009-10-01T23:59:59.000Z

59

Enhancing Railroad Hazardous Materials Transportation Safety  

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

Railroad Hazardous g Railroad Hazardous g Materials Transportation Safety Kevin R. Blackwell Kevin R. Blackwell Kevin R. Blackwell Kevin R. Blackwell Radioactive Materials Program Manager Radioactive Materials Program Manager H d M t i l Di i i H d M t i l Di i i Hazmat Hazardous Materials Division Hazardous Materials Division Federal Railroad Administration Federal Railroad Administration Presentation for the Presentation for the DOE NTSF Meeting DOE NTSF Meeting May 10 May 10- -12, 2011 12, 2011 Our Regulated Community * More than 550 l d railroads * 170,000 miles of track * 220,000 employees * 1.3 million railcars * 20,000 locomotives Hazmat * 3,500 chemical shippers * Roughly 2 Million Roughly 2 Million annual HM shipments HM-232E Introduction * Notice of Proposed Rulemaking d b * Issued December 21, 2006 * Interim Final Rule

60

North American Short Line and Regional Railroads Industry Report  

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

Short Line and American Short Line and Short Line and American Short Line and Regional Railroad Association Regional Railroad Association " " The Voice of America The Voice of America ' ' s Independent Railroads s Independent Railroads " " 4/27/2005 2 ASLRRA Membership ASLRRA Membership 0 100 200 300 400 500 600 700 800 Total Number of Member Companies 1943 1953 1963 1973 1983 1993 2003 Year ASLRRA Member History (1943 - 2003) Associate Railroad

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Kaiser Engineers Railroad Tractive Effort Test, LOFT - A and M track  

SciTech Connect

This LTR contains the original results of the Railroad Locomotive Tractive Effort Test performed by Kaiser Engineers on July 29, 1965, using an existing 24-wheel 500-ton dolly and the existing shielded locomotive. The test was conducted to confirm calculations of the tractive effort required to move the LOFT dolly (MTA) through the four-rail high bay curve and the curve into the LOFT containment vessel.

White, E.R.

1978-05-09T23:59:59.000Z

62

Power System and Railroad Electromagnetic Compatibility Handbook  

Science Conference Proceedings (OSTI)

This book is a source of technology and data for preventing and mitigating ac electrical interference problems on railroads. All aspects of electromagnetic compatibility (EMC) where railroad systems are the receptors are examined. This includes well-understood areas such as magnetic induction from transmission lines as well as less understood areas such as conducted interference from distribution systems and effects of harmonics. Chapters examine all known effects of ac interference, including personnel ...

2006-11-29T23:59:59.000Z

63

Technical Research of Thermal Adjusting in Pulverizing System Intermediate Storage Bunker  

Science Conference Proceedings (OSTI)

As the temperature change effect of the primary air and powder mixture in storage-type milling system, it is difficult to obtain accurate results of the direct measurement of the primary wind speed, resulting in this type of boiler system, the thermal ... Keywords: pulverizing system intermediate storage bunker, thermal adjustment, coal concentration, heat balance

Zhenning Zhao; Yaqin Ge; Hongwei Chen; Ying Zhang; Tao Sun; Xiao Lu

2010-10-01T23:59:59.000Z

64

Remote Sensing of Railroad Locomotive Emissions: A Feasibility Study  

E-Print Network (OSTI)

Remote Sensing of Railroad Locomotive Emissions: A Feasibility Study Peter J. Popp, Gary A. Bishop, DC 20590 #12;Remote Sensing of Railroad Engine Emissions 2 INTRODUCTION Many cities in the United be #12;Remote Sensing of Railroad Engine Emissions 3 operated at a preset power output and fixed engine

Denver, University of

65

Laser Glazing of Railroad Rails [Laser Applications Laboratory] - Nuclear  

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

Laser Glazing of Railroad Laser Glazing of Railroad Rails Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Overview Laser Oil & Gas Well Drilling Laser Heat Treatment Laser Welding of Metals On-line Monitoring Laser Beam Delivery Laser Glazing of Railroad Rails High Power Laser Beam Delivery Decontamination and Decommissioning Refractory Alloy Welding 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 Laser Applications Laboratory Laser Glazing of Railroad Rails Project description: Laser glazing of rails. Category: Project with industrial partner (American Association of Railroads) Bookmark and Share

66

Upgrading railroad test track, Pueblo, Colorado  

Science Conference Proceedings (OSTI)

The railroad test track (RTT) at the Transportation Technology Center (TTC) in Pueblo, Colo., was constructed in the early 1970s to support high-speed testing of new railroad rolling stock. Through the years it has been used to test a wide range of railroad passenger and freight cars and locomotives. Now, 20 years later, a new high-speed train set is being procured by Amtrak for service in the improved Northeast Corridor. The test facilities at Pueblo will play an important role in acceptance and safety testing of new high-speed train sets in the US. The Federal Railroad Administration (FRA) commissioned a study to review the existing condition of the test track and to make recommendations as to possible improvement options so that the facility would be able to test current and future generations of high-speed rail equipment. This paper describes the condition of the test track and explores ways in which it may be modified to accommodate the testing of high-speed train technologies in the near future and into the next century.

Briggs, K. III; Chamberlain, K. [Parsons Brinckerhoff Quade and Douglas, Inc., Boston, MA (United States)

1997-01-01T23:59:59.000Z

67

ILLINOIS -RAILROAD ENGINEERING Impact of Automated Condition  

E-Print Network (OSTI)

oduc o Methods ­ Mainline Efficiency U i Di t hUsing Dispatch Simulation Software Future Work #12Acoustic Bearing Detectors ­ Wheel Impact Load Detectors ­ Hunting Truck Detectors ­ Truck Performance Detectors Administration (FRA) Office of Safety Analysis #12;8/27/2010 10 Slide 10 ILLINOIS - RAILROAD ENGINEERING Cost

Barkan, Christopher P.L.

68

Railroad Commission of Texas | Open Energy Information  

Open Energy Info (EERE)

Jump to: navigation, search Jump to: navigation, search Logo: Railroad Commission of Texas Name Railroad Commission of Texas Address 1701 N. Congress Place Austin, Texas Zip 78701 Year founded 1891 Phone number (512) 463-7158 Website http://www.rrc.state.tx.us/ Coordinates 30.2790636°, -97.7382267° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":30.2790636,"lon":-97.7382267,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

69

Microsoft Word - RailroadIsland_CX.docx  

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

2 2 REPLY TO ATTN OF: KEC-4 SUBJECT: Environmental Clearance Memorandum Dorie Welch Project Manager - KEWM-4 Proposed Action: Railroad Island Property Funding. Fish and Wildlife Project No.: 2011-003-00, Contract # BPA-006468 Categorical Exclusion Applied (from Subpart D, 10 C.F.R. Part 1021): B1.25 Real Property transfers for cultural protection, habitat preservation and wildlife management. Location: Monroe Quadrangle, in Lane County, Oregon (near Junction City, Oregon). Proposed by: Bonneville Power Administration (BPA) Description of the Proposed Action: The BPA is proposing to fund The Mackenzie River Trust (the Trust) to acquire a 63-acre parcel that will be known as Railroad Island. The Trust will provide BPA a conservation easement over the entire 63-acre property that will prevent

70

Closure Report for Corrective Action Unit 214: Bunkers and Storage Areas, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 214 is located in Areas 5, 11, and 25 of the Nevada Test Site (NTS). CAU 214 is listed in the Federal Facility Agreement and Consent Order (FFACO, 1996) as ''Corrective Action Unit 214: Bunkers and Storage Areas,'' and is comprised of nine Corrective Action Sites (CASs): {sm_bullet} CAS 05-99-01, Fallout Shelters {sm_bullet} CAS 11-22-03, Drum {sm_bullet} CAS 25-23-01, Contaminated Materials {sm_bullet} CAS 25-23-19, Radioactive Material Storage {sm_bullet} CAS 25-34-03, Motor Dr/Gr Assembly (Bunker) {sm_bullet} CAS 25-34-04, Motor Dr/Gr Assembly (Bunker) {sm_bullet} CAS 25-34-05, Motor Dr/Gr Assembly (Bunker) {sm_bullet} CAS 25-99-12, Fly Ash Storage {sm_bullet} CAS 25-99-18, Storage Area The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CASs 11-22-03, 25-34-03, 25-34-04, 25-34-05, 25-99-12, and 25-99-18 is No Further Action. Closure activities included: {sm_bullet} Removing and disposing of the fly ash and surrounding wooden structure at CAS 25-99-12 as a best management practice The NDEP-approved corrective action alternative for CAS 05-99-01 in CAU 214 is Clean Closure. Closure activities included: {sm_bullet} Removing and disposing of soil contaminated with the pesticide dieldrin The NDEP-approved corrective action alternative for CASs 25-23-01 and 25-23-19 is Closure in Place with Administrative Controls. Closure activities included: {sm_bullet} Removing and disposing of soil contaminated with chromium and soil impacted with the pesticides chlordane and heptachlor {sm_bullet} Implementing use restrictions (UR) at both CASs as detailed in the CAU 214 Corrective Action Plan (CAP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2005) {sm_bullet} Posting UR warning signs around CASs 25-23-01 and 25-23-19 on the existing chain link fence

NSTec Environmental Restoration

2006-09-01T23:59:59.000Z

71

Market Effects of Environmental Regulation: Coal, Railroads and the 1990 Clean Air Act  

E-Print Network (OSTI)

Rate Study: Final Report on Coal Transportation, DOE/EIA-of Environmental Regulation: Coal, Railroads, and the 1990of Environmental Regulation: Coal, Railroads, and the 1990

Busse, Meghan R.; Keohane, Nathaniel O.

2004-01-01T23:59:59.000Z

72

Railroad Valley Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

form form View source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit with form History Facebook icon Twitter icon » Railroad Valley Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Railroad Valley Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Exploration History 5 Well Field Description 6 Geology of the Area 7 Geofluid Geochemistry 8 NEPA-Related Analyses (0) 9 Exploration Activities (1) 10 References Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"TERRAIN","zoom":6,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"300px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":38.434,"lon":-115.529,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

73

Railroad Consolidation and Market Power: Challenges to a Deregulating Electric Utility Industry  

Science Conference Proceedings (OSTI)

The railroad industry is shrinking into a handful of mega-carriers, a development of great importance to the electric utility industry, which depends on railroads for most shipments of coal. As the electric utilities face deregulation, the impact of railroad market power on the delivered price of coal is a critical competitive issue. This report examines the motivations for railroad consolidation and assesses the likely business strategies of the five major coal hauling railroads.

1997-03-08T23:59:59.000Z

74

Historic Railroad Building Goes Net Zero | Department of Energy  

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

Historic Railroad Building Goes Net Zero Historic Railroad Building Goes Net Zero Historic Railroad Building Goes Net Zero July 29, 2010 - 5:16pm Addthis Richmond and Chesapeake Bay Railway Car Barn will serve as an example of green building in the community. | Photo by Julie Wescott Weissend Richmond and Chesapeake Bay Railway Car Barn will serve as an example of green building in the community. | Photo by Julie Wescott Weissend Lindsay Gsell What are the key facts? Former electric railroad barn uses less energy than it generates. Historic building has solar and geothermal energy systems. Construction company receiving federal and state tax credits. Dovetail Construction Company saw a unique challenge - and opportunity - with a neglected 1880s-era Richmond and Chesapeake Bay Railway Car Barn.

75

Historic Railroad Building Goes Net Zero | Department of Energy  

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

Historic Railroad Building Goes Net Zero Historic Railroad Building Goes Net Zero Historic Railroad Building Goes Net Zero July 29, 2010 - 5:16pm Addthis Richmond and Chesapeake Bay Railway Car Barn will serve as an example of green building in the community. | Photo by Julie Wescott Weissend Richmond and Chesapeake Bay Railway Car Barn will serve as an example of green building in the community. | Photo by Julie Wescott Weissend Lindsay Gsell What are the key facts? Former electric railroad barn uses less energy than it generates. Historic building has solar and geothermal energy systems. Construction company receiving federal and state tax credits. Dovetail Construction Company saw a unique challenge - and opportunity - with a neglected 1880s-era Richmond and Chesapeake Bay Railway Car Barn.

76

Monitoring of Olympic National Park Beaches to determine fate and effects of spilled bunker C fuel oil  

SciTech Connect

On December 23, 1988, the barge Nestucca was accidentally struck by its tow, a Souse Brothers Towing Company tug, releasing approximately 230,000 gallons of Bunker C fuel oil and fouling beaches from Grays Harbor north to Vancouver Island. Affected beaches in Washington included a 40-mile-long strip that has been recently added to Olympic National Park. The purpose of the monitoring program documented in this report was to determine the fate of spilled Bunker C fuel oil on selected Washington coastal beaches. We sought to determine (1) how much oil remained in intertidal and shallow subtidal habitats following clean-up and weathering, (2) to what extent intertidal and/or shallow subtidal biotic assemblages have been contaminated, and (3) how rapidly the oil has left the ecosystem. 45 refs., 18 figs., 8 tabs.

Strand, J.A.; Cullinan, V.I.; Crecelius, E.A.; Fortman, T.J.; Citterman, R.J.; Fleischmann, M.L.

1990-10-01T23:59:59.000Z

77

Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel  

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

Transportation Transportation Stakeholders National Transportation Stakeholders National Transportation Stakeholders National Transportation Stakeholders Forum Forum 2011 Annual Meeting 2011 Annual Meeting 2011 Annual Meeting 2011 Annual Meeting May 11, 2011 May 11, 2011 Evaluation of Shortline Railroads Evaluation of Shortline Railroads & & & & SNF/HLW Rail Shipment Inspections SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel Tasked for the Transportation of Spent Nuclear Fuel Evaluation of Shortline Railroads Evaluation of Shortline Railroads Evaluation of Shortline Railroads Evaluation of Shortline Railroads Task: Task: Task: Task: Identify Shortline Railroads Serving Nuclear Power Plants Identify Shortline Railroads Serving Nuclear Power Plants

78

Assessing the level of service for shipments originating or terminating on short line railroads  

E-Print Network (OSTI)

This thesis measures railroad freight trip time and trip time reliability for freight rail shipments involving short lines in 2006. It is based on an underlying MIT study commissioned by members of the short line railroading ...

Alpert, Steven M

2007-01-01T23:59:59.000Z

79

Railroad Commission of Texas, Oil and Gas Division | Open Energy  

Open Energy Info (EERE)

Railroad Commission of Texas, Oil and Gas Division Railroad Commission of Texas, Oil and Gas Division Jump to: navigation, search State Texas Name Texas Railroad Commission, Oil and Gas Division Address 1701 N. Congress City, State Austin, Texas Zip 78711-2967 Website http://www.rrc.state.tx.us/dat Coordinates 30.2759689°, -97.7359951° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":30.2759689,"lon":-97.7359951,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

80

The Nevada railroad system: Physical, operational, and accident characteristics  

Science Conference Proceedings (OSTI)

This report provides a description of the operational and physical characteristics of the Nevada railroad system. To understand the dynamics of the rail system, one must consider the system`s physical characteristics, routing, uses, interactions with other systems, and unique operational characteristics, if any. This report is presented in two parts. The first part is a narrative description of all mainlines and major branchlines of the Nevada railroad system. Each Nevada rail route is described, including the route`s physical characteristics, traffic type and volume, track conditions, and history. The second part of this study provides a more detailed analysis of Nevada railroad accident characteristics than was presented in the Preliminary Nevada Transportation Accident Characterization Study (DOE, 1990).

NONE

1991-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Audit of the Use of Hanford Site Railroad System, WR-B-97-04...  

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

Railroad System, WR-B-97-04 Audit of the Use of Hanford Site Railroad System, WR-B-97-04 Audit of the Use of Hanford Site Railroad System, WR-B-97-04 More Documents & Publications...

82

Energy Conservation Projects to Benefit the Railroad Industry  

DOE Green Energy (OSTI)

The Energy Conservation Projects to benefit the railroad industry using the Norfolk Southern Company as a model for the railroad industry has five unique tasks which are in areas of importance within the rail industry, and specifically in the area of energy conservation. The NIU Engineering and Technology research team looked at five significant areas in which research and development work can provide unique solutions to the railroad industry in energy the conservation. (1) Alternate Fuels - An examination of various blends of bio-based diesel fuels for the railroad industry, using Norfolk Southern as a model for the industry. The team determined that bio-diesel fuel is a suitable alternative to using straight diesel fuel, however, the cost and availability across the country varies to a great extent. (2) Utilization of fuel cells for locomotive power systems - While the application of the fuel cell has been successfully demonstrated in the passenger car, this is a very advanced topic for the railroad industry. There are many safety and power issues that the research team examined. (3) Thermal and emission reduction for current large scale diesel engines - The current locomotive system generates large amount of heat through engine cooling and heat dissipation when the traction motors are used to decelerate the train. The research team evaluated thermal management systems to efficiently deal with large thermal loads developed by the operating engines. (4) Use of Composite and Exotic Replacement Materials - Research team redesigned various components using new materials, coatings, and processes to provide the needed protection. Through design, analysis, and testing, new parts that can withstand the hostile environments were developed. (5) Tribology Applications - Identification of tribology issues in the Railroad industry which play a significant role in the improvement of energy usage. Research team analyzed and developed solutions which resulted in friction modification to improve energy efficiency.

Clifford Mirman; Promod Vohra

2009-12-31T23:59:59.000Z

83

Optimal Railroad Rail Grinding for Fatigue Mitigation  

E-Print Network (OSTI)

This dissertation aims to study the benefit of rail grinding on service life of railroad rails, focusing on failures due to rolling contact fatigue (RCF) at the rail head. Assuming a tangent rail with one-point contact at the running surface, a finite element analysis of a full-scale wheel-rail rolling contact with a nonlinear isotropic kinematic hardening material model is performed to simulate the accumulation of residual stresses and strains in the rail head. Using rolling stress and strain results from the sixth loading cycle, in which residual stresses and strains are at their steady-state, as input, two critical plane fatigue criteria are proposed for fatigue analyses. The first fatigue criterion is the stress-based approachnamely the Findley fatigue criterion. It suggests an important role of tensile residual stresses on subsurface crack nucleation and early growth in the rail head, but applications of the criterion to the near-running-surface region are limited because of plastic deformation from wheel-rail contact. The second fatigue criterion is the strain-based approachnamely the Fatemi-Socie fatigue criterion. Contributed mainly from shear strain amplitudes and factorized by normal stress components, the criterion also predicts fatigue crack nucleation at the subsurface as a possible failure mode as well as fatigue crack nucleation at the near-surface, while maintaining its validity in both regions. A collection of fatigue test data of various types of rail steel from literature is analyzed to determine a relationship between fatigue damages and number of cycles to failure. Considering a set of wheel loads with their corresponding number of rolling passage as a loading unit (LU), optimizations of grinding schedules with genetic algorithm (GA) show that fatigue life of rail increases by varying amount when compared against that from the no-grinding case. Results show that the proposed grinding schedules, optimized with the exploratory and local-search genetic algorithms, can increase fatigue life of rail by 240 percent. The optimization framework is designed to be able to determine a set of optimal grinding schedules for different types of rail steel and different contact configurations, i.e. two-point contact occurred when cornering.

Tangtragulwong, Potchara

2010-12-01T23:59:59.000Z

84

Floating vessel  

SciTech Connect

The invention relates to a floating vessel which may be used in oil recovery. The assembly consists of a vertical column having a relatively small diameter. The column has a buoyancy capacity and is supplied with a ballast section having a larger diameter at its end. An upper structure is movably connected to the column. The column and the ballast chamber determine the limits of a shaft. The shaft is open at its lower end and is supplied with means to let fluid into the shaft over a relatively large area. (8 claims)

1974-05-14T23:59:59.000Z

85

Hawaii Adjusted Sales of Distillate Fuel Oil by End Use  

U.S. Energy Information Administration (EIA)

Railroad: 3: 5: 4: 33: 4: 4: 1984-2012: Vessel Bunkering: 126,454: 52,243: 61,814: 56,944: 89,341: 81,167: 1984-2012: On-Highway: 52,692: 56,394: ...

86

Alaska Adjusted Sales of Distillate Fuel Oil by End Use  

U.S. Energy Information Administration (EIA)

Railroad: 6,256: 5,439: 5,100: 4,822: 5,799: 5,211: 1984-2012: Vessel Bunkering: 124,379: 106,165: 90,025: 102,827: 119,825: 128,012: 1984-2012: ...

87

Georgia Sales of Distillate Fuel Oil by End Use  

U.S. Energy Information Administration (EIA)

Railroad: 78,927: 69,710: 62,072: 63,770: 71,374: 63,902: 1984-2012: Vessel Bunkering: 14,016: 10,831: 10,765: 12,904: 12,387: 11,300: 1984-2012: ...

88

Midwest (PADD 2) Adjusted Sales of Distillate Fuel Oil by End Use  

U.S. Energy Information Administration (EIA)

Railroad: 1,717,322: 1,508,136: 1,303,015: 1,508,545: 1,375,270: 1,403,064: 1984-2012: Vessel Bunkering: 425,297: 455,194: 438,978: 457,034: 440,679: ...

89

North Dakota Sales of Distillate Fuel Oil by End Use  

U.S. Energy Information Administration (EIA)

Railroad: 124,832: 58,667: 12,849: 8,983: 9,839: 43,907: 1984-2012: Vessel Bunkering: 0: 0: 0: 0: 0: 0: 1984-2012: On-Highway: 177,467: 193,615: ...

90

Railroad transportation of nuclear waste and other Hazardous materials  

Science Conference Proceedings (OSTI)

Railroads continue to have duties to shippers and the public, and they may not take the law into their own hands. Except for emergencies - and then only for the duration of the emergency - they must carry all commodities without regard to whether they are dangerous, unless the proper agency of the federal government has relieved them of that obligation. (author)

McBride, Michael F.

2008-04-15T23:59:59.000Z

91

Energy study of railroad freight transportation. Volume 1. Executive summary  

SciTech Connect

The railroad industry plays a vital role in transporting goods, raw materials, and food necessary to the well being of the population and necessary to facilitate the operations of our industrial economy. Because of the vital part that the railroad industry plays in the economy and because of its ability to move goods with relatively small amounts of fuel, the US ERDA embarked on a study to determine the role of the Federal government in promoting conservation in the industry and in freight movements in general. Toward this final objective, the study compiled a description of the railroad industry, its structure, equipment, facilities, economics, and energy consumption; compiled a description of the regulation of the industry and considered ways in which the regulation has affected fuel consumption by the railroads; and analyzed candidates for fuel efficiency improvement and evaluated them on the basis of economics and the likelihood of their adoption by industry. A description of the industry, an analysis of energy consumption by the industry, a discussion of mechanisms for evaluating efficiency improvement proposals, a description and evaluation of conservation efficiency improvement proposals, a description and evaluation of conservation opportunities, and a discussion of recommended activities are included.

1979-08-01T23:59:59.000Z

92

Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections  

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

Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel Task: Identify Shortline Railroads Serving Nuclear Power Plants Establish Contact Information with Railroads Officials Field Review of each Railroad's Physical and Operational Infrastructure Facilitate Upgrades to Meet Safe Acceptable Standards Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel More Documents & Publications TEC Meeting Summaries - February 2008 Presentations TEC Meeting Summaries - July 2007 Presentations TEC Meeting Summaries - September 2006

93

Corrective Action Decision Document for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Rev. No. 0  

Science Conference Proceedings (OSTI)

The six bunkers included in CAU 204 were primarily used to monitor atmospheric testing or store munitions. The ''Corrective Action Investigation Plan (CAIP) for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada'' (NNSA/NV, 2002a) provides information relating to the history, planning, and scope of the investigation; therefore, it will not be repeated in this CADD. This CADD identifies potential corrective action alternatives and provides a rationale for the selection of a recommended corrective action alternative for each CAS within CAU 204. The evaluation of corrective action alternatives is based on process knowledge and the results of investigative activities conducted in accordance with the CAIP (NNSA/NV, 2002a) that was approved prior to the start of the Corrective Action Investigation (CAI). Record of Technical Change (ROTC) No. 1 to the CAIP (approval pending) documents changes to the preliminary action levels (PALs) agreed to by the Nevada Division of Environmental Protection (NDEP) and DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This ROTC specifically discusses the radiological PALs and their application to the findings of the CAU 204 corrective action investigation. The scope of this CADD consists of the following: (1) Develop corrective action objectives; (2) Identify corrective action alternative screening criteria; (3) Develop corrective action alternatives; (4) Perform detailed and comparative evaluations of corrective action alternatives in relation to corrective action objectives and screening criteria; and (5) Recommend and justify a preferred corrective action alternative for each CAS within CAU 204.

Robert Boehlecke

2004-04-01T23:59:59.000Z

94

Feasibility study and preliminary design for fishing (TUNA) vessel fuel storage and distribution. Final report. Export trade information  

SciTech Connect

The report is divided into the following sections: (1) Introduction; (2) Conclusions and Recommendations; (3) Existing Conditions and Facilities for a Fuel Distribution Center; (4) Pacific Ocean Regional Tuna Fisheries and Resources; (5) Fishing Effort in the FSMEEZ 1992-1994; (6) Current Transshipping Operations in the Western Pacific Ocean; (7) Current and Probale Bunkering Practices of United States, Japanese, Koren, and Taiwanese Offshore-Based Vessels Operating in FSM and Adjacent Waters; (8) Shore-Based Fish-Handling/Processing; (9) Fuels Forecast; (10) Fuel Supply, Storage and Distribution; (11) Cost Estimates; (12) Economic Evaluation of Fuel Supply, Storage and Distribution.

NONE

1995-07-01T23:59:59.000Z

95

Utility Response to Railroad Market Power: Assessment of Options  

Science Conference Proceedings (OSTI)

Coal transportation is one of the largest and potentially least competitive costs of power generation. This report reviews possible strategies and recourse available to utilities to counter railroad market power. The implosion of the major carriers into just two major companies in the east and the west heralds an era of duopoly pricing for which no single solution presents itself, past strategies may no longer apply, and the prospect of burgeoning power transactions may offer surprisingly little help to ...

1997-10-31T23:59:59.000Z

96

The potential for LNG as a railroad fuel in the U.S.  

Science Conference Proceedings (OSTI)

Freight railroad operations in the US represent a substantial opportunity for liquefied natural gas (LNG) to displace diesel fuel. With the promise of achieving an overwhelming economic advantage over diesel fuel, this paper presents some discussion to the question, ``Why is the application of LNG for railroad use in the US moving so slowly?'' A brief overview of the freight railroad operations in the US is given, along with a summary of several railroad LNG demonstration projects. US Environmental Protection Agency and California Air Resources Board exhaust emission regulations may cause the railroad industry to move from small-scale LNG demonstration projects to using LNG as a primary freight railroad transportation fuel in selected regions or route-specific applications.

Fritz, S.G.

2000-01-01T23:59:59.000Z

97

Corrective Action Decision Document for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Revision 0 with ROTC 1, 2, and Errata  

SciTech Connect

This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 204 Storage Bunkers, Nevada Test Site (NTS), Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE); and the U.S. Department of Defense (FFACO, 1996). The NTS is approximately 65 miles (mi) north of Las Vegas, Nevada (Figure 1-1). The Corrective Action Sites (CASs) within CAU 204 are located in Areas 1, 2, 3, and 5 of the NTS, in Nye County, Nevada (Figure 1-2). Corrective Action Unit 204 is comprised of the six CASs identified in Table 1-1. As shown in Table 1-1, the FFACO describes four of these CASs as bunkers one as chemical exchange storage and one as a blockhouse. Subsequent investigations have identified four of these structures as instrumentation bunkers (CASs 01-34-01, 02-34-01, 03-34-01, 05-33-01), one as an explosives storage bunker (CAS 05-99-02), and one as both (CAS 05-18-02). The six bunkers included in CAU 204 were primarily used to monitor atmospheric testing or store munitions. The ''Corrective Action Investigation Plan (CAIP) for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada'' (NNSA/NV, 2002a) provides information relating to the history, planning, and scope of the investigation; therefore, it will not be repeated in this CADD. This CADD identifies potential corrective action alternatives and provides a rationale for the selection of a recommended corrective action alternative for each CAS within CAU 204. The evaluation of corrective action alternatives is based on process knowledge and the results of investigative activities conducted in accordance with the CAIP (NNSA/NV, 2002a) that was approved prior to the start of the Corrective Action Investigation (CAI). Record of Technical Change (ROTC) No. 1 to the CAIP (approval pending) documents changes to the preliminary action levels (PALs) agreed to by the Nevada Division of Environmental Protection (NDEP) and DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This ROTC specifically discusses the radiological PALs and their application to the findings of the CAU 204 corrective action investigation.

Wickline, Alfred

2004-04-01T23:59:59.000Z

98

Corrective Action Investigation Plan for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada (December 2002, Revision No.: 0), Including Record of Technical Change No. 1  

SciTech Connect

The Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 204 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 204 is located on the Nevada Test Site approximately 65 miles northwest of Las Vegas, Nevada. This CAU is comprised of six Corrective Action Sites (CASs) which include: 01-34-01, Underground Instrument House Bunker; 02-34-01, Instrument Bunker; 03-34-01, Underground Bunker; 05-18-02, Chemical Explosives Storage; 05-33-01, Kay Blockhouse; 05-99-02, Explosive Storage Bunker. Based on site history, process knowledge, and previous field efforts, contaminants of potential concern for Corrective Action Unit 204 collectively include radionuclides, beryllium, high explosives, lead, polychlorinated biphenyls, total petroleum hydrocarbons, silver, warfarin, and zinc phosphide. The primary question for the investigation is: ''Are existing data sufficient to evaluate appropriate corrective actions?'' To address this question, resolution of two decision statements is required. Decision I is to ''Define the nature of contamination'' by identifying any contamination above preliminary action levels (PALs); Decision II is to ''Determine the extent of contamination identified above PALs. If PALs are not exceeded, the investigation is completed. If PALs are exceeded, then Decision II must be resolved. In addition, data will be obtained to support waste management decisions. Field activities will include radiological land area surveys, geophysical surveys to identify any subsurface metallic and nonmetallic debris, field screening for applicable contaminants of potential concern, collection and analysis of surface and subsurface soil samples from biased locations, and step-out sampling to define the extent of contamination, as necessary. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

NNSA /NSO

2002-12-12T23:59:59.000Z

99

Thermal And-Or Near Infrared At Railroad Valley Area (Laney, 2005) | Open  

Open Energy Info (EERE)

Railroad Valley Area (Laney, 2005) Railroad Valley Area (Laney, 2005) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Thermal And-Or Near Infrared At Railroad Valley Area (Laney, 2005) Exploration Activity Details Location Railroad Valley Area Exploration Technique Thermal And-Or Near Infrared Activity Date Usefulness useful DOE-funding Unknown Notes Geology and Geophysics of Geothermal Systems, Gregory Nash, 2005. Objectives for FY 2004 were to map mineralogy in Dixie Meadows, NV and thermal anomalies in Railroad Valley, NV. The first objective relates to the project goal of testing hyperspectral imagery for applications in soil-mineralogy mapping to detect hidden faults and buried geothermal phenomena. The second objective relates to testing satellite thermal

100

Prediction of Vessel Icing  

Science Conference Proceedings (OSTI)

Vessel icing from wave-generated spray is a severe hazard to expanded marine operations in high latitudes. Hardships in making observations during operations, combined with differences in vessel type and heading, have resulted in great ...

J. E. Overland; C. H. Pease; R. W. Preisendorfer; A. L. Comiskey

1986-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Vacuum Vessel Remote Handling  

E-Print Network (OSTI)

FIRE Vacuum Vessel and Remote Handling Overview B. Nelson, T. Burgess, T. Brown, H-M Fan, G. Jones #12;13 July 2002 Snowmass Review: FIRE Vacuum Vessel and Remote Handling 2 Presentation Outline · Remote Handling - Maintenance Approach & Component Classification - In-Vessel Transporter - Component

102

Corrective Action Decision Document for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada: Revision 0, Including Errata Sheet  

Science Conference Proceedings (OSTI)

This Corrective Action Decision Document identifies the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's corrective action alternative recommendation for each of the corrective action sites (CASs) within Corrective Action Unit (CAU) 204: Storage Bunkers, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. An evaluation of analytical data from the corrective action investigation, review of current and future operations at each CAS, and a detailed comparative analysis of potential corrective action alternatives were used to determine the appropriate corrective action for each CAS. There are six CASs in CAU 204, which are all located between Areas 1, 2, 3, and 5 on the NTS. The No Further Action alternative was recommended for CASs 01-34-01, 02-34-01, 03-34-01, and 05-99-02; and a Closure in Place with Administrative Controls recommendation was the preferred corrective action for CASs 05-18-02 and 05-33-01. These alternatives were judged to meet all requirements for the technical components evaluated as well as applicable state and federal regulations for closure of the sites and will eliminate potential future exposure pathways to the contaminated media at CAU 204.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2004-04-01T23:59:59.000Z

103

Applications of Engineering and Financial Analysis to the Valuation of Investments in Railroad Infrastructure  

E-Print Network (OSTI)

This record of study presents the findings of industry research projects performed during a one-year doctoral internship with the Austin Rail Group of HNTB Corporation. Four main internship objectives were established that address infrastructure problems related to the railroad industry and required the integration of engineering and financial analysis to develop effective project evaluation tools. Completion of the objectives resulted in: 1. Transformation of the Federal Railroad Administration methodology currently used to perform highway-railroad grade crossing analyses to a system of equations that can easily be used to evaluate regional rail infrastructure investments. Transportation engineering equations based on queuing theory were extended to new but equivalent formulations that accommodate unlimited, discrete train performance data from computer simulations of rail networks. 2. Application of risk assessment methods and railroad accident statistics to recommend a cost-effective alternative to legislative proposals to relocate hazardous materials transported by rail around metropolitan areas. A risk analysis model was developed to predict the risk of exposure from the release of a hazardous material following a train derailment so that changes in exposure achieved by alternative risk mitigation strategies could be observed. 3. A new method of measuring the susceptibility of railroads to financial distress following the catastrophic loss of a timber railroad bridge. Economic and finance principles were used to predict financial distress by determining of the number of revenue periods required to offset economic loss. 4. Demonstration of the use of financial market data in calculating the discount rate of public railroad companies for engineering analyses that involve negotiations with the public agencies. Surface Transportation Board rulings on the determination of a railroad?s cost of equity were applied to a comparative assessment of costs of capital for Class I railroads. A hypothetical example was used to demonstrate the interrelationship between engineering design strategies and their effects on the pricing of compensation to a railroad for right-of-way acquisition. These results, in fulfillment of the doctoral internship objectives, have provided HNTB with economic decision analysis tools and a series of conclusions used to provide recommendations to the Illinois, Missouri, and Texas Departments of Transportation, the Texas Legislature, and the railroad industry.

Roco, Craig E.

2009-05-01T23:59:59.000Z

104

Evaluation of Suspected Steady-State Magnetic Induction by a 345-kV Double-Circuit Transmission Line onto Railroad Track  

Science Conference Proceedings (OSTI)

CenterPoint Energy operates a double circuit 345-kV transmission line north of Houston that parallels the Burlington Northern Santa Fe Railroad (BNSF) for approximately 15 miles. The railroad is experiencing elevated steady-state 60-Hz voltage in the parallel exposure. AC voltages and currents in railroad track can come from many sources. And, railroad systems can withstand reasonable amounts of this electromagnetic interference (EMI) without problems. When problems with EMI on a railroad do appear, it i...

2008-11-12T23:59:59.000Z

105

Future fuels and engines for railroad locomotives. Volume I: summary  

DOE Green Energy (OSTI)

A study was made of the potential for reducing the dependence of railroads on petroleum fuel, particularly diesel No. 2. The study takes two approaches: (1) to determine how the use of diesel No. 2 can be reduced through increased efficiency and conservation, and (2) to use fuels other than diesel No. 2 both in diesel and other types of engines. The study consists of two volumes; volume 1 is a summary and volume 2 is the technical document. The study indicates that the possible reduction in fuel usage by increasing the efficiency of the present engine is limited; it is already highly energy efficient. The use of non-petroleum fuels, particularly the oil shale distillates, offers a greater potential. A coal-fired locomotive using any one of a number of engines appears to be the best alternative to the diesel-electric locomotive with regard to life-cycle cost, fuel availability, and development risk. The adiabatic diesel is the second-rated alternative with high thermal efficiency (up to 64%) as its greatest advantage. The risks associated with the development of the adiabatic diesel, however, are higher than those for the coal-fired locomotive. The advantage of the third alternative, the fuel cell, is that it produces electricity directly from the fuel. At present, the only feasible fuel for a fuel cell locomotive is methanol. Synthetic hydrocarbon fuels, probably derived from oil shale, will be needed if present diesel-electric locomotives are used beyond 1995. Because synthetic hydrocarbon fuels are particularly suited to medium-speed diesel engines, the first commercial application of these fuels may be by the railroad industry.

Liddle, S.G.; Bonzo, B.B.; Purohit, G.P.; Stallkamp, J.A.

1981-11-01T23:59:59.000Z

106

Fire modeling for Building 221-T - T Plant Canyon Deck and Railroad Tunnel  

Science Conference Proceedings (OSTI)

This report was prepared by Hughes Associates, Inc. to document the results of fire models for building 221-T Canyon Deck and Railroad Tunnel. Backup data is contained in document No. WHC-SD-CP-ANAL-010, Rev. 0.

Oar, D.L.

1994-09-29T23:59:59.000Z

107

Energy study of railroad freight transportation. Volume 4. Efficiency improvements and industry future  

DOE Green Energy (OSTI)

Railroad equipment and operating practices were largely developed in an era during which the price of fuel was a relatively minor part of the cost of railroad operations; however, fuel has now become a scarce and expensive resource. Although many opportunities exist for installing new equipment and operating practices that will result in fuel conservation, cost and market factors can promote or retard the rate at which changes are adopted, and only limited technology may be available for use in conservation applications. Conservation opportunities are identified and potential technological and operational improvements are described that can be introduced; the process of introducing new technology in the railroad industry is analyzed; the future of the railroad industry is assessed; and research and development that will contribute to the adoption of energy conservation equipment or processes in the industry are identified.

Not Available

1979-08-01T23:59:59.000Z

108

Railroad electrification in America's future: an assessment of prospects and impacts. Final report  

SciTech Connect

Such considerations as the level of traffic, the relative financial health of individual railroads, the capacity of the associated supply and engineering/construction industries, and the logical connecting points at classifying yards, as well as the national interest value of creating a continuous system, continental in scope, were used to construct a scenario for railroad electrification that closely approximates how an electrification program might be implemented. For the economic reasons cited, much of the US railroad system would remain conventionally powered. This scenario provides for an electrified network involving 14 mainlines operated by 10 companies that could transport much of the nation's rail-borne freight. Five years of planning and engineering work would be required for each link before construction could begin. With 1000 miles or less of electrified route per year, 14 years would be needed to construct the 9000-mile network of our scenario. (The scenario constructed runs from 1980 to 1998.) The analysis was aided with the construction of the SRI Railroad Industry Model. Basically a model of industry operations and finances, the model produces income statements and balance sheets at yearly intervals. Railroad energy costs, railroad freight levels, maintenance costs, purchases and leases of rooling stock, electrification facility investments, future inflation, rate setting practices, annual depreciation, taxes, and profits were calculated.

White, R.K.; Yabroff, I.W.; Dickson, E.M.; Zink, R.A.; Gray, M.E.; Moon, A.E.

1980-01-01T23:59:59.000Z

109

Addendum to the Closure Report for Corrective Action Unit 214: Bunkers and Storage Areas Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This document constitutes an addendum to the September 2006, Closure Report for Corrective Action Unit 214: Bunkers and Storage Areas as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: This cover page that refers the reader to the UR Modification document for additional information The cover and signature pages of the UR Modification document The NDEP approval letter The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the URs for: CAS 25-23-01, Contaminated Materials CAS 25-23-19, Radioactive Material Storage These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

Lynn Kidman

2008-10-01T23:59:59.000Z

110

Ultrasonic guided waves for structural health monitoring and application to rail inspection prototype for the Federal Railroad Administration  

E-Print Network (OSTI)

the European Rail Research Institute,? Wear, 191, pp. 113.Progress in rail integrity research,? Federal RailroadPradier, (1996). ?Rail rolling contact fatigue research by

Coccia, Stefano

2007-01-01T23:59:59.000Z

111

Molecular organic geochemistry of the oil and source rocks in Railroad Valley, eastern Great Basin, Nevada, United States.  

