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


1

STATEMENT OF CONSIDERATIONS REQUEST BY NIAGARA MOHAWK POWER CORPORATION FOR AN  

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

NIAGARA MOHAWK POWER CORPORATION FOR AN NIAGARA MOHAWK POWER CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN PATENT RIGHTS UNDER. CONTRACT NO. DE-FC36-96GO10132, W(A)-96-018, CH-0910 The Niagara Mohawk Power Corporation (hereafter NMPC), a large business, has petitioned for an advance waiver of patent rights under DOE Contract No. DE-FC36- 96GO10132. NMPC is the lead company of a group of organizations call the Salix Consortium which expects to demonstrate that a process called the "Swedish Willow Biomass System" is suitable for electrical power production in the Northeastern United States. NMPC has requested a waiver of domestic and foreign patent rights for all subject inventions of its employees, including those of its wholly owned or controlled subsidiaries or affiliates, as well as those of its subcontractors, at any tier, other than those of domestic small

2

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

3

Niagara Limestone  

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

Niagara Limestone Niagara Limestone Nature Bulletin No. 282-A November 11, 1967 Forest Preserve District of Cook County Richard B. Ogilvie, President Roland F. Eisenbeis, Supt. of Conservation NIAGARA LIMESTONE Chicago stands at the crossroads of America -- the heart of the Middle West -- and one of the most important natural resources upon which it depends is the Niagara limestone beneath it. The bedrock in this region consists of layer upon layer of limestones, shales and sandstones stacked almost a half mile thick on top of the ancient granite, once molten, that formed the original surface of the earth before oceans formed and life appeared. The Niagara limestone is the uppermost layer here but few of us are aware of it because it is covered with soil and ground up rock -- glacial drift -- ranging from a few feet to a hundred or more feet in depth.

4

niagaraVP  

Office of Legacy Management (LM)

Niagara Falls Vicinity Properties, New York. Niagara Falls Vicinity Properties, New York. This site is managed by the U.S. Department of Energy Office of Legacy Management. Site Description and History The Niagara Falls Vicinity Properties, New York (formerly the Niagara Falls Storage Site) is located in Lewiston, New York, approximately 10 miles north of the city of Niagara Falls, New York. The site is a remnant of the U.S. Army's 7,500-acre Lake Ontario

5

SOXAL{trademark} pilot plant demonstration at Niagara Mohawk`s Dunkirk Station  

SciTech Connect

The Clean Air Act Amendments of 1990 made it necessary to accelerate the development of scrubber systems for use by some utilities burning sulfur-containing fuels, primarily coal. While many types of Flue Gas Desulfurization (FGD) systems operate based on lime and limestone scrubbing, these systems have drawbacks when considered for incorporation into long-term emissions control plans. Although the costs associated with disposal of large amounts of scrubber sludge may be manageable today, the trend is toward increased disposal costs. Many new SO{sub 2} control technologies are being pursued in the hope of developing an economical regenerable FGD system did recovers the SO{sub 2} as a saleable commercial product, thus minimizing the formation of disposal waste. Some new technologies include the use of exotic chemical absorbents which are alien to the utility industry and utilities` waste treatment facilities. These systems present utilities with new environmental issues. The SOXAL{trademark} process has been developed so as to eliminate such issues.

Strangway, P.K. [Niagara Mohawk Power Corp., Syracuse, NY (United States)

1995-12-31T23:59:59.000Z

6

NIAGARA FALLS STORAGE SITE  

Office of Legacy Management (LM)

:i" :i" _,, ' _~" ORISE 95/C-70 :E : i:; :' l,J : i.: RADIOLOGICAL SURVEY Op BUILDINGS 401, ' 403, AND ' m HITTMAN BUILDING $ <,' 2:. NIAGARA FALLS STORAGE SITE I .~~ ; " LEWISTON, ' NEW YORK : f? j:,:i I ,.J- ;b f" /: Li _e.*. ~,, I ,,~, ,:,,;:, Prepared by T. .I. Vitkus i,c Environmental Survey and Site Assessment Program Energy/Environment Systems Division ;>::; Oak Ridge Institute for Science and Education .,:, "Oak Ridge, Temressee 37831-0117 .F P ., ? :_ &,d ,,,, ;<:x,, Prepared for the 3 I. Office of Environmental Restoration I, U.S. Department of Energy i gy i. ~: ,,, "! ? ' :' : "' ,//, FINAL REPORT ".$ :,a ,,, MARCH 1995 ; m L ,, ,, ,,,. ., ,,. ' 1 jq ,Ij:,., .,~ _,I_ 1 This report is based on work performed under contract number DE-AC05-760R00033 with the

7

Mohawk Municipal Comm | Open Energy Information  

Open Energy Info (EERE)

Municipal Comm Municipal Comm Jump to: navigation, search Name Mohawk Municipal Comm Place New York Utility Id 12759 Utility Location Yes Ownership M NERC Location NPCC Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Industrial Rate Industrial Large Commercial Commercial Public Street Lighting Lighting Security Lighting 150 w lamp Lighting Security Lighting 175 w lamp Lighting Security Lighting 250 w lamp Lighting Security Lighting 400 w lamp Lighting Single-Phase Residential Residential Small Commercial Business Commercial Average Rates Residential: $0.0366/kWh

8

Wellton-Mohawk Irr & Drain Dist | Open Energy Information  

Open Energy Info (EERE)

Wellton-Mohawk Irr & Drain Dist Wellton-Mohawk Irr & Drain Dist Jump to: navigation, search Name Wellton-Mohawk Irr & Drain Dist Place Arizona Utility Id 25060 Utility Location Yes Ownership P NERC Location WECC NERC WECC Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Agricultural Pumping Service Commercial General Service Commercial Large General Service Commercial Residential Service Residential Average Rates Residential: $0.1000/kWh Commercial: $0.0842/kWh Industrial: $0.0956/kWh References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a"

9

Cleanup Agreed on for Niagara Landfill  

Science Journals Connector (OSTI)

Cleanup Agreed on for Niagara Landfill ... The U.S., New York state, and Occidental Chemical finally have reached agreement on how to clean up toxic liquid wastes at the Hyde Park landfill in Niagara, N.Y. ... The cleanup program is a multifaceted scheme designed to remove and destroy the most concentrated of the hazardous liquids buried in the landfill. ...

LOIS EMBER

1985-12-16T23:59:59.000Z

10

DOE - Office of Legacy Management -- Niagara VP_FUSRAP  

Office of Legacy Management (LM)

Niagara Falls Vicinity Properties, New York, Site Niagara Falls Vicinity Properties, New York, Site FUSRAP Site Niagara Falls Vicinity Properties Map Background-The Niagara Falls Vicinity Properties Site was remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established in 1974 to remediate sites where radioactive contamination remained from Manhattan Project and early U.S. Atomic Energy Commission operations. History-Niagara Falls Storage Site Vicinity Properties, located near Lewiston, New York, consists of 26 properties sold to private owners; the properties were formerly part of the Lake Ontario Ordnance Works. Another portion of the former ordnance works was transferred to the U.S. Atomic Energy Commission and became the Niagara Falls Storage Site. Beginning in 1944, the Manhattan Engineer District stored uranium

11

DOE - Office of Legacy Management -- Niagara Falls Storage Site...  

Office of Legacy Management (LM)

of the Niagara Falls, New York, Storage Site NY.17-1 - AEC Memorandum; Malone to Smith; Subject: Monthly Progress Report for April; April 24, 1951. Attachment: Tonawanda...

12

EIS-0153: Niagara Import Point Project  

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

The Federal Energy Regulatory Commission prepared this statement to assess the environmental impacts of the proposed Niagara Import Point project that would construct an interstate natural gas pipeline to transport gas from Canada and domestic sources to the Northeastern United States market. The U.S. Department of Energy's Office of Fossil Energy was a cooperating agency during statement development and adopted this statement on 6/15/1990.

13

DOE - Office of Legacy Management -- Niagara Falls Vicinity Properties NY -  

Office of Legacy Management (LM)

Niagara Falls Vicinity Properties Niagara Falls Vicinity Properties NY - NY 17 FUSRAP Considered Sites Niagara Falls Vicinity Properties, NY Alternate Name(s): Lake Ontario Ordnance Works (LOOW) Niagara Falls Storage Site (NFSS) DOE-Niagara Falls Storage Site NY.17-1 NY.17-3 Location: Lewiston , New York NY.17-5 Historical Operations: Stored, shipped, and buried radioactive equipment and waste for MED and AEC containing uranium, radium, and thorium. Portions of the former site are privately owned, creating a "site" for the vicinity properties. NY.17-1 NY.17-2 NY.17-14 Eligibility Determination: Eligible NY.17-4 Radiological Survey(s): Assessment Surveys, Verification Surveys NY.17-3 NY.17-5 NY.17-6 NY.17-7 NY.17-8 NY.17-9 NY.17-10 NY.17-11 NY.17-12 NY.17-14 Site Status: Certification Basis, including Federal Register Notice for 23 properties. Cleanup in progress for additional 3 VPs. NY.17-13

14

Niagara Falls, New York: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

Niagara Falls, NY) Niagara Falls, NY) Jump to: navigation, search Equivalent URI DBpedia Coordinates 43.0944999°, -79.0567111° 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":43.0944999,"lon":-79.0567111,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

15

MHK Projects/Niagara Community 2 | Open Energy Information  

Open Energy Info (EERE)

Niagara Community 2 Niagara Community 2 < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":5,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"350px","centre":false,"title":"","label":"","icon":"File:Aquamarine-marker.png","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":43.081,"lon":-79.0111,"alt":0,"address":"","icon":"http:\/\/prod-http-80-800498448.us-east-1.elb.amazonaws.com\/w\/images\/7\/74\/Aquamarine-marker.png","group":"","inlineLabel":"","visitedicon":""}]}

16

Mr. Frank Archer President Niagara Cold Drawn Steel Corporation  

Office of Legacy Management (LM)

Department of Energy Department of Energy Washington, DC 20585 FEB 2 1 1991 ' i-. 1,; ' -, f ' + \ 1 : , .J p- * c - Mr. Frank Archer President Niagara Cold Drawn Steel Corporation 110 Hopkins Street P.O. Box 399 Buffalo, NY 14240 Dear Mr. Archer: I have executed the consent forms for the performance of a radiological survey of the Niagara Cold Drawn Steel Corporation's property under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the U.S. Department of Energy (DOE). I enclose a copy of the consent for your company's records. Oak Ridge Associated Universities (ORAU) will perform the survey of your company's property. MS. Michelle Landis (615-576-2908) is the project manager for ORAU. We have worked with Mr. Shells of your staff on this project and

17

Niagara Falls Storage Site environmental monitoring report. Calendar year 1983  

SciTech Connect

During 1983, an environmental monitoring program was continued at the Niagara Falls Storage Site, a United States Department of Energy (DOE) surplus facility located in Niagara County, New York presently used for the storage of radioactive residues, contaminated soils and rubble. The monitoring program at NFSS measures radon concentrations in air, uranium and radium concentrations in surface water, groundwater, and sediments, and external gamma exposure rates. Radiation doses to the public are also calculated. Environmental samples collected are analyzed to determine compliance with applicable standards. Comparison of 1983 monitoring results with 1982 results shows a significant decrease in radon levels at almost every monitoring location. External gamma exposure rates also showed a general decrease. 9 references, 10 figures, 11 tables

Not Available

1984-07-01T23:59:59.000Z

18

Sandia National Laboratories: PWR  

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

PWR Pratt Whitney Rocketdyne Testing On December 19, 2012, in Concentrating Solar Power, EC, Energy, Facilities, National Solar Thermal Test Facility, News, News & Events,...

19

American Ref-Fuel of Niagara Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Niagara Biomass Facility Niagara Biomass Facility Jump to: navigation, search Name American Ref-Fuel of Niagara Biomass Facility Facility American Ref-Fuel of Niagara Sector Biomass Facility Type Municipal Solid Waste Location Niagara County, New York Coordinates 43.3119496°, -78.7476208° 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":43.3119496,"lon":-78.7476208,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

20

ADDENDUM TO ACTION DESCRIPTION MEMORANDUM NIAGARA FALLS STORAGE SITE  

Office of Legacy Management (LM)

ADDENDUM TO ADDENDUM TO ACTION DESCRIPTION MEMORANDUM NIAGARA FALLS STORAGE SITE PROPOSED INTERIM REMEDIAL ACTIONS FOR FY 1983-85 ACCELERATED PROGRAM (1984 VICINITY PROPERTIES CLEANUP) Prepared by Environmental Research Division Argonne National Laboratory Argonne, Illinois July 1984 Prepared for U.S. Department of Energy Oak Ridge Operations Technical Services Division Oak Ridge, Tennessee CONTENTS Page SUMMARY OF PROPOSED ACTION AND RELATED ACTIVITIES ........... 1 HISTORY AND ENVIRONMENTAL SETTING ........................ 4 RADIOLOGICAL CONTAMINATION AND NEED FOR PROPOSED ACTION ........ 4 Property A .. . . . . . . . . . . . . . . . .. . . . . . . 6 Property C' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Property H ...... ............. ... 7 Property H' . . . . . . . . . . . . . . . . . . .. . . . . . . . . 7 Property L ..... ...... .

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Niagara Falls Storage Site Vicinity Properties in Lewiston, New York,  

Office of Legacy Management (LM)

Niagara Falls Storage Site Vicinity Niagara Falls Storage Site Vicinity Properties in Lewiston, New York, from 7983 through 7986 Depatfment of Energy Former Sites Restoration Division Oak Ridge Field Office July 7 992 I I I I I I I I I I I I I I I I I I I CONTENTS Figures .......................... Tables .......................... Abbreviations ....................... Acronyms ......................... 1.0 Introduction ..................... 2.0 Site History ..................... 3.0 Property Descriptions ................ 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 3.10 3.11 3.12 3.13 3.14 3.15 3.16 3.17 3.18 3.19 3.20 3.21 3.22 3.23 3.24 3.25 3.26 3.27 Property A ............ Property B ............ PropertyC' ........... Property D ............ Property F ........ .' ... PropertyH' ...........

22

West Valley-derived radionuclides in the Niagara river area of Lake Ontario  

Science Journals Connector (OSTI)

The presence of West Valley-derived radionuclides in the densely-populated Niagara...137Cs profile in a 210Pb-dated Lake Ontario sediment core is consistent with the pattern of West Valley discharges to the local...

S. R. Joshi

1988-01-01T23:59:59.000Z

23

DOE - Office of Legacy Management -- Niagara Falls Storage Site NY - NY 17  

Office of Legacy Management (LM)

Niagara Falls Storage Site NY - NY Niagara Falls Storage Site NY - NY 17 FUSRAP Considered Sites Niagara Falls Storage Site, NY Alternate Name(s): Lake Ontario Ordnance Works (LOOW) Niagara Falls Storage Site (NFSS) DOE-Niagara Falls Storage Site NY.17-1 NY.17-3 Location: Lewiston, New York NY.17-5 Historical Operations: Stored, shipped, and buried radioactive equipment and waste for MED and AEC containing uranium, radium, and thorium. Contains Interim Waste Containment Structure. NY.17-1 NY.17-2 NY.17-14 Eligibility Determination: Eligible NY.17-4 Radiological Survey(s): Assessment Surveys NY.17-3 NY.17-5 NY.17-6 NY.17-7 NY.17-8 NY.17-9 NY.17-10 NY.17-11 NY.17-12 NY.17-14 Site Status: Cleanup in progress by U.S. Army Corps of Engineers. NY.17-13 NY.17-14 NY.17-15 NY.17-16 USACE Website Long-term Care Requirements: To be determined upon completion.

24

PRELIMINARY SURVEY OF THE UNION CARBIDE CORPORATION METALS DIVISION PLANT, NIAGARA FALLS, NEW YORK  

Office of Legacy Management (LM)

e e - .' N"lr 7% PRELIMINARY SURVEY OF THE UNION CARBIDE CORPORATION METALS DIVISION PLANT, NIAGARA FALLS, NEW YORK Work performed by the Health and Safety Research Division Oak Ridge Natjonal Laboratory Oak Ridge, Tennessee 37830 December 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program PRELIMINARY SURVEY OF THE UNION CARBIDE CORPORATION METALS DIVISION PLANT, NIAGARA FALLS, NEW YORK B. A. Berven and R. W. Doane Introduction On September 2;, 1980, two representatives from Oak Ridge National Laboratory visited Union Carbide Corporation's Metal Division Plant (UCC-MD) in Niagara Falls, New York. The purpose of the visit was to

25

Niagara Falls Storage Site annual environmental report for calendar year 1991, Lewiston, New York. [Niagara Falls Storage Site  

SciTech Connect

This document describes the environmental monitoring program at the Niagara Falls Storage Site (NFSS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring at NFSS began in 1981. The site is owned by the US Department of Energy (DOE) and is assigned to the DOE Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Additionally, several nonradiological parameters including seven metals are routinely measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

Not Available

1992-09-01T23:59:59.000Z

26

West Valley Plutonium and Americium-241 in Lake Ontario sediments off the mouth of Niagara River  

Science Journals Connector (OSTI)

Recently deposited fine-grained sediments in Lake Ontario off the mouth of Niagara River contain highly toxic238Pu,239,240pu, and241Pu (241Am) from global fallout as well as from low level releases of these radio...

S. R. Joshi

1988-11-01T23:59:59.000Z

27

Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program  

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

Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program (March 2012)

28

PWR GASIFIER PEER REVIEW FINAL REPORT  

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

PWR GASIFIER PEER REVIEW REPORT PWR GASIFIER PEER REVIEW REPORT 2/21/06 Background Pratt and Whitney Rocketdyne (PWR) signed a cooperative agreement with DOE on 9/30/04 to develop a novel gasifier concept, which is expected to improve the availability and efficiency of gasification-based power plants, and to reduce plant capital and operations costs. On 12/21/05, PWR submitted a proposal to continue development of their gasifier into the next phase. On January 24, 2006, a peer review was performed to review the work that PWR has done to date, their technical approach for future development, and to assess the potential benefit of the PWR gasifier and feed system technologies over state-of-the art coal gasification. The peer reviewers also evaluated a DOE analysis of the PWR refractory, and a DOE system study comparing the

29

PWR AXIAL BURNUP PROFILE ANALYSIS  

SciTech Connect

The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to criticality. The effect that the low burnup regions near the ends of spent fuel have on system reactivity is termed the ''end-effect''. This calculation will quantify the end-effects associated with Pressurized Water Reactor (PWR) fuel assemblies emplaced in a hypothetical 21 PWR waste package. The scope of this calculation covers an initial enrichment range of 3.0 through 5.0 wt% U-235 and a burnup range of 10 through 50 GWd/MTU. This activity supports the validation of the process for ensuring conservative generation of spent fuel isotopics with respect to criticality safety applications, and the use of burnup credit for commercial spent nuclear fuel. The intended use of these results will be in the development of PWR waste package loading curves, and applications involving burnup credit. Limitations of this evaluation are that the limiting profiles are only confirmed for use with the B&W 15 x 15 fuel assembly design. However, this assembly design is considered bounding of all other typical commercial PWR fuel assembly designs. This calculation is subject to the Quality Assurance Requirements and Description (QARD) because this activity supports investigations of items or barriers on the Q-list (YMP 2001).

J.M. Acaglione

2003-09-17T23:59:59.000Z

30

Niagara Falls Storage Site environmental report for calendar year 1989, Lewiston, New York  

SciTech Connect

The environmental monitoring program, which began in 1981, was continued during 1989 at the Niagara Falls Storage Site (NFSS), a United States Department of Energy (DOE) surplus facility located in Niagara County, New York, that is currently used for interim storage of radioactive residues, contaminated soils, and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at NFSS measures radon concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the conservative scenario described in this report, this hypothetical individual receives an annual external exposure equivalent to approximately 2 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than a person receives during a one-way flight from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of NFSS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. Results of the 1989 monitoring show that NFSS is in compliance with applicable DOE radiation protection standards. 18 refs., 26 figs., 18 tabs.

Not Available

1990-05-01T23:59:59.000Z

31

EIS-0109: Long-Term Management of the Existing Radioactive Wastes and Residues at the Niagara Falls Storage Site  

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

The U.S. Department of Energy developed this statement to evaluate the environmental impacts of several alternatives for management and control of the radioactive wastes and residues at the Niagara Falls Storage Site, including a no action alternative, an alternative to manage wastes on-site, and two off-site management alternatives.

32

Harquahala Valley Pwr District | Open Energy Information  

Open Energy Info (EERE)

Harquahala Valley Pwr District Harquahala Valley Pwr District Jump to: navigation, search Name Harquahala Valley Pwr District Place Arizona Utility Id 8139 Utility Location Yes Ownership P NERC Location WECC NERC WECC Yes Activity Buying Transmission Yes Activity Buying Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Gin Commercial Irrigation Pumping Commercial Non-Irrigation Agriculture Commercial Average Rates Industrial: $0.0565/kWh References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=Harquahala_Valley_Pwr_District&oldid=410799

33

COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE  

Office of Legacy Management (LM)

COT"IPREITENS IVE RADIOLOGICAL COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE LEWISTON, NEW YORK Prepared for U.S. DePartment of EnergY as part of the Formerly Utilized Sites - Remedial ActLon Program J . D . B e r g e r P r o j e c t S t a f f J. Burden* w.L. Smlth* R.D. Condra T.J. Sowell J.S . Epler* G.M. S tePhens P.Iil. Frame L.B. Taus* W . 0 . H e l t o n C . F . W e a v e r R . C . G o s s l e e B . S . Z a c h a r e k d I I Prepared bY Radiological Slte Assessoent Progran Manpower Educailon Research, and Training Dlvision Oak Ridge Assoclated Universlties Oak Ridge, Tennessee 3783f-0117 I FINAL REPORT March 1984 Thts report ls based on work performed under contract number DE-AC05-760R00033 wiLh the DePartment of EnergY. *Evaluatlon Research Corporatlon, Oak Ridge, Tennessee TABLE OF CONTENTS L i s t o f F i g u

34

Niagara Falls Storage Site environmental surveillance report for calendar year 1993  

SciTech Connect

This report summarizes the results of environmental surveillance activities conducted at the Niagara Falls Storage Site (NFSS) during calendar year 1993. It includes an overview of site operations, the basis for radiological and nonradiological monitoring, a summary of the results, and the estimated dose to the offsite population. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. NFSS is in compliance with National Emission Standards for Hazardous Air Pollutants (NESHAPs) Subpart H of the Clean Air Act as well as the requirements of the National Pollutant Discharge Elimination System (NPDES) under the Clean Water Act. Located in northwestern New York, the site covers 191 acres. From 1944 to the present, the primary use of NFSS has been storage of radioactive residues that were by-products of uranium production. Most onsite areas of residual radioactivity above regulatory guidelines were remediated during the early 1980s. Additional isolated areas of onsite contamination were remediated in 1989, and the materials were consolidated into the waste containment structure in 1991. Remediation of the site has now been completed.

Not Available

1994-06-01T23:59:59.000Z

35

Vermont Yankee Nucl Pwr Corp | Open Energy Information  

Open Energy Info (EERE)

Yankee Nucl Pwr Corp Jump to: navigation, search Name: Vermont Yankee Nucl Pwr Corp Place: Vermont References: EIA Form EIA-861 Final Data File for 2010 - File1a1 EIA Form 861...