E-Print Network (OSTI)

??A comprehensive geochemical study of oils from Railroad Valley, Nevada and two candidate source rock intervals from the nearby Egan Range, was conducted in order (more)

Ahdyar, LaOde

2011-01-01T23:59:59.000Z

112

Welding stainless and 9% nickel steel cryogenic vessels  

SciTech Connect

Gases are often more efficiently stored and shipped as liquids at cryogenic temperatures. Pure gases commonly stored below liquefaction temperatures include oxygen {minus}297 F ({minus}183 C), argon {minus}302 f ({minus}186 C), nitrogen {minus}320 F ({minus}196 C), hydrogen {minus}423 F ({minus}253 C) and helium {minus}452 F ({minus}269 C). Natural gas is also transported and frequently stored as liquefied natural gas (LNG) at temperatures below {minus}261 F ({minus}163 C). Storage tanks for the pure gases are generally shop fabricated in sizes that can be shipped by conventional carriers. Smaller LNG vessels for over-the-road and railroad fuel applications are also shop-fabricated. Shown in a figure is a rail-mounted tank designed to supply liquefied natural gas to locomotives. Another example of a tank installation is also shown. LNG terminal storage tanks are generally field-erected vessels fabricated from 9% nickel steel in sizes of 50,000 to 100,000 m{sup 3} (315,000 to 630,000 bbls). This article focuses on welding practices for shop-fabricated vessels and equipment.

Avery, R.E. [Nickel Development Inst., Londonderry, NH (United States); Parsons, D. [Parsons (David), Hampstead, NH (United States)

1995-11-01T23:59:59.000Z

113

An analysis of railroad accident dynamics in College Station, Texas  

E-Print Network (OSTI)

The intersection between the Union Pacific Railroad (UP) Valley Junction line and Texas A&M University (TAMU) poses a significant potential or risk to the people who utilize the campus. The line carried over I 1,000 loads of hazardous material in 1995.(') The release of hazardous cargo occurring along a 1.2 mile stretch of track near TAMU could produce disastrous results. An ignition of flammable material released could affect tens of people near the tracks. For a release of a toxic material, the effects could reach in the hundreds. For a release of a flammable material followed by an explosion, thousands of people could be affected. The probability of an initiating event (e.g. a derailment, a collision, or terrorist act) occurring is 0.049808 each year. The probability of a release following an imt- iating event is 0.00090' ) each year. Therefore the probability of an initiating event occurring followed by a release is 0.000045. A qualitative analysis shows that this event is undesirable and requires a management decision. A contingency plan for the release of hazardous materials along the track appears warranted in an attempt to reduce the effects of a hazardous release of flammable or toxic materials. Based on the analysis presented herein, the only meaningful solution to eliminate the probability of a potentially catastrophic incident from occurring is to relocate the tracks. Constructing a bridge and raising the tracks would increase the probability of an incident followed by a release.

Brown, Hart Stefan

1998-01-01T23:59:59.000Z

114

Reactor vessel support system  

DOE Patents (OSTI)

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

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

1982-01-01T23:59:59.000Z

115

Cover Heated, Open Vessels  

SciTech Connect

This revised ITP steam tip sheet on covering heated, open vessels provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

2006-01-01T23:59:59.000Z

116

Reconnecting broken blood vessels  

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

Reconnecting broken blood vessels Reconnecting broken blood vessels Name: Catherine A Kraft Status: N/A Age: N/A Location: N/A Country: N/A Date: N/A Question: While watching the television program "Chicago Hope" the other day, I watched a doctor sew someone's ear back on using an elaborate microscope. I was wondering if a surgeon is required to reconnect all the broken blood vessels, and how you would accomplish this? Thanks for your time! Replies: I'm not a surgeon, but I think the answer to your question is "no." The blood will flow across the wound (out the end of one blood vessel and into the end of another), although not efficiently. I believe they sometimes use leeches sucking on the end of the reconnected part to help induce flow of blood in the right direction through the area. You probably do need to put the ends of the major vessels near each other, so the distribution of blood flow is reasonably like it was before the injury, and so the vessels can eventually reconnect. But probably the microscope is used mostly to be sure the various layers of muscle, connective tissue, and fat are connected together correctly.

117

Railroad impact study: 63 rail-line segments in South Dakota  

SciTech Connect

The primary concern of the study (in 2 volumes) was the trade area served by a rail line. The trade area was determined on the assumption that a farmer will haul his grain to the nearest elevator located on a railroad line. The basic approach in this study has been to measure potential demand for rail transportation, not to analyze the traffic data accumulated in the recent past. The first five chapters give the summaries for the entire state of South Dakota. The rail-line segments have been revised and recorded to comply as nearly as possible, with that, used by the various railroad companies. Some railroad data were made available for this study to provide a basis for estimating the rail potential in the major cities of South Dakota.

Poth, L.A.; Peterson, J.

1977-12-01T23:59:59.000Z

118

Reactor vessel annealing system  

DOE Patents (OSTI)

A system for annealing a vessel (14) in situ by heating the vessel (14) to a defined temperature, composed of: an electrically operated heater assembly (10) insertable into the vessel (14) for heating the vessel (14) to the defined temperature; temperature monitoring components positioned relative to the heater assembly (10) for monitoring the temperature of the vessel (14); a controllable electric power supply unit (32-60) for supplying electric power required by the heater assembly (10); a control unit (80-86) for controlling the power supplied by the power supply unit (32-60); a first vehicle (2) containing the power supply unit (32-60); a second vehicle (4) containing the control unit (80-86); power conductors (18,22) connectable between the power supply unit (32-60) and the heater unit (10) for delivering the power supplied by the power supply unit (32-60) to the heater assembly (10); signal conductors (20,24) connectable between the temperature monitoring components and the control unit (80-86) for delivering temperature indicating signals from the temperature monitoring components to the control unit (80-86); and control conductors (8) connectable between the control unit (80-86) and the power supply unit (32-60) for delivering to the power supply unit (32-60) control signals for controlling the level of power supplied by the power supply unit (32-60) to the heater assembly (10).

Miller, Phillip E. (Greensburg, PA); Katz, Leonoard R. (Pittsburgh, PA); Nath, Raymond J. (Murrysville, PA); Blaushild, Ronald M. (Export, PA); Tatch, Michael D. (Randolph, NJ); Kordalski, Frank J. (White Oak, PA); Wykstra, Donald T. (Pittsburgh, PA); Kavalkovich, William M. (Monroeville, PA)

1991-01-01T23:59:59.000Z

119

Attachments for fire modeling for Building 221-T, T Plant canyon deck and railroad tunnel  

SciTech Connect

The purpose of this attachment is to provide historical information and documentation for Document No. WHC-SD-CP-ANAL-008 Rev 0, ``Fire Modeling for Building 221-T--T Plant Canyon Deck and Railroad Tunnel``, dated September 29, 1994. This data compilation contains the following: Resumes of the Technical Director, Senior Engineer and Junior Engineer; Review and Comment Record; Software Files; CFAST Input and Output Files; Calculation Control Sheets; and Estimating Sprinkler Actuation Time in the Canyon and Railroad Tunnel. The T Plant was originally a fuel reprocessing facility. It was modified later to decontaminate and repair PuRex process equipment.

Oar, D.L. [Westinghouse Hanford Co., Richland, WA (United States)

1995-01-23T23:59:59.000Z

120

Decisions decisions plant vessels  

Science Conference Proceedings (OSTI)

This paper describes concepts for a family of plant vessels that help users make decisions or reach goals. The concepts use plants to mark time or answer questions for the user, creating a connection between the user and the individual plant. These concepts ...

Jenny Liang

2007-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Rail-to-Rail: Railroading and the Electronics of Op Amps  

E-Print Network (OSTI)

Abstract: Railroads have had rail-to-rail components for years that were, in fact, nearly rail to rail. Op amps employ the same nearly rail-to-rail tradition. This application note discusses rail-to-rail op amps, and explains why some inputs and outputs can be less than, nearly, or slightly more than the power rails.

unknown authors

2009-01-01T23:59:59.000Z

122

RELATIONSHIP BUILDING WITH FREIGHT RAILROADS CRITICAL TO SUPPORT INTERCITY PASSENGER RAIL DEVELOPMENT  

E-Print Network (OSTI)

RELATIONSHIP BUILDING WITH FREIGHT RAILROADS CRITICAL TO SUPPORT INTERCITY PASSENGER RAIL DEVELOPMENT Kyle Bardo "...if all we do is super-impose high speed passenger rail on existing freight networks everyone in transporta- tion to emphasize rail and water transportation a little bit more than it's been

Illinois at Chicago, University of

123

MEASURING THE IMPACT OF ADDITIONAL RAIL TRAFFIC USING HIGHWAY & RAILROAD METRICS  

E-Print Network (OSTI)

are then illustrated by simulating shared corridor operations with freight and passenger trains. TRANSPORTATION METRICS1 MEASURING THE IMPACT OF ADDITIONAL RAIL TRAFFIC USING HIGHWAY & RAILROAD METRICS Samuel L. Sogin of Illinois Urbana, IL, USA ABSTRACT Long term demand for freight movements in North America is expected

Barkan, Christopher P.L.

124

A Simulation Tool for Combined Rail-Road Transport in Intermodal Terminals  

E-Print Network (OSTI)

A Simulation Tool for Combined Rail-Road Transport in Intermodal Terminals Andrea E. Rizzoli the current flows of freight. On the other side, the growth of freight transport shows a rapidly increasing by road and rail gates and by a set of platforms. Intermodal terminals are inter-connected by rail

Gambardella, Luca Maria

125

Preliminary characterization of the F-Area Railroad Crosstie Pile at the Savannah River Site  

SciTech Connect

Historical information about the F-Area Railroad Crosstie Pile is limited. The unit is believed to have been a borrow area for earth fill that began receiving railroad crossties during the 1960s. The number of crossties at the unit began to increase significantly in 1984 when major repair of the SRS rail system was initiated. An estimated 100,000 used railroad crossties have accumulated at the unit since 1984. In an effort to determine the impact of the railroad crossties on the environment a total of 28 soil samples were collected from four test borings in March of 1991. Sample depths ranged from ground surface to 21.5 feet. Three of the borings were extended to the water table and groundwater samples were collected, one in an upgradient background'' area, and two downgradient from the unit. Few analytes were reported above detection limits. Test results are summarized in Section 4.0 and analytes not detected are summarized in Appendix A to this report. In three soil samples collected from depths between 10 and 21.5 feet, copper occurred at levels slightly above background. These copper values were detected in the sidegradient test boring and in the two downgradient test borings. Three organic analytes, acetone, pyridine, and Toluene, were reported above detection limits but well below drinking water standards (DWS) in all test borings, including the upgradient boring. Radionuclide activities were reported above background in both soil and water samples from all test borings. There do not appear to be any statistically significant trends in radionuclide activities with depth, or between upgradient or downgradient borings. The analytes detected in the test borings downgradient from the unit cannot be attributed to the railroad crosstie pile as they are not significantly different than the values reported for the upgradient, background test boring.

Not Available

1991-10-01T23:59:59.000Z

126

Radiant vessel auxiliary cooling system  

DOE Patents (OSTI)

In a modular liquid-metal pool breeder reactor, a radiant vessel auxiliary cooling system is disclosed for removing the residual heat resulting from the shutdown of a reactor by a completely passive heat transfer system. A shell surrounds the reactor and containment vessel, separated from the containment vessel by an air passage. Natural circulation of air is provided by air vents at the lower and upper ends of the shell. Longitudinal, radial and inwardly extending fins extend from the shell into the air passage. The fins are heated by radiation from the containment vessel and convect the heat to the circulating air. Residual heat from the primary reactor vessel is transmitted from the reactor vessel through an inert gas plenum to a guard or containment vessel designed to contain any leaking coolant. The containment vessel is conventional and is surrounded by the shell.

Germer, John H. (San Jose, CA)

1987-01-01T23:59:59.000Z

127

High pressure storage vessel  

DOE Patents (OSTI)

Disclosed herein is a composite pressure vessel with a liner having a polar boss and a blind boss a shell is formed around the liner via one or more filament wrappings continuously disposed around at least a substantial portion of the liner assembly combined the liner and filament wrapping have a support profile. To reduce susceptible to rupture a locally disposed filament fiber is added.

Liu, Qiang

2013-08-27T23:59:59.000Z

128

Reactor pressure vessel nozzle  

DOE Patents (OSTI)

A nozzle for joining a pool of water to a nuclear reactor pressure vessel includes a tubular body having a proximal end joinable to the pressure vessel and a distal end joinable in flow communication with the pool. The body includes a flow passage therethrough having in serial flow communication a first port at the distal end, a throat spaced axially from the first port, a conical channel extending axially from the throat, and a second port at the proximal end which is joinable in flow communication with the pressure vessel. The inner diameter of the flow passage decreases from the first port to the throat and then increases along the conical channel to the second port. In this way, the conical channel acts as a diverging channel or diffuser in the forward flow direction from the first port to the second port for recovering pressure due to the flow restriction provided by the throat. In the backflow direction from the second port to the first port, the conical channel is a converging channel and with the abrupt increase in flow area from the throat to the first port collectively increase resistance to flow therethrough. 2 figs.

Challberg, R.C.; Upton, H.A.

1994-10-04T23:59:59.000Z

129

Reactor Vessel Embrittlement Management Handbook: A Handbook for Managing Reactor Vessel Embrittlement and Vessel Integrity  

Science Conference Proceedings (OSTI)

For many reactor pressure vessels, embrittlement is the primary concern for continued safe operation. The shutdown of the Yankee Rowe plant because of uncertainties related to embrittlement of the vessel demonstrates the importance of adequately addressing embrittlement issues. Managing embrittlement requires integration, management, and implementation of diverse technical, regulatory, planning, and economic activities. An effective embrittlement management program will ensure vessel safety and reliabili...

1994-01-22T23:59:59.000Z

130

Laser Glazing of Railroad Rail Materials Procedure R & D Zhiyue Xu and Claude B. Reed  

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

Glazing of Railroad Rail Materials Glazing of Railroad Rail Materials Procedure R & D Zhiyue Xu and Claude B. Reed Laser Applications Laboratory Argonne National Laboratory Argonne, Illinois November 15, 2001 Outline * R & D work on further improving ANL's laser glazing technique - Goals ----faster & better surface finish * Preliminary feasibility study on using laser to heal the service-cracked rails Experimental Setup 1.6 kW Pulsed Nd:YAG laser with fiber-optic beam delivery & optics Nitrogen @ 50 CFH as shielding gas Rotational stage A wheel being laser-glazed Recent Procedure R&D Focusing on Increasing Processing Speed and Smoothening Surface Smoother surface by avoiding deep surface melting by lower laser power density and faster feeding. Old procedure New procedure Faster processing speed by

131

Strategic Analysis of Railroad Rate, Cost, and Service Prospects: Conflict or Cooperation  

Science Conference Proceedings (OSTI)

The railroad industry has consolidated into a handful of recently merged mega-carriers, facing mountains of debt, intense pressure to improve financial returns, and wary shippers stung by episodes of poor service. Power generators, too, have been consolidating and are operating under heightened cost pressures. How might these conflicting cost, service, and profit pressures play out over the next five years? This study analyzes these factors for representative movements of eastern and western coal by all ...

1999-11-15T23:59:59.000Z

132

Audit of the Use of Hanford Site Railroad System, WR-B-97-04  

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

AUDIT OF THE USE OF HANFORD SITE RAILROAD SYSTEM The Office of Inspector General wants to make the distribution of its reports as customer friendly and cost-effective as possible. Therefore, this report will be available electronically through the Internet five to seven days after publication at the following alternative addresses: Department of Energy Headquarters Gopher gopher.hr.doe.gov Department of Energy Headquarters Anonymous FTP vm1.hqadmin.doe.gov

133

Vessel structural support system  

SciTech Connect

Vessel structural support system for laterally and vertically supporting a vessel, such as a nuclear steam generator having an exterior bottom surface and a side surface thereon. The system includes a bracket connected to the bottom surface. A support column is pivotally connected to the bracket for vertically supporting the steam generator. The system also includes a base pad assembly connected pivotally to the support column for supporting the support column and the steam generator. The base pad assembly, which is capable of being brought to a level position by turning leveling nuts, is anchored to a floor. The system further includes a male key member attached to the side surface of the steam generator and a female stop member attached to an adjacent wall. The male key member and the female stop member coact to laterally support the steam generator. Moreover, the system includes a snubber assembly connected to the side surface of the steam generator and also attached to the adjacent wall for dampening lateral movement of the steam generator. In addition, the system includes a restraining member of "flat" attached to the side surface of the steam generator and a bumper attached to the adjacent wall. The flat and the bumper coact to further laterally support the steam generator.

Jenko, James X. (N. Versailles, PA); Ott, Howard L. (Kiski Twp., Allegheny County, PA); Wilson, Robert M. (Plum Boro, PA); Wepfer, Robert M. (Murrysville, PA)

1992-01-01T23:59:59.000Z

134

Radiological verification survey results at the Pompton Plains Railroad Spur, Pequannock, New Jersey (PJ008V)  

SciTech Connect

The US Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains railroad spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W.R. Grace facility. The property at the Pompton Plains Railroad Spur, Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil and debris samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at the Pompton Plains railroad spur were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

Rodriguez, R.E.; Johnson, C.A.

1995-05-01T23:59:59.000Z

135

Coal gasification vessel  

DOE Patents (OSTI)

A vessel system (10) comprises an outer shell (14) of carbon fibers held in a binder, a coolant circulation mechanism (16) and control mechanism (42) and an inner shell (46) comprised of a refractory material and is of light weight and capable of withstanding the extreme temperature and pressure environment of, for example, a coal gasification process. The control mechanism (42) can be computer controlled and can be used to monitor and modulate the coolant which is provided through the circulation mechanism (16) for cooling and protecting the carbon fiber and outer shell (14). The control mechanism (42) is also used to locate any isolated hot spots which may occur through the local disintegration of the inner refractory shell (46).

Loo, Billy W. (Oakland, CA)

1982-01-01T23:59:59.000Z

136

Corrective Action Investigation Plan for Corrective Action Unit 214: Bunkers and Storage Areas Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1 and No. 2  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 214 under the Federal Facility Agreement and Consent Order. Located in Areas 5, 11, and 25 of the Nevada Test Site, CAU 214 consists of nine Corrective Action Sites (CASs): 05-99-01, Fallout Shelters; 11-22-03, Drum; 25-99-12, Fly Ash Storage; 25-23-01, Contaminated Materials; 25-23-19, Radioactive Material Storage; 25-99-18, Storage Area; 25-34-03, Motor Dr/Gr Assembly (Bunker); 25-34-04, Motor Dr/Gr Assembly (Bunker); and 25-34-05, Motor Dr/Gr Assembly (Bunker). These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). The suspected contaminants and critical analyte s for CAU 214 include oil (total petroleum hydrocarbons-diesel-range organics [TPH-DRO], polychlorinated biphenyls [PCBs]), pesticides (chlordane, heptachlor, 4,4-DDT), barium, cadmium, chronium, lubricants (TPH-DRO, TPH-gasoline-range organics [GRO]), and fly ash (arsenic). The land-use zones where CAU 214 CASs are located dictate that future land uses will be limited to nonresidential (i.e., industrial) activities. The results of this field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the corrective action decision document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2003-05-16T23:59:59.000Z

137

Reactor vessel support system. [LMFBR  

DOE Patents (OSTI)

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

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

1980-05-09T23:59:59.000Z

138

LPG storage vessel cracking experience  

SciTech Connect

In order to evaluate liquefied petroleum gas (LPG) handling and storage hazards, Caltex Petroleum Corp. (Dallas) surveyed several installations for storage vessel cracking problems. Cracking was found in approximately one-third of the storage vessels. In most cases, the cracking appeared to be due to original fabrication problems and could be removed without compromising the pressure containment. Several in-service cracking problems found were due to exposure to wet hydrogen sulfide. Various procedures were tried in order to minimize the in-service cracking potential. One sphere was condemned because of extensive subsurface cracking. This article's recommendations concern minimizing cracking on new and existing LPG storage vessels.

Cantwell, J.E. (Caltex Petroleum Corp., P.O. Box 619500, Dallas, TX (US))

1988-10-01T23:59:59.000Z

139

LPG storage vessel cracking experience  

SciTech Connect

As part of an overall company program to evaluate LPG handling and storage hazards the authors surveyed several installations for storage vessel cracking problems. Cracking was found in approximately one third of the storage vessels. In most cases the cracking appeared due to original fabrication problems and could be removed without compromising the pressure containment. Several in-service cracking problems due to exposure to wet hydrogen sulfide were found. Various procedures were tried in order to minimize the in-service cracking potential. One sphere was condemned because of extensive subsurface cracking. Recommendations are made to minimize cracking on new and existing LPG storage vessels.

Cantwell, J.E.

1988-01-01T23:59:59.000Z

140

Market effects of environmental regulation: coal, railroads, and the 1990 Clean Air Act  

Science Conference Proceedings (OSTI)

Many environmental regulations encourage the use of 'clean' inputs. When the suppliers of such an input have market power, environmental regulation will affect not only the quantity of the input used but also its price. We investigate the effect of the Title IV emissions trading program for sulfur dioxide on the market for low-sulfur coal. We find that the two railroads transporting coal were able to price discriminate on the basis of environmental regulation and geographic location. Delivered prices rose for plants in the trading program relative to other plants, and by more at plants near a low-sulfur coal source.

Busse, M.R.; Keohane, N.O. [University of California Berkeley, Berkeley, CA (United States)

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Market effects of environmental regulation: coal, railroads, and the 1990 Clean Air Act ?  

E-Print Network (OSTI)

Many environmental regulations encourage the use of clean inputs. When the suppliers of such an input have market power, environmental regulation will affect not only the quantity of the input used, but also its price. We investigate the effect of the Title IV emissions trading program for sulfur dioxide on the market for low-sulfur coal. We find that the two railroads transporting coal were able to price discriminate on the basis of environmental regulation and geographic location. Delivered prices rose for plants in the trading program relative to other plants, and by more at plants near a low-sulfur coal source.

Severin Borenstein; Michael Greenstone; Matthew Kotchen; Jonathan Levin; Paul Macavoy; Fiona Scott Morton; Sharon Oster; Christopher Timmins; Frank Wolak; Rob Williams

2007-01-01T23:59:59.000Z

142

CHF Enhancement by Vessel Coating for External Reactor Vessel Cooling  

SciTech Connect

In-vessel retention (IVR) is a key severe accident management (SAM) strategy that has been adopted by some operating nuclear power plants and advanced light water reactors (ALWRs). One viable means for IVR is the method of external reactor vessel cooling (ERVC) by flooding of the reactor cavity during a severe accident. As part of a joint Korean United States International Nuclear Energy Research Initiative (K-INERI), an experimental study has been conducted to investigate the viability of using an appropriate vessel coating to enhance the critical heat flux (CHF) limits during ERVC. Toward this end, transient quenching and steady-state boiling experiments were performed in the SBLB (Subscale Boundary Layer Boiling) facility at Penn State using test vessels with micro-porous aluminum coatings. Local boiling curves and CHF limits were obtained in these experiments. When compared to the corresponding data without coatings, substantial enhancement in the local CHF limits for the case with surface coatings was observed. Results of the steady state boiling experiments showed that micro-porous aluminum coatings were very durable. Even after many cycles of steady state boiling, the vessel coatings remained rather intact, with no apparent changes in color or structure. Moreover, the heat transfer performance of the coatings was found to be highly desirable with an appreciable CHF enhancement in all locations on the vessel outer surface but with very little effect of aging.

Fan-Bill Cheung; Joy L. Rempe

2004-06-01T23:59:59.000Z

143

Cryogenic Pressure Vessels: Progress and Plans  

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

Pressure Vessel workshop, LLNL, February 15, 2011, p. 1 Cryogenic Pressure Vessels: Progress and Plans Salvador Aceves, Gene Berry, Francisco Espinosa, Ibo Matthews, Guillaume...

144

Reactor vessel seal service fixture  

DOE Patents (OSTI)

An apparatus for the preparation of exposed sealing surfaces along the open rim of a nuclear reactor vessel comprised of a motorized mechanism for traveling along the rim and simultaneously brushing the exposed surfaces is described.

Ritz, W.C.

1975-12-01T23:59:59.000Z

145

A critical analysis of grounding practices for railroad tracks in electric utility stations  

Science Conference Proceedings (OSTI)

A railroad spur is often routed into a large substation or generating plant to facilitate installation of large power transformers or other large pieces of equipment and to transport fuel to the plant. Because the metal rails may transfer hazardous potentials into or out of the switchyard area during ground faults, precautions must be taken to limit the hazardous voltages. This analysis looks for common trends of voltages along railroad tracks in a controlled model of a substation grounding system during a ground fault. Current practices to limit these transferred potentials are based on crude approximations and engineering judgment. Recently developed computer programs allow a much better model of the grounding system, track and the hazardous scenarios to which a person might be subject. Several cases were used to illustrate some of the most common techniques used to limit hazardous voltages, and some of these techniques were found to be quite ineffective. Except for the cases where the tracks near the substation were removed, the potential transferred along the tracks produced several scenarios with touch and/or step voltages exceeding the tolerable limits.

Garrett, D.L.; Wallace, K.A. (Southern Co. Services, Birmingham, AL (United States))

1993-01-01T23:59:59.000Z

146

INTERLINE 5. 0 -- An expanded railroad routing model: Program description, methodology, and revised user's manual  

Science Conference Proceedings (OSTI)

A rail routine model, INTERLINE, has been developed at the Oak Ridge National Laboratory to investigate potential routes for transporting radioactive materials. In Version 5.0, the INTERLINE routing algorithms have been enhanced to include the ability to predict alternative routes, barge routes, and population statistics for any route. The INTERLINE railroad network is essentially a computerized rail atlas describing the US railroad system. All rail lines, with the exception of industrial spurs, are included in the network. Inland waterways and deep water routes along with their interchange points with the US railroadsystem are also included. The network contains over 15,000 rail and barge segments (links) and over 13,000 stations, interchange points, ports, and other locations (nodes). The INTERLINE model has been converted to operate on an IBM-compatible personal computer. At least a 286 computer with a hard disk containing approximately 6 MB of free space is recommended. Enhanced program performance will be obtained by using arandom-access memory drive on a 386 or 486 computer.

Johnson, P.E.; Joy, D.S. (Oak Ridge National Lab., TN (United States)); Clarke, D.B.; Jacobi, J.M. (Tennessee Univ., Knoxville, TN (United States). Transportation Center)

1993-03-01T23:59:59.000Z

147

Emergency response planning for railroad transportation related spills of oil or other hazardous materials  

E-Print Network (OSTI)

In December 1984 an unintentional release of poison gas from a chemical plant in Bhopal, India killed over 2,500 people. Thousands of others were injured. Although this material was not in transportation at the time, this accident raised public awareness. Americans began to ask, "What if something similar happened here?" Chemicals with hazardous properties have become part of daily life. Industry, government, and the public have become aware of the need to respond to problems involving hazardous materials. Safe transportation of hazardous materials is very important. Union Pacific Railroad transports more hazardous material shipments than any other carrier. Early on they realized the benefits to having a dedicated team of personnel to respond to incidents involving hazardous materials. In order to remain the safest carrier of these commodities, an emergency response plan utilizing in house response personnel was needed. This document describes how that plan was created and includes a copy of the plan for the Union Pacific Railroad's Settegast Yard in Houston, Texas. Other carriers may use this as a template to establish their own in house response teams or emergency response plans.

Reeder, Geoffrey Benton

1995-01-01T23:59:59.000Z

148

Relationship Building with Freight Railroads Critical to Support Intercity Passenger Rail Development B.A., Blackburn College, Carlinville, Illinois, 2010  

E-Print Network (OSTI)

Relationship Building with Freight Railroads Critical to Support Intercity Passenger Rail: Setting Roles 19 2.6 Saving American Freight Rail 22 2.7 The Staggers Act 23 2.8 Defining the Modern.9 Freight Rail Service Types: Manifest vs. Unit 37 3.10 Summary 39 4. SHARED USE POLICY, PLANNING

Illinois at Chicago, University of

149

Agent-based Planning and Simulation of Combined Rail/Road Luca Maria Gambardella, Andrea E. Rizzoli  

E-Print Network (OSTI)

Agent-based Planning and Simulation of Combined Rail/Road Transport Luca Maria Gambardella, Andrea. On the other hand, the growth of freight transport shows a rapidly increasing trend in the short and medium) among inland intermodal terminals is presented. The intermodal terminals are inter-connected by rail

Gambardella, Luca Maria

150

Preliminary characterization of the F-Area Railroad Crosstie Pile at the Savannah River Site. Revision 1  

SciTech Connect

Historical information about the F-Area Railroad Crosstie Pile is limited. The unit is believed to have been a borrow area for earth fill that began receiving railroad crossties during the 1960s. The number of crossties at the unit began to increase significantly in 1984 when major repair of the SRS rail system was initiated. An estimated 100,000 used railroad crossties have accumulated at the unit since 1984. In an effort to determine the impact of the railroad crossties on the environment a total of 28 soil samples were collected from four test borings in March of 1991. Sample depths ranged from ground surface to 21.5 feet. Three of the borings were extended to the water table and groundwater samples were collected, one in an upgradient ``background`` area, and two downgradient from the unit. Few analytes were reported above detection limits. Test results are summarized in Section 4.0 and analytes not detected are summarized in Appendix A to this report. In three soil samples collected from depths between 10 and 21.5 feet, copper occurred at levels slightly above background. These copper values were detected in the sidegradient test boring and in the two downgradient test borings. Three organic analytes, acetone, pyridine, and Toluene, were reported above detection limits but well below drinking water standards (DWS) in all test borings, including the upgradient boring. Radionuclide activities were reported above background in both soil and water samples from all test borings. There do not appear to be any statistically significant trends in radionuclide activities with depth, or between upgradient or downgradient borings. The analytes detected in the test borings downgradient from the unit cannot be attributed to the railroad crosstie pile as they are not significantly different than the values reported for the upgradient, background test boring.

Not Available

1991-10-01T23:59:59.000Z

151

Future fuels and engines for railroad locomotives. Volume II. Technical document  

DOE Green Energy (OSTI)

A study was made of the potential for reducing the dependence of railroads on petroleum fuel, particularly Diesel No. 2. The study takes two approaches: (1) to determine how the use of Diesel No. 2 can be reduced through increased efficiency and conservation, and (2) to use fuels other then Diesel No. 2 both in Diesel and other types of engines. The study indicates that the possible reduction in fuel usage by increasing the efficiency of the present engine is limited; it is already highly energy efficient. The use of non-petroleum fuels, particularly the oil shale distillates, offers a greater potential. A coal-fired locomotive using any one of a number of engines appears to be the best alternative to the diesel-electric locomotive with regard to life-cycle cost, fuel availability, and development risk. The adiabatic diesel is the second-rated alternative with high thermal efficiency (up to 64%) as its greatest advantage. The risks associated with the development of the adiabatic diesel, however, are higher than those for the coal-fired locomotive. The advantage of the third alternative, the fuel cell, is that it produces electricity directly from the fuel. At present, the only feasible fuel for a fuel cell locomotive is methanol. Synthetic hydrocarbon fuels, probably derived from oil shale, will be needed if present diesel-electric locomotives are used beyond 1995. Because synthetic hydrocarbon fuels are particularly suited to medium-speed diesel engines, the first commercial application of these fuels may be by the railroad industry.

Liddle, S.G.; Bonzo, B.B.; Purohit, G.P.; Stallkamp, J.A.

1981-11-01T23:59:59.000Z

152

Multi-modal Transportation > Highway Transportation > Trucking > Railroad transportation > Public transit > Rural transportation > Rural transit > Freight pipeline transportation > Airport planning and development > Airport maintenance > Bicycle and pedes  

E-Print Network (OSTI)

Multi-modal Transportation > Highway Transportation > Trucking > Railroad transportation > Public transit > Rural transportation > Rural transit > Freight pipeline transportation > Airport planning and development > Airport maintenance > Bicycle and pedestrian > Ports and waterways >>> Transportation operat

153

http://tti.tamu.edu Multi-modal Transportation > Highway Transportation > Trucking > Railroad transportation > Public transit > Rural transportation > Rural transit > Freight  

E-Print Network (OSTI)

http://tti.tamu.edu Multi-modal Transportation > Highway Transportation > Trucking > Railroad transportation > Public transit > Rural transportation > Rural transit > Freight pipeline transportation >>> Transportation operat > Freight traffic > Commodities > Travel time > Travel demand > http

154

PRESSURE VESSEL FABRICATION USING T-1 STEEL  

SciTech Connect

The fabrication of pressure vessels using C-l steel is described. The welding, welding electrodes, explosionbulge test, and impact and fatigue properties for the pressure vessel are given. (W.L.H.)

Franco-Ferreira, E.A.

1957-11-14T23:59:59.000Z

155

Railroad accident report: Head-on collision between Iowa Interstate Railroad Extra 470 West and Extra 406 East with release of hazardous materials near Altoona, Iowa, on July 30, 1988. Irregular report  

SciTech Connect

About 11:40 a.m. central daylight saving time on July 30, 1988, Iowa Interstate Railroad Ltd. (IAIS) freight trains Extra 470 West and Extra 406 East collided head on within the yard limits of Altoona, Iowa, about 10 miles east of Des Moines, Iowa. All 5 locomotive units from both trains; 11 cars of Extra 406 East; and 3 cars, including two tank cars containing denatured alcohol, of Extra 470 West derailed. The denatured alcohol, which was released through the pressure relief valves and the manway domes of the two derailed tank cars, was ignited by the fire resulting from the collision of the locomotives. Both crew members of Extra 470 West were fatally injured; the two crew members of Extra 406 East were only slightly injured. The estimated damage (including lading) as a result of this accident exceeded $1 million. The major safety issues in the accident include operational methods employed by the IAIS, training and selection of train and engine personnel, supervisory oversight by the IAIS, design of closure fittings on hazardous materials rail tanks, and oversight of regional railroads by the Federal Railroad Administration.

Not Available

1989-07-06T23:59:59.000Z

156

Alaska railroad's future freight market. Volume III. Final report 1 Jul 74-30 Apr 76  

SciTech Connect

The study forecasts the freight market of the Alaska Railroad (ARR) due to natural resource development and pipeline construction in Alaska. This has been done through: (a) evaluation of those resources with commercial development potential which could generate rail service demand; and (b) development and analysis of petroleum development schedules and pipeline construction scenarios. Detailed price and market analysis of Alaskan coal and copper resources were performed. Forecasts of ARR traffic were based upon econometric relationships between the Alaskan economy and petroleum royalties and construction expenditures. Volume three provides a detailed review of ARR's recent freight market, pipeline construction scenarios and other activities which could significantly affect the ARR, and provides forecasts of the Alaska Railroad's freight traffic through 1990.

Hillegas, B.D.; Pernela, L.M.; Lewis, D.C.

1976-06-01T23:59:59.000Z

157

Mechanical behavior analysis of CDIO production-blood vessel robot in curved blood vessel  

Science Conference Proceedings (OSTI)

In order to analyze mechanical behavior of blood vessel robot (student's CDIO production) in curved blood, and provide the data for outline design of robot, the flow field out side of robot is numerical simulated. The results show that the vessel shape ... Keywords: blood vessel robot, curved blood vessel, mechanical behavior analysis, numerical simulation

Fan Jiang; Chunliang Zhang; Yijun Wang

2010-10-01T23:59:59.000Z

158

Railroad system of Texas: A component of the state and national transportation infrastructure. Research report, September 1996--November 1998  

Science Conference Proceedings (OSTI)

Railroads continue to play an important role in the Texas transportation system. This study addresses the potential for implementing a rail planning process in the Texas Department of Transportation. The study is documented in three reports, produced in coordinated and parallel efforts by the Center for Transportation Research and the Texas Transportation Institute. This report documents the work performed by TTI, whereby a rail planning framework is presented which formalizes the planning process and presents the key elements as a series of discrete and logical steps. These steps may be used to guide TxDOT in the formation of goals, identification of issues and affected parties, selection of appropriate analytical methodologies, location of data sources, and implementation of results. The report also presents an in-depth discussion of several key issues facing transportation agencies. These include rail line abandonment, intermodal service planning, and urban rail rationalization. A discussion of the Texas rail system covers the Class 1 railroads, shortline railroads, Amtrak, and the Mexican rail system.

Roop, S.S.; Warner, J.E.; Rosa, D.; Dickinson, R.W.

1998-11-01T23:59:59.000Z

159

Utility of drill-stem tests in determination of the geothermal regime of Railroad Valley, Nye County, Nevada  

Science Conference Proceedings (OSTI)

Accurate representation of geothermal conditions is necessary to determine generation potential of source rocks buried in Railroad Valley. Boreholes, provide the best source of geothermal information, but formation temperature data must be screened for variations caused by drilling. Bottomhole temperatures from wireline logs are affected by initial formation conditions, drilling fluid that moves into the formation while drilling, and lag time between cessation of drilling fluid circulation and acquisition of logs. More accurate indicators of formation conditions are temperatures recorded during drill-stem tests, especially for tests that recovered large amounts of fluid. Over 130 drill-stem tests were examined to establish the viability of this source of data and to determine the geothermal conditions of the Railroad Valley basin. Results indicate that 500 feet or more of fluid recovery on a test is necessary to get a temperature recorded that is not influenced by drilling perturbations. The formation temperature data collected for Railroad Valley indicate the possibility of 2 thermal regimes. A low-temperature gradient regime is probably influenced by meteoric water. The high-temperature gradient regime probably reflects the regional heat flow associated with the thin crust of the Great Basin.

French, D.E. [Independent Geologist, Billings, MT (United States)

1995-06-01T23:59:59.000Z

160

Mercury retorting of calcine waste, contaminated soils and railroad ballast at the Idaho National Egineering Laboratory  

SciTech Connect

The Idaho National Engineering Laboratory (INEL) has been involved in nuclear reactor research and development for over 40 years. One of the earliest major projects involved the development of a nuclear powered aircraft engine, a long-term venture which used mercury as a shielding medium. Over the course of several years, a significant amount of mercury was spilled along the railroad tracks where the test engines were transported and stored. In addition, experiments with volume reduction of waste through a calcine process employing mercury as a catalyst resulted in mercury contaminated calcine waste. Both the calcine and Test Area North wastes have been identified in Department of Energy Action Memorandums to be retorted, thereby separating the mercury from the various contaminated media. Lockheed Idaho Technologies Company awarded the Mercury Retort contract to ETAS Corporation and assigned Parsons Engineering Science, Inc. to manage the treatment field activities. The mercury retort process entails a mobile unit which consists of four trailer-mounted subsystems requiring electricity, propane, and a water supply. This mobile system demonstrates an effective strategy for retorting waste and generating minimal secondary waste.

Cotten, G.B.; Rothermel, J.S. [Parsons Engineering Science, Inc., Houston, TX (United States); Sherwood, J. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Heath, S.A.; Lo, T.Y.R. [ETAS Corporation (United States)

1996-02-28T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Reactor pressure vessel vented head  

DOE Patents (OSTI)

A head for closing a nuclear reactor pressure vessel shell includes an arcuate dome having an integral head flange which includes a mating surface for sealingly mating with the shell upon assembly therewith. The head flange includes an internal passage extending therethrough with a first port being disposed on the head mating surface. A vent line includes a proximal end disposed in flow communication with the head internal passage, and a distal end disposed in flow communication with the inside of the dome for channeling a fluid therethrough. The vent line is fixedly joined to the dome and is carried therewith when the head is assembled to and disassembled from the shell.