36

U.S. Army Corps of Engineers Buffalo District Office 1776 Niagara Street, Buffalo, New York, 14207  

Office of Legacy Management (LM)

Army Corps of Engineers Army Corps of Engineers Buffalo District Office 1776 Niagara Street, Buffalo, New York, 14207 Explanation of Significant Differences for the Rattlesnake Creek Portion of the Ashland Sites Tonawanda, New York September 20, 2004 Formerly Utilized Sites Remedial Action Program Explanation of Significant Differences for the Rattlesnake Creek Portion of the Ashland Sites Table of Contents I. INTRODUCTION 1 II. SITE mSTORY, CONTAMINATION AND SELECTED REMEDy 2 A. Site History 2 B. Original Remedy 3 III. BASIS FOR TmS DOCUMENT.................................*...................*..........*................*.**** 3 A. Summary of Additional Information 3 B. References 4 IV. DESCRIPTION OF SIGNIFICANT DIFFERENCES 4 V. SUPPORT AGENCY COMMENTS 5 VI. STATUTORY DETERMINATIONS 5

37

"1. Robert Moses Niagara","Hydroelectric","New York Power Authority",2353  

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

York" York" "1. Robert Moses Niagara","Hydroelectric","New York Power Authority",2353 "2. Ravenswood","Gas","TC Ravenswood LLC",2330 "3. Nine Mile Point Nuclear Station","Nuclear","Nine Mile Point Nuclear Sta LLC",1773 "4. Oswego Harbor Power","Petroleum","NRG Oswego Harbor Power Operations Inc",1648 "5. Northport","Gas","National Grid Generation LLC",1569 "6. Astoria Generating Station","Gas","U S Power Generating Company LLC",1315 "7. Roseton Generating Station","Gas","Dynegy Northeast Gen Inc",1212 "8. Blenheim Gilboa","Pumped Storage","New York Power Authority",1160

38

Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes  

SciTech Connect

The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

Not Available

1984-01-01T23:59:59.000Z

39

Niagara Falls storage site annual environmental report for calendar year 1990, Lewiston, New York  

SciTech Connect

Environmental monitoring of the US DOE Niagara Falls Storage Site (NFSS) and surrounding area began in 1981. NFSS is part of a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial, operations causing conditions the Congress has authorized DOE to remedy. Environmental monitoring systems at NFSS include sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water sediments, and groundwater. Additionally, several nonradiological parameters are routinely measured in groundwater. During 1990, the average ambient air radon concentration (including background) at NFSS ranged from 0.3 to 0.7 pCi/L (0.01 to 0.03 Bq/L); the maximum at any location for any quarter was 1.6 pCi/L (0.06 Bq/L). The average on-site external gamma radiation exposure level was 69 mR/yr; the average at the property line was 68 mR/yr (including background). The average background radiation level in the area was 66 mR/yr. Average annual concentrations of radium-226 and total uranium in surface water ranged from 0.4E-9 to 0.9E-9 {mu}Ci/m1 (0.02 to 0.03 Bq/L) and from 5E-9 to 9E-9 {mu}Ci/m1 (0.2 to 0.3 Bq/L), respectively. Routine analyses of groundwater samples from NFSS included the indicator parameters total organic carbon, total organic halides, pH, and specific conductivity.

Not Available

1991-08-01T23:59:59.000Z

40

Improving the economics of PWR cores  

SciTech Connect

Economic fuel cycles have become of paramount importance to the nuclear power industry due to the increasing impact of deregulation and competition. This paper describes the PWR core design techniques being employed at Entergy in the quest to meet the ever-decreasing fuel cost targets for these units.

Ober, T.G. [Entergy Operations, Jackson, MS (United States)

1996-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Niagara Falls Storage Site, Annual site environmental report, Lewiston, New York, Calendar year 1986: Surplus Facilities Management Program (SFMP)  

SciTech Connect

During 1986, the environmental monitoring program was continued at the Niagara Falls Storage Site (NFSS), a US Department of Energy (DOE) surplus facility located in Niagara County, New York, presently used for the interim storage of radioactive residues and contaminated soils and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at the NFSS measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6% of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 14 refs., 11 figs., 14 tabs.

Not Available

1987-06-01T23:59:59.000Z

42

The graphs at right show overall variability distribution estimated for the Pentium D 800 series (near) and the T1 Niagara (far) using the FPGA data  

E-Print Network (OSTI)

RESULTS The graphs at right show overall variability distribution estimated for the Pentium D 800 where a core no longer works properly. In the Sun T1 Niagara cores this is done with a built-in- self processors we record the temperature at which the failure occurred and adjust to the frequencies

Renau, Jose

43

RESULTS OF RADIOLOGICAL I'IEASUREMENTS HIGHT{AYS 18 AI.ID IO4 IN NIAGARA  

Office of Legacy Management (LM)

9s' 9s' RESULTS OF RADIOLOGICAL I'IEASUREMENTS HIGHT{AYS 18 AI.ID IO4 IN NIAGARA az76 rl//.ry' ORNL/RASA.85/ 40 TAKEN AT JUNCTION FALLS, NEH YORK Accesr to the information in thit rcport ir limiled to tho!' inOllateO on tho dl3tribution li3t and to OePartment ot Encrgy and Oepartmcnt ol Enotgy Gontracton This report was prepared as an account of work sponsored by an agency of the United States Government. Neitherth€ U nited StatesGovernment norany agency thereof, nor any of their employees, makes any warranty, express or implied' or assumes any legal liability or responsibility for the accuracy, completenessi or usefulness of any information, apparatus, product, or,process disclosed, or represents that its usewould not inlringe privately owned rights" Reference herein

44

RESULTS OF RADIOLOGICAL MEASUREMENTS TAKEN NEAR JUNCTION OF HIGHWAY 3I AND MILITARY ROAD IN NIAGARA FALLSI NEI{ YOR  

Office of Legacy Management (LM)

7At 7At a z'/a tlYr'/ ORNL/RASA-85/ 42 RESULTS OF RADIOLOGICAL MEASUREMENTS TAKEN NEAR JUNCTION OF HIGHWAY 3I AND MILITARY ROAD IN NIAGARA FALLSI NEI{ YOR Accesr to thc inlormalion in thlt rcport is limitcd to tho!. indacatod on the di3tribution lilt and to oopartmont ot Encrgy lnd Oeplrtmcnt of Enorgy Contracton vd' This report was prepared as an account of work sponsored by an agency of the U nited States Government. N€ither the U nited States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied' or assum€s any legal liability or responsibility for the accuracy, completeness' or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not inf ringe privately owned rights. Reference herein

45

THE NUCLEAR ENERGY REVOLUTION1966  

Science Journals Connector (OSTI)

...Edison Niagara Mohawk Connecticut Yankee Commonwealth Edison Boston Edison...E Northern States Power Co. TVA Vermont Yankee Duke Power Company Philadelphia...experience with such power plants as the Yankee pressurized-water reactor (175...

Alvin M. Weinberg; Gale Young

1967-01-01T23:59:59.000Z

46

Ris-M-2209 THE THREE-DIMENSIONAL PWR TRANSIENT CODE  

E-Print Network (OSTI)

and with closed hydraulic channels. INIS descriptors. A CODES, CONTROL ELEMENTS, HYDRAULICS, PWR TYPE REACTORS

47

Radiation embrittlement of PWR vessel supports  

SciTech Connect

Several studies pertaining to radiation damage of PWR vessel supports were conducted between 1978 and 1987. During this period, apparently there was no reason to believe that low-temperature (<100/degree/C) MTR embrittlement data were not appropriate for evaluating embrittlement of PWR vessel supports. However, late in 1986, data from the High Flux Isotope Reactor (HFIR) vessel surveillance program indicated that the embrittlement rates of the several HFIR vessel materials (A212-B, A350-LF3, A105-II) were substantially greater than anticipated on the basis of MTR data. Further evaluation of the HFIR data suggested that a fluence-rate effect was responsible for the apparent discrepancy, and shortly thereafter it became apparent that this rate effect was applicable to the evaluation of LWR vessel supports. As a result, the Nuclear Regulatory Commission (NRC) requested that the Oak Ridge National Laboratory (ORNL) evaluate the impact of the apparent embrittlement rate effect on the integrity of light-water-reactor (LWR) vessel supports. The purpose of the study was to provide an indication of whether the integrity of reactor vessel supports is likely to be challenged by radiation-induced embrittlement. The scope of the evaluation included correlation of the HFIR data for application to the evaluation of LWR vessel supports; a survey and cursory evaluation of all US LWR vessel support designs, selection of two plants for specific-plant evaluation, and a specific-plant evaluation of both plants to determine critical flaw sizes for their vessel supports. 19 refs., 8 figs., 2 tabs.

Cheverton, R.D.; Robinson, G.C.; Pennell, W.E.; Nanstad, R.K.

1989-01-01T23:59:59.000Z

48

Niagara falls storage site: Annual site environmental report, Lewiston, New York, Calendar Year 1988: Surplus Facilities Management Program (SFMP)  

SciTech Connect

The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the conservative scenario described in this report, this hypothetical individual receives an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than a person receives during two round-trip flights from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. Results of the 1988 monitoring show that the NFSS is in compliance with applicable DOE radiation protection standards. 17 refs., 31 figs., 20 tabs.

Not Available

1989-04-01T23:59:59.000Z

49

East River Elec Pwr Coop, Inc | Open Energy Information  

Open Energy Info (EERE)

Elec Pwr Coop, Inc Elec Pwr Coop, Inc Jump to: navigation, search Name East River Elec Pwr Coop, Inc Place South Dakota Utility Id 5552 Utility Location Yes Ownership C NERC Location MRO NERC MRO Yes Activity Transmission Yes Activity Buying Transmission Yes Alt Fuel Vehicle Yes Alt Fuel Vehicle2 Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png No rate schedules available. Average Rates No Rates Available References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=East_River_Elec_Pwr_Coop,_Inc&oldid=410618"

50

Michigan South Central Pwr Agy | Open Energy Information  

Open Energy Info (EERE)

Pwr Agy Pwr Agy Jump to: navigation, search Name Michigan South Central Pwr Agy Place Michigan Utility Id 12807 Utility Location Yes Ownership M NERC Location RFC NERC RFC Yes Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Buying Transmission Yes Activity Wholesale Marketing Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png No rate schedules available. Average Rates No Rates Available References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=Michigan_South_Central_Pwr_Agy&oldid=41107

51

Rushmore Electric Pwr Coop Inc | Open Energy Information  

Open Energy Info (EERE)

Rushmore Electric Pwr Coop Inc Rushmore Electric Pwr Coop Inc Jump to: navigation, search Name Rushmore Electric Pwr Coop Inc Place South Dakota Utility Id 16443 Utility Location Yes Ownership C NERC Location MRO NERC MRO Yes Activity Transmission Yes Activity Buying Transmission Yes Activity Wholesale Marketing Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Residential Average Rates No Rates Available References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=Rushmore_Electric_Pwr_Coop_Inc&oldid=41147

52

Vermont Public Pwr Supply Auth | Open Energy Information  

Open Energy Info (EERE)

Public Pwr Supply Auth Public Pwr Supply Auth Jump to: navigation, search Name Vermont Public Pwr Supply Auth Place Vermont Utility Id 19780 Utility Location Yes Ownership P NERC Location NPCC NERC NPCC Yes ISO NE Yes Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Wholesale Marketing Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png No rate schedules available. Average Rates No Rates Available References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=Vermont_Public_Pwr_Supply_Auth&oldid=411933"

53

Puerto Rico Electric Pwr Authority | Open Energy Information  

Open Energy Info (EERE)

Rico Electric Pwr Authority Rico Electric Pwr Authority Jump to: navigation, search Name Puerto Rico Electric Pwr Authority Place Puerto Rico Utility Id 15497 Utility Location Yes Ownership S NERC Location PR Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Distribution Yes Alt Fuel Vehicle Yes Alt Fuel Vehicle2 Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png 312 - Industrial General at Primary Distribution Average Rates No Rates Available References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=Puerto_Rico_Electric_Pwr_Authority&oldid=411417"

54

Effects of Multiple Drying Cycles on HBU PWR Cladding Alloys  

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

The purpose of this research effort is to determine the effects of canister/cask vacuum drying and storage on radial hydride precipitation in high?burnup (HBU) pressurized water reactor (PWR)...

55

Renville-Sibley Coop Pwr Assn | Open Energy Information  

Open Energy Info (EERE)

Renville-Sibley Coop Pwr Assn Renville-Sibley Coop Pwr Assn Jump to: navigation, search Name Renville-Sibley Coop Pwr Assn Place Minnesota Utility Id 15845 Utility Location Yes Ownership C NERC Location MRO NERC MRO Yes ISO MISO Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png No rate schedules available. Average Rates Residential: $0.0883/kWh Commercial: $0.0867/kWh Industrial: $0.0471/kWh References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=Renville-Sibley_Coop_Pwr_Assn&oldid=41144

56

Fort Drum integrated resource assessment. Volume 3, Resource assessment  

SciTech Connect

The US Army Forces Command (FORSCOM) has tasked Pacific Northwest Laboratory (PNL) as the lead laboratory supporting the US Department of Energy (DOE) Federal Energy Management Program`s (FEMP) mission to identify, evaluate, and assist in acquiring all cost-effective energy projects at Fort Drum. This is a model program PNL is designing for federal customers served by the Niagara Mohawk Power Company (Niagara Mohawk). It will (1) identify and evaluate all electric and fossil fuel cost-effective energy projects; (2) develop a schedule at each installation for project acquisition considering project type, size, timing, capital requirements, as well as energy and dollar savings; and (3) secure 100% of the financing required to implement electric energy efficiency projects from Niagara Mohawk and have Niagara Mohawk procure the necessary contractors to perform detailed audits and install the technologies. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at one of Niagara Mohawk`s primary federal facilities, the FORSCOM Fort Drum facility located near Watertown, New York. It is a companion report to Volume 1, the Executive Summary, and Volume 2, the Baseline Detail.

Dixon, D.R.; Armstrong, P.R.; Daellenbach, K.K.; Dagle, J.E.; Di Massa, F.V.; Elliott, D.B.; Keller, J.M.; Richman, E.E.; Shankle, S.A.; Sullivan, G.P.; Wahlstrom, R.R.

1992-12-01T23:59:59.000Z

57

Targeted Health Assessment for Wastes Contained at the Niagara Falls Storage Site to Guide Planning for Remedial Action Alternatives - 13428  

SciTech Connect

The U.S. Army Corps of Engineers (USACE) is evaluating potential remedial alternatives at the 191-acre Niagara Falls Storage Site (NFSS) in Lewiston, New York, under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Manhattan Engineer District (MED) and Atomic Energy Commission (AEC) brought radioactive wastes to the site during the 1940's and 1950's, and the U.S. Department of Energy (US DOE) consolidated these wastes into a 10-acre interim waste containment structure (IWCS) in the southwest portion of the site during the 1980's. The USACE is evaluating remedial alternatives for radioactive waste contained within the IWCS at the NFSS under the Feasibility Study phase of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process. A preliminary evaluation of the IWCS has been conducted to assess potential airborne releases associated with uncovered wastes, particularly during waste excavation, as well as direct exposures to uncovered wastes. Key technical issues for this assessment include: (1) limitations in waste characterization data; (2) representative receptors and exposure routes; (3) estimates of contaminant emissions at an early stage of the evaluation process; (4) consideration of candidate meteorological data and air dispersion modeling approaches; and (5) estimates of health effects from potential exposures to both radionuclides and chemicals that account for recent updates of exposure and toxicity factors. Results of this preliminary health risk assessment indicate if the wastes were uncovered and someone stayed at the IWCS for a number of days to weeks, substantial doses and serious health effects could be incurred. Current controls prevent such exposures, and the controls that would be applied to protect onsite workers during remedial action at the IWCS would also effectively protect the public nearby. This evaluation provides framing context for the upcoming development and detailed evaluation of remedial alternatives for the IWCS. (authors)

Busse, John; Keil, Karen; Staten, Jane; Miller, Neil; Barker, Michelle [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States)] [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States); MacDonell, Margaret; Peterson, John; Chang, Young-Soo; Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)] [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

2013-07-01T23:59:59.000Z

58

Design report for the interim waste containment facility at the Niagara Falls Storage Site. [Surplus Facilities Management Program  

SciTech Connect

Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection.

Not Available

1986-05-01T23:59:59.000Z

59

E-Print Network 3.0 - air primer pwr Sample Search Results  

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

primer pwr Search Powered by Explorit Topic List Advanced Search Sample search results for: air primer pwr Page: << < 1 2 3 4 5 > >> 1 Document 320834-001 Intel CoreTM i7...

60

Fuel Assembly Shaker Test for Determining Loads on a PWR Assembly...  

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

Assembly Shaker Test for Determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport R0.1 Fuel Assembly Shaker Test for Determining Loads on a PWR...

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Timing analysis of PWR fuel pin failures  

SciTech Connect

This report discusses research conducted to develop and demonstrate a methodology for calculation of the time interval between receipt of the containment isolation signals and the first fuel pin failure for loss-of-coolant accidents (LOCAs). Demonstration calculations were performed for a Babcock and Wilcox (B W) design (Oconee) and a Westinghouse (W) four-loop design (Seabrook). Sensitivity studies were performed to assess the impacts of fuel pin burnup, axial peaking factor, break size, emergency core cooling system availability, and main coolant pump trip on these times. The analysis was performed using the following codes: FRAPCON-2, for the calculation of steady-state fuel behavior; SCDAP/RELAP5/MOD3 and TRACPF1/MOD1, for the calculation of the transient thermal-hydraulic conditions in the reactor system; and FRAP-T6, for the calculation of transient fuel behavior. In addition to the calculation of fuel pin failure timing, this analysis provides a comparison of the predicted results of SCDAP/RELAP5/MOD3 and TRAC-PF1/MOD1 for large-break LOCA analysis. Using SCDAP/RELAP5/MOD3 thermal-hydraulic data, the shortest time intervals calculated between initiation of containment isolation and fuel pin failure are 10.4 seconds and 19.1 seconds for the B W and W plants, respectively. Using data generated by TRAC-PF1/MOD1, the shortest intervals are 10.3 seconds and 29.1 seconds for the B W and W plants, respectively. These intervals are for a double-ended, offset-shear, cold leg break, using the technical specification maximum peaking factor and applied to fuel with maximum design burnup. Using peaking factors commensurate with actual burnups would result in longer intervals for both reactor designs. This document provides appendices K and L of this report which provide plots for the timing analysis of PWR fuel pin failures for Oconee and Seabrook respectively.

Jones, K.R.; Wade, N.L.; Katsma, K.R.; Siefken, L.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Straka, M. (Halliburton NUS, Idaho Falls, ID (United States))

1992-09-01T23:59:59.000Z

62

East Mississippi Elec Pwr Assn | Open Energy Information  

Open Energy Info (EERE)

Mississippi Elec Pwr Assn Mississippi Elec Pwr Assn Jump to: navigation, search Name East Mississippi Elec Pwr Assn Place Mississippi Utility Id 5578 Utility Location Yes Ownership C NERC Location SERC NERC SERC Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png GENERAL POWER RATE--SCHEDULE GSA--Rate 50 Commercial GENERAL POWER RATE--SCHEDULE GSA--Rate 51 Commercial GENERAL POWER RATE--SCHEDULE GSA--Rate 54 GENERAL POWER RATE--SCHEDULE GSA--Rate 80 Commercial GENERAL POWER RATE--SCHEDULE SGSB--Rate 56 General Power- Rate 40 Commercial LIGHTING--SCHEDULE LS--Rate SL

63

Grand Valley Rrl Pwr Line, Inc | Open Energy Information  

Open Energy Info (EERE)

Pwr Line, Inc Pwr Line, Inc Jump to: navigation, search Name Grand Valley Rrl Pwr Line, Inc Place Colorado Utility Id 7563 Utility Location Yes Ownership C NERC Location WECC NERC WECC Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Commercial and Small Power Service, Three Phase Schedule (25)-CSP-1 Commercial Farm and Home (Residential) Service Schedule (10)-FH-1 Residential Industrial Service Schedule (50) -IND-1 Industrial Irrigation Service Schedule (40)-I-1 Commercial Large Power Service Schedule (30) -LP-1 Industrial Nonresidential - General Schedule (20)-NRG-1 Commercial

64

Cuming County Public Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

Cuming County Public Pwr Dist Cuming County Public Pwr Dist (Redirected from Cuming County Public Power District) Jump to: navigation, search Name Cuming County Public Pwr Dist Place West Point, Nebraska Utility Id 4632 Utility Location Yes Ownership P NERC Location MRO NERC MRO Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] SGIC[2] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Gravel Pit Service Rate Industrial High Voltage Delivery Rate Industrial Irrigation Service Anytime Control Industrial Irrigation Service Every-Other-Day Control Industrial Irrigation Service No Control Industrial Large Power Rate Industrial

65

Keosauqua Municipal Light & Pwr | Open Energy Information  

Open Energy Info (EERE)

Keosauqua Municipal Light & Pwr Keosauqua Municipal Light & Pwr Jump to: navigation, search Name Keosauqua Municipal Light & Pwr Place Iowa Utility Id 10181 Utility Location Yes Ownership M NERC Location SERC NERC SERC Yes ISO Other Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Commercial Public Commercial Demand Rate Industrial Industrial Rate Industrial Residential Residential Security Light Lighting Average Rates Residential: $0.1040/kWh Commercial: $0.0858/kWh Industrial: $0.1190/kWh References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a"

66

Seward County Rrl Pub Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

Seward County Rrl Pub Pwr Dist Seward County Rrl Pub Pwr Dist Jump to: navigation, search Name Seward County Rrl Pub Pwr Dist Place Nebraska Utility Id 16954 Utility Location Yes Ownership P NERC Location SPP NERC SPP Yes RTO SPP Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Cabins Commercial Commercial Electric Speace Heating L29 Commercial Commercial Electric Speace Heating L30 Commercial Grain Dryer Accounts Single Phase Commercial Grain Dryer Accounts Three Phase Commercial Industrial Service Industrial Industrial Service L75 Industrial Irrigation Service 3 Day control Industrial

67

Prentiss County Elec Pwr Assn | Open Energy Information  

Open Energy Info (EERE)

Prentiss County Elec Pwr Assn Prentiss County Elec Pwr Assn Jump to: navigation, search Name Prentiss County Elec Pwr Assn Place Mississippi Utility Id 15334 Utility Location Yes Ownership C NERC Location SERC NERC SERC Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png General Power GSA 1 (50 kW and Under) CT Metered Single-Phase Commercial General Power GSA 1 (50 kW and Under) Multi-Phase Commercial General Power GSA 1 (50 kW and Under) Single-Phase Commercial General Power GSA 2 (51 kW - 1000 kW) Commercial General Power GSA 3 (1001 kW - 5000 kW) Industrial

68

Elkhorn Rural Public Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

Rural Public Pwr Dist Rural Public Pwr Dist Jump to: navigation, search Name Elkhorn Rural Public Pwr Dist Place Nebraska Utility Id 5780 Utility Location Yes Ownership P NERC Location SPP NERC SPP Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Mercury Vapor Lamp 175 Watt Lighting Mercury Vapor Lamp 250 Watt Lighting Mercury Vapor Lamp 400 Watt Lighting Metal Halide 1000 Watt Lighting Metal Halide 1500 Watt Lighting Metal Halide 400 Watt Lighting RATE 1,3- Farm Residential, Commercial, Cabins, Seasonal--Single Phase Commercial RATE 12, 69- Urban Commercial Electric Space Heating, Single Phase

69

Pearl River Valley El Pwr Assn | Open Energy Information  

Open Energy Info (EERE)

El Pwr Assn El Pwr Assn Jump to: navigation, search Name Pearl River Valley El Pwr Assn Place Mississippi Utility Id 14563 Utility Location Yes Ownership C NERC Location SERC NERC SERC Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png 1 GS General Service 10 LGS-6 Large General Service 2 GS-DG General Service Distributed Generation 20 LP-6 Large Power 21 LP-AE-2 Large Power All Electric 22 LP-PM-6 Large Power Primary Meter 23 LP-PM-AE-2 Large Power Primary Metering All Electric 3 GS-TWH General Service Tankless Water Heater 3 TGS-1 Temporary General Service

70

South Mississippi El Pwr Assn | Open Energy Information  

Open Energy Info (EERE)

El Pwr Assn El Pwr Assn (Redirected from South Mississippi Electric Power Association (SMEPA)) Jump to: navigation, search Name South Mississippi El Pwr Assn Place Mississippi Utility Id 17568 Utility Location Yes Ownership C NERC Location SERC NERC SERC Yes Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Buying Transmission Yes Activity Wholesale Marketing Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png No rate schedules available. Average Rates No Rates Available References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a"