Sawabe, James K. (San Jose, CA)

1994-01-11T23:59:59.000Z

162

Coal gasification vessel. [Patent application  

DOE Patents (OSTI)

A vessel system comprises an outer shell of carbon fibers held in a binder, a coolant circulation mechanism and control mechanism and an inner shell comprised of a refractory material and is of light weight and capable of withstanding the extreme temperature and pressure environment of, for example, a coal gasification process. The control mechanism can be computer controlled and can be used to monitor and modulate the coolant which is provided through the circulation mechanism for cooling and protecting the carbon fiber and outer shell. The control mechanism is also used to locate any isolated hot spots which may occur through the local disintegration of the inner refractory shell.

Loo, B.W.

1981-03-17T23:59:59.000Z

163

IWTU Construction Workers Set Largest Process Vessel  

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

IWTU Construction Workers Set Largest Process Vessel IWTU Construction Workers Set Largest Process Vessel Click on image to enlarge Construction of the Integrated Waste Treatment Unit (IWTU) took a major step forward on Sept. 2, 2009 as crews lifted into place the largest of the six process vessels that will be used to treat radioactive liquid waste stored at the site. The IWTU will use a steam reforming process to solidify the waste for eventual shipment out of Idaho. The vessel and its skid, or framework, were constructed at Premier Technologies in Blackfoot. (Premier is the main small business partner for CH2M-WG Idaho (CWI), the contractor for DOE's Idaho Cleanup Project.) The Carbon Reduction Reformer vessel and skid weigh approximately 60 tons (120,000 lbs.). Because of the weight of the vessel and the location of the

164

MMA Tugboat/ Barge/ Vessel | Open Energy Information  

Open Energy Info (EERE)

MMA Tugboat/ Barge/ Vessel MMA Tugboat/ Barge/ Vessel Jump to: navigation, search Basic Specifications Facility Name MMA Tugboat/ Barge/ Vessel Overseeing Organization Maine Maritime Academy Hydrodynamic Testing Facility Type Tow Vessel Depth(m) 15.2 Water Type Saltwater Cost(per day) Contact POC Special Physical Features Tug: 73 ft (2)16V-92 Detroits Barge: 43 ft by 230ft Research Vessel Friendship: 40 foot vessel w/ 6 cylinder Cummins diesel engine and A-Frame crane Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 5.1 Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Description Full onbard Navigation, GPS, marine radar and depth plotter; standard PC onboard can be configured as needed for data acquisition needs

165

Neutron Assay System for Confinement Vessel Disposition  

Science Conference Proceedings (OSTI)

Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the CVs. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of special nuclear material (SNM) in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le}100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-13T23:59:59.000Z

166

Rancho Seco Reactor Vessel Segmentation Experience Report  

Science Conference Proceedings (OSTI)

This report documents the approach taken by Sacramento Municipal Utility District (SMUD) in the segmentation and disposal of the Reactor Vessel from the Rancho Seco Nuclear Generating Station (RSNGS). The location of the Rancho Seco plant placed major constraints on the shipping options available for large plant components (Steam Generators and Reactor Vessel). This report details the engineering evaluations leading to the segmentation and disposal of the Reactor Vessel (RV). It describes the key element...

2008-03-18T23:59:59.000Z

167

Embrittlement of Nuclear Reactor Pressure Vessels  

Science Conference Proceedings (OSTI)

Boiler and Pressure Vessel Code Section III App. G Protection Against Nonductile Fracture (New York: American Society of Mechanical Engineers, 1986 ). 3.

168

Lightweight bladder lined pressure vessels - Energy Innovation ...  

A lightweight, low permeability liner for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated ...

169

Crew resource management training's effect on railroad crews' perceptions of task interdependence and teamwork  

E-Print Network (OSTI)

The accuracy and similarity of team members' perceptions regarding the interdependencies of their task as well as the criticality of teamwork behaviors is essential to team performance. Unfortunately, these perceptions are not always accurate or similar, which has led to calls for research evaluating the effectiveness of interventions aimed at improving these perceptions. The present study evaluated the accuracy and similarity of crew members' perceptions of task interdependence and teamwork in the U.S. railroad industry. Specifically, this study assessed (1) the effect of Crew Resource Management (CRM) training on the accuracy and similarity of locomotive and maintenance of way (MOW) crew members' perceptions and (2), the extent to which the accuracy and similarity of those perceptions are retained 2-years after training. The overall results of the present study suggests that CRM training is effective in increasing the accuracy and similarity of crew members' perceptions of team-relatedness (amount of task interdependence) and perceptions regarding the importance of teamwork. However, the effectiveness is often dependent on the metric used (i.e., accuracy vs. similarity), and the specific characteristics of the crew members (i.e., locomotive vs. MOW, higher vs. lower interpositional experience). Furthermore, the results suggest that training did not increase the accuracy or similarity of crew members' perceptions of team workflow pattern (form of task interdependence). Lastly, a small sample size and low power precluded the running of quantitative statistical analysis assessing the long-term retention of the accuracy and similarity of participants' perceptions of task interdependence or teamwork. However, for the sake of completeness, the means, standard deviations, and effect sizes are presented in the Appendix.

Kyte, Tobin Bruce

2008-08-01T23:59:59.000Z

170

Pressure vessel and piping codes  

SciTech Connect

Section III of the ASME Boiler and Pressure Vessel Code contains simplified design formulas for placing bounds on the plastic deformations in nuclear power plant piping systems. For Class 1 piping a simple equation is given in terms of primary load stress indices (B/sub 1/ and B/sub 2/) and nominal pressure and bending stresses. The B/sub 1/ and B/sub 2/ stress indices reflect the capacities of various piping products to carry load without gross plastic deformation. In this paper, the significance of the indices, nominal stresses, and limits given in the Code for Class 1 piping and corresponding requirements for Class 2 and Class 3 piping are discussed. Motivation behind recent (1978-1981) changes in the indices and in the associated stress limits is presented.

Moore, S.E.; Rodabaugh, E.C.

1982-11-01T23:59:59.000Z

171

Reactor pressure vessel vented head  

DOE Patents (OSTI)

A head for closing a nuclear reactor pressure vessel shell includes an arcuate dome having an integral head flange which includes a mating surface for sealingly mating with the shell upon assembly therewith. The head flange includes an internal passage extending therethrough with a first port being disposed on the head mating surface. A vent line includes a proximal end disposed in flow communication with the head internal passage, and a distal end disposed in flow communication with the inside of the dome for channeling a fluid therethrough. The vent line is fixedly joined to the dome and is carried therewith when the head is assembled to and disassembled from the shell. 6 figures.

Sawabe, J.K.

1994-01-11T23:59:59.000Z

172

Device for inspecting vessel surfaces  

DOE Patents (OSTI)

A portable, remotely-controlled inspection crawler for use along the walls of tanks, vessels, piping and the like. The crawler can be configured to use a vacuum chamber for supporting itself on the inspected surface by suction or a plurality of magnetic wheels for moving the crawler along the inspected surface. The crawler is adapted to be equipped with an ultrasonic probe for mapping the structural integrity or other characteristics of the surface being inspected. Navigation of the crawler is achieved by triangulation techniques between a signal transmitter on the crawler and a pair of microphones attached to a fixed, remote location, such as the crawler's deployment unit. The necessary communications are established between the crawler and computers external to the inspection environment for position control and storage and/or monitoring of data acquisition.

Appel, D. Keith (Aiken, SC)

1995-01-01T23:59:59.000Z

173

Fire protection of railroad tank cars carrying hazardous materials - analytical calculations and laboratory screening of thermal insulation candidates  

SciTech Connect

In recent years there have been a number of incidents in which railroad tank cars carrying liquefied petroleum gas (LPG) have been engulfed in fires. The LPG cars have ruptured from the fires, causing extensive property damage and loss of life. This report describes a laboratory screening program to select two thermal insulation candidates for use in future fire tests of fifth-scale and full scale LPG tank cars. Also included are analytical calculations to predict pressures and liquid levels in LPG tank cars being heated by fires.

Levine, D.; Dancer, D.M.

1972-07-21T23:59:59.000Z

174

Nuclear reactor vessel fuel thermal insulating barrier  

DOE Patents (OSTI)

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

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

2013-03-19T23:59:59.000Z

175

A review of vessel extraction techniques and algorithms  

Science Conference Proceedings (OSTI)

Vessel segmentation algorithms are the critical components of circulatory blood vessel analysis systems. We present a survey of vessel extraction techniques and algorithms. We put the various vessel extraction approaches and techniques in perspective ... Keywords: Magnetic resonance angiography, X-ray angiography, medical imaging, neurovascular, vessel extraction

Cemil Kirbas; Francis Quek

2004-06-01T23:59:59.000Z

176

Lightweight bladder lined pressure vessels  

DOE Patents (OSTI)

A lightweight, low permeability liner is described for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated with a thin layer of a low permeability material, such as silver, gold, or aluminum, deposited on a thin polymeric layer or substrate which is formed into a closed bladder using tori spherical or near tori spherical end caps, with or without bosses therein, about which a high strength to weight material, such as graphite epoxy composite shell, is formed to withstand the storage pressure forces. The polymeric substrate may be laminated on one or both sides with additional layers of polymeric film. The liner may be formed to a desired configuration using a dissolvable mandrel or by inflation techniques and the edges of the film sealed by heat sealing. The liner may be utilized in most any type of gas storage system, and is particularly applicable for hydrogen, gas mixtures, and oxygen used for vehicles, fuel cells or regenerative fuel cell applications, high altitude solar powered aircraft, hybrid energy storage/propulsion systems, and lunar/Mars space applications, and other applications requiring high cycle life. 19 figs.

Mitlitsky, F.; Myers, B.; Magnotta, F.

1998-08-25T23:59:59.000Z

177

Lightweight bladder lined pressure vessels  

DOE Patents (OSTI)

A lightweight, low permeability liner for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated with a thin layer of a low permeability material, such as silver, gold, or aluminum, deposited on a thin polymeric layer or substrate which is formed into a closed bladder using torispherical or near torispherical end caps, with or without bosses therein, about which a high strength to weight material, such as graphite epoxy composite shell, is formed to withstand the storage pressure forces. The polymeric substrate may be laminated on one or both sides with additional layers of polymeric film. The liner may be formed to a desired configuration using a dissolvable mandrel or by inflation techniques and the edges of the film seamed by heat sealing. The liner may be utilized in most any type of gas storage system, and is particularly applicable for hydrogen, gas mixtures, and oxygen used for vehicles, fuel cells or regenerative fuel cell applications, high altitude solar powered aircraft, hybrid energy storage/propulsion systems, and lunar/Mars space applications, and other applications requiring high cycle life.

Mitlitsky, Fred (1125 Canton Ave., Livermore, CA 94550); Myers, Blake (4650 Almond Cir., Livermore, CA 94550); Magnotta, Frank (1206 Bacon Way, Lafayette, CA 94549)

1998-01-01T23:59:59.000Z

178

INTERLINE 5.0 -- An expanded railroad routing model: Program description, methodology, and revised user`s manual  

Science Conference Proceedings (OSTI)

A rail routine model, INTERLINE, has been developed at the Oak Ridge National Laboratory to investigate potential routes for transporting radioactive materials. In Version 5.0, the INTERLINE routing algorithms have been enhanced to include the ability to predict alternative routes, barge routes, and population statistics for any route. The INTERLINE railroad network is essentially a computerized rail atlas describing the US railroad system. All rail lines, with the exception of industrial spurs, are included in the network. Inland waterways and deep water routes along with their interchange points with the US railroadsystem are also included. The network contains over 15,000 rail and barge segments (links) and over 13,000 stations, interchange points, ports, and other locations (nodes). The INTERLINE model has been converted to operate on an IBM-compatible personal computer. At least a 286 computer with a hard disk containing approximately 6 MB of free space is recommended. Enhanced program performance will be obtained by using arandom-access memory drive on a 386 or 486 computer.

Johnson, P.E.; Joy, D.S. [Oak Ridge National Lab., TN (United States); Clarke, D.B.; Jacobi, J.M. [Tennessee Univ., Knoxville, TN (United States). Transportation Center

1993-03-01T23:59:59.000Z

179

Reactor vessel using metal oxide ceramic membranes  

DOE Patents (OSTI)

A reaction vessel for use in photoelectrochemical reactions includes as its reactive surface a metal oxide porous ceramic membrane of a catalytic metal such as titanium. The reaction vessel includes a light source and a counter electrode. A provision for applying an electrical bias between the membrane and the counter electrode permits the Fermi levels of potential reaction to be favored so that certain reactions may be favored in the vessel. The electrical biasing is also useful for the cleaning of the catalytic membrane.

Anderson, Marc A. (Madison, WI); Zeltner, Walter A. (Oregon, WI)

1992-08-11T23:59:59.000Z

180

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel...  

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

of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research...

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Analysis of Crack Development Involving a Pressure Vessel in a ...  

Science Conference Proceedings (OSTI)

The vessel is part of a by-product refining system comprising a synthetic natural gas production plant. The vessel processes a mixture of chemical species,...

182

HFIR In-Vessel Irradiation Facilities | ORNL Neutron Sciences  

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

Home Facilities HFIR In-Vessel Irradiation In-Vessel Irradiation Experiment Facilities The HFIR provides a variety of in-core irradiation facilities, allowing for a...

183

To appear in: Journal of Mathematics and Computers in Simulation, IMACS/Elsevier Science A Simulation Tool for Combined Rail/Road Transport  

E-Print Network (OSTI)

A Simulation Tool for Combined Rail/Road Transport in Intermodal Terminals Andrea E. Rizzolia,*, Nicoletta and they can support the current flows of freight. On the other hand, the growth of freight transport shows or given as a deterministic input. The simulator can be used to simulate both a single terminal and a rail

Gambardella, Luca Maria

184

Resistance upset welding for vessel fabrication  

SciTech Connect

Solid-state resistance upset welding has been successfully applied to fabrication of small vessels. The process has advantages compared with the fusion welding processes currently used to join the two halves of such vessels. These advantages result from the improved metallurgical properties of the weld zone and the simplicity of the welding process. Spherical and cylindrical shapes have been fabricated using the upset welding process. Nondestructive and destructive tests have shown excellent weld strength. Storage tests have demonstrated long term compatibility of the welds for cylindrical parts made from 304L stainless steel that have been in storage for eight years. Spherical vessels and reinforced desip vessels made from forged 21-6-9 stainless steel have been prepared for storage.

Kanne, W.R. Jr.

1992-01-01T23:59:59.000Z

185

Resistance upset welding for vessel fabrication  

SciTech Connect

Solid-state resistance upset welding has been successfully applied to fabrication of small vessels. The process has advantages compared with the fusion welding processes currently used to join the two halves of such vessels. These advantages result from the improved metallurgical properties of the weld zone and the simplicity of the welding process. Spherical and cylindrical shapes have been fabricated using the upset welding process. Nondestructive and destructive tests have shown excellent weld strength. Storage tests have demonstrated long term compatibility of the welds for cylindrical parts made from 304L stainless steel that have been in storage for eight years. Spherical vessels and reinforced desip vessels made from forged 21-6-9 stainless steel have been prepared for storage.

Kanne, W.R. Jr.

1992-10-01T23:59:59.000Z

186

Future characteristics of Offshore Support Vessels  

E-Print Network (OSTI)

The objective of this thesis is to examine trends in Offshore Support Vessel (OSV) design and determine the future characteristics of OSVs based on industry insight and supply chain models. Specifically, this thesis focuses ...

Rose, Robin Sebastian Koske

2011-01-01T23:59:59.000Z

187

Ion transport membrane module and vessel system  

DOE Patents (OSTI)

An ion transport membrane system comprising (a) a pressure vessel having an interior, an exterior, an inlet, and an outlet; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region, wherein any inlet and any outlet of the pressure vessel are in flow communication with exterior regions of the membrane modules; and (c) one or more gas manifolds in flow communication with interior regions of the membrane modules and with the exterior of the pressure vessel. The ion transport membrane system may be utilized in a gas separation device to recover oxygen from an oxygen-containing gas or as an oxidation reactor to oxidize compounds in a feed gas stream by oxygen permeated through the mixed metal oxide ceramic material of the membrane modules.

Stein, VanEric Edward (Allentown, PA); Carolan, Michael Francis (Allentown, PA); Chen, Christopher M. (Allentown, PA); Armstrong, Phillip Andrew (Orefield, PA); Wahle, Harold W. (North Canton, OH); Ohrn, Theodore R. (Alliance, OH); Kneidel, Kurt E. (Alliance, OH); Rackers, Keith Gerard (Louisville, OH); Blake, James Erik (Uniontown, OH); Nataraj, Shankar (Allentown, PA); Van Doorn, Rene Hendrik Elias (Obersulm-Willsbach, DE); Wilson, Merrill Anderson (West Jordan, UT)

2012-02-14T23:59:59.000Z

188

Ion transport membrane module and vessel system  

DOE Patents (OSTI)

An ion transport membrane system comprising (a) a pressure vessel having an interior, an exterior, an inlet, and an outlet; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region, wherein any inlet and any outlet of the pressure vessel are in flow communication with exterior regions of the membrane modules; and (c) one or more gas manifolds in flow communication with interior regions of the membrane modules and with the exterior of the pressure vessel.The ion transport membrane system may be utilized in a gas separation device to recover oxygen from an oxygen-containing gas or as an oxidation reactor to oxidize compounds in a feed gas stream by oxygen permeated through the mixed metal oxide ceramic material of the membrane modules.

Stein, VanEric Edward (Allentown, PA); Carolan, Michael Francis (Allentown, PA); Chen, Christopher M. (Allentown, PA); Armstrong, Phillip Andrew (Orefield, PA); Wahle, Harold W. (North Canton, OH); Ohrn, Theodore R. (Alliance, OH); Kneidel, Kurt E. (Alliance, OH); Rackers, Keith Gerard (Louisville, OH); Blake, James Erik (Uniontown, OH); Nataraj, Shankar (Allentown, PA); van Doorn, Rene Hendrik Elias (Obersulm-Willsbach, DE); Wilson, Merrill Anderson (West Jordan, UT)

2008-02-26T23:59:59.000Z

189

Vessel Sanitation Program 2011 Operations Manual  

E-Print Network (OSTI)

and Prevention (CDC) established the Vessel Sanitation Program (VSP) in the 1970s as a cooperative activity............................................................................................ 1 1.1.1 Cooperative Activity.......................................................................................................... 1 1.2 Activities

190

Final Vitrification Melter And Vessels Evaluation Documentation  

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

DOE has prepared final evaluations and made waste incidental to reprocessing determinations for the vitrification melter and feed vessels (the concentrator feed makeup tank and the melter feed hold...

191

TMI-2 Vessel Investigation Project integration report  

Science Conference Proceedings (OSTI)

The Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project (VIP) was an international effort that was sponsored by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The primary objectives of the VIP were to extract and examine samples from the lower head and to evaluate the potential modes of failure and the margin of structural integrity that remained in the TMI-2 reactor vessel during the accident. This report presents a summary of the major findings and conclusions that were developed from research during the VIP. Results from the various elements of the project are integrated to form a cohesive understanding of the vessel`s condition after the accident.

Wolf, J. R.; Rempe, J. L.; Stickler, L. A.; Korth, G. E.; Diercks, D. R.; Neimark, L. A.; Akers, D W; Schuetz, B. K.; Shearer, T L; Chavez, S. A.; Thinnes, G. L.; Witt, R. J.; Corradini, M L; Kos, J. A. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1994-03-01T23:59:59.000Z

192

Decommissioning: Reactor Pressure Vessel Internals Segmentation  

Science Conference Proceedings (OSTI)

Decommissioning a nuclear plant covers a wide variety of challenging projects. One of the most challenging areas is the removal and disposal of the reactor pressure vessel (RPV) and the RPV internals. This report describes commercial reactor pressure vessel segmentation projects that have been completed and discusses several projects that are still in the planning stages. The report also covers lessons learned from each project.

2001-10-11T23:59:59.000Z

193

Test of 6-inch-thick pressure vessels. Series 1: intermediate test vessels V-1 and V-2  

SciTech Connect

The intermediate vessel tests have been subdivided into four seriesi flaws in cylindrical vessels, A508, class 2 forging steel-two vessels; flaws in cylindrical vessels with longitudinal weld seams, A508, class 2 forging steel, submerged-arc welds-three vessels; flaws in cylindrical vessels wlth longitudinal weld seams, A533, grade B, class l plate steel, submerged-arc weld-two vessels; and cylindrical vessels with radially attached nozzles, vessels of A508, chass 2 forging steel and A533, grade B, class 1 plate steel; nozzle of A508 class 2 forging steel-three vessels. A comprehensive description of the pertinent factors considered in the design of the vessels is presented. Construction of the test facility and documentation of test results and fracture predictions are included. Emphasis is placed on providing the test results in such a manner that they form a resource for amy investigators interested in the problem of fracture. (auth)

Derby, R.W.; Merkle, J.G.; Robinson, G.C.; Whitman, G.D.; Witt, F.J.

1974-02-01T23:59:59.000Z

194

Alaska railroad's future freight market. Volume II. Final report 1 Jul 74--30 Apr 76  

SciTech Connect

The study forecasts the freight market of the Alaska Railroad (ARR) due to natural resource development and pipeline construction in Alaska. This has been done through: (a) evaluation of these resources with commercial development potential which could generate rail service demand; and (b) development and analysis of petroleum development schedules and pipeline construction scenarios. Detailed price and market analysis of Alaskan coal and copper resources were performed. Forecasts of ARR traffic were based upon econometric relationships between the Alaskan economy and petroleum royalties and construction expenditures. Volume Two inventories Alaskan natural resources. It includes detailed coal and copper evaluations, describes petroleum related growth and development in Alaska, and contains schedules of petroleum production, employment, state revenues, and pipeline construction employment by scenario.

Hillegas, B.D.; Pernela, L.M.; Lewis, D.C.

1976-06-01T23:59:59.000Z

195

The Alaska railroad's future freight market. Volume I. Final report, 1 Jul 1974--30 Apr 1976  

SciTech Connect

The study forecasts the freight market of The Alaska Railroad (ARR) due to natural resource development and pipeline construction in Alaska. This has been done through: (a) evaluation of those resources with commercial development potential which could generate rail service demand; and (b) development and analysis of petroleum development schedules and pipeline construction scenarios. Detailed price and market analyses of Alaskan coal and copper resources were performed. Forecasts of ARR traffic were based upon econometric relationship between the Alaska economy and petroleum royalties and construction expenditures. Volume One contains the Executive Summary; it describes the study scope and methodology, and highlights ARR's recent experiences, the Alaskan economy, and resource development status.

Hillegas, B.D.; Pernela, L.M.; Lewis, D.C.

1976-06-01T23:59:59.000Z

196

Results of the radiological survey at the Niagara-Mohawk property, Railroad Avenue, Colonie, New York (AL218)  

SciTech Connect

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The Niagara-Mohawk property on Railroad Avenue in Colonie, New York, was the subject of a radiological investigation initiated June 11, 1987. This commercial property is an irregularly shaped lot partially occupied by an electric power substation and associated transmission lines. Portions of the property that were swampy and heavily vegetated were inaccessible to the survey team. There are no buildings on the property. A diagram showing the approximate boundaries and the 15-m grid network established for measurements on the property is shown. The lot included in the radiological survey was /approximately/45 m wide by 246 m deep. Two views of the property are shown. 13 refs., 6 figs., 4 tabs.

Marley, J.L.; Carrier, R.F.

1987-12-01T23:59:59.000Z

197

EDS V25 containment vessel explosive qualification test report.  

SciTech Connect

The V25 containment vessel was procured by the Project Manager, Non-Stockpile Chemical Materiel (PMNSCM) as a replacement vessel for use on the P2 Explosive Destruction Systems. It is the first EDS vessel to be fabricated under Code Case 2564 of the ASME Boiler and Pressure Vessel Code, which provides rules for the design of impulsively loaded vessels. The explosive rating for the vessel based on the Code Case is nine (9) pounds TNT-equivalent for up to 637 detonations. This limit is an increase from the 4.8 pounds TNT-equivalency rating for previous vessels. This report describes the explosive qualification tests that were performed in the vessel as part of the process for qualifying the vessel for explosive use. The tests consisted of a 11.25 pound TNT equivalent bare charge detonation followed by a 9 pound TNT equivalent detonation.

Rudolphi, John Joseph

2012-04-01T23:59:59.000Z

198

Reactor pressure vessel with forged nozzles  

DOE Patents (OSTI)

Inlet nozzles for a gravity-driven cooling system (GDCS) are forged with a cylindrical reactor pressure vessel (RPV) section to which a support skirt for the RPV is attached. The forging provides enhanced RPV integrity around the nozzle and substantial reduction of in-service inspection costs by eliminating GDCS nozzle-to-RPV welds.

Desai, Dilip R. (Fremont, CA)

1993-01-01T23:59:59.000Z

199

Design of a smart, survivable sensor system for enhancing the safe and secure transportation of hazardous or high-value cargo on railroads  

SciTech Connect

An application of smart sensor technology developed by Sandia National Laboratories for use in the safe and secure transportation of high value of hazardous materials is proposed for a railroad application. The Green Box would be capable of surviving most typical railroad accidents. In an accident, the system would send a distress signal notifying authorities of the location and condition of the cargo; permitting them to respond in the most effective manner. The concept proposes a strap-on sensor package, the Green Box, that could be attached to any railroad car or cargo container. Its primary purpose is to minimize the number, severity and consequences of accidents and to reduce losses due to theft. The system would also be capable of recognizing component failure conditions, notifying the operators and logging sensor data for use in directing preventative maintenance. The modular implementation, which facilitates system integration in a number of applications including the Advanced Train Control System (ACTS), is discussed. The methodology for determining the environmental specification for accident survivability is presented. A test plan for evaluating hardware performance in both normal operating and accident conditions is described.

Hogan, J.R.; Rey, D.; Faas, S.E.

1994-01-01T23:59:59.000Z

200

MAAP5 BWR Vessel Penetration and Ex-Vessel Equipment Model Enhancement Description  

Science Conference Proceedings (OSTI)

This report describes proposed enhancements to the Modular Accident Analysis Program (MAAP) vessel penetration and ex-vessel equipment model for BWR designs. MAAP is anEPRI-owned and -licensed computer program that simulates the operation of light water and heavy water moderated nuclear power plants for both current and advanced light water reactor (ALWR) designs.The report explores the manner in which the in-core instrument tubes would respond during severe core damage events that ...

2013-02-25T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

On the interactive 3D reconstruction of Iberian vessels  

Science Conference Proceedings (OSTI)

Reconstructing vessels from sherds is a complex task, specially for hand made pottery. That is the case of the Iberian vessels. The reconstruction process can be done in three steps: orientation of the sherd, computing the symmetry axis and detecting ...

F. J. Melero; J. C. Torres; A. Len

2003-11-01T23:59:59.000Z

202

Operating an Acoustic Doppler Current Profiler aboard a Container Vessel  

Science Conference Proceedings (OSTI)

Since October 1992 an acoustic Doppler current profiler (ADCP) has been in near-continuous operation on board a 118-m-long container vessel, the container motor vessel Oleander, which operates on a weekly schedule between Port Elizabeth, New ...

C. N. Flagg; G. Schwartze; E. Gottlieb; T. Rossby

1998-02-01T23:59:59.000Z

203

Project Trinidad: explosive excavation of railroad cuts 2 and 3 by mounding and directed blasting. Final technical report  

SciTech Connect

The objectives, design, and results of two explosive excavation experiments performed as the final phase of Project Trinidad, a comprehensive series of tests to determine the cratering properties of interbedded sandstones and shales, are summarized. The experiments were performed in September 1971 by the U.S. Army Engineer Waterways Experiment Station Explosive Excavation Research Laboratory. These final experiments were designed to excavate through- cuts for relocation of the Colorado and Wyoming Railroad at the Trinidad Dam and Lake Project. The first of the two experiments tested a charge array designed to break up material within a 19,000-yd/sup 3/ cut to facilitate later removal of the material by mechanical means. The concept tested was mounding, a blasting technique in which charges are positioned with respect to the horizontal ground surface rather than a vertical bench face. The results from this experiment confirmed the applicability of empirical scaling methods to the design of an array of deeply buried charges. The second experiment was a directed blasting detonation that was designed to produce a 30.000-yd/sup 3/ throughcut by cratering. This experiment tested a charge array design that had been developed by a combination of empirical scaling and kinematical methods. (auth)

Lattery, J.E.

1973-01-01T23:59:59.000Z

204

Materials Reliability Program: Reactor Pressure Vessel Integrity Primer (MRP-278)  

Science Conference Proceedings (OSTI)

This primer is based on two earlier Electric Power Research Institute (EPRI) reports: Reactor Vessel Embrittlement Management Handbook: A Handbook for Managing Reactor Vessel Embrittlement and Vessel Integrity (TR-101975-T2) and Primer: Fracture Mechanics in the Nuclear Power Industry (NP-5792-SR, Rev. 1). The information in those earlier reports has been updated extensively and focuses on todays reactor pressure vessel (RPV) embrittlement, integrity, and plant license renewal issues. This RPV integrity ...

2010-06-09T23:59:59.000Z

205

Responses of wintering humpback whales to vessel traffic  

Science Conference Proceedings (OSTI)

Responses of humpback whales to vessel traffic were monitored over two winter seasons during 19831984 in Maui

Gordon B. Bauer; Joseph R. Mobley; Louis M. Herman

1993-01-01T23:59:59.000Z

206

www.eia.gov  

U.S. Energy Information Administration (EIA)

Zip Code: 21. Contact information: (eg. Street Address, Building, Floor, Suite) 10. Type of Report (Check One): Form Approved Vessel Bunkering (Shipping & Boating):

207

Total Adjusted Sales of Residual Fuel Oil  

Annual Energy Outlook 2012 (EIA)

End Use: Total Commercial Industrial Oil Company Electric Power Vessel Bunkering Military All Other Period: Annual Download Series History Download Series History Definitions,...

208

Blood vessel segmentation methodologies in retinal images - A survey  

Science Conference Proceedings (OSTI)

Retinal vessel segmentation algorithms are a fundamental component of automatic retinal disease screening systems. This work examines the blood vessel segmentation methodologies in two dimensional retinal images acquired from a fundus camera and a survey ... Keywords: Blood vessel segmentation, Image segmentation, Medical imaging, Retinal images, Retinopathy, Survey

M. M. Fraz; P. Remagnino; A. Hoppe; B. Uyyanonvara; A. R. Rudnicka; C. G. Owen; S. A. Barman

2012-10-01T23:59:59.000Z

209

Investigation of impulsively loaded pressure vessels  

SciTech Connect

Explosion containment vessels for containing from 2,000 to 3,000 five ton nuclear explosions are considered. Analysis methods appear adequate and lowest weights using the most advanced materials available in the next five years are projected.None of these materials can be fabricated today and all require extensive development. Present material technology limits the choice of materials and defines the weight. The addition of safety factors and fixtures (nozzles, etc.) will add to this weight considerably, and may well radically alter the vessel response. Improvements in the strength weight ratios of metals and glasses over those considered in this report do not appear reasonable at this time. Winding schemes to utilize the high strength of steel wires and somehow maintain a reasonable thickness appear to offer the most promise. A `ductile` beryllium would of course offer vast improvement, but no indications that this is being developed have appeared and all presently known beryllium is much too brittle.

Brown, N.; Cornwell, R.; Hanner, D.; Leichter, H.; Mohr, P.

1963-10-15T23:59:59.000Z

210

Photoacoustic removal of occlusions from blood vessels  

DOE Patents (OSTI)

Partial or total occlusions of fluid passages within the human body are removed by positioning an array of optical fibers in the passage and directing treatment radiation pulses along the fibers, one at a time, to generate a shock wave and hydrodynamics flows that strike and emulsify the occlusions. A preferred application is the removal of blood clots (thrombin and embolic) from small cerebral vessels to reverse the effects of an ischemic stroke. The operating parameters and techniques are chosen to minimize the amount of heating of the fragile cerebral vessel walls occurring during this photo acoustic treatment. One such technique is the optical monitoring of the existence of hydrodynamics flow generating vapor bubbles when they are expected to occur and stopping the heat generating pulses propagated along an optical fiber that is not generating such bubbles.

Visuri, Steven R. (Livermore, CA); Da Silva, Luiz B. (Danville, CA); Celliers, Peter M. (Berkeley, CA); London, Richard A. (Orinda, CA); Maitland, IV, Duncan J. (Lafayette, CA); Esch, Victor C. (San Francisco, CA)

2002-01-01T23:59:59.000Z

211

Nuclear reactor pressure vessel support system  

DOE Patents (OSTI)

A support system for nuclear reactor pressure vessels which can withstand all possible combinations of stresses caused by a postulated core disrupting accident during reactor operation. The nuclear reactor pressure vessel is provided with a flange around the upper periphery thereof, and the flange includes an annular vertical extension formed integral therewith. A support ring is positioned atop of the support ledge and the flange vertical extension, and is bolted to both members. The plug riser is secured to the flange vertical extension and to the top of a radially outwardly extension of the rotatable plug. This system eliminates one joint through which fluids contained in the vessel could escape by making the fluid flow path through the joint between the flange and the support ring follow the same path through which fluid could escape through the plug risers. In this manner, the sealing means to prohibit the escape of contained fluids through the plug risers can also prohibit the escape of contained fluid through the securing joint.

Sepelak, George R. (McMurray, PA)

1978-01-01T23:59:59.000Z

212

Vehicular Storage of Hydrogen in Insulated Pressure Vessels  

DOE Green Energy (OSTI)

This paper describes the development of an alternative technology for storing hydrogen fuel onboard automobiles. Insulated pressure vessels are cryogenic-capable pressure vessels that can accept cryogenic liquid fuel, cryogenic compressed gas or compressed gas at ambient temperature. Insulated pressure vessels offer advantages over conventional H{sub 2} storage approaches. Insulated pressure vessels are more compact and require less carbon fiber than GH{sub 2} vessels. They have lower evaporative losses than LH{sub 2} tanks, and are much lighter than metal hydrides. After outlining the advantages of hydrogen fuel and insulated pressure vessels, the paper describes the experimental and analytical work conducted to verify that insulated pressure vessels can be used safely for vehicular H{sub 2} storage. The paper describes tests that have been conducted to evaluate the safety of insulated pressure vessels. Insulated pressure vessels have successfully completed a series of DOT, ISO and SAE certification tests. A draft procedure for insulated pressure vessel certification has been generated to assist in a future commercialization of this technology. An insulated pressure vessel has been installed in a hydrogen fueled truck and it is currently being subjected to extensive testing.

Aceves, S M; Berry, G D; Martinez-Frias, J; Espinosa-Loza, F

2005-01-03T23:59:59.000Z

213

Confinement Vessel Assay System: Calibration and Certification Report  

SciTech Connect

Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1 to 2 inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the vessels. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of SNM in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le} 100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The system was calibrated in three different mass regions (low, medium, and high) to cover the entire plutonium mass range that will be assayed. The low mass calibration and medium mass calibration were verified for material positioned in the center of an empty vessel. The systematic uncertainty due to position bias was estimated using an MCNPX model to simulate the response of the system to material localized at various points along the inner surface of the vessel. The background component due to cosmic ray spallation was determined by performing measurements of an empty vessel and comparing to measurements in the same location with no vessel present. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements of CVs before and after cleanout.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Gomez, Cipriano [Retired CMR-OPS: OPERATIONS; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-17T23:59:59.000Z

214

Adjusted Distillate Fuel Oil Sales for Residential Use  

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

End Use/ Product: Residential - Distillate Fuel Oil Residential - No. 1 Residential - No. 2 Residential - Kerosene Commercial - Distillate Fuel Oil Commercial - No. 1 Distillate Commercial - No. 2 Distillate Commercial - No. 2 Fuel Oil Commercial - Ultra Low Sulfur Diesel Commercial - Low Sulfur Diesel Commercial - High Sulfur Diesel Commercial - No. 4 Fuel Oil Commercial - Residual Fuel Oil Commercial - Kerosene Industrial - Distillate Fuel Oil Industrial - No. 1 Distillate Industrial - No. 2 Distillate Industrial - No. 2 Fuel Oil Industrial - Low Sulfur Diesel Industrial - High Sulfur Diesel Industrial - No. 4 Fuel Oil Industrial - Residual Fuel Oil Industrial - Kerosene Farm - Distillate Fuel Oil Farm - Diesel Farm - Other Distillate Farm - Kerosene Electric Power - Distillate Fuel Oil Electric Power - Residual Fuel Oil Oil Company Use - Distillate Fuel Oil Oil Company Use - Residual Fuel Oil Total Transportation - Distillate Fuel Oil Total Transportation - Residual Fuel Oil Railroad Use - Distillate Fuel Oil Vessel Bunkering - Distillate Fuel Oil Vessel Bunkering - Residual Fuel Oil On-Highway - No. 2 Diesel Military - Distillate Fuel Oil Military - Diesel Military - Other Distillate Military - Residual Fuel Oil Off-Highway - Distillate Fuel Oil Off-Highway - Distillate F.O., Construction Off-Highway - Distillate F.O., Non-Construction All Other - Distillate Fuel Oil All Other - Residual Fuel Oil All Other - Kerosene Period:

215

Annabella: a North American coasting vessel  

E-Print Network (OSTI)

The coasting schooner Annabella was built at Port Elizabeth, New Jersey, in 1834. Originally constructed as a sloop, the vessel was built specifically for transporting raw materials such as cordwood, brick, coal, and perishables to markets and industries along the northeast United States coast. During its lengthy 50-year career, ownership of Annabella was transferred among numerous merchants in Philadelphia, Plymouth, Boston, and, finally, Cape Neddick, Maine. The vessel was finally abandoned on October 17, 1885, in the Cape Neddick River, in Cape Neddick, Maine, beyond repair and no longer fit for service. This study covers the following topics: the 1994 and 1995 archaeological field seasons, including hull and artifact descriptions and analyses; the history of the coasting trade and the cordwood industry during the 19th century in the vicinity of southern Maine; and an analysis of historical documents that detail the history ofannabella. Toward these ends, this thesis will present a description and analysis of a type of craft that once was common to the eastern seaboard, including discussions about how the craft was designed and built for transporting specific cargoes, and how this ship may be representative of maritime activities and shipbuilding technologies of the 19th century

Claesson, Stefan Hans

1998-01-01T23:59:59.000Z

216

Engineering Test Reactor (ETR) Vessel Relocated after 50 years.  

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

Printer Friendly Printer Friendly Engineering Test Reactor (ETR) Vessel Relocated Engineering Test Reactor Vessel Pre-startup 1957 Click on image to enlarge. Image 1 of 5 Gantry jacks attached to ETR vessel. Initial lift starts. - Click on image to enlarge. Image 2 of 5 ETR vessel removed from substructure. Vessel lifted approximately 40 ft. - Click on image to enlarge. On Monday, September 24, 2007 the Engineering Test Reactor (ETR) vessel was removed from its location and delivered to the Idaho CERCLA Disposal Facility (ICDF). The long history of the ETR began for this water-cooled reactor with its start up in 1957, after taking only 2 years to build. According to "Proving the Principles," by Susan M. Stacy: When the Engineering Test Reactor started up at the Test Reactor Area in

217

Application of Computational Physics: Blood Vessel Constrictions and Medical Infuses  

E-Print Network (OSTI)

Application of computation in many fields are growing fast in last two decades. Increasing on computation performance helps researchers to understand natural phenomena in many fields of science and technology including in life sciences. Computational fluid dynamic is one of numerical methods which is very popular used to describe those phenomena. In this paper we propose moving particle semi-implicit (MPS) and molecular dynamics (MD) to describe different phenomena in blood vessel. The effect of increasing the blood pressure on vessel wall will be calculate using MD methods, while the two fluid blending dynamics will be discussed using MPS. Result from the first phenomenon shows that around 80% of constriction on blood vessel make blood vessel increase and will start to leak on vessel wall, while from the second phenomenon the result shows the visualization of two fluids mixture (drugs and blood) influenced by ratio of drugs debit to blood debit. Keywords: molecular dynamic, blood vessel, fluid dynamic, moving particle semi implicit.