71

Polk County Rural Pub Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

County Rural Pub Pwr Dist County Rural Pub Pwr Dist Jump to: navigation, search Name Polk County Rural Pub Pwr Dist Place Nebraska Utility Id 15188 Utility Location Yes Ownership P NERC Location MRO Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Cabin Residential City of Stromsburg - CYC 3/REV 8 Commercial Commercial Elec Space Heating - One Phase Commercial Commercial Elec Space Heating - Three Phase Commercial General Service CYC 2/REV1 - Three Phase Residential General Service CYC/Rev1 - Single Phase Residential Irrigation CYC 1 - Five 1/2 day - Single Phase Industrial

72

Crawfordsville Elec, Lgt & Pwr | Open Energy Information  

Open Energy Info (EERE)

Crawfordsville Elec, Lgt & Pwr Crawfordsville Elec, Lgt & Pwr Jump to: navigation, search Name Crawfordsville Elec, Lgt & Pwr Place Indiana Utility Id 4508 Utility Location Yes Ownership M NERC Location RFC NERC RFC Yes ISO MISO Yes Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Commercial General Power- Single Phase Commercial Commercial General Power- Three Phase Commercial Industrial Primary Power Industrial Outdoor Lighting- 100 watt sodium vapor Lighting Outdoor Lighting- 175 watt mercury vapor Lighting

73

Singing River Elec Pwr Assn | Open Energy Information  

Open Energy Info (EERE)

Singing River Elec Pwr Assn Singing River Elec Pwr Assn Place Alabama Utility Id 17252 References Energy Information Administration.[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png No rate schedules available. Average Rates Residential: $0.1080/kWh Commercial: $0.1110/kWh The following table contains monthly sales and revenue data for Singing River Elec Pwr Assn (Alabama). Month RES REV (THOUSAND $) RES SALES (MWH) RES CONS COM REV (THOUSAND $) COM SALES (MWH) COM CONS IND_REV (THOUSAND $) IND SALES (MWH) IND CONS OTH REV (THOUSAND $) OTH SALES (MWH) OTH CONS TOT REV (THOUSAND $) TOT SALES (MWH) TOT CONS 2009-03 34.718 304.244 306 4.774 40.12 19 39.492 344.364 325

74

South Central Public Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

Pwr Dist Pwr Dist Jump to: navigation, search Name South Central Public Pwr Dist Place Nebraska Utility Id 17548 Utility Location Yes Ownership P NERC Location MRO NERC MRO Yes RTO SPP Yes Activity Distribution Yes Activity Retail Marketing Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Area&Directional Lighting Service District Owned Pole Rental Lighting Area&Directional Lighting Service District Owned Span of Conductor Rent Lighting Area&Directional Lighting Service Rate N721 Lighting Area&Directional Lighting Service Rate N721 - Fringe Lighting

75

Examination of dissimilar metal welds in BWR and PWR piping  

SciTech Connect

This paper addresses dissimilar metal weld examinations at PWRS. Surveys were conducted to document the dissimilar metal weld configurations at PWR plants and to update the information known about dissimilar metal weld configurations at BWR plants. The experiences which BWR utilities have had with dissimilar metal weld examinations are documented and include: correct identification of IGSCC, indications thought to be IGSCC but were actually fabrication flaws, and difficulties encountered with the examination of dissimilar metal welds after stress improvement. An experimental program was conducted which verified that the longitudinal wave procedures developed for BWRs are also applicable to PWR designs.

MacDonald, D.E. [Electric Power Research Inst., Charlotte, NC (United States). NDE Center

1994-12-31T23:59:59.000Z

76

Ris9-R-609(EN) Simulation ofa PWR Power Plant  

E-Print Network (OSTI)

with steam line, turbine and condenser, interconnected with pumps, valves and controllers. The model can system consists of a condenser connected to the steam generator via a single pump. A single by the traditional PWR plant components, primary circuit with reactor, prcssurizer and steam generator, steam circuit

77

Fort Drum integrated resource assessment  

SciTech Connect

The US Army Forces Command (FORSCOM) has tasked Pacific Northwest Laboratory (PNL) as the lead laboratory supporting the US Department of Energy (DOE) Federal Energy Management Program's (FEMP) mission to identify, evaluate, and assist in acquiring all cost-effective energy projects at Fort Drum. This is a model program PNL is designing for federal customers served by the Niagara Mohawk Power Company (Niagara Mohawk). It will (1) identify and evaluate all electric and fossil fuel cost-effective energy projects; (2) develop a schedule at each installation for project acquisition considering project type, size, timing, capital requirements, as well as energy and dollar savings; and (3) secure 100% of the financing required to implement electric energy efficiency projects from Niagara Mohawk and have Niagara Mohawk procure the necessary contractors to perform detailed audits and install the technologies. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at one of Niagara Mohawk's primary federal facilities, the FORSCOM Fort Drum facility located near Watertown, New York. It is a companion report to Volume 1, the Executive Summary, and Volume 2, the Baseline Detail.

Dixon, D.R.; Armstrong, P.R.; Daellenbach, K.K.; Dagle, J.E.; Di Massa, F.V.; Elliott, D.B.; Keller, J.M.; Richman, E.E.; Shankle, S.A.; Sullivan, G.P.; Wahlstrom, R.R.

1992-12-01T23:59:59.000Z

78

ORNL/RASA-85/1 RESULTS OF THE II4OBILE GAMMA SCANNING ACTIVITIES IN NIAGARA FALLS, NEvl YORK AREA  

Office of Legacy Management (LM)

Nf7 n-q Nf7 n-q gz75 tLtY r 1 irl,r:'a :.a l: i , l : i l ',:lr.:'. itl:t i .,,::l ' i , t . . ORNL/RASA-85/1 RESULTS OF THE II4OBILE GAMMA SCANNING ACTIVITIES IN NIAGARA FALLS, NEvl YORK AREA Access to the information in this report is limited to thoss indicated on the distribution list and io Department ol Energy ancl Depsrtment of Energy Contractors This report was prepared as an account ol work sponsored by an agency of the United States Government. Neither the U nited StatesGovernment nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any informalion, apparatus, product, or process disclosed, or represents thal its use would not inf ringe

79

North Central Public Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

North Central Public Pwr Dist North Central Public Pwr Dist Place Nebraska Utility Id 13698 Utility Location Yes Ownership P NERC Location MRO NERC MRO Yes RTO SPP Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png 1- Single Phase Farm Residential Residential 10- Irrigation - Pivot Drive Commercial 11- Irrigation - No Control Commercial 12- Irrigation - 2 Day Control & Sunday Control Commercial 13- Irrigation - 3 Day Control & Sunday Control Commercial 14- Irrigation - Anytime Control & Sunday control Commercial 19- Single Phase Farm Residential (Leased areas) Commercial

80

South Mississippi El Pwr Assn | Open Energy Information  

Open Energy Info (EERE)

Assn Assn Jump to: navigation, search Name South Mississippi El Pwr Assn Place Mississippi Utility Id 17568 Utility Location Yes Ownership C NERC Location SERC NERC SERC Yes Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Buying Transmission Yes Activity Wholesale Marketing Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png No rate schedules available. Average Rates No Rates Available References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=South_Mississippi_El_Pwr_Assn&oldid=411549

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Cuming County Public Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

Cuming County Public Pwr Dist Cuming County Public Pwr Dist Place West Point, Nebraska Utility Id 4632 Utility Location Yes Ownership P NERC Location MRO NERC MRO Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] SGIC[2] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Gravel Pit Service Rate Industrial High Voltage Delivery Rate Industrial Irrigation Service Anytime Control Industrial Irrigation Service Every-Other-Day Control Industrial Irrigation Service No Control Industrial Large Power Rate Industrial Municipal Commercial Demand Rate Commercial Municipal Commercial Demand Rate Three Phase V2 Commercial Municipal Commercial Electric Space Heating Rate Commercial

82

21-PWR WASTE PACKAGE WITH ABSORBER PLATES LOADING CURVE EVALUATION  

SciTech Connect

The objective of this calculation is to evaluate the required minimum burnup as a function of initial pressurized water reactor (PWR) assembly enrichment that would permit loading of spent nuclear fuel into the 21 PWR waste package with absorber plates design as provided in Attachment IV. This calculation is an example of the application of the methodology presented in the ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent U-235, and a burnup range of 0 through 45 GWd/MTU. Higher burnups were not necessary because 45 GWd/MTU was high enough for the loading curve determination. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing PWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report. (2) The results are based on 1.5 wt% Gd in the Ni-Gd Alloy material and having no tuff inside the waste package. If the Gd loading is reduced or a process to introduce tuff inside the waste package is defined, then this report would need to be reevaluated based on the alternative materials. This calculation is subject to the ''Quality Assurance Requirements and Description'' (QARD) (DOE 2004) because it concerns engineered barriers that are included in the ''Q-List'' (BSC 2004k, Appendix A) as items important to safety and waste isolation.

J.M. Scaglione

2004-12-17T23:59:59.000Z

83

Niagara Falls Storage Site, Lewiston, New York: Annual site environmental report, Calendar year 1987: Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect

The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1987 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 13 refs., 10 figs., 20 tabs.

Not Available

1988-04-01T23:59:59.000Z

84

Niagara Falls Storage Site environmental report for calendar year 1992, 1397 Pletcher Road, Lewiston, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)  

SciTech Connect

This report describes the environmental surveillance program at the Niagara Falls Storage Site (NFSS) and provides the results for 1992. From 1944 to the present, the primary use of NFSS has been storage of radioactive residues produced as a by-product of uranium production. All onsite areas of residual radioactivity above guidelines have been remediated. Materials generated during remediation are stored onsite in the 4-ha (10-acre) waste containment structure (WCS). The WCS is a clay-lined, clay-capped, and grass-covered storage pile. The environmental surveillance program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Several chemical parameters, including seven metals, are also routinely measured in groundwater. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Results of environmental monitoring during 1992 indicate that levels of the parameters measured were in compliance with all but one requirement: Concentrations of iron and manganese in groundwater were above NYSDEC groundwater quality standards. However, these elements occur naturally in the soils and groundwater associated with this region. In 1992 there were no environmental occurrences or reportable quantity releases.

Not Available

1993-05-01T23:59:59.000Z

85

Advanced Integral-type Small-size PWR - SMART  

SciTech Connect

SMART - an advanced integral-type small-size PWR has been developed for the dual purpose applications of seawater desalination and small-scale power generation. SMART, rated thermal power of 330 MW, adopts various new and innovative design features along with proven PWR technologies, and the non-site-specific basic design has been completed. Highly enhanced safety and reliability, improved performance, simplicity, and modularization are those of strongly emphasized design philosophies which were applied to the system design. The inherent safety improving design and passive safety design features are the key safety design features uniquely characterizing SMART compared to the conventional loop-type reactors. Various transients and accidents were analyzed for the SMART basic design, and the results confirm that safety is assured with margins in any postulated transient and accident. Further, the level-1 full power PSA shows that the core damage frequency is about two orders of magnitude less than those of the existing conventional PWRs. Based on the safety and reliability analyses, it is found that design optimization will further improve the level of safety. Various design verification efforts have been carried out and others are currently underway. (authors)

Chang, Moon H.; Zee, Sung Q.; Kim, Keung K.; Kim, Si-Hwan [Korea Atomic Energy Research Institute, P. O. Box 105, Yuseong, Daejeon (Korea, Republic of)

2004-07-01T23:59:59.000Z

86

Griffiss AFB integrated resource assessment. Volume 2, Electric baseline detail  

SciTech Connect

The US Air Force Air Combat Command has tasked the Pacific Northwest Laboratory (PNL) as the lead laboratory supporting the US Department of Energy (DOE) Federal Energy Management Program`s (FEMP) mission to identify, evaluate, and assist in acquiring all cost-effective energy projects at Griffiss Air Force Base (AFB). This is a model program PNL is designing for federal customers served by the Niagara Mohawk Power Company (Niagara Mohawk). It will (1) identify and evaluate all electric cost-effective energy projects; (2) develop a schedule at each installation for project acquisition considering project type, size, timing, and capital requirements, as well as energy and dollar savings; and (3) secure 100% of the financing required to implement electric energy efficiency projects from Niagara Mohawk and have Niagara Mohawk procure the necessary contractors to perform detailed audits and install the technologies. This report documents the assessment of baseline energy use at one of Niagara Mohawk`s primary federal facilities, Griffiss AFB, an Air Combat Command facility located near Rome, New York. It is a companion report to Volume 1, the Executive Summary, and Volume 3, the Electric Resource Assessment. The analysis examines the characteristics of electric, gas, oil, propane, coal, and purchased thermal capacity use for fiscal year (FY) 1990. The results include energy-use intensities for the facilities at Griffiss AFB by building type and electric energy end use. A complete electric energy consumption reconciliation is presented that accounts for the distribution of all major electric energy uses and losses among buildings, utilities, and central systems.

Dixon, D.R.; Armstrong, P.R.; Keller, J.M.

1993-02-01T23:59:59.000Z

87

Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184  

SciTech Connect

The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: ? Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. ? DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. ? DOE must continue to maintain constructive relationships with the U.S. Army Corps of Engineers and state and federal regulators.

Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

2012-02-26T23:59:59.000Z

88

Wolverine Pwr Supply Coop, Inc | Open Energy Information  

Open Energy Info (EERE)

Supply Coop, Inc Supply Coop, Inc Jump to: navigation, search Name Wolverine Pwr Supply Coop, Inc Place Michigan Utility Id 20910 Utility Location Yes Ownership C NERC Location RFC NERC RFC Yes Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Buying Transmission Yes Activity Distribution Yes Activity Wholesale Marketing Yes Activity Bundled Services Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png LP-C ( Large Power Choice) Schedule A- Residential Residential Schedule AH- Residential Residential Schedule AS- Residential Residential

89

Benefits of Integrating PWR and RTI Advanced Gasification Technologies for  

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

Syngas Processing Systems Syngas Processing Systems Benefits of Integrating PWR and RTI Advanced Gasification Technologies for Hydrogen-Rich Syngas Production Research Triangle Institute (RTI) Project Number: FE0012066 Project Description The project will assess the potential for integrated advanced technologies to substantially reduce capital and production costs for hydrogen-rich syngas with near-zero emissions from coal gasification for power production with carbon capture and for coal-to-liquids (specifically methanol) with carbon capture. These integrated technologies include those already tested successfully at pilot-scale with a new and innovative water-gas-shift technology, to show how multiple advanced technologies will leverage each other for significant cost and efficiency gains.

90

Stanton County Public Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

(Redirected from Stanton County Public Power District) (Redirected from Stanton County Public Power District) Jump to: navigation, search Name Stanton County Public Pwr Dist Place Stanton, Nebraska Utility Id 17979 Utility Location Yes Ownership P NERC Location SPP NERC SPP Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] SGIC[2] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Stanton County Public Power District Smart Grid Project was awarded $397,000 Recovery Act Funding with a total project value of $794,000. Utility Rate Schedules Grid-background.png Commercial Pumping Single Phase Commercial Commercial Pumping Three Phase Commercial Commercial Single Phase Commercial Commercial Three Phase Commercial

91

Red River Valley Coop Pwr Assn | Open Energy Information  

Open Energy Info (EERE)

Assn Assn Jump to: navigation, search Name Red River Valley Coop Pwr Assn Place Minnesota Utility Id 26939 Utility Location Yes Ownership C NERC Location MRO NERC MRO Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Decorative Post Light Lighting General - Three Phase Industrial Post Light Lighting Residential - Off-Peak Residential Residential - Single Phase Residential Security Parking Light Lighting Yard Light Lighting Average Rates Residential: $0.0892/kWh Commercial: $0.0883/kWh References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a"

92

Solving chemical and mechanical problems of PWR steam generators  

SciTech Connect

Steam generators in power plants, based on pressurized water reactors (PWRs), transfer heat from a primary coolant system (pressurized water) to a secondary coolant system. Primary coolant water is heated in the core and passes through the steam generator that transfers heat to the secondary coolant water to make steam. The steam then drives a turbine that turns an electric generator. Steam is condensed and returned to the steam generator as feedwater. Two types of PWR steam generators are in use: recirculating steam generators (RSGs) and once-through steam generators (OTSGs). Since most of the units are vertical, only vertical units are discussed in this article. Some vertical units have operated with a minimum of problems, while others have experienced a variety of corrosion and mechanically-induced problems that have caused unscheduled outages and expensive repairs.

Green, S.J.

1987-07-01T23:59:59.000Z

93

Singing River Elec Pwr Assn (Mississippi) | Open Energy Information  

Open Energy Info (EERE)

Assn (Mississippi) Assn (Mississippi) Jump to: navigation, search Name Singing River Elec Pwr Assn Place Mississippi Utility Id 17252 Utility Location Yes Ownership C NERC Location SERC NERC ERCOT Yes NERC SERC Yes ISO Other Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1]Energy Information Administration Form 826[2] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Commercial Delivery Point Service (Over 2500 kW) Commercial Commercial General Service (25 kw - 249 kW) Commercial Commercial General Service (25 kw - 249 kW) Primary Voltage Commercial Commercial Large General Service (250 kW - 749 kW) Commercial

94

Advanced pressurized water reactor for improved resource utilization, part II - composite advanced PWR concept  

SciTech Connect

This report evaluates the enhanced resource utilization in an advanced pressurized water reactor (PWR) concept using a composite of selected improvements identified in a companion study. The selected improvements were in the areas of reduced loss of neutrons to control poisons, reduced loss of neutrons in leakage from the core, and improved blanket/reflector concepts. These improvements were incorporated into a single composite advanced PWR. A preliminary assessment of resource requirements and costs and impact on safety are presented.

Turner, S.E.; Gurley, M.K.; Kirby, K.D.; Mitchell, W III

1981-09-15T23:59:59.000Z

95

Forthcoming Events  

Science Journals Connector (OSTI)

...Industrial and Commercial Power Systems, conf...of Botany and Plant Pathology, Purdue...Industrial and Commercial Power Systems, conf...Think about it. For specifications and warranty, write...Niagara Mohawk Power Corp., 300 Erie...25-27. Electrical Insulation, Natl. Acad...

1965-08-27T23:59:59.000Z

96

A Feasibility Study of an Integral PWR for Space Applications  

SciTech Connect

Fission space power systems are well suited to provide safe, reliable, economic and robust energy sources, in the order of 100 KWe. A preliminary feasibility study of a nuclear fission reactor is here presented with the following requirements: i) high reliability, ii) R and D program of moderate cost, iii) to be deployed within a reasonable period of time (e.g. 2015), iv) to be operated and controlled for a long time (10 years) without human intervention, v) possibly to be also used as a byproduct for some particular terrestrial application (or at least to share common technologies), vi) to start with stationary application. The driving idea is to extend as much as possible the PWR technology, by recurring to an integral type reactor. Two options are evaluated for the electricity production: a Rankine steam cycle and a Rankine organic fluid cycle. The neutronics calculation is based on WIMS code benchmarked with MCNP code. The reactivity control is envisaged by changing the core geometry. The resulting system appears viable and of reasonable size, well fit to the present space vector capabilities. Finally, a set of R and D needs has been identified: cold well, small steam turbines, fluid leakage control, pumps, shielding, steam generator in low-gravity conditions, self pressurizer, control system. A R and D program of reasonable extent may yield the needed answers, and some demanding researches are of interest for the new generation Light Water Reactors. (authors)

Grandis, S. De; Finzi, E.; Lombardi, C.V.; Mandelli, D.; Padovani, E.; Passoni, M.; Ricotti, M.E.; Santini, L. [Dipartimento di Ingegneria Nucleare, Politecnico di Milano, Via Ponzio, 34/3, 20133 Milano (Italy); Summerer, L. [ESA Advanced Concepts Team, ESTEC, SER-A, Keplerlaan 1, 2201 AZ Noordwijk (Netherlands)

2004-07-01T23:59:59.000Z

97

Griffiss AFB integrated resource assessment  

SciTech Connect

The US Air Force Air Combat Command has tasked the Pacific Northwest Laboratory (PNL) as the lead laboratory supporting the US Department of Energy (DOE) Federal Energy Management Program's (FEMP) mission to identify, evaluate, and assist in acquiring all cost-effective energy projects at Griffiss Air Force Base (AFB). This is a model program PNL is designing for federal customers served by the Niagara Mohawk Power Company (Niagara Mohawk). It will (1) identify and evaluate all electric cost-effective energy projects; (2) develop a schedule at each installation for project acquisition considering project type, size, timing, and capital requirements, as well as energy and dollar savings; and (3) secure 100% of the financing required to implement electric energy efficiency projects from Niagara Mohawk and have Niagara Mohawk procure the necessary contractors to perform detailed audits and install the technologies. This report documents the assessment of baseline energy use at one of Niagara Mohawk's primary federal facilities, Griffiss AFB, an Air Combat Command facility located near Rome, New York. It is a companion report to Volume 1, the Executive Summary, and Volume 3, the Electric Resource Assessment. The analysis examines the characteristics of electric, gas, oil, propane, coal, and purchased thermal capacity use for fiscal year (FY) 1990. The results include energy-use intensities for the facilities at Griffiss AFB by building type and electric energy end use. A complete electric energy consumption reconciliation is presented that accounts for the distribution of all major electric energy uses and losses among buildings, utilities, and central systems.

Dixon, D.R.; Armstrong, P.R.; Keller, J.M.

1993-02-01T23:59:59.000Z

98

Fuel Assembly Shaker Test for Determining Loads on a PWR Assembly under  

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

Assembly Shaker Test for Determining Loads on a PWR Assembly Assembly Shaker Test for Determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport R0.1 Fuel Assembly Shaker Test for Determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport R0.1 The United States current approach of long-term storage at its nuclear power plants and independent spent fuel storage installation, and deferred transportation of used nuclear fuel (UNF), along with the trend of nuclear power plants using reactor fuel for a longer time, creates questions concerning the ability of this aged, high-burnup fuel to withstand stresses and strains seen during normal conditions of transport from its current location to a future consolidated storage facility or permanent repository. UNFD R&D conducted testing employing surrogate instrumented

99

Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys | Department  

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

Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Structural analyses of high-burnup (HBU) fuel require cladding mechanical properties and failure limits to assess fuel behavior during long-term dry-cask storage and transportation. Pre-storage drying-transfer operations and early stage storage subject cladding to higher temperatures and pressure-induced tensile hoop stresses relative to in-reactor operation and pool storage. Under these conditions, radial hydrides may precipitate during slow cooling and provide an additional embrittlement mechanism as the cladding temperature decreases below the ductile-to-brittle transition temperature (DBTT). Graphic and photographic details of the testing are

100

What Future for Niagara Falls?  

Science Journals Connector (OSTI)

...count ry , ice plucking, abras ion by wind driven spray, and cavitat ion. In the...is going into s torage or th rough the turbines. T h e Niaga ra River is subject to...Tonawanda Harbor, N. Y.; Soundings after maintenance dredging: no. 106-A-274/6, sheet...

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty  

E-Print Network (OSTI)

A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty@csam.ucl.ac.be, Gevers@csam.ucl.ac.be 2 Electricite de France, Direction des Etudes et Recherches, 6 Quai Watier, F-78041 of a controller for the secondary circuit of a nu- clear Pressurized Water Reactor, leading to the conclu- sions

Gevers, Michel

102

Energy Spectra of Stray Neutron Fields at PWR Nuclear Power Plants  

Science Journals Connector (OSTI)

......Protection Dosimetry Article Energy Spectra of Stray Neutron Fields at PWR Nuclear Power Plants P. ~Jujak...equivalent to workers at nuclear power plants are discussed...The measured spectra of energy distribution of neutron...protection of the staff at nuclear power plants are presented......

P. ~Jujak; P. Carn; Z. Prouza; J. Hermansk

1987-07-01T23:59:59.000Z

103

Assessment of void swelling in austenitic stainless steel PWR core internals.  