Suprijadi; Mohamad Rendi; Petrus Subekti; Sparisoma Viridi

2013-12-14T23:59:59.000Z

218

International Hydrogen Fuel and Pressure Vessel Forum 2010 Proceedings  

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

challenges in harmonizing test protocols and requirements for compressed natural gas (CNG), hydrogen, and CNG-hydrogen (HCNG) blend pressure vessels and to define next steps for...

219

A Xenon Condenser with a Remote Liquid Storage Vessel  

E-Print Network (OSTI)

We describe the design and operation of a system for xenon liquefaction in which the condenser is separated from the liquid storage vessel. The condenser is cooled by a pulse tube cryocooler, while the vessel is cooled only by the liquid xenon itself. This arrangement facilitates liquid particle detector research by allowing easy access to the upper and lower flanges of the vessel. We find that an external xenon gas pump is useful for increasing the rate at which cooling power is delivered to the vessel, and we present measurements of the power and efficiency of the apparatus.

Slutsky, S; Breuer, H; Dobi, A; Hall, C; Langford, T; Leonard, D; Kaufman, L J; Strickland, V; Voskanian, N

2009-01-01T23:59:59.000Z

220

A Xenon Condenser with a Remote Liquid Storage Vessel  

E-Print Network (OSTI)

We describe the design and operation of a system for xenon liquefaction in which the condenser is separated from the liquid storage vessel. The condenser is cooled by a pulse tube cryocooler, while the vessel is cooled only by the liquid xenon itself. This arrangement facilitates liquid particle detector research by allowing easy access to the upper and lower flanges of the vessel. We find that an external xenon gas pump is useful for increasing the rate at which cooling power is delivered to the vessel, and we present measurements of the power and efficiency of the apparatus.

S. Slutsky; Y. -R. Yen; H. Breuer; A. Dobi; C. Hall; T. Langford; D. S. Leonard; L. J. Kaufman; V. Strickland; N. Voskanian

2009-07-13T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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to obtain the most current and comprehensive results.


221

Reactor Pressure Vessel Task of Light Water Reactor Sustainability...  

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

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment Reactor Pressure...

222

Damage analysis of composite pressure vessels using acoustic emission monitoring.  

E-Print Network (OSTI)

??Composite pressure vessels (CPVs) fabricated using a metal or plastic liner under a composite structural skin are commonly used for natural gas storage on road (more)

Chou, H

2012-01-01T23:59:59.000Z

223

Fuel Oil and Kerosene Sales - Energy Information Administration  

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

Petrolem Reports Petrolem Reports Fuel Oil and Kerosene Sales With Data for 2012 | Release Date: November 15, 2013 | Next Release Date: November 2014 Previous Issues Year: 2012 2011 2010 2009 2008 2007 2006 2005 2004 2003 2002 2001 2000 1999 1998 1997 1996 1995 Go The Fuel Oil and Kerosene Sales 2012 report provides information, illustrations and State-level statistical data on end-use sales of kerosene; No.1, No. 2, and No. 4 distillate fuel oil; and residual fuel oil. State-level kerosene sales include volumes for residential, commercial, industrial, farm, and all other uses. State-level distillate sales include volumes for residential, commercial, industrial, oil company, railroad, vessel bunkering, military, electric utility, farm, on-highway, off-highway construction, and other uses. State-level residual fuel sales

224

Fatigue analysis of stringer to floor beam connections in through plate girder and through truss railroad bridges  

E-Print Network (OSTI)

The objective of this thesis is to determine fatigue stresses in the stringer to floor beam connections of through plate girder (TPG) and through truss (TT) bridges in order to predict failure. Field observations by the Association of American Railroads (AAR) indicate failure in the stringer to floor beam connections of both the TPG and TT bridges, although a higher frequency of failure appears in the TT bridges. Accordingly, this study includes 1) creating analytical models for the TPG and TT bridges, 2) determining member internal forces, 3) developing force envelopes, 4) determining maximum internal stresses, and 5) comparing these results to field observations. First, bridge models for the TPG and TT bridge were assembled using a finite element analysis program in order to evaluate member internal forces. The TPG bridge model was taken from the plans of an existing bridge designed in 1912 and located near TX Highway 21 between College Station and Caldwell, TX. The TT bridge model was taken from the plans of an existing bridge designed in 1902 in the Chicago Office of the American Bridge Company. Next, a finite element analysis was conducted to obtain member internal forces. The resulting forces were compiled to create axial load, shear force, and moment envelopes. These envelopes were constructed to provide the magnitudes and location of the maximum forces required for analysis. These forces were also used to develop maximum tensile stresses for the rivets in the floor beams. After examining the results, the following conclusions were drawn. Axial load was predicted to be a source of higher failure frequency within TT bridges versus TPG bridges. Lower chord deformation in the TT bridge caused elongation of the floor system that, in turn, produced axial loads in the bridge members. The TPG bridge members, however, carried no axial load. Shear force was not predicted to be a contributing factor for increased connection failure rates in the TT bridges as compared to the TPG bridges, but bending moment was. This result, however, was sensitive to the degree of fixity in the stringer to floor beam connection.

Evans, Leslie Virginia

1999-01-01T23:59:59.000Z

225

Closure Report for Corrective Action Unit 539: Areas 25 and 26 Railroad Tracks Nevada National Security Site, Nevada with ROTC-1, Revision 0  

SciTech Connect

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 539: Areas 25 and 26 Railroad Tracks, Nevada National Security Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 539 are located within Areas 25 and 26 of the Nevada National Security Site. Corrective Action Unit 539 comprises the following CASs: 25-99-21, Area 25 Railroad Tracks 26-99-05, Area 26 Railroad Tracks The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CASs within CAU 539 were met. To achieve this, the following actions were performed: Reviewed documentation on historical and current site conditions, including the concentration and extent of contamination. Conducted radiological walkover surveys of railroad tracks in both Areas 25 and 26. Collected ballast and soil samples and calculated internal dose estimates for radiological releases. Collected in situ thermoluminescent dosimeter measurements and calculated external dose estimates for radiological releases. Removed lead bricks as potential source material (PSM) and collected verification samples. Implemented corrective actions as necessary to protect human health and the environment. Properly disposed of corrective action and investigation wastes. Implemented an FFACO use restriction (UR) for radiological contamination at CAS 25-99-21. The approved UR form and map are provided in Appendix F and will be filed in the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Facility Information Management System; the FFACO database; and the NNSA/NSO CAU/CAS files. From November 29, 2010, through May 2, 2011, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 539: Areas 25 and 26 Railroad Tracks, Nevada Test Site, Nevada. The purposes of the activities as defined during the data quality objectives process were as follows: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels (FALs) to determine COCs for CAU 539. Assessment of the data generated from closure activities revealed the following: At CAS 26-99-05, the total effective dose for radiological releases did not exceed the FAL of 25 millirem per Industrial Area year. Potential source material in the form of lead bricks was found at three locations. A corrective action of clean closure was implemented at these locations, and verification samples indicated that no further action is necessary. At CAS 25-99-21, the total effective dose for radiological releases exceeds the FAL of 25 millirem per Industrial Area year. Potential source material in the form of lead bricks was found at eight locations. A corrective action was implemented by removing the lead bricks and soil above FALs at these locations, and verification samples indicated that no further action is necessary. Pieces of debris with high radioactivity were identified as PSM and remain within the CAS boundary. A corrective action of closure in place with a UR was implemented at this CAS because closure activities showed evidence of remaining soil contamination and radioactive PSM. Future land use will be restricted from surface and intrusive activities. Closure activities generated waste streams consisting of industrial solid waste, recyclable materials, low-level radioactive waste, and mixed low-level radioactive waste. Wastes were disposed of in the appropriate onsite landfills. The NNSA/NSO prov

Mark Kauss

2011-06-01T23:59:59.000Z

226

Retinal vessel segmentation using multiwavelet kernels and multiscale hierarchical decomposition  

Science Conference Proceedings (OSTI)

We propose a comprehensive method for segmenting the retinal vasculature in fundus camera images. Our method does not require preprocessing and training and can therefore be used directly on different images sets. We enhance the vessels using matched ... Keywords: Matched filter, Multiscale hierarchical decomposition, Multiwavelet, Retinal images, Segmentation, Vessel detection

Yangfan Wang; Guangrong Ji; Ping Lin; Emanuele Trucco

2013-08-01T23:59:59.000Z

227

Core Vessel Insert Handling Robot for the Spallation Neutron Source  

Science Conference Proceedings (OSTI)

The Spallation Neutron Source provides the world's most intense pulsed neutron beams for scientific research and industrial development. Its eighteen neutron beam lines will eventually support up to twenty-four simultaneous experiments. Each beam line consists of various optical components which guide the neutrons to a particular instrument. The optical components nearest the neutron moderators are the core vessel inserts. Located approximately 9 m below the high bay floor, these inserts are bolted to the core vessel chamber and are part of the vacuum boundary. They are in a highly radioactive environment and must periodically be replaced. During initial SNS construction, four of the beam lines received Core Vessel Insert plugs rather than functional inserts. Remote replacement of the first Core Vessel Insert plug was recently completed using several pieces of custom-designed tooling, including a highly complicated Core Vessel Insert Robot. The design of this tool are discussed.

Graves, Van B [ORNL; Dayton, Michael J [ORNL

2011-01-01T23:59:59.000Z

228

Nuclear reactor construction with bottom supported reactor vessel  

DOE Patents (OSTI)

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

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

1987-01-01T23:59:59.000Z

229

Unity, Justice and Protection: The Colored Trainmen of America's Struggle to End Jim Crow in the American Railroad Industry [and Elsewhere  

E-Print Network (OSTI)

The Colored Trainmen of America (CTA) actively challenged Jim Crow policies on the job and in the public sphere between the 1930s and 1950s. In response to lingering questions concerning the relationship between early black labor activism and civil rights protest, this study goes beyond both local lure and cursory research. This study examines the Colored Trainmen's major contributions to the advancement of African Americans. It also provides context for some of the organization's shortcomings in both realms. On the job the African American railroad workers belonging to the CTA fought valiantly to receive the same opportunities for professional growth and development as whites working in the operating trades of the railroad industry. In the public sphere, these men collectively protested second-class services and accommodations both on and off the clock. Neither their agenda, the scope of their activities, nor their influence was limited to the railroad lines the members of the CTA operated within the Gulf Coast region. The CTA belonged to a progressive coalition comprised of four other powerful independent African American labor unions committed to unyielding labor activism and the toppling of Jim Crow. Together, they all worked to effectuate meaningful social change in partnership with national civil rights attorney Charles H. Houston. Houston's experience and direction, coupled with the CTA's dedicated membership and willingness to challenge authority, created considerable momentum in movements aimed at toppling racial inequality in the workplace and elsewhere. Like most of their predecessors, the CTA's struggle for advancement fits within a continuum of successive challenges to economic exploitation and racial inequality. No single person or organization can take full credit for ending segregation or achieving equality. Many who remain nameless and faceless contributed and sacrificed. This study not only chronicles the contribution of a relatively unsung African American labor organization that waged war against Jim Crow on two different fronts, it also pays homage to a few more individuals who made a difference in the lives of an entire race of people during the course of a bitterly contested, never-ending struggle for racial equality in the United States of America during the twentieth century.

James, Ervin

2012-08-01T23:59:59.000Z

230

Welding the AT-400A Containment Vessel  

SciTech Connect

Early in 1994, the Department of Energy assigned Sandia National Laboratories the responsibility for designing and providing the welding system for the girth weld for the AT-400A containment vessel. (The AT-400A container is employed for the shipment and long-term storage of the nuclear weapon pits being returned from the nation's nuclear arsenal.) Mason Hanger Corporation's Pantex Plant was chosen to be the production facility. The project was successfully completed by providing and implementing a turnkey welding system and qualified welding procedure at the Pantex Plant. The welding system was transferred to Pantex and a pilot lot of 20 AT-400A containers with W48 pits was welded in August 1997. This document is intended to bring together the AT-400A welding system and product (girth weld) requirements and the activities conducted to meet those requirements. This document alone is not a complete compilation of the welding development activities but is meant to be a summary to be used with the applicable references.

Brandon, E.

1998-11-01T23:59:59.000Z

231

Welding the AT-400A Containment Vessel  

SciTech Connect

Early in 1994, the Department of Energy assigned Sandia National Laboratories the responsibility for designing and providing the welding system for the girth weld for the AT-400A containment vessel. (The AT-400A container is employed for the shipment and long-term storage of the nuclear weapon pits being returned from the nation's nuclear arsenal.) Mason Hanger Corporation's Pantex Plant was chosen to be the production facility. The project was successfully completed by providing and implementing a turnkey welding system and qualified welding procedure at the Pantex Plant. The welding system was transferred to Pantex and a pilot lot of 20 AT-400A containers with W48 pits was welded in August 1997. This document is intended to bring together the AT-400A welding system and product (girth weld) requirements and the activities conducted to meet those requirements. This document alone is not a complete compilation of the welding development activities but is meant to be a summary to be used with the applicable references.

Brandon, E.

1998-11-01T23:59:59.000Z

232

Confinement Vessel Assay System: Design and Implementation Report  

SciTech Connect

Los Alamos National Laboratory has a number of spherical confinement vessels remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1- to 2-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the vessels. We have developed a neutron assay system for the purposes of Materials Control and Accountability (MC&A) measurements of the vessel prior to and after cleanout. We present our approach to confronting the challenges in designing, building, and testing such a system. The system was designed to meet a set of functional and operational requirements. A Monte Carlo model was developed to aid in optimizing the detector design as well as to predict the systematic uncertainty associated with confinement vessel measurements. Initial testing was performed to optimize and determine various measurement parameters, and then the system was characterized using {sup 252}Cf placed a various locations throughout the measurement system. Measurements were also performed with a {sup 252}Cf source placed inside of small steel and HDPE shells to study the effect of moderation. These measurements compare favorably with their MCNPX model equivalent, making us confident that we can rely on the Monte Carlo simulation to predict the systematic uncertainty due to variations in response to material that may be localized at different points within a vessel.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Gomez, Cipriano D. [Retired CMR-OPS: OPERATIONS; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-18T23:59:59.000Z

233

Start-up control system and vessel for LMFBR  

DOE Patents (OSTI)

A reflux condensing start-up system comprises a steam generator, a start-up vessel connected parallel to the steam generator, a main steam line connecting steam outlets of the steam generator and start-up vessel to a steam turbine, a condenser connected to an outlet of the turbine and a feedwater return line connected between the condenser and inlets of the steam generator and start-up vessel. The start-up vessel has one or more heaters at the bottom thereof for heating feedwater which is supplied over a start-up line to the start-up vessel. Steam is thus generated to pressurize the steam generator before the steam generator is supplied with a heat transfer medium, for example liquid sodium, in the case of a liquid metal fast breeder reactor. The start-up vessel includes upper and lower bulbs with a smaller diameter mid-section to act as water and steam reservoirs. The start-up vessel can thus be used not only in a start-up operation but as a mixing tank, a water storage tank and a level control at low loads for controlling feedwater flow.

Durrant, Oliver W. (Akron, OH); Kakarala, Chandrasekhara R. (Clinton, OH); Mandel, Sheldon W. (Galesburg, IL)

1987-01-01T23:59:59.000Z

234

Start-up control system and vessel for LMFBR  

DOE Patents (OSTI)

A reflux condensing start-up system includes a steam generator, a start-up vessel connected parallel to the steam generator, a main steam line connecting steam outlets of the steam generator and start-up vessel to a steam turbine, a condenser connected to an outlet of the turbine and a feedwater return line connected between the condenser and inlets of the steam generator and start-up vessel. The start-up vessel has one or more heaters at the bottom thereof for heating feedwater which is supplied over a start-up line to the start-up vessel. Steam is thus generated to pressurize the steam generator before the steam generator is supplied with a heat transfer medium, for example liquid sodium, in the case of a liquid metal fast breeder reactor. The start-up vessel includes upper and lower bulbs with a smaller diameter mid-section to act as water and steam reservoirs. The start-up vessel can thus be used not only in a start-up operation but as a mixing tank, a water storage tank and a level control at low loads for controlling feedwater flow.

Durrant, Oliver W. (Akron, OH); Kakarala, Chandrasekhara R. (Clinton, OH); Mandel, Sheldon W. (Galesburg, IL)

1987-01-01T23:59:59.000Z

235

Thermal Expansion Coefficient of Steels Used in LWR Vessels  

Science Conference Proceedings (OSTI)

Because of the impact that melt relocation and vessel failure have on subsequent progression and associated consequences of a Light Water Reactor (LWR) accident, it is important to accurately predict the heat-up and relocation of materials within the reactor vessel and heat transfer to and from the reactor vessel. Accurate predictions of such heat transfer phenomena require high temperature thermal properties. However, a review of vessel and structural steel material properties in severe accident analysis codes reveals that the required high temperature material properties are extrapolated with little, if any, data above 700C. To reduce uncertainties in predictions relying upon this extrapolated high temperature data, new thermal expansion data were obtained using pushrod dilatometry techniques for two metals used in LWR vessels: SA 533 Grade B, Class 1 (SA533B1) low alloy steel, which is used to fabricate most US LWR reactor vessels; and Type 304 Stainless Steel (SS304), which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data and compares it to existing, lower temperature data in the literature.

Joshua E. Daw; Joy L. Rempe; Darrell L. Knudson; John C. Crepeau

2008-05-01T23:59:59.000Z

236

High temperature thermal properties for metals used in LWR vessels  

Science Conference Proceedings (OSTI)

Because of the impact that melt relocation and vessel failure has on subsequent progression and associated consequences of an Light Water Reactor (LWR) accident, it is important to accurately predict the heatup and relocation of materials within the reactor vessel and heat transfer to and from the reactor vessel. Accurate predictions of such heat transfer phenomena require high temperature thermal properties. However, a review of vessel and structural steel material properties in severe accident analysis codes reveals that the required high temperature material properties are extrapolated, with little if any, data above 700 C. To reduce uncertainties in predictions relying upon this extrapolated high temperature data, INL obtained data using laser-flash thermal diffusivity techniques for two metals used in LWR vessels: SA533B1 carbon steel, which is used to fabricate most US LWR reactor vessels; and SS304, which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data, compares it to existing data in the literature, and provides recommended correlations for thermal properties based on this data.

Joy L. Rempe

2008-01-01T23:59:59.000Z

237

An Enhanced In-Vessel Core Catcher for Improving In-Vessel Retention Margins  

SciTech Connect

In-vessel retention (IVR) of core melt that may relocate to the lower head of a reactor vessel is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for several advanced light water reactors. A U.S.-Korean International Nuclear Energy Research Initiative project has been initiated to explore design enhancements that could increase the margin for IVR for advanced reactors with higher power levels [up to 1500 MW(electric)]. As part of this effort, an enhanced in-vessel core catcher is being designed and evaluated. To reduce cost and simplify manufacture and installation, this new core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. If needed, the core catcher can be manufactured with holes to accommodate lower head penetrations. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary). The first is a base material that has the capability to support and contain the mass of core materials that may relocate during a severe accident; the second is an oxide coating on top of the base material, which resists interactions with high-temperature core materials; and the third is an optional coating on the bottom side of the base material to protect it from oxidation during the lifetime of the reactor. This paper summarizes results from the invessel core catcher design and evaluation efforts, focusing on recently obtained results from materials interaction tests and prototypic testing activities.

Joy L. Rempe

2005-11-01T23:59:59.000Z

238

Pressure vessel reliability as a function of allowable stress  

SciTech Connect

From Winter meeting of American Society of Mechanical Engineers; Detroit, Michigan, USA (11 Nov 1973). The probability of failure corresponding to specified levels of allowable design stress was calculated for pressure vessels designed in accordance with the ASME Boiler and Pressure Vessel Code. The analysis was performed for maximum shear stress failure and for cyclic stress failure. The significance of such failure prediction is ddscussed and a rationale for selecting an allowable stress is presented. Examples are presented that demonstrate the estimation of vessel failure probability as a function of load variation, strength variation, and design safety factor. (auth)

Arnold, H.G.

1972-01-01T23:59:59.000Z

239

Float level switch for a nuclear power plant containment vessel  

DOE Patents (OSTI)

This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel. 1 figures.

Powell, J.G.

1993-11-16T23:59:59.000Z

240

Float level switch for a nuclear power plant containment vessel  

DOE Patents (OSTI)

This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel.

Powell, James G. (Clifton Park, NY)

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

242

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

243

Experiment Hazard Class 5.3 High Pressure Vessels  

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

3 High Pressure Vessels 3 High Pressure Vessels Applicability This hazard classification applies to working with pressure vessels and systems. Other hazard classifications and associated controls may apply to experiments in this hazard class. Experiment Category Experiments involving previously reviewed hazard controls are catergorized as medium risk experiments. Experiments involving new equipment, processes or materials, or modified hazard control schemes are categorized as high risk experiments. Hazard Control Plan Verification Statements Engineered Controls - The establishment of applicable controls in accordance with the (American Society of Mechanical Engineers) ASME Boiler and Pressure Code, ASME B.31 Piping Code and applicable federal, state, and local codes. Verify vessel is stampled with ASME Code Symbol or allowable

244

NETL: News Release - Ocean Research Vessel Returns with Undersea 'Treasure'  

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

23, 2002 23, 2002 Ocean Research Vessel Returns with Undersea 'Treasure' of Methane Hydrates Largest Amount of Marine Hydrate Core Ever Recovered - The R/V JOIDES Resolution - The R/V JOIDES Resolution VICTORIA, BRITISH COLUMBIA - An internationally funded ocean research vessel has returned to port after a two-month expedition off the Oregon coast, bringing with it the largest amount of marine methane hydrate core samples ever recovered for scientific study. The R/V JOIDES Resolution, the world's largest scientific drillship, docked at Victoria, British Columbia earlier this month and began offloading pressure vessels containing methane hydrates recovered 50 miles offshore of Oregon from an area known as Hydrate Ridge. The pressure vessels, each six feet long and four inches in diameter, will

245

Prediction of Vessel Icing for Near-Freezing Sea Temperatures  

Science Conference Proceedings (OSTI)

The operational NOAA categorical vessel icing algorithm is evaluated with regard to advances in understanding of the icing process and forecasting experience. When sea temperatures are <23C above the saltwater freezing point there is the ...

James E. Overland

1990-03-01T23:59:59.000Z

246

Analysis of the Catastrophic Rupture of a Pressure Vessel  

E-Print Network (OSTI)

occurred at a petroleum refinery in Chicago, killing 17 people and causing extensive property damage [1]. NBS was requested by the Occupational Safety and Health Administration (OSHA) to conduct an investigation into the failure of the pressure vessel that eyewitnesses identified as the initial source of the explosion and fire. This vessel was an amine absorber tower used to strip hydrogen sulfide from a process stream of propane and butane. The vessel was 18.8 m tall, 2.6 m in diameter, and constructed from 25 mm thick plates of type ASTM A516 Grade 70 steel. The investigation was complicated by the damage caused by the explosion and fire. The explosive force had been sufficient to propel the upper 14 m of the vessel a distance of 1 km from its original location,

unknown authors

1984-01-01T23:59:59.000Z

247

Experimental investigation of creep behavior of reactor vessel lower head  

SciTech Connect

The objective of the USNRC supported Lower Head Failure (LHF) Experiment Program at Sandia National Laboratories is to experimentally investigate and characterize the failure of the reactor pressure vessel (RPV) lower head due to the thermal and pressure loads of a severe accident. The experimental program is complemented by a modeling program focused on the development of a constitutive formulation for use in standard finite element structure mechanics codes. The problem is of importance because: lower head failure defines the initial conditions of all ex-vessel events; the inability of state-of-the-art models to simulate the result of the TMI-II accident (Stickler, et al. 1993); and TMI-II results suggest the possibility of in-vessel cooling, and creep deformation may be a precursor to water ingression leading to in-vessel cooling.

Chu, T.Y.; Pilch, M.; Bentz, J.H. [Sandia National Labs., Albuquerque, NM (United States); Behbahani, A. [NRC, Washington, DC (United States)

1998-03-01T23:59:59.000Z

248

Using SA508/533 for the HTGR Vessel Material  

SciTech Connect

This paper examines the influence of High Temperature Gas-cooled Reactor (HTGR) module power rating and normal operating temperatures on the use of SA508/533 material for the HTGR vessel system with emphasis on the calculated times at elevated temperatures approaching or exceeding ASME Code Service Limits (Levels B&C) to which the reactor pressure vessel could be exposed during postulated pressurized and depressurized conduction cooldown events over its design lifetime.

Larry Demick

2012-06-01T23:59:59.000Z

249

LNG Imports by Vessel into the U.S. Form | Department of Energy  

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

Vessel into the U.S. Form LNG Imports by Vessel into the U.S. Form Excel Version of LNG Imports by Vessel into the U.S. Form.xlsx PDF Version of LNG Imports by Vessel into the U.S....

250

Forum Agenda: International Hydrogen Fuel and Pressure Vessel Forum  

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

FORUM AGENDA FORUM AGENDA U.S. Department of Energy and Tsinghua University International Hydrogen Fuel and Pressure Vessel Forum Tsinghua University Beijing, PRC September 27 - 29, 2010 The U.S. Department of Energy (DOE) and Tsinghua University in Beijing co-hosted the International Hydrogen Fuel and Pressure Vessel Forum on September 27 - 29, 2010 in Beijing, China. High pressure vessel experts gathered to share lessons learned from CNG and hydrogen vehicle deployments, and to identify R&D needs to aid the global harmonization of regulations, codes and standards to enable the successful deployment of hydrogen and fuel cell technologies. Forum Objectives: * Address and share data and information on specific technical topics discussed at the workshop in

251

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research  

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

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program The Department of Energy's (DOE's) Light Water Reactor Sustainability (LWRS) Program is a five year effort that works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operation of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging

252

Tritium permeation and wall loading in the TFTR vacuum vessel  

SciTech Connect

The problems of tritium permeation through and loading of the TFTR vacuum vessel wall structural components are considered. A general analytical solution to the time dependent diffusion equation which takes into account the boundary conditions arising from the tritium filling gas as well as the source function associated with implanted energetic charge exchange tritium is presented. Expressions are derived for two quantities of interest: (1) the total amount of tritium leaving the outer surface of a particular vessel component as a function of time, and (2) the amount retained as a function of time. These quantities are evaluated for specific TFTR operating scenarios and outgassing modes. The results are that permeation through the vessel is important only for the bellows during discharge cleaning if the wall temperature rises above approximately 150/sup 0/C. At 250/sup 0/C, after 72 hours of discharge cleaning 195 Ci would be lost.

Cecchi, J.L.

1978-05-01T23:59:59.000Z

253

The Westinghouse Electric Corporation Reactor Vessel Radiation Surveillance Program  

Science Conference Proceedings (OSTI)

Westinghouse recognized that the disruption of the atomic lattice of metals by collision from energetic neutrons could alter the properties of the metals to such an extent that the changes could be of engineering significance. Furthermore, it was recognized that a physical-metallurgical phenomenon such as aging, both thermal and mechanical, also could alter the properties of a metal over its service life. Because of the potential changes in properties, reactor vessel radiation surveillance programs to monitor the effect of neutron radiation and other environmental factors on the reactor vessel materials during operational conditions over the life of the plant were initiated for Westinghouse plants with the insertion of reactor vessel material radiation surveillance capsules into the Yankee Atomic Company's Yankee Rowe plant in 1961.

Mayer, T.R.; Anderson, S.L.; Yanichko, S.E.

1983-01-01T23:59:59.000Z

254

Sterilization of fermentation vessels by ethanol/water mixtures  

DOE Patents (OSTI)

This invention is comprised of a method for sterilizing process fermentation vessels with a concentrated alcohol and water mixture integrated in a fuel alcohol or other alcohol production facility. Hot, concentrated alcohol is drawn from a distillation or other purification stage and sprayed into the empty fermentation vessels. This sterilizing alcohol/water mixture should be of a sufficient concentration, preferably higher than 12% alcohol by volume, to be toxic to undesirable microorganisms. Following sterilization, this sterilizing alcohol/water mixture can be recovered back into the same distillation or other purification stage from which it was withdrawn. The process of this invention has its best application in, but is not limited to, batch fermentation processes, wherein the fermentation vessels must be emptied, cleaned, and sterilized following completion of each batch fermentation process.

Wyman, C.E.

1991-03-20T23:59:59.000Z

255

Sterilization of fermentation vessels by ethanol/water mixtures  

DOE Patents (OSTI)

A method is described for sterilizing process fermentation vessels with a concentrated alcohol and water mixture integrated in a fuel alcohol or other alcohol production facility. Hot, concentrated alcohol is drawn from a distillation or other purification stage and sprayed into the empty fermentation vessels. This sterilizing alcohol/water mixture should be of a sufficient concentration, preferably higher than 12% alcohol by volume, to be toxic to undesirable microorganisms. Following sterilization, this sterilizing alcohol/water mixture can be recovered back into the same distillation or other purification stage from which it was withdrawn. The process of this invention has its best application in, but is not limited to, batch fermentation processes, wherein the fermentation vessels must be emptied, cleaned, and sterilized following completion of each batch fermentation process. 2 figs.

Wyman, C.E.

1999-02-09T23:59:59.000Z

256

Sterilization of fermentation vessels by ethanol/water mixtures  

DOE Patents (OSTI)

A method for sterilizing process fermentation vessels with a concentrated alcohol and water mixture integrated in a fuel alcohol or other alcohol production facility. Hot, concentrated alcohol is drawn from a distillation or other purification stage and sprayed into the empty fermentation vessels. This sterilizing alcohol/water mixture should be of a sufficient concentration, preferably higher than 12% alcohol by volume, to be toxic to undesirable microorganisms. Following sterilization, this sterilizing alcohol/water mixture can be recovered back into the same distillation or other purification stage from which it was withdrawn. The process of this invention has its best application in, but is not limited to, batch fermentation processes, wherein the fermentation vessels must be emptied, cleaned, and sterilized following completion of each batch fermentation process.

Wyman, Charles E. (Lakewood, CO)

1999-02-09T23:59:59.000Z

257

Fabrication of toroidal composite pressure vessels. Final report  

DOE Green Energy (OSTI)

A method for fabricating composite pressure vessels having toroidal geometry was evaluated. Eight units were fabricated using fibrous graphite material wrapped over a thin-walled aluminum liner. The material was wrapped using a machine designed for wrapping, the graphite material was impregnated with an epoxy resin that was subsequently thermally cured. The units were fabricated using various winding patterns. They were hydrostatically tested to determine their performance. The method of fabrication was demonstrated. However, the improvement in performance to weight ratio over that obtainable by an all metal vessel probably does not justify the extra cost of fabrication.

Dodge, W.G.; Escalona, A.

1996-11-24T23:59:59.000Z

258

DHCVIM: A direct heating containment vessel interactions module  

SciTech Connect

Models for prediction of direct containment heating phenomena as implemented in the DHCVIM computer module are described. The models were designed to treat thermal, chemical and hydrodynamic processes in the three regions of the Sandia National Laboratory Surtsey DCH test facility: the melt generator, cavity and vessel. The fundamental balance equations, along with constitutive relations are described. A combination of Eulerian treatment for the gas phase and Lagrangian treatment for the droplet phase is used in the modeling. Comparisons of calculations and DCH-1 test results are presented. Reasonable agreement is demonstrated for the vessel pressure rise, melt generator pressure decay and particle size distribution.

Ginsberg, T.; Tutu, N.K.

1987-01-01T23:59:59.000Z

259

Simulation of Diffusive Lithium Evaporation Onto the NSTX Vessel Walls  

Science Conference Proceedings (OSTI)

A model for simulating the diffusive evaporation of lithium into a helium filled NSTX vacuum vessel is described and validated against an initial set of deposition experiments. The DEGAS 2 based model consists of a three-dimensional representation of the vacuum vessel, the elastic scattering process, and a kinetic description of the evaporated atoms. Additional assumptions are required to account for deuterium out-gassing during the validation experiments. The model agrees with the data over a range of pressures to within the estimated uncertainties. Suggestions are made for more discriminating experiments that will lead to an improved model.

D.P. Stotler, C.H. Skinner, W.R. Blanchard, P.S. Krstic, H.W. Kugel, H. Schneider, and L.E. Zakharov

2010-12-09T23:59:59.000Z

260

BWRVIP-44-A: BWR Vessel and Internals Project: Underwater Weld Repair of Nickel Alloy Reactor Vessel Internals  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on BWR vessel and internals issues. This report describes work performed to qualify a flux-core welding process for use in repairing reactor internals at a water depth of up to 50 feet. A previous version of this report was published as BWRVIP-44 (EPRI report TR-108708). The current report, BWRVIP-44-A, incorporates changes proposed by the BWRVIP in response to U.S. Nuc...

2006-08-16T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

FIRE Vacuum Vessel Cost estimate and R&D needs  

E-Print Network (OSTI)

for remote handling mockup to be used for demonstration of : - Transfer cask docking - Divertor handling - FW and will serve as mockup for remote handling facility #12; tile handling / alignment - Recovery operations - Etc. #12;6 June 2001 FIRE Review: Vacuum Vessel

262

Angiotensin II receptors in rabbit renal preglomerular vessels  

SciTech Connect

Controversy exists regarding the specific sites within the renal microcirculation affected by angiotensin II (ANG II). Under some conditions, ANG II can elicit direct vasoconstrictor responses in the preglomerular vessels and efferent arterioles. These experiments were designed to evaluate the binding of {sup 125}I-ANG II in preglomerular vessels. Arcuate and interlobular arteries, with attached proximal segments of afferent arterioles, were microdissected from rabbit renal cortexes. A membrane preparation was obtained from the pooled freshly dissected vessels and utilized in an ANG II radioreceptor assay on the same day. The dissociation of bound ANG II was enhanced in the presence of a nonhydrolyzable analogue of GTP. Linear Scatchard plots were obtained, indicating the presence of a single class of high-affinity binding sites. In conclusion, there is a single class of specific ANG II receptors in preglomerular vessels. The K{sub D} and N are similar, but the binding inhibition potencies of selected ANG analogues differ in renal and extrarenal vascular tissues. Intrarenal vascular receptors also appear to differ from glomerular receptors. Furthermore, these data support the concept that ANG II may affect renal vascular resistance at sites proximal to the distal afferent arterioles.

Brown, G.P.; Venuto, R.C. (State Univ. of New York, Buffalo (USA))

1988-07-01T23:59:59.000Z

263

Fillables: everyday vessels as tangible controllers with adjustable haptics  

Science Conference Proceedings (OSTI)

We introduce Fillables: low-cost and ubiquitous everyday vessels that are appropriated as tangible controllers whose haptics are tuned ad-hoc by filling, e.g., with water. We show how Fillables can assist users in video navigation and drawing tasks with ... Keywords: appropriation, everyday objects, tangible user interfaces, ubiquitous computing, up-and-down transformed response (udtr), weber's law

Christian Corsten; Chat Wacharamanotham; Jan Borchers

2013-04-01T23:59:59.000Z

264

Ion transport membrane module and vessel system with directed internal gas flow  

DOE Patents (OSTI)

An ion transport membrane system comprising (a) a pressure vessel having an interior, an inlet adapted to introduce gas into the interior of the vessel, an outlet adapted to withdraw gas from the interior of the vessel, and an axis; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region; and (c) one or more gas flow control partitions disposed in the interior of the pressure vessel and adapted to change a direction of gas flow within the vessel.

Holmes, Michael Jerome (Thompson, ND); Ohrn, Theodore R. (Alliance, OH); Chen, Christopher Ming-Poh (Allentown, PA)

2010-02-09T23:59:59.000Z

265

AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION  

SciTech Connect

An IBM 7090 FORTRAN program was written for the preliminary design and cost estimation of unfired pressure vessels with or without a jacket. Both vessel and jacket designs conform to the 1959 ASME Boiler and Pressure Vessel Code, Section VIII, Unfired Pressure Vessels. Vessels and jackets from 5 in. pipe through 84 in. o.d. and 1/4 in. through 1 1/2 in. in metal thickness may be designed by this program as written. Total vessel cost is the sum of metal and fabrication costs, each on a weight basis. (auth)

Prince, C.E.; Milford, R.P.

1962-10-17T23:59:59.000Z

266

TR-105696-R16 (BWRVIP-03) Revision 16: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines  

Science Conference Proceedings (OSTI)

This report provides the boiling water reactor (BWR) fleet with inspection options for all of the safety-related vessel internal components, and provides a stable mechanism for documenting the capability of the evolving inspection technology. It is the sole resource for internals inspection information for BWR ...

2013-12-14T23:59:59.000Z

267

LNG Exports by Vessel in ISO Containers out of the U.S. Form...  

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

in ISO Containers out of the U.S. Form LNG Exports by Vessel in ISO Containers out of the U.S. Form Excel Version of LNG Exports by Vessel in ISO Container out of the U.S....

268

Mechanical safety subcommittee guideline for design of thin windows for vacuum vessels  

SciTech Connect

This guideline specifies the usage of thin windows for vacuum vessels in terms of their design and application a Fermilab.

Western, J.L.

1993-03-01T23:59:59.000Z

269

Mechanical Safety Subcommittee guideline for design of thin windows for vacuum vessels  

SciTech Connect

This guideline specifies the usage of thin windows for vacuum vessels in terms of their design and application at Fermilab.

Western, J.L.

1991-03-06T23:59:59.000Z

270

Mechanical safety subcommittee guideline for design of thin windows for vacuum vessels. Revised  

SciTech Connect

This guideline specifies the usage of thin windows for vacuum vessels in terms of their design and application a Fermilab.

Western, J.L.

1993-03-01T23:59:59.000Z

271

BWRVIP-244: BWR Vessel and Internals Project, Nondestructive Evaluation Development 2010  

Science Conference Proceedings (OSTI)

This report provides 2010 results of the nondestructive evaluation NDE development task of the Boiling Water Reactor Vessel and Internals Project BWRVIP Inspection Focus Group. The scope of activity includes applications of various NDE techniques to boiling water reactor vessels and vessel internals components.

2010-12-23T23:59:59.000Z

272

LNG Exports by Vessel out of the U.S. Form | Department of Energy  

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

out of the U.S. Form LNG Exports by Vessel out of the U.S. Form Excel Version of LNG Exports by Vessel out of the U.S. Form.xlsx PDF Version of LNG Exports by Vessel out of the...

273

Materials Reliability Program: Reactor Pressure Vessel Integrity Training Module (MRP-286)  

Science Conference Proceedings (OSTI)

For many reactor pressure vessels, embrittlement is the primary concern in ensuring continued safe operation. The shutdown of the Yankee Rowe plant, which occurred because of uncertainties related to embrittlement of the vessel, demonstrated the importance of adequately addressing embrittlement issues. Managing embrittlement involves the integration, management, and implementation of diverse technical, regulatory, planning, and economic activities. Reactor vessel embrittlement management is an essential ...