SciTech Connect

As many pressurized water reactors (PWRs) age and life extension of the aged plants is considered, void swelling behavior of austenitic stainless steel (SS) core internals has become the subject of increasing attention. In this report, the available database on void swelling and density change of austenitic SSs was critically reviewed. Irradiation conditions, test procedures, and microstructural characteristics were carefully examined, and key factors that are important to determine the relevance of the database to PWR conditions were evaluated. Most swelling data were obtained from steels irradiated in fast breeder reactors at temperatures >385 C and at dose rates that are orders of magnitude higher than PWR dose rates. Even for a given irradiation temperature and given steel, the integral effects of dose and dose rate on void swelling should not be separated. It is incorrect to extrapolate swelling data on the basis of 'progressive compounded multiplication' of separate effects of factors such as dose, dose rate, temperature, steel composition, and fabrication procedure. Therefore, the fast reactor data should not be extrapolated to determine credible void swelling behavior for PWR end-of-life (EOL) or life-extension conditions. Although the void swelling data extracted from fast reactor studies is extensive and conclusive, only limited amounts of swelling data and information have been obtained on microstructural characteristics from discharged PWR internals or steels irradiated at temperatures and at dose rates comparable to those of a PWR. Based on this relatively small amount of information, swelling in thin-walled tubes and baffle bolts in a PWR is not considered a concern. As additional data and relevant research becomes available, the newer results should be integrated with existing data, and the worthiness of this conclusion should continue to be scrutinized. PWR baffle reentrant corners are the most likely location to experience high swelling rates, and hence, high swelling at EOL, especially in internal regions of small volume where irradiation temperature is high. However, it is considered unlikely that void swelling in a reentrant corner will exceed the threshold level of {approx}4% beyond which the swelling rate reaches the steady state rate of 1%/dpa. However, this estimation is only preliminary, and a more accurate quantification of maximum temperature of reentrant corners at EOL and life-extension situations would be useful.

Chung, H. M.; Energy Technology

2006-01-31T23:59:59.000Z

104

CANDU core analysis with spent PWR fuel of fixed {sup 235}U and {sup 239}Pu content  

SciTech Connect

The direct use of spent pressurized water reactor (PWR) fuel in a CANDU (DUPIC) fuel cycle requires that the spent PWR fuel be refabricated as a DUPIC fuel to be used in a CANDU reactor that was originally designed for the natural uranium fuel. Because there is no separation of isotopes from the spent PWR fuel, the DUPIC fuel contains all the actinides and fission products as fuel constituents and, therefore, the isotopic composition changes depending on the initial and discharge conditions of PWR fuels. Such heterogeneity in fuel composition is not desirable, especially for a CANDU reactor that adopts an on-power refueling scheme, because the operational flexibility is reduced appreciably if the fuel bundles of different composition are loaded throughout the core.

Choi, Hangbok; Roh, Gyu H.; Park, J.W. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-01T23:59:59.000Z

105

MC21 analysis of the MIT PWR benchmark: Hot zero power results  

SciTech Connect

MC21 Monte Carlo results have been compared with hot zero power measurements from an operating pressurized water reactor (PWR), as specified in a new full core PWR performance benchmark from the MIT Computational Reactor Physics Group. Included in the comparisons are axially integrated full core detector measurements, axial detector profiles, control rod bank worths, and temperature coefficients. Power depressions from grid spacers are seen clearly in the MC21 results. Application of Coarse Mesh Finite Difference (CMFD) acceleration within MC21 has been accomplished, resulting in a significant reduction of inactive batches necessary to converge the fission source. CMFD acceleration has also been shown to work seamlessly with the Uniform Fission Site (UFS) variance reduction method. (authors)

Kelly Iii, D. J.; Aviles, B. N. [Knolls Atomic Power Laboratory, Bechtel Marine Propulsion Corporation, P.O. Box 1072, Schenectady, NY 12301-1072 (United States); Herman, B. R. [Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139-4307 (United States)

2013-07-01T23:59:59.000Z

106

Application of the RCP01 Code to Depletion of a PWR Spent Nuclear Fuel Sample  

SciTech Connect

An essential component of a proposed burnup credit methodology for commercial PWR spent nuclear fuel (SNF) is the validation of the tools used for isotopic and criticality calculations. A number of benchmark experiments have been analyzed to establish the validation of the tools and to determine biases and corrections. To benchmark the RCP01 Monte Carlo computer code, an isotopic validation study was conducted for one of the benchmark experiments, a SNF sample taken from the Calvert Cliffs PWR Unit-1 (CCPU1). Modeling considerations and nuclear data associated with the RCP01 transport/depletion calculations are discussed. The accuracy of RCP01 calculations is demonstrated to be very good when RCP01 results are compared to destructive chemical assay data for major actinides and important fission products in the SNF sample.

Joo, Hansem

2002-01-01T23:59:59.000Z

107

MELCOR model for an experimental 17x17 spent fuel PWR assembly.  

SciTech Connect

A MELCOR model has been developed to simulate a pressurized water reactor (PWR) 17 x 17 assembly in a spent fuel pool rack cell undergoing severe accident conditions. To the extent possible, the MELCOR model reflects the actual geometry, materials, and masses present in the experimental arrangement for the Sandia Fuel Project (SFP). The report presents an overview of the SFP experimental arrangement, the MELCOR model specifications, demonstration calculation results, and the input model listing.

Cardoni, Jeffrey

2010-11-01T23:59:59.000Z

108

Design Study of 300 MWt PWR Fueled With UO{sub 2} Coated Fuel Particle  

SciTech Connect

A neutronic design was performed for 300 MWt Pressurized Water Reactor (PWR) with UO{sub 2} compacts made of coated fuel particles (CFP) comparing that with sintered pellets made of UO{sub 2} powder as ordinary fuel type. UO{sub 2} CFP type was enriched 4.8% of {sup 235}U and UO{sub 2} ordinary type was enriched 5% of {sup 235}U. Both reactors were operated with single batch refueling system with a cycle period of 3 years. The purpose of the design was to investigate the applicability of UO{sub 2} CFP type to PWR comparing with UO{sub 2} ordinary type that commonly used for PWR. The calculation was done with SRAC (Standard Reactor Analysis Code) computer code and nuclear library of JENDL-33. The results of calculation showed that k-effective for both type of fuel could be maintained at critical condition for 3 years operation without refueling. The k-effective and the Doppler coefficients have been calculated for all types of fuel at 600 K and 900 K degrees. The results of calculation showed that for all types of fuel Doppler coefficient was negative, which was good for inherent safety characteristic. The size optimization design showed that the active core dimensions of UO{sub 2} CFP type reactor was about 2 times larger than the UO{sub 2} ordinary type reactor. (authors)

Abu Khalid Rivai; Ferhat Aziz; Minoru Takahashi [Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)

2006-07-01T23:59:59.000Z

109

Comparative analysis of high conversion achievable in thorium-fueled slightly modified CANDU and PWR reactors  

Science Journals Connector (OSTI)

We study here the conversion performance of thorium-fueled standard or only slightly modified CANDU and PWR reactors with unchanged core envelope and equipments, to be eventually used as the third and last tier of symbiotic scenarios. For instance, plutonium extracted from the spent fuel of UOX \\{PWRs\\} could be converted in Th/Pu \\{CANDUs\\} to uranium (mainly 233U), finally used to feed a thorium-fueled water-cooled high converting third component. This could be a convenient way to replace likely delayed Generation IV in the case of an important increase of uranium-based energy demand. In order to assess the competitiveness of such symbiotic scenarios, detailed burnup and conversion data are obtained by means of a core-equivalent simulation methodology developed for CANDU-6 and adapted to N4-type PWR. Once-through cycles in CANDU are firstly evaluated for various Th/Pu and Th/233U fuels as regards detailed conversion and basic safety performance. Breeding in Th/233U CANDU is achieved for a 1.30wt% homogeneous fissile enrichment and a relatively short burnup of 7GWd/t. Small increase of enrichment (to 1.35wt%) considerably extends cycle length (to 14GWd/t) at the cost of slight sub-breeding. Heterogeneity of fissile load can bring another 70% gain on burnup with no significant impact on conversion. Multirecycling gives even shorter burnup (about 5GWd/t) for the breeding case, while performance close to the once-through 1.35wt% case is obtained for a slightly sub-breeding regime sustained by a small add of uranium from Th/Pu CANDU. Th/U cycle neutronic analysis explains the convenient feature of almost constant burnup as 233U load is unchanged at each recycle. Two symbiotic scenarios based on UOX PWRs, Th/Pu \\{CANDUs\\} and Th/233U \\{CANDUs\\} in a first open version or optimized Th/U \\{CANDUs\\} in a second closed version are compared. At standard power and moderation levels, Th/233U PWR conversion performance is much lower than CANDU with only a bit more than half of initial fissile load remaining after 50GWd/t. Contrary to CANDU, fuel heterogeneity does not increase burnup. Conversion is mainly improved by enhanced sub-moderation down to minimal acceptable water over fuel volume ratio of 0.8 at standard power. In this limit case, a 3.00wt% enrichment ensures a burnup of 33GWd/t with 80% of initial fissile load remaining. By comparing a few Th/233U CANDU and PWR high converting cases, we understand that main part of the CANDU-PWR conversion gap results from neutron-economical CANDU operation conditions based on frequent online refueling and therefore why sub-moderation improves PWR conversion. From this better understanding, we deduce and preliminarily evaluate two possible ways to really higher conversion with thorium fuel in PWR envelope based on faster spectra either with light water and power derating or with heavy water and Spectral Shift Control.

A. Nuttin; P. Guillemin; A. Bidaud; N. Capellan; R. Chambon; S. David; O. Mplan; J.N. Wilson

2012-01-01T23:59:59.000Z

110

Impact of radiation embrittlement on integrity of pressure vessel supports for two PWR plants  

SciTech Connect

Recent data from the HFIR vessel surveillance program indicate a substantial radiation embrittlement rate effect at low irradiation temperatures (/approximately/120/degree/F) for A212-B, A350-LF3, A105-II, and corresponding welds. PWR vessel supports are fabricated of similar materials and are subjected to the same low temperatures and fast neutron fluxes (10/sup 8/ to 10/sup 9/ neutrons/cm/sup 2//center dot/s, E > 1.0 MeV) as those in the HFIR vessel. Thus, the embrittlement rate of these structures may be greater than previously anticipated. A study sponsored by the NRC is under way at ORNL to determine the impact of the rate effect on PWR vessel-support life expectancy. The scope includes the interpretation and application of the HFIR data, a survey of all light-water-reactor vessel support designs, and a structural and fracture-mechanics analysis of the supports for two specific PWR plants of particular interest with regard to a potential for support failure as a result of propagation of flaws. Calculations performed thus far indicate best-estimate critical flaw sizes, corresponding to 32 EFPY, of /approximately/0.2 in. for one plant and /approximately/0.4 in. for the other. These flaw sizes are small enough to be of concern. However, it appears that low-cycle fatigue is not a viable mechanism for creation of flaws of this size, and thus, presumably, such flaws would have to exist at the time of fabrication. 59 refs., 128 figs., 49 tabs.

Cheverton, R.D.; Pennell, W.E.; Robinson, G.C.; Nanstad, R.K.

1989-01-01T23:59:59.000Z

111

Neutronics and safety characteristics of a 100% MOX fueled PWR using weapons grade plutonium  

SciTech Connect

Preliminary neutronics and safety studies, pertaining to the feasibility of using 100% weapons grade mixed-oxide (MOX) fuel in an advanced PWR Westinghouse design are presented in this paper. The preliminary results include information on boron concentration, power distribution, reactivity coefficients and xenon and control rode worth for the initial and the equilibrium cycle. Important safety issues related to rod ejection and steam line break accidents and shutdown margin requirements are also discussed. No significant change from the commercial design is needed to denature weapons-grade plutonium under the current safety and licensing criteria.