2010-11-22T23:59:59.000Z

274

An approach to localize the retinal blood vessels using bit planes and centerline detection  

Science Conference Proceedings (OSTI)

The change in morphology, diameter, branching pattern or tortuosity of retinal blood vessels is an important indicator of various clinical disorders of the eye and the body. This paper reports an automated method for segmentation of blood vessels in ... Keywords: Bit plane slicing, Blood vessel segmentation, First order derivative of Gaussian, Image segmentation, Mathematical morphology, Medical imaging, Retinal image, Ocular fundus

M. M. Fraz; S. A. Barman; P. Remagnino; A. Hoppe; A. Basit; B. Uyyanonvara; A. R. Rudnicka; C. G. Owen

2012-11-01T23:59:59.000Z

275

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

276

Inexpensive Delivery of Compressed Hydrogen with Advanced Vessel Technology  

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

delivery of compressed hydrogen delivery of compressed hydrogen with advanced vessel technology Gene Berry Andrew Weisberg Salvador M. Aceves Lawrence Livermore National Laboratory (925) 422-0864 saceves@LLNL.GOV DOE and FreedomCar & Fuel Partnership Hydrogen Delivery and On-Board Storage Analysis Workshop Washington, DC January 25, 2006 LLNL is developing innovative concepts for efficient containment of hydrogen in light duty vehicles concepts may offer advantages for hydrogen delivery Conformable containers efficiently use available space in the vehicle. We are pursuing multiple approaches to conformability High Strength insulated pressure vessels extend LH 2 dormancy 10x, eliminate boiloff, and enable efficiencies of flexible refueling (compressed/cryogenic H 2 /(L)H 2 ) The PVT properties of H

277

Lightweight pressure vessels and unitized regenerative fuel cells  

DOE Green Energy (OSTI)

Energy storage systems have been designed using lightweight pressure vessels with unitized regenerative fuel cells (URFCs). The vessels provide a means of storing reactant gases required for URFCs; they use lightweight bladder liners that act as inflatable mandrels for composite overwrap and provide a permeation barrier. URFC systems have been designed for zero emission vehicles (ZEVs); they are cost competitive with primary FC powered vehicles that operate on H/air with capacitors or batteries for power peaking and regenerative braking. URFCs are capable of regenerative braking via electrolysis and power peaking using low volume/low pressure accumulated oxygen for supercharging the power stack. URFC ZEVs can be safely and rapidly (<5 min.) refueled using home electrolysis units. Reversible operation of cell membrane catalyst is feasible without significant degradation. Such systems would have a rechargeable specific energy > 400 Wh/kg.

Mitlitsky, F.; Myers, B.; Weisberg, A.H.

1996-09-06T23:59:59.000Z

278

DEMO Hot Cell and Ex-Vessel Remote Handling  

E-Print Network (OSTI)

In Europe the work on the specification and design of a Demonstration Power Plant (DEMO) is being carried out by EFDA in the Power Plant Physics and Technology (PPP&T) programme. DEMO will take fusion from experimental research into showing the potential for commercial power generation. This paper describes the first steps being taken towards the design of the DEMO Hot Cell. It will show a comparison of the current DEMO in-vessel maintenance concepts from a Hot Cell perspective, describe a proposed ex-vessel transport system, and summarize the facilities that have been identified as required within the Hot Cell, examine current RH technology and discuss the identified critical development issues.

Thomas, Justin; Bachmann, Christian; Harman, Jon

2013-01-01T23:59:59.000Z

279

Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database  

SciTech Connect

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

Wang, Jy-An John [ORNL

2010-08-01T23:59:59.000Z

280

PRESSURIZATION OF CONTAINMENT VESSELS FROM PLUTONIUM OXIDE CONTENTS  

Science Conference Proceedings (OSTI)

Transportation and storage of plutonium oxide is typically done using a convenience container to hold the oxide powder which is then placed inside a containment vessel. Intermediate containers which act as uncredited confinement barriers may also be used. The containment vessel is subject to an internal pressure due to several sources including; (1) plutonium oxide provides a heat source which raises the temperature of the gas space, (2) helium generation due to alpha decay of the plutonium, (3) hydrogen generation due to radiolysis of the water which has been adsorbed onto the plutonium oxide, and (4) degradation of plastic bags which may be used to bag out the convenience can from a glove box. The contributions of these sources are evaluated in a reasonably conservative manner.

Hensel, S.

2012-03-27T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

282

IMPACT OF NUCLEAR MATERIAL DISSOLUTION ON VESSEL CORROSION  

Science Conference Proceedings (OSTI)

Different nuclear materials require different processing conditions. In order to maximize the dissolver vessel lifetime, corrosion testing was conducted for a range of chemistries and temperature used in fuel dissolution. Compositional ranges of elements regularly in the dissolver were evaluated for corrosion of 304L, the material of construction. Corrosion rates of AISI Type 304 stainless steel coupons, both welded and non-welded coupons, were calculated from measured weight losses and post-test concentrations of soluble Fe, Cr and Ni.

Mickalonis, J.; Dunn, K.; Clifton, B.

2012-10-01T23:59:59.000Z

283

BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in th e BWR Environment  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals materials issues. This report provides a methodology for assessing crack growth in BWR low alloy steel pressure vessels and nozzles. A previous version of this report was published as BWRVIP-60 (TR-108709). This report (BWRVIP-60-A) incorporates the U.S. Nuclear Regulatory Commission (NRC) Safety Evaluation (SE) and ot...

2003-06-09T23:59:59.000Z

284

INAA and distribution patterns of Classic Mimbres Black-on-white vessels during the Classic period  

E-Print Network (OSTI)

Distribution patterns of Classic Mimbres Black-on-white (Style III) bowls and jars were determined by instrumental neutron activation analysis (INAA) to identify vessel movement between geographically defined regions and between villages within individual regions of southwestern New Mexico. Ceramic and clay samples (n=288) from 15 sites in the Gila, Mimbres, and Rio Grande valleys composed the data set. Vessel movement was identified at the regional and site level to determine the degree of regional and site-specific interactions. Fifteen sites composed the regional level data set whereas only five sites contributed large enough sample sizes to determine vessel movement between sites at the site level of analysis. The operating hypotheses of the project were: (1) bowls were distributed throughout the Mimbres cultural system more often than jars; (2) vessel movement between sites within a region exceeded vessel movement between regions; (3) the Mimbres manufactured vessels at the village level; and, (4) elites did not control ceramic vessel distribution. Discriminant function analysis was used to identify vessel movement based on INAA data. The statistical results indicated that bowls were more frequently exchanged than jars, a higher number of vessels were moved between sites within the same region than between regions, vessels were manufactured at the village level, and an elite that controlled vessel distribution most likely did not exist in the Mimbres culture. The absence of a controlling elite was inferred from the overall low levels of exchange and the identification of site-specific production locations.

Dahlin, Eleanor Sherlock

2003-01-01T23:59:59.000Z

285

GRR/Section 6-HI-e - Boiler Pressure Vessel Permit | Open Energy  

Open Energy Info (EERE)

GRR/Section 6-HI-e - Boiler Pressure Vessel Permit GRR/Section 6-HI-e - Boiler Pressure Vessel Permit < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 6-HI-e - Boiler Pressure Vessel Permit 06HIGBoilerPressureVesselPermit.pdf Click to View Fullscreen Contact Agencies Hawaii Department of Labor and Industrial Relations Occupational Safety and Health Division Regulations & Policies Boiler and Pressure Vessel Regulations Triggers None specified Click "Edit With Form" above to add content 06HIGBoilerPressureVesselPermit.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative Boiler/Pressure Vessel Permit

286

Method and apparatus for detecting irregularities on or in the wall of a vessel  

DOE Patents (OSTI)

A method of detecting irregularities on or in the wall of a vessel by detecting localized spatial temperature differentials on the wall surface, comprising scanning the vessel surface with a thermal imaging camera and recording the position of the or each region for which the thermal image from the camera is indicative of such a temperature differential across the region. The spatial temperature differential may be formed by bacterial growth on the vessel surface; alternatively, it may be the result of defects in the vessel wall such as thin regions or pin holes or cracks. The detection of leaks through the vessel wall may be enhanced by applying a pressure differential or a temperature differential across the vessel wall; the testing for leaks may be performed with the vessel full or empty, and from the inside or the outside.

Bowling, Michael Keith (Blackborough Cullompton, GB)

2000-09-12T23:59:59.000Z

287

Bunker: a privacy-oriented platform for network tracing  

Science Conference Proceedings (OSTI)

ISPs are increasingly reluctant to collect and store raw network traces because they can be used to compromise their customers' privacy. Anonymization techniques mitigate this concern by protecting sensitive information. Trace anonymization can be performed ...

Andrew G. Miklas; Stefan Saroiu; Alec Wolman; Angela Demke Brown

2009-04-01T23:59:59.000Z

288

Upgrade of the DIII-D vacuum vessel protection system  

SciTech Connect

An upgrade of the General Atomics DIII-D tokamak armor protection system has been completed. The upgrade consisted of armoring the outer wall and the divertor gas baffle with monolithic graphite tiles and cleaning the existing floor, ceiling, and inner wall tiles to remove any deposited impurity layer from the tile surfaces. The new tiles replace the graphite tiles used as local armor for neutral beam shine through, three graphite poloidal back-up limiter bands, and miscellaneous Inconel protection tiles. The total number of tiles increased from 1636 to 3200 and corresponding vessel coverage from 40% to 90%. A new, graphite armored, toroidally continuous, gas baffle between the outer wall and the biased divertor ring was installed in order to accommodate the cryocondensation pump that was installed in parallel with the outer wall tiles. To eliminate a source of copper in the plasma, GRAFOIL gaskets replaced the copper felt metal gaskets previously used as a compliant heat transfer interface between the inertially cooled tiles and the vessel wall. GRAFOIL, an exfoliated, flexible graphite material from Union Carbide, Inc., was used between each tile and the vessel wall and also between each tile and its hold-down hardware. Testing was performed to determine the mechanical compliance, thermal conductance, and vacuum characteristics of the GRAFOIL material. To further decrease the quantity of high Z materials exposed to the plasma, the 1636 existing graphite tiles were identified, removed, and grit blasted to eliminate a thin layer of deposited metals which included nickel, chromium, and molybdenum. Prior to any processing, a selected set of tiles was tested for radioactivity, including tritium contamination. The tiles were grit blasted in a negative-pressure blasting cabinet using 37 {mu}m boron carbide powder as the blast media and dry nitrogen as the propellant.

Hollerbach, M.A.; Lee, R.L.; Smith, J.P.; Taylor, P.L.

1993-10-01T23:59:59.000Z

289

Workbook Contents  

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

SalesDeliveries to Vessel Bunkering Consumers (Thousand Gallons)","U.S. No 2 Diesel SalesDeliveries to On-Highway Consumers (Thousand Gallons)","U.S. Total Distillate Sales...

290

,"U.S. Total Adjusted Sales of Distillate Fuel Oil by End Use...  

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

SalesDeliveries to Vessel Bunker Consumers (Thousand Gallons)","U.S. No 2 Diesel Adj SalesDeliveries to On-Highway Consumers (Thousand Gallons)","U.S. Total Distillate Adj...

291

Remotely Operated Equipment for Post Irradiation Examination of the SNS Target Vessel  

Science Conference Proceedings (OSTI)

The Spallation Neutron Source produces neutrons by accelerating protons into flowing mercury contained inside a stainless steel target vessel. During facility operation the target vessel is degraded by a combination of high-energy neutrons, the proton beam, and cavitation-induced corrosion. The degradation is primarily concentrated at the nose of the target vessel, where the proton beam passes through. Currently, the Spallation Neutron Source has replaced three target vessels and is operating the fourth. To minimize the operational costs of manufacturing and disposing of target vessels, efforts are underway to increase the operational lifetimes of the target vessels by conducting post irradiation examinations of spent vessels. This examination involves remotely removing multiple coupons from the nose of the target vessel using a single piece of equipment, called the Nose Sampling Cutter, installed inside the Spallation Neutron Source s hot cell. The Cutter produces circular coupons approximately 2 inches in diameter using a carbide-tipped hole saw. The nose of the target vessel consists of four layers of material, and the Nose Sampling Cutter is capable of cutting through the layers in a single stroke. This remote operation has been successfully completed twice. In addition to the Nose Sampling Cutter, a large reciprocation saw capable of removing a sizable section of the nose of the target vessel has been constructed and tested, but never implemented. To support this large reciprocation saw other equipment has also been designed. The details of the Nose Sampling Cutter, reciprocation saw, and associated equipment are discussed.

Carroll, Adam J [ORNL; Graves, Van B [ORNL; Dayton, Michael J [ORNL; Riemer, Bernie [ORNL

2011-01-01T23:59:59.000Z

292

Certification Testing and Demonstration of Insulated Pressure Vessels for Vehicular Hydrogen and Natural Gas Storage  

Science Conference Proceedings (OSTI)

We are working on developing an alternative technology for storage of hydrogen or natural gas on light-duty vehicles. This technology has been titled insulated pressure vessels. Insulated pressure vessels are cryogenic-capable pressure vessels that can accept either liquid fuel or ambient-temperature compressed fuel. Insulated pressure vessels offer the advantages of cryogenic liquid fuel tanks (low weight and volume), with reduced disadvantages (fuel flexibility, lower energy requirement for fuel liquefaction and reduced evaporative losses). The work described in this paper is directed at verifying that commercially available pressure vessels can be safely used to store liquid hydrogen or LNG. The use of commercially available pressure vessels significantly reduces the cost and complexity of the insulated pressure vessel development effort. This paper describes a series of tests that have been done with aluminum-lined, fiber-wrapped vessels to evaluate the damage caused by low temperature operation. All analysis and experiments to date indicate that no significant damage has resulted. Future activities include a demonstration project in which the insulated pressure vessels will be installed and tested on two vehicles. A draft standard will also be generated for obtaining insulated pressure vessel certification.

Aceves, S M; Martinez-Frias, J; Espinosa-Loza, F; Schaffer, R; Clapper, W

2002-05-22T23:59:59.000Z

293

Conceptual design of an in-vessel core catcher  

Science Conference Proceedings (OSTI)

An enhanced in-vessel core catcher is being designed and evaluated as part of a joint United States (US)Korean International Nuclear Energy Research Initiative (INERI) investigating methods to insure retention of materials that may relocate to the lower head of a reactor vessel under severe accident conditions in advanced reactors. This enhanced core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary): a base material, which has the capability to support and contain the mass of core materials that may relocate during a severe accident; an insulator coating material on top of the base material, which resists interactions with high-temperature core materials; and an optional coating on the bottom side of the base material to prevent any potential oxidation of the base material during the lifetime of the reactor. This paper summarizes results from thermal, flow, and structural analyses as well as initial scoping materials interaction tests that were completed to support the conceptual design of the core catcher.

Joy L. Rempe; D. L. Knudson; K. G. Condie; K. Y. Suh; F. B.Cheung; S. B. Kim

2004-05-01T23:59:59.000Z

294

Blowdown of hydrocarbons pressure vessel with partial phase separation  

E-Print Network (OSTI)

We propose a model for the simulation of the blowdown of vessels containing two-phase (gas-liquid) hydrocarbon fluids, considering non equilibrium between phases. Two phases may be present either already at the beginning of the blowdown process (for instance in gas-liquid separators) or as the liquid is formed from flashing of the vapor due to the cooling induced by pressure decrease. There is experimental evidence that the assumption of thermodynamic equilibrium is not appropriate, since the two phases show an independent temperature evolution. Thus, due to the greater heat transfer between the liquid phase with the wall, the wall in contact with the liquid experiences a stronger cooling than the wall in contact with the gas, during the blowdown. As a consequence, the vessel should be designed for a lower temperature than if it was supposed to contain vapor only. Our model is based on a compositional approach, and it takes into account internal heat and mass transfer processes, as well as heat transfer with ...

Speranza, Alessandro; 10.1142/9789812701817_0046

2011-01-01T23:59:59.000Z

295

Calculations to estimate the margin to failure in the TMI-2 vessel  

SciTech Connect

As part of the OECD-sponsored Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project (VIP), margin-to-failure calculations for mechanisms having the potential to threaten the integrity of the vessel were performed to improve understanding of events that occurred during the TMI-2 accident. Analyses considered four failure mechanisms: tube rupture, tube ejection, global vessel failure, and localized vessel failure. Calculational input was based on data from the TMI-2 VIP examinations of the vessel steel samples, the instrument tube nozzles, and samples of the hard layer of debris found on the TMI-2 vessel lower head. Sensitivity studies were performed to investigate the uncertainties in key parameters for these analyses.

Stickler, L.A.; Rempe, J.L.; Chavez, S.A.; Thinnes, G.L.; Snow, S.D. [EG& G Idaho, Inc., Idaho Falls, ID (United States); Witt, R.J.; Corradini, M.L.; Kos, J.A. [Univ. of Wisconsin, Madison, WI (United States)

1994-03-01T23:59:59.000Z

296

PRESTRESSING A TWO-LAYER PRESSURE VESSEL BY CONTROLLED YIELDING OF THE INNER LAYER  

SciTech Connect

A method of designing a two-layer pressure vessel is presented wherein contact between the layers is produced by controlled yielding of the inner vessel by internal pressure. The amount of prestress depends upon the dimensions of the vessel, the properties of the material of construction, and the prestressing pressure. The method takes into account the actual stress-strain curve of the material and satisfies the rales of plastic flow with work hardening. (auth)

Schneider, R.W.

1964-04-01T23:59:59.000Z

297

PRESTRESSING A TWO-LAYER PRESSURE VESSEL BY CONTROLLED YIELDING OF THE INNER LAYER  

SciTech Connect

A method is presented for designing a two-layer pressure vessel wherein contact between the layers is produced by controlled yielding of the inner vessel by internal pressure. The amount of prestress depends upon the dimensions of the vessel, the properties of the material of construction, and the prestressing pressure. The method takes into account the actual stress-strain curve of the material and satisfies the rules of plastic flow with work hardening. (auth)

Schneider, R.W.

1964-01-29T23:59:59.000Z

298

Recent United States and International Experiences in Reactor Vessel and Internals Segmentation  

Science Conference Proceedings (OSTI)

The segmentation of reactor vessels and internals is one of the most challenging tasks in nuclear power plant decommissioning. Many experiences, lessons learned, and best practices have been gained through the execution of the first few reactor vessel and internals segmentation projects. The Electric Power Research Institute (EPRI) previously documented the experiences, lessons learned, best practices, and technologies used in decommissioning reactor vessel and internals segmentation projects in the Unit...

2011-11-29T23:59:59.000Z

299

BWRVIP-189: BWR Vessel and Internals Project, Evaluation of RAMA Fluence Methodology Calculational Uncertainty  

Science Conference Proceedings (OSTI)

This report documents the overall calculational uncertainty associated with the application of the Radiation Application Modeling Application (RAMA) Fluence Methodology to BWR reactor pressure vessel fluence evaluations.

2008-07-07T23:59:59.000Z

300

Nuclear reactor having a polyhedral primary shield and removable vessel insulation  

DOE Patents (OSTI)

A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel. 5 figures.

Ekeroth, D.E.; Orr, R.

1993-12-07T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Nuclear reactor having a polyhedral primary shield and removable vessel insulation  

DOE Patents (OSTI)

A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel.

Ekeroth, Douglas E. (Delmont, PA); Orr, Richard (Pittsburgh, PA)

1993-01-01T23:59:59.000Z

302

Impacts of reducing shipboard NOx? and SOx? emissions on vessel performance  

E-Print Network (OSTI)

The international maritime community has been experiencing tremendous pressures from environmental organizations to reduce the emissions footprint of their vessels. In the last decade, air emissions, including nitrogen ...

Caputo, Ronald J., Jr. (Ronald Joseph)

2010-01-01T23:59:59.000Z

303

Experiment DTA report for semiscale transparent vessel countercurrent flow tests  

SciTech Connect

Steady state air-water tests were performed as part of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project to investigate downcomer countercurrent flow and downcomer bypass flow phenomena. These tests were performed in a plexiglass representation of the Semiscale pressure vessel which allowed changes to be madein the geometry of the upper annulus and downcomer for the purpose of investigating the sensitivity of downcomer and bypass flow to changes in system geometry. Tests were also performed to investigate the effects of two-phase inlet flows and different initial system pressures on countercurrent and bypass flow. Results for each test are presented in the form of computer printout of the measurements and of a summary of the pertinent calculated flow rates, pressures, and dimensionless volumetric fluxes. Descriptions of the test facility, instrumentation, operating procedures, and test conditions are also presented. An error analysis is presented for selected volumetric flux calculations. 10 references. (auth)

Hanson, D.J.

1975-10-01T23:59:59.000Z

304

Reactor Vessel Head Disposal Campaign for Nuclear Management Company  

SciTech Connect

After establishing a goal to replace as many reactor vessel heads as possible - in the shortest time and at the lowest cost as possible - Nuclear Management Company (NMC) initiated an ambitious program to replace the heads on all six of its pressurized water reactors. Currently, four heads have been replaced; and four old heads have been disposed of. In 2002, NMC began fabricating the first of its replacement reactor vessel heads for the Kewaunee Nuclear Plant. During its fall 2004 refueling outage, Kewaunee's head was replaced and the old head was prepared for disposal. Kewaunee's disposal project included: - Down-ending, - Draining, - Decontamination, - Packaging, - Removal from containment, - On-Site handling, - Temporary storage, - Transportation, - Disposal. The next two replacements took place in the spring of 2005. Point Beach Nuclear Plant (PBNP) Unit 2 and Prairie Island Nuclear Generating Plant (PINGP) Unit 2 completed their head replacements during their scheduled refueling outages. Since these two outages were scheduled so close to each other, their removal and disposal posed some unique challenges. In addition, changes to the handling and disposal programs were made as a result of lessons learned from Kewaunee. A fourth head replacement took place during PBNP Unit 1's refueling outage during the fall of 2005. A number of additional changes took place. All of these changes and challenges are discussed in the paper. NMC's future schedule includes PINGP Unit 1's installation in Spring 2006 and Palisades' installation during 2007. NMC plans to dispose of these two remaining heads in a similar manner. This paper presents a summary of these activities, plus a discussion of lessons learned. (authors)

Hoelscher, H.L.; Closs, J.W. [Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 (United States); Johnson, S.A. [Duratek, Inc., 140 Stoneridge Drive, Columbia, SC 29210 (United States)

2006-07-01T23:59:59.000Z

305

Instrumentation of a prestressed concrete containment vessel model  

Science Conference Proceedings (OSTI)

A series of static overpressurization tests of scale models of nuclear containment structures is being conducted by Sandia National Laboratories for the Nuclear Power Engineering Corporation of Japan and the U.S. Nuclear Regulatory Commission. At present, two tests are being planned: a test of a model of a steel containment vessel (SCV) that is representative of an improved, boiling water reactor (BWR) Mark II design; and a test of a model of a prestressed concrete containment vessel (PCCV). This paper discusses plans and the results of a preliminary investigation of the instrumentation of the PCCV model. The instrumentation suite for this model will consist of approximately 2000 channels of data to record displacements, strains in the reinforcing steel, prestressing tendons, concrete, steel liner and liner anchors, as well as pressure and temperature. The instrumentation is being designed to monitor the response of the model during prestressing operations, during Structural Integrity and Integrated Leak Rate testing, and during test to failure of the model. Particular emphasis has been placed on instrumentation of the prestressing system in order to understand the behavior of the prestressing strands at design and beyond design pressure levels. Current plans are to place load cells at both ends of one third of the tendons in addition to placing strain measurement devices along the length of selected tendons. Strain measurements will be made using conventional bonded foil resistance gages and a wire resistance gage, known as a {open_quotes}Tensmeg{close_quotes}{reg_sign} gage, specifically designed for use with seven-wire strand. The results of preliminary tests of both types of gages, in the laboratory and in a simulated model configuration, are reported and plans for instrumentation of the model are discussed.

Hessheimer, M.F.; Rightley, M.J. [Sandia National Labs., Albuquerque, NM (United States); Matsumoto, T. [Nuclear Power Engineering Corp., Tokyo (Japan)] [and others

1995-09-01T23:59:59.000Z

306

The Disruption of Vessel-Spanning Bubbles with Sloped Fins in Flat-Bottom and 2:1 Elliptical-Bottom Vessels  

DOE Green Energy (OSTI)

Radioactive sludge was generated in the K-East Basin and K-West Basin fuel storage pools at the Hanford Site while irradiated uranium metal fuel elements from the N Reactor were being stored and packaged. The fuel has been removed from the K Basins, and currently, the sludge resides in the KW Basin in large underwater Engineered Containers. The first phase to the Sludge Treatment Project being led by CH2MHILL Plateau Remediation Company (CHPRC) is to retrieve and load the sludge into sludge transport and storage containers (STSCs) and transport the sludge to T Plant for interim storage. The STSCs will be stored inside T Plant cells that are equipped with secondary containment and leak-detection systems. The sludge is composed of a variety of particulate materials and water, including a fraction of reactive uranium metal particles that are a source of hydrogen gas. If a situation occurs where the reactive uranium metal particles settle out at the bottom of a container, previous studies have shown that a vessel-spanning gas layer above the uranium metal particles can develop and can push the overlying layer of sludge upward. The major concern, in addition to the general concern associated with the retention and release of a flammable gas such as hydrogen, is that if a vessel-spanning bubble (VSB) forms in an STSC, it may drive the overlying sludge material to the vents at the top of the container. Then it may be released from the container into the cells secondary containment system at T Plant. A previous study demonstrated that sloped walls on vessels, both cylindrical coned-shaped vessels and rectangular vessels with rounded ends, provided an effective approach for disrupting a VSB by creating a release path for gas as a VSB began to rise. Based on the success of sloped-wall vessels, a similar concept is investigated here where a sloped fin is placed inside the vessel to create a release path for gas. A key potential advantage of using a sloped fin compared to a vessel with a sloped wall is that a small fin decreases the volume of a vessel available for sludge storage by a very small fraction compared to a cone-shaped vessel. The purpose of this study is to quantify the capability of sloped fins to disrupt VSBs and to conduct sufficient tests to estimate the performance of fins in full-scale STSCs. Experiments were conducted with a range of fin shapes to determine what slope and width were sufficient to disrupt VSBs. Additional tests were conducted to demonstrate how the fin performance scales with the sludge layer thickness and the sludge strength, density, and vessel diameter based on the gravity yield parameter, which is a dimensionless ratio of the force necessary to yield the sludge to its weight.( ) Further experiments evaluated the difference between vessels with flat and 2:1 elliptical bottoms and a number of different simulants, including the KW container sludge simulant (complete), which was developed to match actual K-Basin sludge. Testing was conducted in 5-in., 10-in., and 23-in.-diameter vessels to quantify how fin performance is impacted by the size of the test vessel. The most significant results for these scale-up tests are the trend in how behavior changes with vessel size and the results from the 23-in. vessel. The key objective in evaluating fin performance is to determine the conditions that minimize the volume of a VSB when disruption occurs because this reduces the potential for material inside the STSC from being released through vents.

Gauglitz, Phillip A.; Buchmiller, William C.; Jenks, Jeromy WJ; Chun, Jaehun; Russell, Renee L.; Schmidt, Andrew J.; Mastor, Michael M.

2010-09-22T23:59:59.000Z

307

BWRVIP-34-A: BWR Vessel and Internals Project, Technical Basis for Part Circumference Weld Overlay Repair of Vessel Internal Core Sp ray Piping  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. This report summarizes the results of the design and analysis activities and the testing programs conducted to provide BWR utilities with a contingency repair option for internal core spray piping for BWR2/6 plants. A previous version of this report was published as BWRVIP-34 (TR-108198). This report (BWRVIP-34...

2008-03-11T23:59:59.000Z

308

Materials Reliability Project: Benchmark Study of Reactor Pressure Vessel Integrity Probabilistic Computational Results Using the Fracture Analysis of Vessels Oak Ridge (FAVOR) Software Code (MRP-371)  

Science Conference Proceedings (OSTI)

This report reports the results from the Fracture Analysis of Vessels Oak Ridge (FAVOR) software analysis of three transients that simulated pressurized thermal shock events in pressurized water reactor (PWR) reactor pressure vessels (RPVs). It was determined that software modifications would be required to complete the probabilistic analyses for the wide range of flaw sizes and locations of interest in the study. Consequently, two software revisions were provided by EPRI to enable ...

2013-08-22T23:59:59.000Z

309

Qualification of In-Service Examination of the Yankee Rowe Reactor Pressure Vessel  

Science Conference Proceedings (OSTI)

An effective in-service examination of the reactor pressure vessel was an essential part of the restart program for the Yankee Atomic Power Company plant in Rowe, Massachusetts. This report describes development of an effective examination strategy, demonstration of performance of the examination procedures, and development of data on the distribution of flaws in reactor pressure vessels.

1993-01-01T23:59:59.000Z

310

BWRVIP-269: BWR Vessel and Internals Project, Nondestructive Evaluation Development 2012  

Science Conference Proceedings (OSTI)

The purpose of this report is to describe the results of nondestructive evaluation (NDE) activities conducted in the previous year within the NDE Development task of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Inspection Focus Group. The scope of the ongoing NDE Development task includes the reactor vessel and its internal components. This task attempts to develop solutions for the more difficult ...

2012-12-12T23:59:59.000Z

311

BWR Vessel and Internals Project: Quantitative Safety Assessment of BWR Reactor Internals (BWRVIP-09)  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June, 1994, is an association of utilities focused exclusively on BWR vessel and internals issues. This BWRVIP report documents the results of a quantitative safety assessment conducted to evaluate the safety significance of failures of certain BWR internal components.

1997-02-20T23:59:59.000Z

312

Conceptual Design of a Reactor Pressure Vessel and its Internals for a HPLWR  

Science Conference Proceedings (OSTI)

A design for the Reactor Pressure Vessel (RPV) and its internals for a HPLWR (High Performance Light Water Reactor) is presented. The RPV has been dimensioned using the pressure vessel code for nuclear power plants in Germany. In order to use conventional vessel materials such as 20 MnMoNi 5 5 (United States: SA 508), the vessel inner wall has to be kept only in contact with coolant at inlet temperature. Therefore, the hot coolant pipe connection from the steam plenum to the outlet is separated from the RPV inner wall using a thermal sleeve. The core inside the vessel rests on a support plate which is connected to the core barrel. The steam plenum is fixed on top of the core using support brackets which are attached to the adjustable steam outlet pipes. This way, the steam plenum rests on the outlet flanges of the lower vessel, while the core barrel is suspended at the closure head flange of the vessel to control thermal expansions between the internals and the RPV and to minimize thermal stresses. Both, inlet and outlet mass flows are separated via C-ring seals to prevent mixing. The control rod guides in the upper plenum are also suspended at the vessel flange and aligned inside the core barrel using centering pins. (authors)

Fischer, Kai [EnBW Kraftwerke AG, Kernkraftwerk Philippsburg, Rheinschanzinsel D-76661 Philippsburg (Germany); Starflinger, Joerg; Schulenberg, Thomas [Forschungszentrum Karlsruhe GmbH, Institute for Nuclear and Energy Technologies P.O. Box 3640, D-76021 Karlsruhe (Germany)

2006-07-01T23:59:59.000Z

313

HIGH TEMPERATURE THERMAL AND STRUCTURAL MATERIAL PROPERTIES FOR METALS USED IN LWR VESSELS  

Science Conference Proceedings (OSTI)

Because of the impact that melt relocation and vessel failure may have on subsequent progression and associated consequences of a Light Water Reactor (LWR) accident, it is important to accurately predict heating and relocation of materials within the reactor vessel, heat transfer to and from the reactor vessel, and the potential for failure of the vessel and structures within it. Accurate predictions of such phenomena require high temperature thermal and structural properties. However, a review of vessel and structural steel material properties used in severe accident analysis codes reveals that the required high temperature material properties are extrapolated with little, if any, data above 1000 K. To reduce uncertainties in predictions relying upon extrapolated high temperature data, Idaho National Laboratory (INL) obtained high data for two metals used in LWR vessels: SA 533 Grade B, Class 1 (SA533B1) low alloy steel, which is used to fabricate most US LWR reactor vessels; and Type 304 Stainless Steel SS304, which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data, and compares it to existing data.

J.L. Rempe; D.L. Knudson; J. E. Daw; J. C. Crepeau

2008-06-01T23:59:59.000Z

314

RIS-M-2186 INTERPRETATIOM OF STRAIN HBASUREMEMTS ON NUCLEAR PRESSURE VESSELS  

E-Print Network (OSTI)

RIS?-M- 2186 INTERPRETATIOM OF STRAIN HBASUREMEMTS ON NUCLEAR PRESSURE VESSELS Svend Ib Andersen Preben Engbzk Abstract. Selected results from strain measurements on 4 nuclear pressure vessels procedure before and after the test as well as a detailed knowledge of the behaviour of the signal from

315

Repair Technology for Degraded Pressure Vessel and Heat Exchanger Shells: RRAC Task 91  

Science Conference Proceedings (OSTI)

The ability to repair pressure vessels and heat exchangers offers utilities significant cost savings compared to replacing these components. This is especially the case if outage time and loss of production are factored into the cost of replacement. This guide provides a review of various current and proposed repair methods that can be used for pressure vessel and heat exchanger applications.

2002-12-02T23:59:59.000Z

316

REACTION OF DOLPHINS TO A SURVEY VESSEL: EFFECTS ON CENSUS DATA  

E-Print Network (OSTI)

REACTION OF DOLPHINS TO A SURVEY VESSEL: EFFECTS ON CENSUS DATA RoGER P. HEWITI'l ABSTRACf A field of a survey vessel prior to their detection by shipboard observers and that the use of a monotonically decreasing detection function is adequate to minimize bias. Aerial and shipboard estimates of school size

317

Marine Casualty and Pollution Database - Vessel Events for 2002 to 2010 |  

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

Vessel Events for 2002 to 2010 Vessel Events for 2002 to 2010 Ocean Data Tools Technical Guide Map Gallery Regional Planning Feedback Ocean You are here Data.gov » Communities » Ocean » Data Marine Casualty and Pollution Database - Vessel Events for 2002 to 2010 Dataset Summary Description The Marine Casualty and Pollution Data files provide details about marine casualty and pollution incidents investigated by Coast Guard Offices throughout the United States. The database can be used to analyze marine accidents and pollution incidents by a variety of factors including vessel or facility type, injuries, fatalities, pollutant details, location, and date. The data collection period began in 1982 for marine casualties and 1973 for polluting incidents, and is ongoing. Documentation includes entity and attribute descriptions along with suggested solutions to general marine pollution, vessel casualty, and personnel injury and death questions.

318

Blood Vessel Normalization in the Hamster Oral Cancer Model for Experimental Cancer Therapy Studies  

Science Conference Proceedings (OSTI)

Normalization of tumor blood vessels improves drug and oxygen delivery to cancer cells. The aim of this study was to develop a technique to normalize blood vessels in the hamster cheek pouch model of oral cancer. Materials and Methods: Tumor-bearing hamsters were treated with thalidomide and were compared with controls. Results: Twenty eight hours after treatment with thalidomide, the blood vessels of premalignant tissue observable in vivo became narrower and less tortuous than those of controls; Evans Blue Dye extravasation in tumor was significantly reduced (indicating a reduction in aberrant tumor vascular hyperpermeability that compromises blood flow), and tumor blood vessel morphology in histological sections, labeled for Factor VIII, revealed a significant reduction in compressive forces. These findings indicated blood vessel normalization with a window of 48 h. Conclusion: The technique developed herein has rendered the hamster oral cancer model amenable to research, with the potential benefit of vascular normalization in head and neck cancer therapy.

Ana J. Molinari; Romina F. Aromando; Maria E. Itoiz; Marcela A. Garabalino; Andrea Monti Hughes; Elisa M. Heber; Emiliano C. C. Pozzi; David W. Nigg; Veronica A. Trivillin; Amanda E. Schwint

2012-07-01T23:59:59.000Z

319

Method of design for vertical oil shale retorting vessels and retorting therewith  

DOE Patents (OSTI)

A method of designing the gas flow parameters of a vertical shaft oil shale retorting vessel involves determining the proportion of gas introduced in the bottom of the vessel and into intermediate levels in the vessel to provide for lateral distribution of gas across the vessel cross section, providing mixing with the uprising gas, and determining the limiting velocity of the gas through each nozzle. The total quantity of gas necessary for oil shale treatment in the vessel may be determined and the proportion to be injected into each level is then determined based on the velocity relation of the orifice velocity and its feeder manifold gas velocity. A limitation is placed on the velocity of gas issuing from an orifice by the nature of the solid being treated, usually physical tests of gas velocity impinging the solid.

Reeves, Adam A. (Rifle, CO)

1978-01-03T23:59:59.000Z

320

Method for forming a bladder for fluid storage vessels  

DOE Green Energy (OSTI)

A lightweight, low permeability liner for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated with a thin layer of a low permeability material, such as silver, gold, or aluminum, deposited on a thin polymeric layer or substrate which is formed into a closed bladder using torispherical or near torispherical end caps, with or without bosses therein, about which a high strength to weight material, such as graphite epoxy composite shell, is formed to withstand the storage pressure forces. The polymeric substrate may be laminated on one or both sides with additional layers of polymeric film. The liner may be formed to a desired configuration using a dissolvable mandrel or by inflation techniques and the edges of the film seamed by heat sealing. The liner may be utilized in most any type of gas storage system, and is particularly applicable for hydrogen, gas mixtures, and oxygen used for vehicles, fuel cells or regenerative fuel cell applications, high altitude solar powered aircraft, hybrid energy storage/propulsion systems, and lunar/Mars space applications, and other applications requiring high cycle life.

Mitlitsky, Fred (Livermore, CA); Myers, Blake (Livermore, CA); Magnotta, Frank (Lafayette, CA)

2000-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

In-vessel activation monitors in JET: Progress in modeling  

SciTech Connect

Activation studies were performed in JET with new in-vessel activation monitors. Though primarily dedicated to R and D in the challenging issue of lost {alpha} diagnostics for ITER, which is being addressed at JET with several techniques, these monitors provide for both neutron and charged particle fluences. A set of samples with different orientation with respect to the magnetic field is transported inside the torus by means of a manipulator arm (in contrast with the conventional JET activation system with pneumatic transport system). In this case, radionuclides with longer half-life were selected and ultralow background gamma-ray measurements were needed. The irradiation was closer to the plasma and this potentially reduces the neutron scattering problem. This approach could also be of interest for ITER, where the calibration methods have yet to be developed. The MCNP neutron transport model for JET was modified to include the activation probe and so provide calculations to help assess the new data. The neutron induced activity on the samples are well reproduced by the calculations.

Bonheure, Georges [Laboratory for Plasma Physics, Association 'Euratom-Belgian State', Avenue de la Renaissance 30, B-1000 Brussels (Belgium); Lengar, I. [Slovenian Fusion Association, Jozef Stefan Institute, Jamova 39, SI-1000 Ljubljana (Slovenia); Syme, B.; Popovichev, S. [Euratom/UKAEA Association, Culham Science Centre, Abingdon, OX14 3DB Oxon (United Kingdom); Wieslander, Elisabeth; Hult, Mikael; Gasparro, Joeel; Marissens, Gerd [EC-JRC-IRMM, Institute for Reference Materials and Measurements, Retieseweg 111, B-2440 Geel (Belgium); Arnold, Dirk [Physikalisch-Technische Bundesanstalt, 6.1 Radioactivity, Bundesallee 100, D-38116 Braunschweig (Germany); Laubenstein, Matthias [Laboratori Nazionali del Gran Sasso, S.S, 17/bis, km 18-910, I-67010 Assergi (Italy)

2008-10-15T23:59:59.000Z

322

BWRVIP-239: BWR Vessel and Internals Project, Updated Evaluation of the Integrated Surveillance Program (ISP) Capsule Withdrawal Sch edule  

Science Conference Proceedings (OSTI)

This report evaluates updated reactor pressure vessel and surveillance capsule fluence data for potential impacts on the Boiling Water Reactor Vessel and Internals Project Integrated Surveillance Program (BWRVIP ISP) capsule withdrawal schedule.

2010-07-16T23:59:59.000Z

323

Investigation of downward facing critical heat flux with water-based nanofluids for In-Vessel Retention applications  

E-Print Network (OSTI)

In-Vessel Retention ("IVR") is a severe accident management strategy that is power limiting to the Westinghouse AP1000 due to critical heat flux ("CHF") at the outer surface of the reactor vessel. Increasing the CHF level ...

DeWitt, Gregory L

2011-01-01T23:59:59.000Z

324

Comparison of Pressure Vessel Design and Inspection Requirements as Defined by ASME Code and Germany's TRD Code  

Science Conference Proceedings (OSTI)

This report compares the American Society of Mechanical Engineers (ASME) Code with the German TRD Code for pressure vessel engineering, fabrication, inspection, and other pressure vessel processes. The report compares calculations of minimum required wall thickness for pressure vessels such as boiler tubes, pipes, headers, and drums. It also compares material allowable stress values and reviews the major materials permitted by both codes for use in pressure vessel engineering and manufacturing. The repor...

1994-09-22T23:59:59.000Z

325

USING AN ADAPTER TO PERFORM THE CHALFANT-STYLE CONTAINMENT VESSEL PERIODIC MAINTENANCE LEAK RATE TEST  

Science Conference Proceedings (OSTI)

Recently the Packaging Technology and Pressurized Systems (PT&PS) organization at the Savannah River National Laboratory was asked to develop an adapter for performing the leak-rate test of a Chalfant-style containment vessel. The PT&PS organization collaborated with designers at the Department of Energy's Pantex Plant to develop the adapter currently in use for performing the leak-rate testing on the containment vessels. This paper will give the history of leak-rate testing of the Chalfant-style containment vessels, discuss the design concept for the adapter, give an overview of the design, and will present results of the testing done using the adapter.

Loftin, B.; Abramczyk, G.; Trapp, D.

2011-06-03T23:59:59.000Z

326

Fast neutron fluence of yonggwang nuclear unit 1 reactor pressure vessel  

Science Conference Proceedings (OSTI)

The Code of Federal Regulations, Title 10, Part 50, Appendix H, requires that the neutron dosimetry be present to monitor the reactor vessel throughout plant life. The Ex-Vessel Neutron Dosimetry System has been installed for Yonggwang Nuclear Unit 1 after complete withdrawal of all six in-vessel surveillance capsules. This system has been installed in the reactor cavity annulus in order to measure the fast neutron spectrum coming out through the reactor pressure vessel. Cycle specific neutron transport calculations were performed to obtain the energy dependent neutron flux throughout the reactor geometry including dosimetry positions. Comparisons between calculations and measurements were performed for the reaction rates of each dosimetry sensors and results show good agreements. (authors)

Yoo, C.; Km, B.; Chang, K.; Leeand, S. [Korea Atomic Energy Research Inst., 150 Dukjin-dong, Yuseung-gu, Daejeon 305-353 (Korea, Republic of); Park, J. [Chungnam National Univ., 220 Gung-dong, Yuseung-gu, Daejeon 305-764 (Korea, Republic of)

2006-07-01T23:59:59.000Z

327

Potential market for LNG-fueled marine vessels in the United States  

E-Print Network (OSTI)

The growing global concern over ship emissions in recent years has driven policy change at the international level toward more stringent vessel emissions standards. The policy change has also been an impetus for innovation ...

Brett, Bridget C

2008-01-01T23:59:59.000Z

328

Hydrogen degradation and microstructural effects of the near-threshold fatigue resistance of pressure vessel steels  

E-Print Network (OSTI)

Safety of pressure vessels for applications such as coal conversion reactors requires understanding of the mechanism of environmentally-induced crack propagation and the mechanism by which process-induced microstructures ...

Fuquen-Molano, Rosendo

1982-01-01T23:59:59.000Z

329

A Small, Low Flow, High Sensitivity Reaction Vessel for NO Chemiluminescence Detectors  

Science Conference Proceedings (OSTI)

Details of a reaction vessel suitable for atmospheric measurements of nitric oxide at parts per trillion mixing ratios using the chemiluminescent reaction with ozone are provided. It is designed to operate at an ambient air flow of 1 standard ...

B. A. Ridley; F. E. Grahek

1990-04-01T23:59:59.000Z

330

CO/sub 2/ welding used to attach inspection manway to NASA hydrogen pressure vessel  

SciTech Connect

Welding of inspection manway for internal survey of a gaseous hydrogen storage vessel is described. Pre-welding activities are reviewed, along with welding operations, and in-process welding control. (JRD)

Palmer, G.; Conklin, D.

1976-09-01T23:59:59.000Z

331

Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel  

DOE Patents (OSTI)

The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel to form a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor.

Schreiber, Roger B. (Penn Twp., PA); Fero, Arnold H. (New Kensington, PA); Sejvar, James (Murrysville, PA)

1997-01-01T23:59:59.000Z

332

Substantiation of Thermodynamic Criteria of Explosion Safety in Process of Severe Accidents in Pressure Vessel Reactors  

E-Print Network (OSTI)

The paper represents original development of thermodynamic criteria of occurrence conditions of steam-gas explosions in the process of severe accidents. The received results can be used for modelling of processes of severe accidents in pressure vessel reactors.

Skalozubov, V I; Jarovoj, S S; Kochnyeva, V Yu

2012-01-01T23:59:59.000Z

333

Substantiation of Thermodynamic Criteria of Explosion Safety in Process of Severe Accidents in Pressure Vessel Reactors  

E-Print Network (OSTI)

The paper represents original development of thermodynamic criteria of occurrence conditions of steam-gas explosions in the process of severe accidents. The received results can be used for modelling of processes of severe accidents in pressure vessel reactors.

V. I. Skalozubov; V. N. Vashchenko; S. S. Jarovoj; V. Yu. Kochnyeva

2012-03-27T23:59:59.000Z

334

Pipeline and Pressure Vessel R&D under the Hydrogen Regional...  

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

Pipeline and Pressure Vessel R&D under the Hydrogen Regional Infrastructure Program In Pennsylvania Kevin L. Klug, Ph.D. 25 September 2007 DOE Hydrogen Pipeline Working Group...

335

In-Situ Repairs of Oil Industry Pipelines, Tanks and Vessels by ...  

Science Conference Proceedings (OSTI)

Abstract Scope, Metal arc welding under oil (MAW-UO) is a new, revolutionary process to repair a pipeline, tank or vessel by welding in case of flaws and...

336

Nonlinear response of vessel walls due to short-time thermomechanical loading  

Science Conference Proceedings (OSTI)

Maintaining structural integrity of the reactor pressure vessel (RPV) during a postulated core melt accident is an important safety consideration in the design of the vessel. This study addresses the failure predictions of the vessel due to thermal and pressure loadings fro the molten core debris depositing on the lower head of the vessel. Different loading combinations were considered based on the dead load, yield stress assumptions, material response and internal pressurization. The analyses considered only short term failure (quasi static) modes, long term failure modes were not considered. Short term failure modes include plastic instabilities of the structure and failure due to exceeding the failure strain. Long term failure odes would be caused by creep rupture that leads to plastic instability of the structure. Due to the sort time durations analyzed, creep was not considered in the analyses presented.

Pfeiffer, P.A.; Kulak, R.F.

1994-06-01T23:59:59.000Z

337

Experimental and Numerical Study of the Turbulence Characteristics of Airflow around a Research Vessel  

Science Conference Proceedings (OSTI)

Airflow distortion by research vessels has been shown to significantly affect micrometeorological measurements. This study uses an efficient time-dependent large-eddy simulation numerical technique to investigate the effect of the R/V Tangaroa on ...

Stphane Popinet; Murray Smith; Craig Stevens

2004-10-01T23:59:59.000Z

338

Draft report: application of organic Rankine cycle heat recovery systems to diesel powered marine vessels  

DOE Green Energy (OSTI)

The analysis and results of an investigation of the application of organic Rankine cycle heat recovery systems to diesel-powered marine vessels are described. The program under which this study was conducted was sponsored jointly by the US Energy Research and Development Administration, the US Navy, and the US Maritime Administration. The overall objective of this study was to investigate diesel bottoming energy recovery systems, currently under development by three US concerns, to determine the potential for application to marine diesel propulsion and auxiliary systems. The study primarily focused on identifying the most promising vessel applications (considering vessel type, size, population density, operational duty cycle, etc.) so the relative economic and fuel conservation merits of energy recovery systems could be determined and assessed. Vessels in the current fleet and the projected 1985 fleet rated at 1000 BHP class and above were investigated.

Not Available

1977-07-15T23:59:59.000Z

339

Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel  

DOE Patents (OSTI)

The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel to form a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor. 8 figs.

Schreiber, R.B.; Fero, A.H.; Sejvar, J.

1997-12-16T23:59:59.000Z

340

An accurate model for seaworthy container vessel stowage planning with ballast tanks  

Science Conference Proceedings (OSTI)

Seaworthy container vessel stowage plans generated under realistic assumptions are a key factor for stowage decision support systems in the shipping industry. We propose a linear model with ballast tanks for generating master plans, the first phase of ...

Dario Pacino; Alberto Delgado; Rune Mller Jensen; Tom Bebbington

2012-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

BWRVIP-160: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2006 Update  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. As a group, the utilities have developed a set of guidelines that recommend inspecting specific BWR internal components. Results of these inspections are reported to EPRI where they are compiled and made available to all member utilities. This report documents results of inspections performed between approximately 1996 and early 2006.

2006-10-03T23:59:59.000Z

342

BWRVIP-198: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2008 Update  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. As a group, the utilities have developed a set of guidelines that recommend inspecting specific BWR internal components. Results of these inspections are reported to EPRI where they are compiled and made available to all member utilities. This report documents results of inspections performed between approximately 1996 and spring of 2008.

2008-10-16T23:59:59.000Z

343

BWRVIP-242: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2010 Update  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. As a group, the utilities have developed a set of guidelines that recommend inspecting specific BWR internal components. Results of these inspections are reported to EPRI where they are compiled and made available to all member utilities. This report documents results of inspections performed between approximately 1996 and spring of 2010.

2010-12-07T23:59:59.000Z

344

Transient PVT measurements and model predictions for vessel heat transfer. Part II.  

SciTech Connect

Part I of this report focused on the acquisition and presentation of transient PVT data sets that can be used to validate gas transfer models. Here in Part II we focus primarily on describing models and validating these models using the data sets. Our models are intended to describe the high speed transport of compressible gases in arbitrary arrangements of vessels, tubing, valving and flow branches. Our models fall into three categories: (1) network flow models in which flow paths are modeled as one-dimensional flow and vessels are modeled as single control volumes, (2) CFD (Computational Fluid Dynamics) models in which flow in and between vessels is modeled in three dimensions and (3) coupled network/CFD models in which vessels are modeled using CFD and flows between vessels are modeled using a network flow code. In our work we utilized NETFLOW as our network flow code and FUEGO for our CFD code. Since network flow models lack three-dimensional resolution, correlations for heat transfer and tube frictional pressure drop are required to resolve important physics not being captured by the model. Here we describe how vessel heat transfer correlations were improved using the data and present direct model-data comparisons for all tests documented in Part I. Our results show that our network flow models have been substantially improved. The CFD modeling presented here describes the complex nature of vessel heat transfer and for the first time demonstrates that flow and heat transfer in vessels can be modeled directly without the need for correlations.

Felver, Todd G.; Paradiso, Nicholas Joseph; Winters, William S., Jr.; Evans, Gregory Herbert; Rice, Steven F.

2010-07-01T23:59:59.000Z

345

Guidelines for Managing Reactor Vessel Material Uncertainties: Part 1: General Approach Part 2: Implementation Guide  

Science Conference Proceedings (OSTI)

Uncertainties about reactor vessel material toughness properties can be a concern for utilities when characterizing vessel integrity. In addition, recent emphasis on variability in material chemistry and initial toughness properties has added to regulatory concerns. This two-part guidelines document provides a general approach (Part 1) for dealing with weld metal property variability and material uncertainties and demonstrates examples of different approaches (Part 2) for dealing with these uncertainties...

1997-04-30T23:59:59.000Z

346

BWRVIP-167: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables  

Science Conference Proceedings (OSTI)

Ongoing issues related to degradation of boiling water reactor (BWR) pressure vessels, reactor internals, and American Society of Mechanical Engineers (ASME) Class 1 piping components have resulted in the need for a summary tool to assist in prioritizing and addressing research and development (R&D) issues. This BWR Vessel and Internals Project (BWRVIP) report provides BWR Issue Management Tables that identify, rank, and describe R&D gaps.

2007-03-20T23:59:59.000Z

347

BWRVIP-167NP, Revision 2: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables  

Science Conference Proceedings (OSTI)

Nuclear utilities face numerous ongoing issues related to degradation of boiling water reactor (BWR) pressure vessels, reactor internals, and American Society of Mechanical Engineers (ASME) Class 1 piping components. These issues have resulted in the need for a summary tool to assist in prioritizing and addressing research and development (R&D) issues and BWR Vessel and Internals Project (BWRVIP) requirements. The BWR Issue Management Tables (IMTs) in the report are living documents that summarize the st...

2010-08-24T23:59:59.000Z

348

BWRVIP-267: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2012 Update  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. As a group, the utilities have developed a set of guidelines that recommend inspecting specific BWR internal components. Results of these inspections are reported to the Electric Power Research Institute (EPRI) where they are compiled and made available to all member utilities. This report documents results of inspections performed between ...

2012-10-10T23:59:59.000Z

349

Welding and Repair Technology Center: Repair Technology for Degraded Pressure Vessel and Heat Exchanger Shells  

Science Conference Proceedings (OSTI)

BackgroundPressure vessels and heat exchangers are subject to a number of degradation mechanisms that can cause thinning of component walls and deterioration of internal components. With many repair options available, the Electric Power Research Institute (EPRI) Welding and Repair Technology Center (WRTC) has developed this report to assist operations and engineering personnel who are faced with defective or failed vessel components. Many available repair options allow ...

2013-10-30T23:59:59.000Z

350

BWRVIP-277: BWR Vessel and Internals Project, Nondestructive Evaluation Development 2013  

Science Conference Proceedings (OSTI)

This report describes the results of nondestructive evaluation (NDE) activities conducted in the previous year within the NDE development task of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Inspection Focus Group. The scope of the ongoing task includes the reactor vessel and its internal components. This task attempts to develop solutions for the more difficult inspections recommended by the BWRVIP, to determine limitations to inspection capability, and sometimes to demonstrate ...

2013-11-27T23:59:59.000Z

351

Word Pro - Untitled1  

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

5 5 Table 5.15 Fuel Oil and Kerosene Sales, Selected Years, 1984-2010 (Thousand Barrels per Day) Year Distillate Fuel Oil Residential Commercial Industrial Oil Company Farm Electric Power 1 Railroad Vessel Bunkering On-Highway Diesel Military Off-Highway Diesel Other Total 1984 534 360 166 55 208 42 192 115 1,093 46 114 46 2,971 1985 504 291 159 45 202 34 182 111 1,127 43 99 11 2,809 1990 475 260 169 49 222 50 203 135 1,393 46 118 (s) 3,120 1991 442 246 151 48 206 39 188 133 1,336 53 107 (s) 2,949 1992 474 245 150 43 228 35 206 144 1,391 42 114 (s) 3,075 1993 475 241 139 46 222 36 196 141 1,485 32 137 (s) 3,150 1994 472 246 148 44 213 43 205 143 1,594 40 140 (s) 3,289 1995 447 237 146 45 227 39 224 153 1,668 30 142 - - 3,357 1996 450 234 149 48 234 43 224 162 1,754 30 146 - - 3,472 1997 426 216 151 56 231 41 214 168 1,867 28 149 - - 3,546 1998

352

In-Vessel Retention of Molten Core Debris in the Westinghouse AP1000 Advanced Passive PWR  

SciTech Connect

In-vessel retention (IVR) of molten core debris via external reactor vessel cooling is the hallmark of the severe accident management strategies in the AP600 passive PWR. The vessel is submerged in water to cool its external surface via nucleate boiling heat transfer. An engineered flow path through the reactor vessel insulation provides cooling water to the vessel surface and vents steam to promote IVR. For the 600 MWe passive plant, the predicted heat load from molten debris to the lower head wall has a large margin to the critical heat flux on the external surface of the vessel, which is the upper limit of the cooling capability. Up-rating the power of the passive plant from 600 to 1000 MWe (AP1000) significantly increases the heat loading from the molten debris to the reactor vessel lower head in the postulated bounding severe accident sequence. To maintain a large margin to the coolability limit for the AP1000, design features and severe accident management (SAM) strategies to increase the critical heat flux on the external surface of the vessel wall need to be implemented. A test program at the ULPU facility at University of California Santa Barbara (UCSB) has been initiated to investigate design features and SAM strategies that can enhance the critical heat flux. Results from ULPU Configuration IV demonstrate that with small changes to the ex-vessel design and SAM strategies, the peak critical heat flux in the AP1000 can be increased at least 30% over the peak critical heat flux predicted for the AP600 configuration. The design and SAM strategy changes investigated in ULPU Configuration IV can be implemented in the AP1000 design and will allow the passive plant to maintain the margin to critical heat flux for IVR, even at the higher power level. Continued testing for IVR phenomena is being performed at UCSB to optimize the AP1000 design and to ensure that vessel failure in a severe accident is physically unreasonable. (authors)

Scobel, James H.; Conway, L.E. [Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, PA 15230-0355 (United States); Theofanous, T.G. [Center for Risk Studies and Safety, University of California Santa Barbara (United States)

2002-07-01T23:59:59.000Z

353

Thermal energy storage using Prestressed Cast Iron Vessels (PCIV). Final report  

DOE Green Energy (OSTI)

The wide-spread application of thermal energy and high-pressure air storage to electric power generation has so far been hampered by the lack of large high-pressure storage vessels of reasonable cost. Welded steel vessels are too expensive for this purpose. However, the Prestressed Cast Iron Vessel (PCIV), developed as a nuclear reactor pressure vessel by Siempelkamp Giesserei KG of Krefeld, FRG, has the potential of complying with these requirements. Applications of the PCIV include: high-pressure air storage for the quick start-up of open cycle gas turbines; pressurized high-temperature sensible heat storage by means of solids with a gaseous heat transfer medium for closed cycle gas turbines of future solar power stations; and pressurized hot water storage for nuclear, solar, or coal-fired steam power plants, employing either separate peaking turbines or overloadable main turbine sets. A reference PCIV of 8000 m/sup 3/, 275/sup 0/C, with hot going walls and cold going tendons was developed, designed, and stress-analysed. A parametric study showed that pressures between 4 and 8 MPa and L/D ratios larger than 4 should be optimal. Cost of the reference vessel is about $10,000,000 or 33 to 50 $/kWh electric energy stored. Cost of peak power will be from 30 to 100 mills/kWh, depending on many parameters.

Gilli, P.V.; Beckmann, G.; Schilling, F.E.

1977-06-01T23:59:59.000Z

354

US EPR Tests Performed to confirm the Mechanical and Hydraulic Design of the Vessel Internals  

SciTech Connect

The EPR is an Evolutionary high-Power Reactor which is based on the best French and German experience of the past twenty years in plant design construction and operation. In the present detailed engineering phase of the plant under construction in Finland (Okiluoto 3) or scheduled in France (Flamanville 3), a few actions are still ongoing mainly to complement equipment validation files. Design and validation of the main EPR components were performed within Framatome ANP's engineering teams and its two Technical Centers located in France and Germany, which develop state of the art methods in the field of thermo hydraulic testing. The Reactor Pressure Vessel internals are mainly derived from components already implemented on presently operating plants, but they differ in some features from the design used in French N4 or German Konvoi. The aim of this paper is to present the tests performed to confirm the hydraulic and mechanical design of the EPR vessel internals. - Four different mock-ups are presented to illustrate these tests: - JULIETTE for the reactor pressure vessel lower internals; - ROMEO for the reactor pressure vessel upper internals; - MAGALY for the design of the skeleton-type control rod guide assembly; - HYDRAVIB for the vibratory response of the reactor pressure vessel lowers internals. (authors)

Dolleans, Philippe; Chambrin, Jean-Luc; Muller, Thierry [FRAMATOME ANP, Tour AREVA 1 place de la Coupole, 92084 PARIS La D ense (France)

2006-07-01T23:59:59.000Z

355

In-Vessel Retention of Molten Corium: Lessons Learned and Outstanding Issues  

Science Conference Proceedings (OSTI)

In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Advanced 600 MWe Pressurized Water Reactor (PWR) designed by Westinghouse (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for IVR, resulted in the U.S. Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing Light Water Reactors (LWRs). However, it is not clear that the ERVC proposed for the AP600 could provide sufficient heat removal for higher-power reactors (up to 1500 MWe) without additional enhancements. This paper reviews efforts made and results reported regarding the enhancement of IVR in LWRs. Where appropriate, the paper identifies what additional data or analyses are needed to demonstrate that there is sufficient margin for successful IVR in high power thermal reactors.

J.L. Rempe; K.Y. Suh; F. B. Cheung; S. B. Kim

2008-03-01T23:59:59.000Z

356

BWRVIP-265: BWR Vessel and Internals Project, Crack Growth in High Fluence BWR Materials-Phase 2  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP) has developed a methodology to evaluate crack growth rates (CGR) in irradiated stainless steel components in the BWR vessel. This methodology is documented in BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (EPRI report 1016566), and is applicable to neutron doses of 0.7 to 4.2 displacements per atom (dpa) (5x1020 to 3x1021 ...

2012-11-14T23:59:59.000Z

357

BWRVIP-270, Revision 1: BWR Vessel and Internals Project, Compilation of Fluence Estimates for Boiling Water Reactor Materials  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP) is an association of utilities focused on BWR vessel and internals issues. Many of the BWR internal components receive high exposure to neutron flux due to their proximity to the fuel in the Reactor Pressure Vessel (RPV). Identifying how predicted fluence values will impact the materials at these locations is a focus of the BWRVIP proactive materials strategy. As part of this approach, this report provides visual and tabular summaries ...

2013-12-09T23:59:59.000Z

358

Comparison of ALICE-II code predictions with SRI complex vessel experiments  

Science Conference Proceedings (OSTI)

Several complex vessel experiments on 1/20-scale models of the Clinch River Breeder Reactor Project (CRBR) were performed by SRI International to help evaluate the containment structural integrity subjected to HCDAs. Among these experiments SM-3 is a simple model which consists of a radial shield, core barrel, upper internal structure (UIS), and a primary vessel. Tests SM-4 and SM-5 are more complex models than SM-3. This paper presents comparisons of the ALICE-II code (Arbitrary Lagrangian Implicit-explicit Continuous Fluid Eulerian containment code - second version) with experiments SM-3 through SM-5. Two calculations are performed with ALICE-II on each of these three experiments, using both the pressure-time histories (p-t) and the pressure-volume relationships (p-v) as input to describe the energy source. Pressure profiles, dynamic strains, and vessel deformations are used as the basis of the comparison.

Ku, J.L.; Wang, C.Y.; Zeuch, W.R.

1983-01-01T23:59:59.000Z

359

Progress in understanding the mechanical behavior of pressure-vessel materials at elevated temperatures  

SciTech Connect

Progress during the 1970's on the production of high-temperature mechanical properties data for pressure vessel materials was reviewed. The direction of the research was toward satisfying new data requirements to implement advances in high-temperature inelastic design methods. To meet these needs, servo-controlled testing machines and high-resolution extensometry were developed to gain more information on the essential behavioral features of high-temperature alloys. The similarities and differences in the mechanical response of various pressure vessel materials were identified. High-temperature pressure vessel materials that have received the most attention included Type 304 stainless steel, Type 316 stainless steel, 2 1/4 Cr-1 Mo steel, alloy 800H, and Hastelloy X.

Swindeman, R.W.; Brinkman, C.R.

1981-01-01T23:59:59.000Z

360

In-Vessel Coil Material Failure Rate Estimates for ITER Design Use  

SciTech Connect

The ITER international project design teams are working to produce an engineering design for construction of this large tokamak fusion experiment. One of the design issues is ensuring proper control of the fusion plasma. In-vessel magnet coils may be needed for plasma control, especially the control of edge localized modes (ELMs) and plasma vertical stabilization (VS). These coils will be lifetime components that reside inside the ITER vacuum vessel behind the blanket modules. As such, their reliability is an important design issue since access will be time consuming if any type of repair were necessary. The following chapters give the research results and estimates of failure rates for the coil conductor and jacket materials to be used for the in-vessel coils. Copper and CuCrZr conductors, and stainless steel and Inconel jackets are examined.

L. C. Cadwallader

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

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

362

Scaled Testing to Evaluate Pulse Jet Mixer Performance in Waste Treatment Plant Mixing Vessels  

Science Conference Proceedings (OSTI)

The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pre-treat and vitrify the waste in Hanfords 177 underground waste storage tanks. Numerous process vessels will hold waste at various stages in the WTP. These vessels have pulse jet mixer (PJM) systems. A test program was developed to evaluate the adequacy of mixing system designs in the solids-containing vessels in the WTP. The program focused mainly on non-cohesive solids behavior. Specifically, the program addressed the effectiveness of the mixing systems to suspend settled solids off the vessel bottom, and distribute the solids vertically. Experiments were conducted at three scales using various particulate simulants. A range of solids loadings and operational parameters were evaluated, including jet velocity, pulse volume, and duty cycle. In place of actual PJMs, the tests used direct injection from tubes with suction at the top of the tank fluid. This gave better control over the discharge duration and duty cycle and simplified the facility requirements. The mixing system configurations represented in testing varied from 4 to 12 PJMs with various jet nozzle sizes. In this way the results collected could be applied to the broad range of WTP vessels with varying geometrical configurations and planned operating conditions. Data for just-suspended velocity, solids cloud height, and solids concentration vertical profile were collected, analyzed, and correlated. The correlations were successfully benchmarked against previous large-scale test results, then applied to the WTP vessels using reasonable assumptions of anticipated waste properties to evaluate adequacy of the existing mixing system designs.

Fort, James A.; Meyer, Perry A.; Bamberger, Judith A.; Enderlin, Carl W.; Scott, Paul A.; Minette, Michael J.; Gauglitz, Phillip A.

2010-03-07T23:59:59.000Z

363

NEWASH AND TECUMSETH: ANALYSIS OF TWO POST-WAR OF 1812 VESSELS ON THE GREAT LAKES  

E-Print Network (OSTI)

In 1953 the tangled, skeletal remains of a ship were pulled from the small harbor of Penetanguishene, Ontario. Local historians had hoped to raise the hull of a War of 1812 veteran, but the vessel pulled from the depths did not meet the criteria. Identified as H.M. Schooner Tecumseth, the vessel was built just after the War of 1812 had ended. Historical research of Tecumseth and her sister ship Newash, which remained in Penetanguishene harbor, illuminated the ships? shadowy past. Conceived and built after the war, the vessels sailed for only two years before being rendered obsolete by the terms of the Rush-Bagot disarmament agreement. Nevertheless, the two vessels offer a unique perspective from which to view the post-war period on the Great Lakes. The schooners? hulls were interpreted and analyzed using archaeological evidence. A theoretical rigging reconstruction was created, using contemporary texts and documentary evidence of the ships themselves. Architectural hull analysis was carried out to explore the nature of these vessels. From these varied approaches, a conception of Newash and Tecumseth has emerged, revealing ways in which the hulls were designed to fulfill their specific duties. The hulls were sharp, yet had capacious cargo areas. The rigs combined square-rigged and fore-and-aft sails for maximum flexibility. The designs of the hulls and rigging also reflect predominant attitudes of the period, in which naval vessels on the lakes gave way to merchant craft. Taken as a whole, Tecumseth and Newash illustrate how ships, while fluid in the nature of their work, are also singular entities that truly encapsulate a specific point in time and place.

Gordon, Leeanne E.

2009-05-01T23:59:59.000Z

364

MAGNESIUM MONO POTASSIUM PHOSPHATE GROUT FOR P-REACTOR VESSEL IN-SITU DECOMISSIONING  

Science Conference Proceedings (OSTI)

The objective of this report is to document laboratory testing of magnesium mono potassium phosphate grouts for P-Reactor vessel in-situ decommissioning. Magnesium mono potassium phosphate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout (pH of about 12.4). A less alkaline material ({ash), and (4) Ceramicrete{reg_sign} magnesium mono potassium phosphate-based grouts prepared at Argonne National Laboratory. Boric acid was evaluated as a set retarder in the magnesium mono potassium phosphate mixes.

Langton, C.; Stefanko, D.

2011-01-05T23:59:59.000Z

365

Structural integrity of vessels for coal conversion systems. [ASME and ANSI codes  

DOE Green Energy (OSTI)

The integrity of a coal conversion system need not be compromised by material considerations in design or fabrication. The ASME and ANSI Codes assure the structural integrity of the large pressure vessels and piping when they are placed into service. Imposing additional requirements, such as increased impact toughness, will further assure the reliability and safety of the Code-fabricated vessel. Incorporating in-service surveillance as part of the operational plan will ensure the integrity of the pressure-containing components for the anticipated service life.

Canonico, D.A.

1979-09-01T23:59:59.000Z

366

The dissolution vessel for plutonium pits at the U.S. DOE Pantex Plant  

Science Conference Proceedings (OSTI)

The US DOE Pantex Plant has been given the mission to recertify and requalify plutonium pits for reuse in existing War Reserve nuclear weapons. The first process common to both recertification and requalification is cleaning the plutonium pit. The pit will be cleaned in a dissolution vessel using N-methyl pyrrolidone (NMP) solvent. The recertification and requalification programs are both in the design concept phase at Pantex Plant. The US DOE Pantex Plant secures the national security of the United States by using safe vessels for cleaning plutonium pits in a manner that protects the health and safety of employees, the public and the environment.

Eifert, E.J.; Vickers, L.D.

2000-02-01T23:59:59.000Z

367

BWRVIP-53-A: BWR Vessel and lnternals Project, Standby Liquid Control Line Repair Design Criteria  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June, 1994, is an association of utilities focused exclusively on BWR vessel and internals issues. This BWRVIP report documents criteria which can be used to design a repair for the standby liquid control (SLC) line in a BWR. A previous version of this report was published as BWRVIP-53 (TR-108716). This report (BWRVIP-53- A) incorporates changes proposed by the BWRVIP in response to U.S. Nuclear Regulatory Commission (NRC) Request...

2005-09-07T23:59:59.000Z

368

Protective interior wall and attach8ing means for a fusion reactor vacuum vessel  

DOE Patents (OSTI)

An array of connected plates mounted on the inside wall of the vacuum vessel of a magnetic confinement reactor in order to provide a protective surface for energy deposition inside the vessel. All fasteners are concealed and protected beneath the plates, while the plates themselves share common mounting points. The entire array is installed with torqued nuts on threaded studs; provision also exists for thermal expansion by mounting each plate with two of its four mounts captured in an oversize grooved spool. A spool-washer mounting hardware allows one edge of a protective plate to be torqued while the other side remains loose, by simply inverting the spool-washer hardware.

Phelps, Richard D. (Greeley, CO); Upham, Gerald A. (Valley Center, CA); Anderson, Paul M. (San Diego, CA)

1988-01-01T23:59:59.000Z

369

Tank vessels transferring Outer Continental Shelf (OCS) oil proposed design and equipment standards  

SciTech Connect

The US Coast Guard proposes to require US and foreign flag tank vessels engaged in the transfer of OCS oil in bulk as cargo from an offshore oil exploitation or production facility to shore to have segregated ballast tanks, dedicated clean ballast tanks, or special ballast arrangements by 6/1/80. This proposal would implement the Port and Tanker Safety Act of 1978 and would eliminate the mixing of ballast water and oil, thus reducing operational pollution that could occur if there was a substantial increase in vessel traffic. Comments must be received by 6/16/80.

1980-05-01T23:59:59.000Z

370

Detailed Analysis of In-Vessel Melt Progression in the Loss of Coolant Accident of OPR1000  

Science Conference Proceedings (OSTI)

An in-vessel severe accident progression has been analyzed to generate the basic data for an evaluation of the in-vessel severe accident management strategies and to identify the thermal hydraulic condition of the reactor vessel and the damage state of the in-vessel materials at a reactor vessel failure by using the SCDAP/RELAP5/MOD3.3 computer code during the Loss Of Coolant Accident (LOCA) without the Safety Injection (SI) of the OPR (Optimized Pressurize Reactor) 1000. Best estimate calculation of the small break LOCAs of 1.35 inch and 2 inch, the medium break LOCAs of 3 inch and a 4.28 inch, and a large break LOCA of 9.8 inch without the SI have been performed from a transient initiation to a reactor vessel failure. The SCDAP/RELAP5/MOD3.3 results have shown that in all the transients, approximately 30-40 % of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of a reactor vessel failure. In the small and large break LOCAs, the reactor vessel failed at an early time of approximately 70-110 minutes after the transients were initiated. Since the Safety Injection Tanks (SITs) were actuated effectively in the medium break LOCAs, the reactor vessel failed at a later time of approximately 200-400 minutes after the transients were initiated. At the time of a reactor vessel failure, approximately 45-55 % of the fuel rod cladding was oxidized in the small and medium break LOCAs. However, approximately 20 % of the fuel rod cladding was oxidized because of a coolant loss through the break in the large break LOCA of the OPR1000. (authors)

Park, R.J.; Kim, S.B.; Kim, H.D. [Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2006-07-01T23:59:59.000Z

371

Detection and characterization of indications in segments of reactor pressure vessels  

Science Conference Proceedings (OSTI)

Studies have been conducted to estimate flaw density in segments cut from light water reactor (LWR) pressure vessels as part of the Oak Ridge National Laboratory's Heavy-Section Steel Technology (HSST) Program. Segments from the Hope Creek Unit 2 vessel and the Pilgrim Unit 2 vessel were purchased from salvage dealers. Hope Creek was a boiling water reactor (BWR) design and Pilgrim was a pressurized water reactor (PWR) design. Neither were ever placed in service. Objectives were to evaluate these LWR segments for flaws with ultrasonic and liquid penetrant techniques and to compare the results with current assumptions related to probabilistic risk assessment. Both objectives were successfully completed. Ultrasonic techniques beyond those required by the 1986 edition of the ASME Boiler and Pressure Vessel Code were necessary for the detection and reporting of the detected discontinuities. Extra care and analysis must be exercised when conducting ultrasonic examination through cladding. The detection of the discontinuities in the arbitrarily selected sections implies that the Marshall report estimates (and others) are nonconservative for such small flaws. 8 refs., 9 figs.

Cook, K.V.; Cunningham, R.A. Jr.; McClung, R.W.

1989-08-01T23:59:59.000Z

372

Vessel routing and scheduling under uncertainty in the liquefied natural gas business  

Science Conference Proceedings (OSTI)

Liquefied natural gas (LNG) is natural gas transformed into liquid state for the purpose of transportation mainly by specially built LNG vessels. This paper considers a real-life LNG ship routing and scheduling problem where a producer is responsible ... Keywords: Liquefied natural gas, Maritime transportation, Ship routing and scheduling, Simulation, Uncertainty

Elin E. Halvorsen-Weare; Kjetil Fagerholt; Mikael RNnqvist

2013-01-01T23:59:59.000Z

373

V1.6 Development of Advanced Manufacturing Technologies for Low Cost Hydrogen Storage Vessels  

Science Conference Proceedings (OSTI)

The goal of this project is to develop an innovative manufacturing process for Type IV high-pressure hydrogen storage vessels, with the intent to significantly lower manufacturing costs. Part of the development is to integrate the features of high precision AFP and commercial FW. Evaluation of an alternative fiber to replace a portion of the baseline fiber will help to reduce costs further.

Leavitt, Mark; Lam, Patrick; Nelson, Karl M.; johnson, Brice A.; Johnson, Kenneth I.; Alvine, Kyle J.; Ruiz, Antonio; Adams, Jesse

2012-10-01T23:59:59.000Z

374

Scaling Theory for Pulsed Jet Mixed Vessels, Sparging, and Cyclic Feed Transport Systems for Slurries  

SciTech Connect

This document is a previously unpublished work based on a draft report prepared by Pacific Northwest National Laboratory (PNNL) for the Hanford Waste Treatment and Immobilization Plant (WTP) in 2012. Work on the report stopped when WTPs approach to testing changed. PNNL is issuing a modified version of the document a year later to preserve and disseminate the valuable technical work that was completed. This document establishes technical bases for evaluating the mixing performance of Waste Treatment Plant (WTP) pretreatment process tanks based on data from less-than-full-scale testing, relative to specified mixing requirements. The technical bases include the fluid mechanics affecting mixing for specified vessel configurations, operating parameters, and simulant properties. They address scaling vessel physical performance, simulant physical performance, and scaling down the operating conditions at full scale to define test conditions at reduced scale and scaling up the test results at reduced scale to predict the performance at full scale. Essentially, this document addresses the following questions: Why and how can the mixing behaviors in a smaller vessel represent those in a larger vessel? What information is needed to address the first question? How should the information be used to predict mixing performance in WTP? The design of Large Scale Integrated Testing (LSIT) is being addressed in other, complementary documents.

Kuhn, William L.; Rector, David R.; Rassat, Scot D.; Enderlin, Carl W.; Minette, Michael J.; Bamberger, Judith A.; Josephson, Gary B.; Wells, Beric E.; Berglin, Eric J.

2013-09-27T23:59:59.000Z

375

Fracture Toughness Characterization of Japanese Reactor Pressure Vessel Steels: Joint EPRI-CRIEPI RPV Embrittlement Studies  

Science Conference Proceedings (OSTI)

EPRI has examined five Japanese reactor pressure vessel steels to characterize the material properties over a complete temperature range, including the brittle/ductile transition region and the upper shelf typical of normal operation. The test results provide the unirradiated baseline needed for evaluating the effects of radiation embrittlement.

1993-07-01T23:59:59.000Z

376

Pressurized thermal shock probabilistic fracture mechanics sensitivity analysis for Yankee Rowe reactor pressure vessel  

SciTech Connect

The Nuclear Regulatory Commission (NRC) requested Oak Ridge National Laboratory (ORNL) to perform a pressurized-thermal-shock (PTS) probabilistic fracture mechanics (PFM) sensitivity analysis for the Yankee Rowe reactor pressure vessel, for the fluences corresponding to the end of operating cycle 22, using a specific small-break-loss- of-coolant transient as the loading condition. Regions of the vessel with distinguishing features were to be treated individually -- upper axial weld, lower axial weld, circumferential weld, upper plate spot welds, upper plate regions between the spot welds, lower plate spot welds, and the lower plate regions between the spot welds. The fracture analysis methods used in the analysis of through-clad surface flaws were those contained in the established OCA-P computer code, which was developed during the Integrated Pressurized Thermal Shock (IPTS) Program. The NRC request specified that the OCA-P code be enhanced for this study to also calculate the conditional probabilities of failure for subclad flaws and embedded flaws. The results of this sensitivity analysis provide the NRC with (1) data that could be used to assess the relative influence of a number of key input parameters in the Yankee Rowe PTS analysis and (2) data that can be used for readily determining the probability of vessel failure once a more accurate indication of vessel embrittlement becomes available. This report is designated as HSST report No. 117.

Dickson, T.L.; Cheverton, R.D.; Bryson, J.W.; Bass, B.R.; Shum, D.K.M.; Keeney, J.A. [Oak Ridge National Lab., TN (United States)

1993-08-01T23:59:59.000Z

377

Why Web GIS May Not be Enough: A Case Study with the Virtual Research Vessel  

E-Print Network (OSTI)

Why Web GIS May Not be Enough: A Case Study with the Virtual Research Vessel DAWN J. WRIGHT1 infrastructure is desired and needed for ready access to data and the resulting maps via web GIS, in order, and the quantitative evaluation of scientific hypotheses. For widespread data access, web GIS is therefore only

Wright, Dawn Jeannine

378

White Paper on Reactor Vessel Integrity Requirements for Level A and B Conditions  

Science Conference Proceedings (OSTI)

The ASME Section XI Task Group recommends that the Reactor Vessel Integrity Requirements of the ASME code be updated in several areas to reflect current technology. This report reviews current regulations to identify areas of conservatism and potential nonconservatism and to provide recommendations for future code improvements.

1993-03-09T23:59:59.000Z

379

ITER Engineering Design Activities -R & DITER-In-Vessel Remote Handling  

E-Print Network (OSTI)

ITER Engineering Design Activities - R & DITER- In-Vessel Remote Handling Blanket Module Remote Handling Project (L-6) Divertor Remote Handling Project (L-7) Objective To develop and demonstrate handling equipment, port handling equipment, auxiliary remote handling tools and a blanket mockup structure

380

Test Results Using a Bell Jar to Measure Containment Vessel Pressurization  

SciTech Connect

A bell jar is used to determine containment vessel pressurization due to outgassing of plutonium materials. Fifteen food cans containing plutonium bearing materials, including plutonium packaged in direct contact with plastic and plutonium contaminated enriched oxide have been tested to date.

Hensel, S.J.

2002-05-10T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

MAGNESIUM MONO POTASSIUM PHOSPHATE GROUT FOR P-REACTOR VESSEL IN-SITU DECOMISSIONING  

SciTech Connect

The objective of this report is to document laboratory testing of magnesium mono potassium phosphate grouts for P-Reactor vessel in-situ decommissioning. Magnesium mono potassium phosphate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout (pH of about 12.4). A less alkaline material ({<=} 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere. Fresh and cured properties were measured for: (1) commercially blended magnesium mono potassium phosphate packaged grouts, (2) commercially available binders blended with inert fillers at SRNL, (3) grouts prepared from technical grade MgO and KH{sub 2}PO{sub 4} and inert fillers (quartz sands, Class F fly ash), and (4) Ceramicrete{reg_sign} magnesium mono potassium phosphate-based grouts prepared at Argonne National Laboratory. Boric acid was evaluated as a set retarder in the magnesium mono potassium phosphate mixes.

Langton, C.; Stefanko, D.

2011-01-05T23:59:59.000Z

382

Calvert Cliffs 1 Reactor Vessel: Pressurized Thermal Shock Analysis for a Small Steam Line Break  

Science Conference Proceedings (OSTI)

Analysis of this Maryland reactor revealed a wide safety margin in its two-loop Combustion Engineering PWR pressure vessel for transients caused by small steam line breaks. The study employed a new method for analyzing pressurized thermal shock effects that combines several EPRI computer codes.

1984-11-01T23:59:59.000Z

383

Measurements of the hydrogenic recombination coefficient for the TFTR vacuum vessel  

DOE Green Energy (OSTI)

Characteristic values of the recombination rate coefficient for hydrogen and deuterium in stainless steel have been measured for the inner wall of the TFTR vacuum vessel for vessel temperatures of 25 to 100 C. In situ measurements of k/sub r/ are important for predicting the hydrogen isotope retention in the wall as a function of time, temperature, and discharge exposure, particularly because existing laboratory measurements of k/sub r/ for stainless steel span a range of four orders of magnitude. The measurement technique involved the observation of the decrease in hydrogen pressure during a glow discharge in the TFTR vacuum vessel with an initial static gas fill. The resulting values of k/sub r/ at 25 C are in the range of (0.4 to 4) x 10/sup -27/cm/sup 4/-s/sup -1/ assuming a value of the hydrogenic diffusivity of 2 x 10/sup -12/cm/sup 2/-s/sup -1/ at room temperature. No significant isotopic dependence was observed and the temperature dependence of k/sub r/ is consistent with the literature value (0.5 eV) of the activation energy. The implications of this range of values of k/sub r/, for the estimation of the in-vessel tritium inventory following D-T operation in TFTR are discussed.

Dylla, H.F.; Cecchi, J.L.; Knize, R.J.

1983-12-01T23:59:59.000Z

384

Pipeline and Pressure Vessel R&D under the Hydrogen Regional Infrastructure  

E-Print Network (OSTI)

Pipeline and Pressure Vessel R&D under the Hydrogen Regional Infrastructure Program In Pennsylvania Kevin L. Klug, Ph.D. 25 September 2007 DOE Hydrogen Pipeline Working Group Meeting, Aiken, SCPerComp Engineering Inc. (HEI) ­ American Society Of Mechanical Engineers (ASME) ­ Pipeline Working Group (PWG) #12

385

K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations  

DOE Green Energy (OSTI)

Four bounding accidents postulated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing a hydrogen explosion, and a fire breaching filter vessel and enclosure. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

PIEPHO, M.G.

2000-01-10T23:59:59.000Z

386

BWRVIP-199: BWR Vessel and Internals Project, Testing and Evaluation of the Monticello 300 Degree Capsule  

Science Conference Proceedings (OSTI)

In the late 1990s, a BWR Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) was developed to improve the surveillance of the U. S. BWR fleet. This report describes testing and evaluation of the Monticello 300 Capsule. These results will be used to monitor embrittlement as part of the BWRVIP ISP.

2008-12-03T23:59:59.000Z

387

Walking and Climbing Service Robots for Safety Inspection of Nuclear Reactor Pressure Vessels  

E-Print Network (OSTI)

in this paper. Keywords: Remote inspection, Service robot, Non-destructive test, Nuclear, Climbing robotWalking and Climbing Service Robots for Safety Inspection of Nuclear Reactor Pressure Vessels B of Electronics and Computer Science, University of Southampton, Southampton, UK Abstract: Nuclear reactor

Chen, Sheng

388

Vessel centerline tracking in CTA and MRA images using hough transform  

Science Conference Proceedings (OSTI)

Vascular disease is characterized by any condition that affects the circulatory system. Recently, a demand for sophisticated software tools that can characterize the integrity and functional state of vascular networks from different vascular imaging ... Keywords: CTA, MRA, angiographic images, hough transform, lumen segmentation, vessel tracking

Maysa M. G. Macedo; Choukri Mekkaoui; Marcel P. Jackowski

2010-11-01T23:59:59.000Z

389

BWRVIP-200: BWR Vessel and Internals Project, Implementation Plan for Two-sided Inspection of BWR Shroud Welds  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP) formed in June 1994 and is an association of utilities focused exclusively on BWR vessel and internals issues. This BWRVIP report provides the technical basis for implementing two-sided inspections of BWR shrouds to satisfy the ultrasonic testing (UT) inspection requirements contained in BWRVIP-03 and BWRVIP-76.

2008-11-10T23:59:59.000Z

390

Design of control system for hydraulic lifting platform with jack-up wind-power installation vessel  

Science Conference Proceedings (OSTI)

Jack-up wind-power installation vessel is the most important tool in construction of wind farm. And the control system for hydraulic lifting platform is the key point of jack-up wind-power installation vessel. Therefore the design of the control system ... Keywords: hydraulic control, hydraulic lifting platform, programmable logic controller, wind-power

Xuejin Yang; Dingfang Chen; Mingwang Dong; Taotao Li

2012-11-01T23:59:59.000Z

391

DEVELOPMENT OF ASME SECTION X CODE RULES FOR HIGH PRESSURE COMPOSITE HYDROGEN PRESSURE VESSELS WITH NON-LOAD SHARING LINERS  

DOE Green Energy (OSTI)

The Boiler and Pressure Vessel Project Team on Hydrogen Tanks was formed in 2004 to develop Code rules to address the various needs that had been identified for the design and construction of up to 15000 psi hydrogen storage vessel. One of these needs was the development of Code rules for high pressure composite vessels with non-load sharing liners for stationary applications. In 2009, ASME approved new Appendix 8, for Section X Code which contains the rules for these vessels. These vessels are designated as Class III vessels with design pressure ranging from 20.7 MPa (3,000 ps)i to 103.4 MPa (15,000 psi) and maximum allowable outside liner diameter of 2.54 m (100 inches). The maximum design life of these vessels is limited to 20 years. Design, fabrication, and examination requirements have been specified, included Acoustic Emission testing at time of manufacture. The Code rules include the design qualification testing of prototype vessels. Qualification includes proof, expansion, burst, cyclic fatigue, creep, flaw, permeability, torque, penetration, and environmental testing.

Rawls, G.; Newhouse, N.; Rana, M.; Shelley, B.; Gorman, M.

2010-04-13T23:59:59.000Z

392

DETERMINATION OF LIQUID FILM THICKNESS FOLLOWING DRAINING OF CONTACTORS, VESSELS, AND PIPES IN THE MCU PROCESS  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) identified the caustic side solvent extraction (CSSX) process as the preferred technology to remove cesium from radioactive waste solutions at the Savannah River Site (SRS). As a result, Washington Savannah River Company (WSRC) began designing and building a Modular CSSX Unit (MCU) in the SRS tank farm to process liquid waste for an interim period until the Salt Waste Processing Facility (SWPF) begins operations. Both the solvent and the strip effluent streams could contain high concentrations of cesium which must be removed from the contactors, process tanks, and piping prior to performing contactor maintenance. When these vessels are drained, thin films or drops will remain on the equipment walls. Following draining, the vessels will be flushed with water and drained to remove the flush water. The draining reduces the cesium concentration in the vessels by reducing the volume of cesium-containing material. The flushing, and subsequent draining, reduces the cesium in the vessels by diluting the cesium that remains in the film or drops on the vessel walls. MCU personnel requested that Savannah River National Laboratory (SRNL) researchers conduct a literature search to identify models to calculate the thickness of the liquid films remaining in the contactors, process tanks, and piping following draining of salt solution, solvent, and strip solution. The conclusions from this work are: (1) The predicted film thickness of the strip effluent is 0.010 mm on vertical walls, 0.57 mm on horizontal walls and 0.081 mm in horizontal pipes. (2) The predicted film thickness of the salt solution is 0.015 mm on vertical walls, 0.74 mm on horizontal walls, and 0.106 mm in horizontal pipes. (3) The predicted film thickness of the solvent is 0.022 mm on vertical walls, 0.91 mm on horizontal walls, and 0.13 mm in horizontal pipes. (4) The calculated film volume following draining is: (a) Salt solution receipt tank--1.6 gallons; (b) Salt solution feed tank--1.6 gallons; (c) Decontaminated salt solution hold tank--1.6 gallons; (d) Contactor drain tank--0.40 gallons; (e) Strip effluent hold tank--0.33 gallons; (f) Decontaminated salt solution decanter--0.37 gallons; (g) Strip effluent decanter--0.14 gallons; (h) Solvent hold tank--0.30 gallon; and (i) Corrugated piping between contactors--16-21 mL. (5) After the initial vessel draining, flushing the vessels with 100 gallons of water using a spray nozzle that produces complete vessel coverage and draining the flush water reduces the source term by the following amounts: (i) Salt solution receipt tank--63X; (ii) Salt solution feed tank--63X; (iii) Decontaminated salt solution hold tank--63X; (iv) Contactor drain tank--250X; (v) Strip effluent hold tank--300X; (vi) Decontaminated salt solution decanter--270X; (vii) Strip effluent decanter--710X; (viii) Solvent hold tank--330X. Understand that these estimates of film thickness are based on laboratory testing and fluid mechanics theory. The calculations assume drainage occurs by film flow. Much of the data used to develop the models came from tests with very ''clean'' fluids. Impurities in the fluids and contaminants on the vessels walls could increase liquid holdup. The application of film thickness models and source term reduction calculations should be considered along with operational conditions and H-Tank Farm/Liquid Waste operating experience. These calculations exclude the PVV/HVAC duct work and piping, as well as other areas that area outside the scope of this report.

Poirier, M; Fernando Fondeur, F; Samuel Fink, S

2006-06-06T23:59:59.000Z

393

Design, fabrication and testing of a model heating and cooling system for a vacuum vessel  

SciTech Connect

A full-size model of a typical cooling and heating system for a vacuum vessel was manufactured and examined in order to clarify and enhance the efficiency and reliability of the designed system. The model consisted of two parts; one of which had the same structure as the other and was located facing each other to simulate the adiabatic condition of the vacuum-side of a vacuum vessel. Its components were rectangular plates, eletric heater units, cooling pipes inside of which water and air flew as cooling fluid. A lot of kinds of tests and measurements were performed to evaluate efficiency and reliability on the model. The numerical and theoretical analyses on the system were also carried out using the dimensional finite difference technique. The analytical results agreed pretty well with the experimental.

Shimizu, M.; Miyauchi, Y.; Nakamura, H.; Kajiura, S.; Koizumi, M.; Hata, M.

1981-01-01T23:59:59.000Z

394

Passive air cooling of liquid metal-cooled reactor with double vessel leak accommodation capability  

DOE Patents (OSTI)

A passive and inherent shutdown heat removal method with a backup air flow path which allows decay heat removal following a postulated double vessel leak event in a liquid metal-cooled nuclear reactor is disclosed. The improved reactor design incorporates the following features: (1) isolation capability of the reactor cavity environment in the event that simultaneous leaks develop in both the reactor and containment vessels; (2) a reactor silo liner tank which insulates the concrete silo from the leaked sodium, thereby preserving the silo`s structural integrity; and (3) a second, independent air cooling flow path via tubes submerged in the leaked sodium which will maintain shutdown heat removal after the normal flow path has been isolated. 5 figures.

Hunsbedt, A.; Boardman, C.E.

1995-04-11T23:59:59.000Z

395

Passive air cooling of liquid metal-cooled reactor with double vessel leak accommodation capability  

SciTech Connect

A passive and inherent shutdown heat removal method with a backup air flow path which allows decay heat removal following a postulated double vessel leak event in a liquid metal-cooled nuclear reactor. The improved reactor design incorporates the following features: (1) isolation capability of the reactor cavity environment in the event that simultaneous leaks develop in both the reactor and containment vessels; (2) a reactor silo liner tank which insulates the concrete silo from the leaked sodium, thereby preserving the silo's structural integrity; and (3) a second, independent air cooling flow path via tubes submerged in the leaked sodium which will maintain shutdown heat removal after the normal flow path has been isolated.

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

1995-01-01T23:59:59.000Z

396

USING A CONTAINMENT VESSEL LIFTING APPARATUS FOR REMOTE OPERATIONS OF SHIPPING PACKAGES  

SciTech Connect

The 9977 and the 9975 shipping packages are used in various nuclear facilities within the Department of Energy. These shipping packages are often loaded in designated areas with designs using overhead cranes or A-frames with lifting winches. However, there are cases where loading operations must be performed in remote locations where these facility infrastructures do not exist. For these locations, a lifting apparatus has been designed to lift the containment vessels partially out of the package for unloading operations to take place. Additionally, the apparatus allows for loading and closure of the containment vessel and subsequent pre-shipment testing. This paper will address the design of the apparatus and the challenges associated with the design, and it will describe the use of the apparatus.

Loftin, Bradley [Savannah River National Laboratory; Koenig, Richard [Savannah River National Laboratory

2013-08-08T23:59:59.000Z

397

Use of Polycarbonate Vacuum Vessels in High-Temperature Fusion-Plasma Research  

Science Conference Proceedings (OSTI)

Magnetic fusion energy (MFE) research requires ultrahigh-vacuum (UHV) conditions, primarily to reduce plasma contamination by impurities. For radiofrequency (RF)-heated plasmas, a great benefit may accrue from a non-conducting vacuum vessel, allowing external RF antennas which avoids the complications and cost of internal antennas and high-voltage high-current feedthroughs. In this paper we describe these and other criteria, e.g., safety, availability, design flexibility, structural integrity, access, outgassing, transparency, and fabrication techniques that led to the selection and use of 25.4-cm OD, 1.6-cm wall polycarbonate pipe as the main vacuum vessel for an MFE research device whose plasmas are expected to reach keV energies for durations exceeding 0.1 s

B. Berlinger, A. Brooks, H. Feder, J. Gumbas, T. Franckowiak and S.A. Cohen

2012-09-27T23:59:59.000Z

398

Vessel-Spanning Bubble Formation in K-Basin Sludge Stored in Large-Diameter Containers  

DOE Green Energy (OSTI)

The K Basin sludge to be retrieved and stored in the large diameter containers (LDCs) contains some fraction of uranium metal that generates hydrogen gas, which introduces potential upset conditions. One postulated upset condition is a rising plug of sludge supported by a hydrogen bubble that is driven into the vent filters at the top of the container. In laboratory testing with actual K Basin sludge, vessel-spanning bubbles that lifted plugs of sludge were observed in 3-inch-diameter graduated cylinders. This report presents a series of analytical assessments performed by the Pacific Northwest National Laboratory to address the potential for the generation of a vessel spanning bubble in the LDCs. The assessments included the development and evaluation of static and dynamic bubble formation models over the projected range of K Basin sludge physical properties. Additionally, the theory of circular plates was extrapolated to examine conditions under which a plug of sludge would collapse and release a spanning bubble.

Terrones, Guillermo; Gauglitz, Phillip A.

2002-03-01T23:59:59.000Z

399

Weld Repair of a Stamped Pressure Vessel in a Radiologically Controlled Zone  

Science Conference Proceedings (OSTI)

In September 2012 an ASME B&PVC Section VIII stamped pressure vessel located at the DOE Hanford Site Effluent Treatment Facility (ETF) developed a through-wall leak. The vessel, a steam/brine heat exchanger, operated in a radiologically controlled zone (by the CH2MHill PRC or CHPRC), had been in service for approximately 17 years. The heat exchanger is part of a single train evaporator process and its failure caused the entire system to be shut down, significantly impacting facility operations. This paper describes the activities associated with failure characterization, technical decision making/planning for repair by welding, logistical challenges associated with performing work in a radiologically controlled zone, performing the repair, and administrative considerations related to ASME code requirements.

Cannell, Gary L. [Fluor Enterprises, Inc.; Huth, Ralph J. [CH2MHill Plateau Remediation Company; Hallum, Randall T. [Fluor Government Group

2013-08-26T23:59:59.000Z

400

Interim Report: Coiled Tubing Drilling and Intervention System Using Cost Effective Vessel  

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

DOCUMENT TITLE: DOCUMENT TITLE: Self Supporting Riser Technology to Enable Coiled Tubing Intervention for Deepwater Wells Document No.: 08121-1502-12 RPSEA PROJECT TITLE: Coil Tubing Drilling and Intervention System Using a Cost Effective Vessel RPSEA Project No.: 08121-1502 01 April 2011 Charles R. Yemington, PE Project Manager Nautilus International 400 North Sam Houston Parkway East, Suite 105 Houston, Texas 77060 RPSEA Project No.: 08121-1502 Coiled Tubing Drilling and Intervention System Using a Cost Effective Vessel RPSEA Project 08121-1502 01 April 2011 Page 2 of 91 LEGAL NOTICE This report was prepared by Nautilus International, LLC. as an account of work sponsored by the Research Partnership to Secure Energy for America (RPSEA). RPSEA members, the

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Materials Reliability Program, Reactor Vessel Head Boric Acid Corrosion Testing (MRP-165)  

Science Conference Proceedings (OSTI)

Pressurized water reactor (PWR) coolant leakage from stress corrosion cracking of an Alloy 600 control rod drive mechanism (CRDM) penetration has led to one case of severe corrosion and cavity formation in a low-alloy steel reactor vessel head (RVH). The detailed progression of RVH wastage following initial leakage is complicated and probably involves several corrosion mechanisms. The Materials Reliability Program (MRP) has completed three tasks of a comprehensive program to examine postulated sequential...

2005-12-14T23:59:59.000Z

402

AUTHORIZATION OF THE TROJAN REACTOR VESSEL PACKAGE FOR ONE-TIME SHIPMENT FOR DISPOSAL (1)  

E-Print Network (OSTI)

Request Commission approval, by negative consent, for the staff to grant two specific exemptions from package test requirements specified in 10 CFR Part 71 for the Trojan Reactor Vessel Package (TRVP), and to authorize the TRVP for one-time transport for disposal. BACKGROUND: Portland General Electric Company (PGE) has requested approval of the TRVP (including internals) for transport to the disposal facility operated by US

L. Joseph; Callan Executive; Director Operations; John R. Cook

1998-01-01T23:59:59.000Z

403

Materials Reliability Program: San Onofre Nuclear Generating Station Reactor Vessel Internals Management Engineering Program (MRP-303)  

Science Conference Proceedings (OSTI)

All operating pressurized water reactors must have a reactor vessel internals aging management document in place by December 2011 according to the mandatory requirement under Nuclear Energy Institute (NEI) 03-08. This program should be developed to meet the guidance provided by Materials Reliability Program (MRP) -227, Rev. 0, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines. For non-license renewal plants, the requirements are valid within the current license period, and the Elec...

2011-02-28T23:59:59.000Z

404

Qualification of in-service examination of the Yankee Rowe reactor pressure vessel  

SciTech Connect

Technical support was provided to assist the Yankee Atomic Electric Company with their restart effort for the Yankee plant in Rowe, Massachusetts. Demonstration of adequate margin during a postulated pressurized thermal shock accident was an important part of the justification for restarting the plant, and effective inservice examination of the critical inner surface of the vessel in the beltline region was a key objective and a significant component of the safety analysis. This report discussed this inservice inspection.

Ammirato, F.; Kietzman, K.; Becker, L.; Ashwin, P.; Selby, G.; Krzywosz, K.; Findlan, S. (Electric Power Research Inst., Charlotte, NC (United States). Nondestructive Evaluation Center); Lance, J. (Yankee Atomic Electric Co., Bolton, MA (United States))

1992-12-01T23:59:59.000Z

405

Analysis of the ANL Test Method for 6CVS Containment Vessels  

Science Conference Proceedings (OSTI)

In the fall of 2010, Argonne National Laboratory (ANL) contracted with vendors to design and build 6CVS containment vessels as part of their effort to ship Fuel Derived Mixed Fission Product material. The 6CVS design is based on the Savannah River National Laboratory's (SRNL) design for 9975 and 9977 six inch diameter containment vessels. The main difference between the designs is that the 6CVS credits the inner O-ring seal as the containment boundary while the SRNL design credits the outer O-ring seal. Since the leak test must be done with the inner O-ring in place, the containment vessel does not have a pathway for getting the helium into the vessel during the leak test. The leak testing contractor was not able to get acceptable leak rates with the specified O-ring, but they were able to pass the leak test with a slightly larger O-ring. ANL asked the SRNL to duplicate the leak test vendor's method to determine the cause of the high leak rates. The SRNL testing showed that the helium leak indications were caused by residual helium left within the 6CVS Closure Assembly by the leak test technique, and by helium permeation through the Viton O-ring seals. After SRNL completed their tests, the leak testing contractor was able to measure acceptable leak rates by using the slightly larger O-ring size, by purging helium from the lid threads, and by being very quick in getting the bell jar under a full vacuum. This paper describes the leak test vendor's test technique, and other techniques that could be have been used to successfully leak test the 6CVS's.

Trapp, D.; Crow, G.

2011-06-06T23:59:59.000Z

406

Pressure vessel sliding support unit and system using the sliding support unit  

DOE Patents (OSTI)

Provided is a sliding support and a system using the sliding support unit. The sliding support unit may include a fulcrum capture configured to attach to a support flange, a fulcrum support configured to attach to the fulcrum capture, and a baseplate block configured to support the fulcrum support. The system using the sliding support unit may include a pressure vessel, a pedestal bracket, and a plurality of sliding support units.

Breach, Michael R.; Keck, David J.; Deaver, Gerald A.

2013-01-15T23:59:59.000Z

407

Materials Reliability Program: Reactor Vessel Head Boric Acid Corrosion Testing (MRP-199)  

Science Conference Proceedings (OSTI)

PWR coolant leakage from stress corrosion cracking of an Alloy 600 control rod drive mechanism (CRDM) penetration has led to one case of severe corrosion and cavity formation in a low-alloy steel reactor vessel head (RVH). The detailed progression of RVH wastage following initial leakage is complicated and probably involves several corrosion mechanisms. The Materials Reliability Program (MRP) has completed three tasks of a comprehensive program to examine postulated sequential stages of boric acid corros...

2007-06-27T23:59:59.000Z

408

Materials Reliability Program: Destructive Examination of the North Anna 2 Reactor Pressure Vessel Head (MRP-198)  

Science Conference Proceedings (OSTI)

This document is the final of three reports concerning the nondestructive and destructive examinations of selected control rod drive mechanism (CRDM) penetrations from the decommissioned North Anna Unit 2 reactor vessel head (RVH). The phase-1 report of the EPRI-MRP (Materials Reliability Program) managed program described the selection and removal of penetrations from the decommissioned RVH and the penetration decontamination and laboratory nondestructive evaluation (NDE). The phase-2 report detailed th...

2006-11-13T23:59:59.000Z

409

Materials Reliability Program: Utility Preparation for Nondestructive Evaluation of Reactor Vessel Upper Head Penetrations (MRP-360)  

Science Conference Proceedings (OSTI)

The purpose of this report is to provide nuclear power plant owners with recommendations for planning and executing reactor vessel upper head (RVUH) penetration examinations in a manner that will minimize the occurrence of human errors while maximizing the probability of success. RVUH penetrations include control rod drive mechanism, control element drive mechanism, in-core instrumentation, and vent line penetrations. These encompass the standard nomenclatures for domestic utilities but might not ...

2013-12-19T23:59:59.000Z

410

Simulant Melt Experiments on Performance of the In-Vessel Core Catcher  

SciTech Connect

In order to enhance the feasibility of in-vessel retention (IVR) of molten core material during a severe accident for high-power reactors, an in-vessel core catcher (IVCC) was designed and evaluated as part of a joint United States-Korean International Nuclear Energy Research Initiative (INERI). The proposed IVCC is expected to increase the thermal margin for success of IVR by providing an engineered gap for heat transfer from materials that relocate during a severe accident and potentially serving as a sacrificial material under a severe accident. In this study, LAVA-GAP experiments were performed to investigate the thermal and mechanical performance of the IVCC using the alumina melt as simulant. The LAVAGAP experiments aim to examine the feasibility and sustainability of the IVCC under the various test conditions using 1/8th scale hemispherical test sections. As a feasibility test of the proposed IVCC in this INERI project, the effects of IVCC base steel materials, internal coating materials, and gap size between the IVCC and the vessel lower head were examined. The test results indicated that the internally coated IVCC has high thermal performance compared with the uncoated IVCC. In terms of integrity of the base steel, carbon steel is superior to stainless steel and the effect of bond coat is found to be trivial for the tests performed in this study. The thermal load is mitigated via boiling heat removal in the gap between the IVCC and the vessel lower head. The current test results imply that gaps less than 10mm are not enough to guarantee effective cooling induced by water ingression and steam venting there through. Selection of endurable material and pertinent gap size is needed to implement the proposed IVCC concept into advanced reactor designs.

Kyoung-Ho Kang; Rae-Joon Park; Sang-Baik Kim; K. Y. Suh; F. B. Cheung; J. L. Rempe

2007-09-01T23:59:59.000Z

411

Development of an Enhanced Core Catcher for Improving In-Vessel Retention Margins  

Science Conference Proceedings (OSTI)

In-vessel retention (IVR) of core melt that may relocate to the lower head of a reactor vessel is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for several advanced light water reactors. A U.S.-Korean International Nuclear Energy Research Initiative project has been initiated to explore design enhancements that could increase the margin for IVR for advanced reactors with higher power levels [up to 1500 MW(electric)]. As part of this effort, an enhanced in-vessel core catcher is being designed and evaluated. To reduce cost and simplify manufacture and installation, this new core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. If needed, the core catcher can be manufactured with holes to accommodate lower head penetrations. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary). The first is a base material that has the capability to support and contain the mass of core materials that may relocate during a severe accident; the second is an oxide coating on top of the base material, which resists interactions with high-temperature core materials; and the third is an optional coating on the bottom side of the base material to protect it from oxidation during the lifetime of the reactor. This paper summarizes results from the in-vessel core catcher design and evaluation efforts, focusing on recently obtained results from materials interaction tests and prototypic testing activities.

Rempe, J.L. [Idaho National Engineering and Environmental Laboratory (United States); Condie, K.G. [Idaho National Engineering and Environmental Laboratory (United States); Knudson, D.L. [Idaho National Engineering and Environmental Laboratory (United States); Suh, K.Y. [Seoul National University (Korea, Republic of); Cheung, F.B. [The Pennsylvania State University (United States); Kim, S.B. [Korea Atomic Energy Research Institute (Korea, Republic of)

2005-11-15T23:59:59.000Z

412

Trojan Nuclear Power Plant Reactor Vessel and Internals Removal: Trojan Nuclear Plant Decommissioning Experience  

Science Conference Proceedings (OSTI)

One goal of the EPRI Decommissioning Technology Program is to capture the growing utility experience in nuclear plant decommissioning activities for the benefit of other utilities facing similar challenges in the future. This report provides historical information on the background, scope, organization, schedule, cost, contracts, and support activities associated with the Trojan Nuclear Plant Reactor Vessel and Internals Removal (RVAIR) Project. Also discussed are problems, successes, and lessons learned...

2000-10-16T23:59:59.000Z

413

BWRVIP-118: BWR Vessel and Internals Project: NMCA Experience Report and Applications Guidelines, 2003 Revision  

Science Conference Proceedings (OSTI)

The boiling water reactor (BWR) fleet has widely embraced noble metal chemical addition (NMCA) to provide protection against intergranular stress corrosion cracking (IGSCC). This report, prepared by a Boiling Water Reactor Vessel and Internals Project (BWRVIP) focus group, updates a report issued in 2001 that compiled data from plants operating on NMCA. It provides guidance for BWRs planning to implement NMCA, and information about expected plant response to operation with NMCA. It also identifies steps ...

2003-11-24T23:59:59.000Z

414

File:06HIGBoilerPressureVesselPermit.pdf | Open Energy Information  

Open Energy Info (EERE)

HIGBoilerPressureVesselPermit.pdf HIGBoilerPressureVesselPermit.pdf Jump to: navigation, search File File history File usage File:06HIGBoilerPressureVesselPermit.pdf Size of this preview: 463 × 599 pixels. Other resolution: 464 × 600 pixels. Full resolution ‎(1,275 × 1,650 pixels, file size: 47 KB, MIME type: application/pdf) File history Click on a date/time to view the file as it appeared at that time. Date/Time Thumbnail Dimensions User Comment current 09:08, 24 October 2012 Thumbnail for version as of 09:08, 24 October 2012 1,275 × 1,650 (47 KB) Dklein2012 (Talk | contribs) 12:32, 23 October 2012 Thumbnail for version as of 12:32, 23 October 2012 1,275 × 1,650 (47 KB) Dklein2012 (Talk | contribs) 16:30, 24 July 2012 Thumbnail for version as of 16:30, 24 July 2012 1,275 × 1,650 (44 KB) Alevine (Talk | contribs)

415

A Flaw Tolerance Approach to Address Reactor Vessel Head Penetration Cracking Issue  

SciTech Connect

Nickel-based alloys and the associated welds are susceptible to Primary Water Stress Corrosion Cracking. In Pressurized Water Reactor nuclear power plants, the reactor vessel closure head upper penetration nozzles used for the Control Rod Drive Mechanisms and other instrumentation systems are made of such nickel-based alloys. Cracking and leakage have been observed in the upper head penetration nozzles in nuclear power plants worldwide. Such cracking and the resulting leakage is a degradation of the reactor vessel pressure boundary. Regulatory requirements have been issued by the Nuclear Regulatory Commission regarding periodic inspection of the susceptible areas to enable detection of indications and provide reasonable assurance of continued structural integrity for reactor vessel closure head. A flaw tolerance approach has been used in the disposition of detected indications to minimize outage delays, by performing up-front fracture mechanics evaluations for the common types of indications detected in the susceptible areas. Details of the flaw tolerance approach are presented in this paper. (authors)

Ng, C. K.; Jirawongkraisorn, S.; Swamy, S. [Westinghouse Electric Company, LLC, Nuclear Services Division, P. O. Box 158, Madison, PA 15663 (United States)

2006-07-01T23:59:59.000Z

416

DESIGN OF A CONTAINMENT VESSEL CLOSURE FOR SHIPMENT OF TRITIUM GAS  

SciTech Connect

This paper presents a design summary of the containment vessel closure for the Bulk Tritium Shipping Package (BTSP). This new package is a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The new design is based on changes in the regulatory requirements. The BTSP design incorporates many improvements over its predecessor by implementing improved testing, handling, and maintenance capabilities, while improving manufacturability and incorporating new engineered materials that enhance the package's ability to withstand dynamic loading and thermal effects. This paper will specifically summarize the design philosophy and engineered features of the BTSP containment vessel closure. The closure design incorporates a concave closure lid, metallic C-Ring seals for containing tritium gas, a metal bellows valve and an elastomer O-Ring for leak testing. The efficient design minimizes the overall vessel height and protects the valve housing from damage during postulated drop and crush scenarios. Design features will be discussed.

Eberl, K; Paul Blanton, P

2007-07-03T23:59:59.000Z

417

Refractory lining system for high wear area of high temperature reaction vessel  

DOE Patents (OSTI)

A refractory-lined high temperature reaction vessel comprises a refractory ring lining constructed of refractory brick, a cooler, and a heat transfer medium disposed between the refractory ring lining and the cooler. The refractory brick comprises magnesia (MgO) and graphite. The heat transfer medium contacts the refractory brick and a cooling surface of the cooler, and is composed of a material that accommodates relative movement between the refractory brick and the cooler. The brick is manufactured such that the graphite has an orientation providing a high thermal conductivity in the lengthwise direction through the brick that is higher than the thermal conductivity in directions perpendicular to the lengthwise direction. The graphite preferably is flake graphite, in the range of about 10 to 20 wt %, and has a size distribution selected to provide maximum brick density. The reaction vessel may be used for performing a reaction process including the steps of forming a layer of slag on a melt in the vessel, the slag having a softening point temperature range, and forming a protective frozen layer of slag on the interior-facing surface of the refractory lining in at least a portion of a zone where the surface contacts the layer of slag, the protective frozen layer being maintained at or about the softening point of the slag. 10 figs.

Hubble, D.H.; Ulrich, K.H.

1998-09-22T23:59:59.000Z

418

Refractory lining system for high wear area of high temperature reaction vessel  

DOE Patents (OSTI)

A refractory-lined high temperature reaction vessel comprises a refractory ring lining constructed of refractory brick, a cooler, and a heat transfer medium disposed between the refractory ring lining and the cooler. The refractory brick comprises magnesia (MgO) and graphite. The heat transfer medium contacts the refractory brick and a cooling surface of the cooler, and is composed of a material that accommodates relative movement between the refractory brick and the cooler. The brick is manufactured such that the graphite has an orientation providing a high thermal conductivity in the lengthwise direction through the brick that is higher than the thermal conductivity in directions perpendicular to the lengthwise direction. The graphite preferably is flake graphite, in the range of about 10 to 20 wt %, and has a size distribution selected to provide maximum brick density. The reaction vessel may be used for performing a reaction process including the steps of forming a layer of slag on a melt in the vessel, the slag having a softening point temperature range, and forming a protective frozen layer of slag on the interior-facing surface of the refractory lining in at least a portion of a zone where the surface contacts the layer of slag, the protective frozen layer being maintained at or about the softening point of the slag.

Hubble, David H. (Export, PA); Ulrich, Klaus H. (Duisburg, DE)

1998-01-01T23:59:59.000Z

419

HYDROGEN EFFECTS ON THE BURST PROPERTIES OF TYPE 304L STAINLESS STEEL FLAWED VESSELS  

DOE Green Energy (OSTI)

The effect of hydrogen on the burst properties Type 304L stainless steel vessels was investigated. The purpose of the study was to compare the burst properties of hydrogen-exposed stainless steel vessels burst with different media: water, helium gas, or deuterium gas. A second purpose of the tests was to provide data for the development of a predictive finite-element model. The burst tests were conducted on hydrogen-exposed and unexposed axially-flawed cylindrical vessels. The results indicate that samples burst pneumatically had lower volume ductility than those tested hydraulically. Deuterium gas tests had slightly lower ductility than helium gas tests. Burst pressures were not affected by burst media. Hydrogen-charged samples had lower volume ductility and slightly higher burst pressures than uncharged samples. Samples burst with deuterium gas fractured by quasi-cleavage near the inside wall. The results of the tests were used to improve a previously developed predictive finite-element model. The results show that predicting burst behavior requires as a material input the effect of hydrogen on the plastic strain to fracture from tensile tests. The burst test model shows that a reduction in the plastic strain to fracture of the material will result in lower volume ductility without a reduction in burst pressure which is in agreement with the burst results.

Morgan, M; Monica Hall, M; Ps Lam, P; Dean Thompson, D

2008-03-27T23:59:59.000Z

420

Fabrication Flaw Density and Distribution In Repairs to Reactor Pressure Vessel and Piping Welds  

Science Conference Proceedings (OSTI)

The Pacific Northwest National Laboratory is developing a generalized fabrication flaw distribution for the population of nuclear reactor pressure vessels and for piping welds in U.S. operating reactors. The purpose of the generalized flaw distribution is to predict component-specific flaw densities. The estimates of fabrication flaws are intended for use in fracture mechanics structural integrity assessments. Structural integrity assessments, such as estimating the frequency of loss-of-coolant accidents, are performed by computer codes that require, as input, accurate estimates of flaw densities. Welds from four different reactor pressure vessels and a collection of archived pipes have been studied to develop empirical estimates of fabrication flaw densities. This report describes the fabrication flaw distribution and characterization in the repair weld metal of vessels and piping. This work indicates that large flaws occur in these repairs. These results show that repair flaws are complex in composition and sometimes include cracks on the ends of the repair cavities. Parametric analysis using an exponential fit is performed on the data. The relevance of construction records is established for describing fabrication processes and product forms. An analysis of these records shows there was a significant change in repair frequency over the years when these components were fabricated. A description of repair flaw morphology is provided with a discussion of fracture mechanics significance. Fabrication flaws in repairs are characterized using optimized-access, high-sensitivity nondestructive ultrasonic testing. Flaw characterizations are then validated by other nondestructive evaluation techniques and complemented by destructive testing.

GJ Schuster, FA Simonen, SR Doctor

2008-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Distillate Fuel Oil Sales for Railroad Use  

Gasoline and Diesel Fuel Update (EIA)

3,634,512 3,229,625 2,759,140 2,974,641 3,121,150 3,118,150 3,634,512 3,229,625 2,759,140 2,974,641 3,121,150 3,118,150 1984-2012 East Coast (PADD 1) 580,632 500,071 459,324 482,929 514,418 492,156 1984-2012 New England (PADD 1A) 69,282 47,582 43,763 53,930 51,126 33,306 1984-2012 Connecticut 4,450 3,219 2,219 2,006 2,006 5,195 1984-2012 Maine 126 1,694 7,252 8,284 6,818 5,970 1984-2012 Massachusetts 63,896 40,378 24,852 33,130 32,647 12,307 1984-2012 New Hampshire 119 126 697 86 124 116 1984-2012 Rhode Island 13 72 4 24 3 133 1984-2012 Vermont 678 2,092 8,740 10,400 9,528 9,586 1984-2012 Central Atlantic (PADD 1B) 210,461 177,750 152,309 196,570 233,005 204,527 1984-2012 Delaware 1,404 1,120 1,096 879 126 149 1984-2012 District of Columbia 0 0 0 1,229 6,392 6,770 1984-2012

422

Distillate Fuel Oil Sales for Railroad Use  

U.S. Energy Information Administration (EIA)

Central Atlantic (PADD 1B) 210,461: 177,750: 152,309: 196,570: 233,005: 204,527: 1984-2012: Delaware: 1,404: 1,120: ... Washington: 105,180: 78,701: ...

423

Railroads and shippers clash over coal dust  

Science Conference Proceedings (OSTI)

In an effort to reduce coal spillage from railcars, mines in the Powder River Basin (PRB) now load coal with a loaf profile but, reportedly, beginning in 2008, Burlington Northern Santa Fe (BNSF) will announce guidelines requiring all PRB coal loads to be sprayed with a chemical surfactant. If this does not fix the problem, greater measures will be taken. At the time of going to press, the details of how this would be implemented and regulated were unresolved. 1 photo.

Buchsbaum, L.

2007-11-15T23:59:59.000Z

424

Railroad Valley Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Power Plants (0) Projects (0) Activities (1) NEPA(0) Geothermal Area Profile Location Nevada Exploration Region Northern Basin and Range Geothermal Region GEA Development Phase...

425

Lower railroad energy consumption reflects improved efficiency ...  

U.S. Energy Information Administration (EIA)

Energy use in homes, commercial buildings, manufacturing, and transportation. ... Alternative Fuels. Includes hydropower, solar, wind, geothermal, biomass and ethanol.

426

Railroad transportation of spent nuclear fuel  

Science Conference Proceedings (OSTI)

This report documents a detailed analysis of rail operations that are important for assessing the risk of transporting high-level nuclear waste. The major emphasis of the discussion is towards ''general freight'' shipments of radioactive material. The purpose of this document is to provide a basis for selecting models and parameters that are appropriate for assessing the risk of rail transportation of nuclear waste.

Wooden, D.G.

1986-03-01T23:59:59.000Z

427

Sitewide railroad ties volatile organic package  

SciTech Connect

The initial GC/MS calibration and continuing calibration met all protocols. The calibration working standard is made from 9 separate mixes. One of the mixes (Restek semivolatile mix 3) was doubled, increasing the calibration concentration curve by a factor of two. None of the compounds of interest were affected, and all of the forms have been adjusted. All mass spectral tuning requirements were met for all standards and samples. Internal standard criteria were met for field blank R5306. Perylene-d12 was out on the low side. This sample was reanalyzed and all internal standard criteria were met. The R5302rerr was reported instead of R5302re (the original run of the re-extract) because R5302re failed its internal standard criteria. RSBLK03rr was reported instead of RSBLK03 (the original run of the method blank) because RSBLK03 failed its internal standard criteria. Internal standard criteria for all other samples in this package were met.

Vogel, R.E.

1994-08-31T23:59:59.000Z

428

Railroad Civil Rights Policies | Data.gov  

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

dan.morgan.ctr@dot.gov Unique Identifier DOT-4360 Public Access Level public Data Dictionary Data Download URL http:www.fra.dot.govPages2055.shtml Format HTML License...

429

Karen Hedlund, Chief Counsel Federal Railroad Administration  

E-Print Network (OSTI)

Communities +200% land consumption per capita (1977-2010) (Source: Center for Neighborhood Technology Dependency 13m barrels/day for transportation ­ 5x E.U. (Source: U.S. Energy Information Administration - Population Growth Studies project dramatic growth in population which will drive increased passenger mobility

Bustamante, Fabián E.

430

Locomotion : a railroad museum for Chattanooga  

E-Print Network (OSTI)

This thesis is about exploring an architecture that serves a dual purpose: one, as witness to the past, and, two, as evidence of a constantly changing built environment. It is about exploring a landscape rich with associative ...

Kim, Julie Ju Youn

1994-01-01T23:59:59.000Z

431

Lower railroad energy consumption reflects improved efficiency ...  

U.S. Energy Information Administration (EIA)

Electricity. Sales, revenue and prices, power plants, fuel use, stocks, generation, ... Tonnage moved in 2012 was significantly lower than the 2006 ...

432

A Multisensor Comparison of Ocean Wave Frequency Spectra from a Research Vessel during the Southern Ocean Gas Exchange Experiment  

Science Conference Proceedings (OSTI)

Obtaining accurate measurements of wave statistics from research vessels remains a challenge due to platform motion. One principal correction is the removal of ship heave and Doppler effects from point measurements. Here, open ocean wave ...

Alejandro Cifuentes-Lorenzen; James. B. Edson; Christopher J. Zappa; Ludovic Bariteau

433

Measurement of Wind Waves and Wave-Coherent Air Pressures on the Open Sea from a Moving SWATH Vessel  

Science Conference Proceedings (OSTI)

The design and implementation on a Small Waterline Area Twin Hull (SWATH) vessel of a complete system for measuring the directional distribution of wind waves and the concomitant fluctuations of air pressure and wind speed immediately above them ...

Mark A. Donelan; Fred W. Dobson; Hans C. Graber; Niels Madsen; Cyril McCormick

2005-07-01T23:59:59.000Z

434

Investigation of downward facing critical heat flux with water-based nanofluids for In-Vessel Retention applications.  

E-Print Network (OSTI)

??In-Vessel Retention ("IVR") is a severe accident management strategy that is power limiting to the Westinghouse AP1000 due to critical heat flux ("CHF") at the (more)

DeWitt, Gregory L

2011-01-01T23:59:59.000Z

435

Investigation of the use of nanofluids to enhance the In-Vessel Retention capabilities of Advanced Light Water Reactors  

E-Print Network (OSTI)

Nanofluids at very low concentrations experimentally exhibit a substantial increase in Critical Heat Flux (CHF) compared to water. The use of a nanofluid in the In-Vessel Retention (IVR) severe accident management strategy, ...

Hannink, Ryan Christopher

2007-01-01T23:59:59.000Z

436

Program on Technology Innovation: Weld Metals and Welding Processes for Fabrication of Advanced Light Water Reactor Pressure Vessels  

Science Conference Proceedings (OSTI)

Light water reactors have traditionally been constructed using roll-formed plates for the reactor pressure vessel (RPV) shells, which were assembled via horizontal and vertical seam welds. Weld filler metals often contained significant quantities of copper, other residual elements such as vanadium, and nonmetallic elements such as phosphorous and sulfur. Low-alloy steel weld filler metals of this chemical composition contributed to the degree of neutron radiation-induced embrittlement of vessel ...

2013-06-26T23:59:59.000Z

437

BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) has developed methodologies to evaluate crack growth in internal components of stainless steel and nickel-base alloys in the BWR vessel. One BWRVIP reportBWRVIP-14developed an approach to evaluate crack growth by intergranular stress corrosion cracking in austenitic stainless steel core shrouds exposed to a limited amount of neutron irradiation. Subsequently another reportBWRVIP-99was prepared to provide a crack growth methodology applicable to irradiated...

2008-11-24T23:59:59.000Z

438

BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan  

Science Conference Proceedings (OSTI)

This report describes the boiling water reactor (BWR) Integrated Surveillance Program (ISP). Based on recommendations from BWR Vessel and Internals Project (BWRVIP) utilities, it was concluded that combining all separate BWR surveillance programs into a single integrated program would be beneficial. In the integrated program, representative materials chosen for a specific reactor pressure vessel (RPV) can be materials from another plant surveillance program or other source that better represents the ...

2012-10-01T23:59:59.000Z

439

BWRVIP-41, Revision 3: BWR Vessel and Internals Project, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on BWR vessel and internals issues. This BWRVIP report provides information on potential failure locations in BWR/3-6 jet pump components and recommends an inspection program designed to ensure that the integrity of all jet pump safety functions is maintained. EPRI published a previous version of this report as BWRVIP-41, Revision 2 (EPRI 1019570). This report (EPRI Rep...

2010-09-10T23:59:59.000Z

440

BWRVIP-18, Revision 1-A: BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. This BWRVIP report contains generic guidelines that describe locations on the core spray piping and spargers for which inspection is needed, categories of plants for which inspection needs would differ, extent of inspection and reinspection for each location, and flaw evaluation procedures to determine ...

2012-04-09T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

Manufacturing Cost Analysis of Novel Steel/Concrete Composite Vessel for Stationary Storage of High-Pressure Hydrogen  

SciTech Connect

A novel, low-cost, high-pressure, steel/concrete composite vessel (SCCV) technology for stationary storage of compressed gaseous hydrogen (CGH2) is currently under development at Oak Ridge National Laboratory (ORNL) sponsored by DOE s Fuel Cell Technologies (FCT) Program. The SCCV technology uses commodity materials including structural steels and concretes for achieving cost, durability and safety requirements. In particular, the hydrogen embrittlement of high-strength low-alloy steels, a major safety and durability issue for current industry-standard pressure vessel technology, is mitigated through the use of a unique layered steel shell structure. This report presents the cost analysis results of the novel SCCV technology. A high-fidelity cost analysis tool is developed, based on a detailed, bottom-up approach which takes into account the material and labor costs involved in each of the vessel manufacturing steps. A thorough cost study is performed to understand the SCCV cost as a function of the key vessel design parameters, including hydrogen pressure, vessel dimensions, and load-carrying ratio. The major conclusions include: The SCCV technology can meet the technical/cost targets set forth by DOE s FCT Program for FY2015 and FY2020 for all three pressure levels (i.e., 160, 430 and 860 bar) relevant to the hydrogen production and delivery infrastructure. Further vessel cost reduction can benefit from the development of advanced vessel fabrication technologies such as the highly automated friction stir welding (FSW). The ORNL-patented multi-layer, multi-pass FSW can not only reduce the amount of labor needed for assembling and welding the layered steel vessel, but also make it possible to use even higher strength steels for further cost reductions and improvement of vessel structural integrity. It is noted the cost analysis results demonstrate the significant cost advantage attainable by the SCCV technology for different pressure levels when compared to the industry-standard pressure vessel technology. The real-world performance data of SCCV under actual operating conditions is imperative for this new technology to be adopted by the hydrogen industry for stationary storage of CGH2. Therefore, the key technology development effort in FY13 and subsequent years will be focused on the fabrication and testing of SCCV mock-ups. The static loading and fatigue data will be generated in rigorous testing of these mock-ups. Successful tests are crucial to enabling the near-term impact of the developed storage technology on the CGH2 storage market, a critical component of the hydrogen production and delivery infrastructure. In particular, the SCCV has high potential for widespread deployment in hydrogen fueling stations.

Feng, Zhili [ORNL; Zhang, Wei [ORNL; Wang, Jy-An John [ORNL; Ren, Fei [ORNL

2012-09-01T23:59:59.000Z

442

Detection and characterization of flaws in segments of light water reactor pressure vessels  

Science Conference Proceedings (OSTI)

Studies have been conducted to determine flaw density in segments cut from light water reactor (LWR) pressure vessels as part of the Oak Ridge National Laboratory's Heavy-Section Steel Technology (HSST) Program. Segments from the Hope Creek Unit 2 vessil and the Pilgrim Unit 2 Vessel were purchased from salvage dealers. Hope Creek was a boiling water reactor (BWR) design and Pilgrim was a pressurized water reactor (PWR) design. Neither were ever placed in service. Objectives were to evaluate these LWR segments for flaws with ultrasonic and liquid penetrant techniques. Both objectives were successfully completed. One significant indication was detected in a Hope Creek seam weld by ultrasonic techniques and characterized by further analyses terminating with destructive correlation. This indication (with a through-wall dimension of approx.6 mm (approx.0.24 in.)) was detected in only 3 m (10 ft) of weldment and offers extremely limited data when compared to the extent of welding even in a single pressure vessel. However, the detection and confirmation of the flaw in the arbitrarily selected sections implies the Marshall report estimates (and others) are nonconservative for such small flaws. No significant indications were detected in the Pilgrim material by ultrasonic techniques. Unfortunately, the Pilgrim segments contained relatively little weldment; thus, we limited our ultrasonic examinations to the cladding and subcladding regions. Fluorescent liquid penetrant inspection of the cladding surfaces for both LWR segments detected no significant indications (i.e., for a total of approximately 6.8 m/sup 2/ (72 ft/sup 2/) of cladding surface).

Cook, K.V.; Cunningham, R.A. Jr.; McClung, R.W.

1987-01-01T23:59:59.000Z

443

Application of small specimens to fracture mechanics characterization of irradiated pressure vessel steels  

SciTech Connect

In this study, precracked Charpy V-notch (PCVN) specimens were used to characterize the fracture toughness of unirradiated and irradiated reactor pressure vessel steels in the transition region by means of three-point static bending. Fracture toughness at cleavage instability was calculated in terms of elastic-plastic K{sub Jc} values. A statistical size correction based upon weakest-link theory was performed. The concept of a master curve was applied to analyze fracture toughness properties. Initially, size-corrected PCVN data from A 533 grade B steel, designated HSST Plate O2, were used to position the master curve and a 5% tolerance bound for K{sub Jc} data. By converting PCVN data to IT compact specimen equivalent K{sub Jc} data, the same master curve and 5% tolerance bound curve were plotted against the Electric Power Research Institute valid linear-elastic K{sub Jc} database and the ASME lower bound K{sub Ic} curve. Comparison shows that the master curve positioned by testing several PCVN specimens describes very well the massive fracture toughness database of large specimens. These results give strong support to the validity of K{sub Jc} with respect to K{sub Ic} in general and to the applicability of PCVN specimens to measure fracture toughness of reactor vessel steels in particular. Finally, irradiated PCVN specimens of other materials were tested, and the results are compared to compact specimen data. The current results show that PCVNs demonstrate very good capacity for fracture toughness characterization of reactor pressure vessel steels. It provides an opportunity for direct measurement of fracture toughness of irradiated materials by means of precracking and testing Charpy specimens from surveillance capsules. However, size limits based on constraint theory restrict the operational test temperature range for K{sub Jc} data from PCVN specimens. 13 refs., 8 figs., 1 tab.

Sokolov, M.A.; Wallin, K.; McCabe, D.E.

1996-12-31T23:59:59.000Z

444

Dual shell reactor vessel: A pressure-balanced system for high pressure and temperature reactions  

Science Conference Proceedings (OSTI)

The main purpose of this work was to demonstrate the Dual Shell Pressure Balanced Vessel (DSPBV) as a safe and economical reactor for the hydrothermal water oxidation of hazardous wastes. Experimental tests proved that the pressure balancing piston and the leak detection concept designed for this project will work. The DSPBV was sized to process 10 gal/hr of hazardous waste at up to 399{degree}C (750{degree}F) and 5000 psia (34.5 MPa) with a residence time of 10 min. The first prototype reactor is a certified ASME pressure vessel. It was purchased by Innotek Corporation (licensee) and shipped to Pacific Northwest Laboratory for testing. Supporting equipment and instrumentation were, to a large extent, transported here from Battelle Columbus Division. A special air feed system and liquid pump were purchased to complete the package. The entire integrated demonstration system was assembled at PNL. During the activities conducted for this report, the leak detector design was tested on bench top equipment. Response to low levels of water in oil was considered adequate to ensure safety of the pressure vessel. Shakedown tests with water only were completed to prove the system could operate at 350{degree}C at pressures up to 3300 psia. Two demonstration tests with industrial waste streams were conducted, which showed that the DSPBV could be used for hydrothermal oxidation. In the first test with a metal plating waste, chemical oxygen demand, total organic carbon, and cyanide concentrations were reduced over 90%. In the second test with a munitions waste, the organics were reduced over 90% using H{sub 2}O{sub 2} as the oxidant.

Robertus, R.J.; Fassbender, A.G.; Deverman, G.S.

1995-03-01T23:59:59.000Z

445

CHARACTERIZATION OF RADIOACTIVITY IN THE REACTOR VESSEL OF THE HEAVY WATER COMPONENT TEST REACTOR  

Science Conference Proceedings (OSTI)

The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that was used to test candidate fuel designs for heavy water power reactors. The reactor operated at nominal power of 50 MW{sub th}. The reactor coolant loop operated at 1200 psig and 250 C. Two isolated test loop were designed into the reactor to provide special test conditions. Fig. 1 shows a cut-away view of the reactor. The two loops are contained in four inch diameter stainless steel piping. The HWCTR was operated for only a short duration, from March 1962 to December 1964 in order to test the viability of test fuel elements and other reactor components for use in a heavy water power reactor. The reactor achieved 13,882 MWd of total power while testing 36 different fuel assemblies. In the course of operation, HWCTR experienced the cladding failures of 10 separate test fuel assemblies. In each case, the cladding was breached with some release of fuel core material into the isolated test loop, causing fission product and actinide contamination in the main coolant loop and the liquid and boiling test loops. Despite the contribution of the contamination from the failed fuel, the primary source of radioactivity in the HWCTR vessel and internals is the activation products in the thermal shields, and to a lesser degree, activation products in the reactor vessel walls and liner. A detailed facility characterization report of the HWCTR facility was completed in 1996. Many of the inputs and assumptions in the 1996 characterization report were derived from the HWCTR decommissioning plan published in 1975. The current paper provides an updated assessment of the radioisotopic characteristics of the HWCTR vessel and internals to support decommissioning activities on the facility.

Vinson, Dennis

2010-06-01T23:59:59.000Z

446

Domestic Coal Distribution 2009 Q1 by Origin State: Alabama  

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

Q1 by Origin State: Alabama Q1 by Origin State: Alabama (1000 Short Tons) 1 / 58 Domestic Coal Distribution 2009 Q1 by Origin State: Alabama (1000 Short Tons) Destination State Transportation Mode Electricity Generation Coke Plants Industrial Plants Excluding Coke Commercial & Institutional Total Alabama Railroad 950 4 84 - 1,038 Alabama River 1,110 - - - 1,110 Alabama Truck 37 170 249 - 456 Alabama Total 2,096 174 333 - 2,603 Florida Railroad - - 22 - 22 Georgia Railroad 45 - - - 45 Georgia Truck s - 20 - 21 Georgia Total 45 - 20 - 65 Hawaii Ocean Vessel s - - - s Indiana Railroad - 78 - - 78 Indiana Truck - 32 - - 32 Indiana Total - 110 - - 110 South Carolina Truck - - 2 - 2 Tennessee Truck - - 1 - 1 Texas Railroad 72 - - - 72 Origin State Total 2,213 284 378 - 2,875 Ocean Vessel s - - - s Railroad 1,066 82 106 - 1,255 River 1,110 - - - 1,110 Truck 37 202 272 - 511 2 / 58

447

Elliptical Local Vessel Density: a Fast and Robust Quality Metric for Fundus Images  

SciTech Connect

A great effort of the research community is geared towards the creation of an automatic screening system able to promptly detect diabetic retinopathy with the use of fundus cameras. In addition, there are some documented approaches to the problem of automatically judging the image quality. We propose a new set of features independent of Field of View or resolution to describe the morphology of the patient's vessels. Our initial results suggest that they can be used to estimate the image quality in a time one order of magnitude shorter respect to previous techniques.

Giancardo, Luca [ORNL; Chaum, Edward [ORNL; Karnowski, Thomas Paul [ORNL; Meriaudeau, Fabrice [ORNL; Tobin Jr, Kenneth William [ORNL; Abramoff, M.D. [University of Iowa

2008-01-01T23:59:59.000Z

448

Ex-vessel core catcher materials interactions. Annual progress report. [LMFBR  

SciTech Connect

A twelve-month program to investigate ex-vessel core catcher materials interactions has been completed. The investigations, involving depleted uranium dioxide, magnesia brick, stainless steel, and low-carbon steel, were conducted in furnaces and associated facilities existing at Aerospace, which were modified to process molten and solidified radioactive samples. In addition to developing efficient methods for the melting, pouring, and sustained heating of UO/sub 2/, extensive sample characterizations and microanalyses were performed. Theoretical analyses were also made in data interpretation for the purpose of understanding the interaction kinetics.

Swanson, D.G.; Zehms, E.H.; Ang, C.Y.; McClelland, J.D.; Meyer, R.A.; vanPaassen, H.L.L.

1976-10-30T23:59:59.000Z

449

EXPERIMENTAL RESULTS FOR THE ISOTOPIC EXCHANGE OF A 1600 LITER TITANIUM HYDRIDE STORAGE VESSEL  

Science Conference Proceedings (OSTI)

Titanium is used as a low pressure tritium storage material. The absorption/desorption rates and temperature rise during air passivation have been reported previously for a 4400 gram prototype titanium hydride storage vessel (HSV). A desorption limit of roughly 0.25 Q/M was obtained when heating to 700 C which represents a significant residual tritium process vessel inventory. To prepare an HSV for disposal, batchwise isotopic exchange has been proposed to reduce the tritium content to acceptable levels. A prototype HSV was loaded with deuterium and exchanged with protium to determine the effectiveness of a batch-wise isotopic exchange process. A total of seven exchange cycles were performed. Gas samples were taken nominally at the beginning, middle, and end of each desorption cycle. Sample analyses showed the isotopic exchange process does not follow the standard dilution model commonly reported. Samples taken at the start of the desorption process were lower in deuterium (the gas to be removed) than those taken later in the desorption cycle. The results are explained in terms of incomplete mixing of the exchange gas in the low pressure hydride.

Klein, J.

2010-12-14T23:59:59.000Z

450

Calculation of Eddy Currents In the CTH Vacuum Vessel and Coil Frame  

SciTech Connect

Knowledge of eddy currents in the vacuum vessel walls and nearby conducting support structures can significantly contribute to the accuracy of Magnetohydrodynamics (MHD) equilibrium reconstruction in toroidal plasmas. Moreover, the magnetic fields produced by the eddy currents could generate error fields that may give rise to islands at rational surfaces or cause field lines to become chaotic. In the Compact Toroidal Hybrid (CTH) device (R0 = 0.75 m, a = 0.29 m, B ? 0.7 T), the primary driver of the eddy currents during the plasma discharge is the changing flux of the ohmic heating transformer. Electromagnetic simulations are used to calculate eddy current paths and profile in the vacuum vessel and in the coil frame pieces with known time dependent currents in the ohmic heating coils. MAXWELL and SPARK codes were used for the Electromagnetic modeling and simulation. MAXWELL code was used for detailed 3D finite-element analysis of the eddy currents in the structures. SPARK code was used to calculate the eddy currents in the structures as modeled with shell/surface elements, with each element representing a current loop. In both cases current filaments representing the eddy currents were prepared for input into VMEC code for MHD equilibrium reconstruction of the plasma discharge. __________________________________________________

A. Zolfaghari, A. Brooks, A. Michaels, J. Hanson, and G. Hartwell

2012-09-25T23:59:59.000Z

451

Consequence evaluation of radiation embrittlement of Trojan reactor pressure vessel supports  

SciTech Connect

This report describes a consequence evaluation to address safety concerns raised by the radiation embrittlement of the reactor pressure vessel (RPV) supports for the Trojan nuclear power plant. The study comprises a structural evaluation and an effects evaluation and assumes that all four reactor vessel supports have completely lost the load carrying capability. By demonstrating that the ASME code requirements governing Level D service limits are satisfied, the structural evaluation concludes that the Trojan reactor coolant loop (RCL) piping is capable of transferring loads to the steam generator (SG) supports and the reactor coolant pump (RCP) supports. A subsequent design margins to accommodate additional loads transferred to them through the RCL piping. The effects evaluation, employing a systems analysis approach, investigates initiating events and the reliability of the engineered safeguard systems as the RPV is subject to movements caused by the RPV support failure. The evaluation identifies a number of areas of additional safety concerns, but further investigation of the above safety concerns, however, concludes that a hypothetical failure of the Trojan RPV supports due to radiation embrittlement will not result in consequences of significant safety concerns.

Lu, S.C.; Sommer, S.C.; Johnson, G.L. (Lawrence Livermore National Lab., CA (USA)); Lambert, H.E. (FTA Associates, Oakland, CA (USA))

1990-10-01T23:59:59.000Z

452

In-vessel coolability and retention of a core melt. Volume 2  

Science Conference Proceedings (OSTI)

The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the Risk Oriented Accident Analysis Methodology (ROAAM), and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow the delineation of the failure boundaries. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is physically unreasonable. Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. The AP600 is particularly favorable to in-vessel retention. Some ideas to enhance the assessment basis as well as performance in this respect, for applications to larger and/or higher power density reactors are also provided.

Theofanous, T.G.; Liu, C.; Additon, S.; Angelini, S.; Kymaelaeinen, O.; Salmassi, T. [California Univ., Santa Barbara, CA (United States). Center for Risk Studies and Safety

1996-10-01T23:59:59.000Z

453

Computation of initial stage of RBMK reactor fuel channel vessel rupture  

SciTech Connect

Objective of this work is estimation of temperature and time characteristics for rupture of the zirconium pipe which is the RBMK reactor fuel channel (FC) vessel under emergencies. As an emergency the zirconium pipe temperature rise process is considered which results in loss of pipe material strength properties and pipe rupture under the action of internal pressure P=80MPa. The work was carried out under Task Order 007 of University of California - VNIIEF Subcontract No. 0002P0004-95. The problem formulation is stated in Protocol (Task 3, Appendix 3) of the Russian-American Workshop which was held in December, 1994 in Los Alamos. Physical-mechanical and geometry characteristics of structure elements (FC vessel with graphite ring and graphite slug) are presented by NIKIET. The temperature mode of the structure is taken in conformity with the NIKIET data obtained with the RELAP5/MOD3 code. Numerical simulation of structure element behavior in an emergency is performed using the DRAKON program comlex oriented to solving strength problems for complex spatial structures at intense dynamic loading. The {open_quotes}DRAKON{close_quotes} program complex is described and compared with similar western codes in its capabilities.

Pevnitsky, A.V.; Solovyev, V.P.; Abakumov, A.I. [and others

1995-12-31T23:59:59.000Z

454

Helium leak testing of a radioactive contaminated vessel under high pressure in a contaminated environment  

Science Conference Proceedings (OSTI)

At ANL-W, with the shutdown of EBR-II, R&D has evolved from advanced reactor design to the safe handling, processing, packaging, and transporting spent nuclear fuel and nuclear waste. New methods of processing spent fuel rods and transforming contaminated material into acceptable waste forms are now in development. Storage of nuclear waste is a high interest item. ANL-W is participating in research of safe storage of nuclear waste, with the WIPP (Waste Isolation Pilot Plant) site in New Mexico the repository. The vessel under test simulates gas generated by contaminated materials stored underground at the WIPP site. The test vessel is 90% filled with a mixture of contaminated material and salt brine (from WIPP site) and pressurized with N2-1% He at 2500 psia. Test acceptance criteria is leakage jar method is used to determine leakage rate using a mass spectrometer leak detector (MSLD). The efficient MSLD and an Al bell jar replaced a costly, time consuming pressure decay test setup. Misinterpretation of test criterion data caused lengthy delays, resulting in the development of a unique procedure. Reevaluation of the initial intent of the test criteria resulted in leak tolerances being corrected and test efficiency improved.

Winter, M.E.

1996-10-01T23:59:59.000Z

455

Helium leak testing of a radioactive contaminated vessel under high pressure in a contaminated environment  

SciTech Connect

At ANL-W, with the shutdown of EBR-II, R&D has evolved from advanced reactor design to the safe handling, processing, packaging, and transporting spent nuclear fuel and nuclear waste. New methods of processing spent fuel rods and transforming contaminated material into acceptable waste forms are now in development. Storage of nuclear waste is a high interest item. ANL-W is participating in research of safe storage of nuclear waste, with the WIPP (Waste Isolation Pilot Plant) site in New Mexico the repository. The vessel under test simulates gas generated by contaminated materials stored underground at the WIPP site. The test vessel is 90% filled with a mixture of contaminated material and salt brine (from WIPP site) and pressurized with N2-1% He at 2500 psia. Test acceptance criteria is leakage < 10{sup -7} cc/seconds at 2500 psia. The bell jar method is used to determine leakage rate using a mass spectrometer leak detector (MSLD). The efficient MSLD and an Al bell jar replaced a costly, time consuming pressure decay test setup. Misinterpretation of test criterion data caused lengthy delays, resulting in the development of a unique procedure. Reevaluation of the initial intent of the test criteria resulted in leak tolerances being corrected and test efficiency improved.

Winter, M.E.

1996-10-01T23:59:59.000Z

456

Generic BWR-4 degraded core in-vessel study. Status report  

SciTech Connect

Original intent of this project was to produce a phenomenological study of the in-vessel degradation which occurs during the TQUX and TQUV sequences for a generic BWR-4 from the initiation of the FSAR Chapter 15 operational transient through core debris bed formation to the failure of the primary pressure boundary. Bounding calculations were to be performed for the two high pressure and low pressure non-LOCA scenarios to assess the uncertainties in the current state of knowledge regarding the source terms for containment integrity studies. Source terms as such were defined in terms of hydrogen generation, unreacted metal, and coolant inventroy, and in terms of the form, sequencing and mode of dispersal through the primary vessel boundary. Fission product release was not to be considered as part of this study. Premature termination of the project, however, led to the dicontinuation of work on an as is basis. Work on the in-core phase from the point of scram to core debris bed formation was largely completed. A preliminary scoping calculation on the debris bed phase had been initiated. This report documents the status of the study at termination.

Not Available

1984-11-01T23:59:59.000Z

457

Design and Evaluation of an Enhanced In-Vessel Core Catcher  

SciTech Connect

An enhanced in-vessel core catcher is being designed and evaluated as part of a joint United States (U.S.) - Korean International Nuclear Engineering Research Initiative (INERI) investigating methods to insure In-Vessel Retention (IVR) of core materials that may relocate under severe accident conditions in advanced reactors. To reduce cost and simplify manufacture and installation, this new core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. If needed, the core catcher can be manufactured with holes to accommodate lower head penetrations. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary): a base material, which has the capability to support and contain the mass of core materials that may relocate during a severe accident; an oxide coating material on top of the base material, which resists interactions with high-temperature core materials; and an optional coating on the bottom side of the base material to prevent any potential oxidation of the base material during the lifetime of the reactor. This paper summarizes the status of core catcher design and evaluation efforts, including analyses, materials interaction tests, and prototypic testing efforts.

Joy L. Rempe

2004-06-01T23:59:59.000Z

458

An Approach to Understanding Cohesive Slurry Settling, Mobilization, and Hydrogen Gas Retention in Pulsed Jet Mixed Vessels  

DOE Green Energy (OSTI)

The Hanford Waste Treatment and Immobilization Plant (WTP) is being designed and built to pretreat and vitrify a large portion of the waste in Hanfords 177 underground waste storage tanks. Numerous process vessels will hold waste at various stages in the WTP. Some of these vessels have mixing-system requirements to maintain conditions where the accumulation of hydrogen gas stays below acceptable limits, and the mixing within the vessels is sufficient to release hydrogen gas under normal conditions and during off-normal events. Some of the WTP process streams are slurries of solid particles suspended in Newtonian fluids that behave as non-Newtonian slurries, such as Bingham yield-stress fluids. When these slurries are contained in the process vessels, the particles can settle and become progressively more concentrated toward the bottom of the vessels, depending on the effectiveness of the mixing system. One limiting behavior is a settled layer beneath a particle-free liquid layer. The settled layer, or any region with sufficiently high solids concentration, will exhibit non-Newtonian rheology where it is possible for the settled slurry to behave as a soft solid with a yield stress. In this report, these slurries are described as settling cohesive slurries.

Gauglitz, Phillip A.; Wells, Beric E.; Fort, James A.; Meyer, Perry A.

2009-05-22T23:59:59.000Z

459

Thermal Analysis to Calculate the Vessel Temperature and Stress in Alcator C-Mod Due to the Divertor Upgrade  

SciTech Connect

Alcator C-Mod is planning an upgrade to its outer divertor. The upgrade is intended to correct the existing outer divertor alignment with the plasma, and to operate at elevated temperatures. Higher temperature operation will allow study of edge physics behavior at reactor relevant temperatures. The outer divertor and tiles will be capable of operating at 600oC. Longer pulse length, together with the plasma and RF heat of 9MW, and the inclusion of heater elements within the outer divertor produces radiative energy which makes the sustained operation much more difficult than before. An ANSYS model based on ref. 1 was built for the global thermal analysis of C-Mod. It models the radiative surfaces inside the vessel and between the components, and also includes plasma energy deposition. Different geometries have been simulated and compared. Results show that steady state operation with the divertor at 600oC is possible with no damage to major vessel internal components. The differential temperature between inner divertor structure, or "girdle" and inner vessel wall is ~70oC. This differential temperature is limited by the capacity of the studs that hold the inner divertor backing plates to the vessel wall. At a 70oC temperature differential the stress on the studs is within allowable limits. The thermal model was then used for a stress pass to quantify vessel shell stresses where thermal gradients are significant.

Han Zhang, Peter H. Titus, Robert Ellis, Soren Harrison and Rui Vieira

2012-08-29T23:59:59.000Z

460

Documentation of Probabilistic Fracture Mechanics Codes Used for Reactor Pressure Vessels Subjected to Pressurized Thermal Shock Loa ding: Parts 1 and 2  

Science Conference Proceedings (OSTI)

Pressurized thermal shock (PTS) can impact the safety and operability of PWR vessels with significant radiation embrittlement in the vessel walls. This report documents the results of probabilistic fracture mechanics analysis benchmark studies performed to validate the use of several codes for evaluating vessel PTS. Such benchmark studies provide the industry with a standard reference method for verifying probabilistic fracture mechanics codes used in PTS analyses.

1995-08-08T23:59:59.000Z

Note: This page contains sample records for the topic "railroad vessel bunkering" 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

BWRVIP-27-A: BWR Vessel and Internals Project, BWR Standby Liquid Control System / Core Plate Delta-P Inspection and Flaw Evaluation Guidelines  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June, 1994, is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. This BWRVIP report defines inspection requirements for BWR standby liquid control (SLC) system piping from the vessel nozzle safe-end inward. A previous version of this report was published as BWRVIP-27 (TR-107286). This report (BWRVIP-27-A) incorporates changes proposed by the BWRVIP in response to "U.S. Nucl...

2003-08-04T23:59:59.000Z

462

Role of ex-vessel interactions in determining the severe reactor-accident source term for fission products. [PWR; BWR  

SciTech Connect

The role fission-product release and aerosol generation outside the primary system can have in determining the severe reactor-accident source term is reviewed. Recent analytical and experimental studies of major causes of ex-vessel fission product release and aerosol generation are described. The ejection of molten-core debris from a pressurized-reactor vessel is shown to be a potentially large source of aerosols that has not been recognized in past severe-accident evaluations. A mechanistic model of fission-product release during core-debris interactions with concrete is discussed. Calculations with this model are compared to correlations of experimental data and previous estimates of ex-vessel fission-product release. Predictions with the mechanistic model agree quite well with the data correlations but do not agree at all well with estimates made in the past.

Powers, D.A.; Brockmann, J.E.; Bradley, D.R.; Tarbell, W.W.

1983-01-01T23:59:59.000Z

463

A guide for the ASME code for austenitic stainless steel containment vessels for high-level radioactive materials  

Science Conference Proceedings (OSTI)

The design and fabrication criteria recommended by the US Department of Energy (DOE) for high-level radioactive materials containment vessels used in packaging is found in Section III, Division 1, Subsection NB of the ASME Boiler and Pressure Vessel Code. This Code provides material, design, fabrication, examination, and testing specifications for nuclear power plant components. However, many of the requirements listed in the Code are not applicable to containment vessels made from austenitic stainless steel with austenitic or ferritic steel bolting. Most packaging designers, engineers, and fabricators are intimidated by the sheer volume of requirements contained in the Code; consequently, the Code is not always followed and many requirements that do apply are often overlooked during preparation of the Safety Analysis Report for Packaging (SARP) that constitutes the basis to evaluate the packaging for certification.

Raske, D.T.

1995-06-01T23:59:59.000Z

464

Initial observations of cavitation-induced erosion of liquid metal spallation target vessels at the Spallation Neutron Source  

Science Conference Proceedings (OSTI)

During operation of the Spallation Neutron Source (SNS) at Oak Ridge National Laboratory the mechanical properties of the AISI 316L target module are altered by high-energy neutron and proton radiation. The interior surfaces of the target vessel are also damaged by cavitation-induced erosion, which results from repetitive rapid heating of the liquid mercury by high-energy proton beam pulses. Until recently no observations of cavitation-induced erosion were possible for conditions prototypical to the SNS. Post irradiation examination (PIE) of the first and second operational SNS targets was performed to gain insight into the radiation-induced changes in mechanical properties of the 316L target material and the extent of cavitation-induced erosion to the target vessel inner surfaces. Observations of cavitation-induced erosion of the first and second operational SNS target modules are presented here, including images of the target vessel interiors and specimens removed from the target beam-entrance regions.

McClintock, David A [ORNL; Riemer, Bernie [ORNL; Ferguson, Phillip D [ORNL; Carroll, Adam J [ORNL; Dayton, Michael J [ORNL

2012-01-01T23:59:59.000Z

465

Tank vessels of 20,000 dwt or more carrying oil in bulk. proposed design, equipment, and personnel standards  

SciTech Connect

The U.S. Coast Guard (USCG) proposes to add to the rules for tank vessels carrying oil in bulk, standards for segregated ballast tanks, dedicated clean ballast tanks, and crude washing systems, and to withdraw a previous proposal for double bottoms and segregated ballast tanks for certain tank vessels. Adoption of the proposal would reduce the probability of spillage of oil into the navigable waters of the U.S. from vessel accidents, reduce the amount of operational discharges into the oceans by deballasting and tank cleaning, and contribute to the conservation of oil. Written comments must be received by the USCG on or before 4/16/79. Public hearings will be held on 3/21/79 and 3/28/79.

1979-02-12T23:59:59.000Z

466

Materials Reliability Program: Inspection and Evaluation Guidelines for Reactor Vessel Bottom-Mounted Nozzles in U.S. PWR Plants (MR P-206)  

Science Conference Proceedings (OSTI)

This report presents inspection and evaluation guidelines for reactor vessel bottom-mounted nozzles in U.S. pressurized water reactor (PWR) plants.

2009-03-23T23:59:59.000Z

467

ADDITIONAL STRESS AND FRACTURE MECHANICS ANALYSES OF PRESSURIZED WATER REACTOR PRESSURE VESSEL NOZZLES  

Science Conference Proceedings (OSTI)

In past years, the authors have undertaken various studies of nozzles in both boiling water reactors (BWRs) and pressurized water reactors (PWRs) located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Those studies described stress and fracture mechanics analyses performed to assess various RPV nozzle geometries, which were selected based on their proximity to the core beltline region, i.e., those nozzle configurations that are located close enough to the core region such that they may receive sufficient fluence prior to end-of-life (EOL) to require evaluation of embrittlement as part of the RPV analyses associated with pressure-temperature (P-T) limits. In this paper, additional stress and fracture analyses are summarized that were performed for additional PWR nozzles with the following objectives: To expand the population of PWR nozzle configurations evaluated, which was limited in the previous work to just two nozzles (one inlet and one outlet nozzle). To model and understand differences in stress results obtained for an internal pressure load case using a two-dimensional (2-D) axi-symmetric finite element model (FEM) vs. a three-dimensional (3-D) FEM for these PWR nozzles. In particular, the ovalization (stress concentration) effect of two intersecting cylinders, which is typical of RPV nozzle configurations, was investigated. To investigate the applicability of previously recommended linear elastic fracture mechanics (LEFM) hand solutions for calculating the Mode I stress intensity factor for a postulated nozzle corner crack for pressure loading for these PWR nozzles. These analyses were performed to further expand earlier work completed to support potential revision and refinement of Title 10 to the U.S. Code of Federal Regulations (CFR), Part 50, Appendix G, Fracture Toughness Requirements, and are intended to supplement similar evaluation of nozzles presented at the 2008, 2009, and 2011 Pressure Vessels and Piping (PVP) Conferences. This work is also relevant to the ongoing efforts of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, Working Group on Operating Plant Criteria (WGOPC) efforts to incorporate nozzle fracture mechanics solutions into a revision to ASME B&PV Code, Section XI, Nonmandatory Appendix G.

Walter, Matthew [Structural Integrity Associates, Inc.; Yin, Shengjun [ORNL; Stevens, Gary [U.S. Nuclear Regulatory Commission; Sommerville, Daniel [Structural Integrity Associates, Inc.; Palm, Nathan [Westinghouse Electric Company, Cranberry Township, PA; Heinecke, Carol [Westinghouse Electric Company, Cranberry Township, PA

2012-01-01T23:59:59.000Z

468

Tumor blood vessel "normalization" improves the therapeutic efficacy of boron neutron capture therapy (BNCT) in experimental oral cancer  

Science Conference Proceedings (OSTI)

We previously demonstrated the efficacy of BNCT mediated by boronophenylalanine (BPA) to treat tumors in a hamster cheek pouch model of oral cancer with no normal tissue radiotoxicity and moderate, albeit reversible, mucositis in precancerous tissue around treated tumors. It is known that boron targeting of the largest possible proportion of tumor cells contributes to the success of BNCT and that tumor blood vessel normalization improves drug delivery to the tumor. Within this context, the aim of the present study was to evaluate the effect of blood vessel normalization on the therapeutic efficacy and potential radiotoxicity of BNCT in the hamster cheek pouch model of oral cancer.

D. W. Nigg

2012-01-01T23:59:59.000Z

469

In-vessel Zircaloy oxidation/hydrogen generation behavior during severe accidents  

DOE Green Energy (OSTI)

In-vessel Zircaloy oxidation and hydrogen generation data from various US Nuclear Regulatory Commission severe-fuel damage test programs are presented and compared, where the effects of Zircaloy melting, bundle reconfiguration, and bundle quenching by reflooding are assessed for common findings. The experiments e