Biswas, D.; Rathbun, R.; Lee, Si Young [Westinghouse Savannah River Co., Aiken, SC (United States); Rosenthal, P. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

1993-12-31T23:59:59.000Z

112

O:ELECTRICPP-190.PDF  

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

authority to grant Presidential permits for the construction of electric transmission lines at the U.S. authority to grant Presidential permits for the construction of electric transmission lines at the U.S. 1 international border was transferred from the FPC to the Department of Energy by Executive Order 12038. PRESIDENTIAL PERMIT NIAGARA MOHAWK POWER CORPORATION PERMIT NO. PP-190 I. BACKGROUND The Office of Fossil Energy (FE) of the Department of Energy (DOE) has the responsibility for implementing Executive Order (EO) 10485, as amended by EO 12038, which requires the issuance of Presidential permits for the construction, connection, operation, and maintenance of electric transmission facilities at the United States international border. In an application dated July 21, 1998, and amended October 29, 1998, Niagara Mohawk

113

Secondary Startup Neutron Sources as a Source of Tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS)  

SciTech Connect

The hypothesis of this paper is that the Zircaloy clad fuel source is minimal and that secondary startup neutron sources are the significant contributors of the tritium in the RCS that was previously assigned to release from fuel. Currently there are large uncertainties in the attribution of tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS). The measured amount of tritium in the coolant cannot be separated out empirically into its individual sources. Therefore, to quantify individual contributors, all sources of tritium in the RCS of a PWR must be understood theoretically and verified by the sum of the individual components equaling the measured values.

Shaver, Mark W.; Lanning, Donald D.

2010-02-01T23:59:59.000Z

114

Application of the MELCOR code to design basis PWR large dry containment analysis.  

SciTech Connect

The MELCOR computer code has been developed by Sandia National Laboratories under USNRC sponsorship to provide capability for independently auditing analyses submitted by reactor manufactures and utilities. MELCOR is a fully integrated code (encompassing the reactor coolant system and the containment building) that models the progression of postulated accidents in light water reactor power plants. To assess the adequacy of containment thermal-hydraulic modeling incorporated in the MELCOR code for application to PWR large dry containments, several selected demonstration designs were analyzed. This report documents MELCOR code demonstration calculations performed for postulated design basis accident (DBA) analysis (LOCA and MSLB) inside containment, which are compared to other code results. The key processes when analyzing the containment loads inside PWR large dry containments are (1) expansion and transport of high mass/energy releases, (2) heat and mass transfer to structural passive heat sinks, and (3) containment pressure reduction due to engineered safety features. A code-to-code benchmarking for DBA events showed that MELCOR predictions of maximum containment loads were equivalent to similar predictions using a qualified containment code known as CONTAIN. This equivalency was found to apply for both single- and multi-cell containment models.

Phillips, Jesse; Notafrancesco, Allen (USNRC, Office of Nuclear Regulatory Research, Rockville, MD); Tills, Jack Lee (Jack Tills & Associates, Inc., Sandia Park, NM)

2009-05-01T23:59:59.000Z

115

MHK Projects/Mohawk MHK Project | Open Energy Information  

Open Energy Info (EERE)

MHK Project MHK Project < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":5,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"350px","centre":false,"title":"","label":"","icon":"File:Aquamarine-marker.png","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":[]}

116

WAPD-SC-545 HYDROGEN FLAMMABILITY DATA AND APPLICATION TO PWR  

Office of Scientific and Technical Information (OSTI)

WAPD-SC-545 WAPD-SC-545 HYDROGEN FLAMMABILITY DATA AND APPLICATION TO PWR LOSS-OF-COOLANT ACCIDENT CONTRACT A T - I M - G E N - H BETTIS PLANT PITTSBURGH, PENNSYLVANIA Operated for the U.S. ATOMIC ENERGY COMMISSION by WESTINGHOUSE ELECTRIC CORPORATION DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product,

117

Evaluation of steam-generator fluid mixing during layup. Final report. [PWR  

SciTech Connect

The objective of this project was to develop practical methods of achieving an adequately mixed chemical environment on the secondary side of PWR steam generators during periods of shutdown, cold shutdown (layup), and startup. Layup chemicals introduced into the steam generator could then be evenly dispersed to minimize corrosion processes which may occur if the chemical environment was not properly maintained. Systems for chemical feed, mixing, sampling, and removal of contaminant chemicals in the steam generator secondary side were also evaluated and recommendations have been made. Test results from a plexiglass model indicated that forced circulation and turbulent mixing were the most effective methods of achieving a rapid, homogeneous chemical environment. Natural convection and diffusion, on the other hand, were found to be less effective in achieving a thorough mixing.

MacArthur, A.D.

1983-05-01T23:59:59.000Z

118

Irradiation Test of Advanced PWR Fuel in Fuel Test Loop at HANARO  

SciTech Connect

A new fuel test loop has been constructed in the research reactor HANARO at KAERI. The main objective of the FTL (Fuel Test Loop) is an irradiation test of a newly developed LWR fuel under PWR or Candu simulated conditions. The first test rod will be loaded within 2007 and its irradiation test will be continued until a rod average their of 62 MWd/kgU. A total of five test rods can be loaded into the IPS (In-Pile Section) and fuel centerline temperature, rod internal pressure and fuel stack elongation can be measured by an on-line real time system. A newly developed advanced PWR fuel which consists of a HANA{sup TM} alloy cladding and a large grain UO{sub 2} pellet was selected as the first test fuel in the FTL. The fuel cladding, the HANA{sup TM} alloy, is an Nb containing Zirconium alloy that has shown better corrosion and creep resistance properties than the current Zircaloy-4 cladding. A total of six types of HANA{sup TM} alloy were developed and two or three of these candidate alloys will be used as test rod cladding, which have shown a superior performance to the others. A large-grain UO{sub 2} pellet has a 14{approx}16 micron 2D diameter grain size for a reduction of a fission gas release at a high burnup. In this paper, characteristics of the FTL and IPS are introduced and the expected operation and irradiation conditions are summarized for the test periods. Also the preliminary fuel performance analysis results, such as the cladding oxide thickness, fission gas release and rod internal pressure, are evaluated from the test rod safety analysis aspects. (authors)

Yang, Yong Sik; Bang, Je Geon; Kim, Sun Ki; Song, Kun Woo [LWR Fuel Development Division, Korea Atomic Energy Research Institute, 1045, Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of); Park, Su Ki [HANARO Utilization Technology Development Division, Korea Atomic Energy Research Institute, 1045, Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of); Seo, Chul Gyo [HANARO Management Division, Korea Atomic Energy Research Institute, 1045, Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2007-07-01T23:59:59.000Z

119

Impact of radiation embrittlement on integrity of pressure vessel supports for two PWR (pressurized-water-reactor) plants  

SciTech Connect

Recent pressure-vessel surveillance data from the High Flux Isotope Reactor (HFIR) indicate an embrittlement fluence-rate effect that is applicable to the evaluation of the integrity of light-water reactor (LWR) pressure vessel supports. A preliminary evaluation using the HFIR data indicated increases in the nil ductility transition temperature at 32 effective full-power years (EFPY) of 100 to 130/degree/C for pressurized-water-reactor (PWR) vessel supports located in the cavity at midheight of the core. This result indicated a potential problem with regard to life expectancy. However, an accurate assessment required a detailed, specific-plant, fracture-mechanics analysis. After a survey and cursory evaluation of all LWR plants, two PWR plants that appeared to have a potential problem were selected. Results of the analyses indicate minimum critical flaw sizes small enough to be of concern before 32 EFPY. 24 refs., 16 figs., 7 tabs.

Cheverton, R.D.; Pennell, W.E.; Robinson, G.C.; Nanstad, R.K.

1988-01-01T23:59:59.000Z

120

Subchannel Thermal-Hydraulic Experimental Program (STEP). Volume 1. Mixing in a pressurized water reactor (PWR) rod bundle. Final report  

SciTech Connect

This volume describes an experiment that was performed to determine the mixing characteristics of a pressurized water reactor (PWR) rod bundle. The objective of this project was to improve the subchannel computer code models of the reactor core. The experimental technique was isokinetic subchannel withdrawal of the entire flow from two sample subchannels. Once withdrawn, the sample fluid was condensed and its enthalpy was measured by regenerative heat exchange calorimetry. The test bundle was a 4 x 6 electrically heated array with a 50% power upset. The COBRA IIIC code was used to model the experiment and to determine the value of the thermal mixing coefficient, ..beta.., that was necessary to predict the measured results. Both single- and two-phase data were obtained over a range of PWR operating conditions. The results indicate that both single- and two-phase mixing is small. The COBRA model predicts the enthalpy data using a turbulent mixing coefficient, ..beta.. approx. = 0.002.

Barber, A.R.; Zielke, L.A.

1980-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Impact of an apparent radiation embrittlement rate on the life expectancy of PWR (pressurized-water-reactor) vessel supports  

SciTech Connect

Recent data from the HFIR vessel surveillance program indicate a substantial radiation embrittlement rate effect at low irradiation temperatures (/approximately/120/degree/F) for A212-B, A350-LF3, A105-II and corresponding welds. PWR vessel supports are fabricated of similar materials and are subjected to the same low temperatures and fast neutron fluxes (10/sup 8/ /minus/ 10/sup 9/ n/cm/sup 2//center dot/s, E > 1.0 MeV) as those in the HFIR vessel. Thus, the embrittlement rate of these structures may be greater than previously anticipated. A study sponsored by the NRC is under way at ORNL to determine the impact of the rate effect on PWR vessel support life expectancy. The scope includes the interpretation and application of the HFIR data, a survey of all LWR vessel support designs, and a structural and fracture-mechanics analysis of the supports for two specific PWR plants of particular interest with regard to a potential for support failure as a result of propagation of flaws. Calculations performed for one of the plants indicate best-estimate critical flaw size corresponding to 32 EFPY, of /approximately/0.4 in. It appears that low-cycle fatigue is not a viable mechanism for creation of flaws of this size. Thus, presumably such flaws would have to exist at the time of fabrication. 19 refs., 8 figs., 3 tabs.

Cheverton, R.D.; Pennell, W.E.; Robinson, G.C.; Nanstad, R.K.

1989-01-01T23:59:59.000Z

122

Development and Application of Laser Peening System for PWR Power Plants  

SciTech Connect

Laser peening is a process to improve residual stress from tensile to compressive in surface layer of materials by irradiating high-power laser pulses on the material in water. Toshiba has developed a laser peening system composed of Q-switched Nd:YAG laser oscillators, laser delivery equipment and underwater remote handling equipment. We have applied the system for Japanese operating BWR power plants as a preventive maintenance measure for stress corrosion cracking (SCC) on reactor internals like core shrouds or control rod drive (CRD) penetrations since 1999. As for PWRs, alloy 600 or 182 can be susceptible to primary water stress corrosion cracking (PWSCC), and some cracks or leakages caused by the PWSCC have been discovered on penetrations of reactor vessel heads (RVHs), reactor bottom-mounted instrumentation (BMI) nozzles, and others. Taking measures to meet the unconformity of the RVH penetrations, RVHs themselves have been replaced in many PWRs. On the other hand, it's too time-consuming and expensive to replace BMI nozzles, therefore, any other convenient and less expensive measures are required instead of the replacement. In Toshiba, we carried out various tests for laser-peened nickel base alloys and confirmed the effectiveness of laser peening as a preventive maintenance measure for PWSCC. We have developed a laser peening system for PWRs as well after the one for BWRs, and applied it for BMI nozzles, core deluge line nozzles and primary water inlet nozzles of Ikata Unit 1 and 2 of Shikoku Electric Power Company since 2004, which are Japanese operating PWR power plants. In this system, laser oscillators and control devices were packed into two containers placed on the operating floor inside the reactor containment vessel. Laser pulses were delivered through twin optical fibers and irradiated on two portions in parallel to reduce operation time. For BMI nozzles, we developed a tiny irradiation head for small tubes and we peened the inner surface around J-groove welds after laser ultrasonic testing (LUT) as the remote inspection, and we peened the outer surface and the weld for Ikata Unit 2 supplementary. For core deluge line nozzles and primary water inlet nozzles, we peened the inner surface of the dissimilar metal welding, which is of nickel base alloy, joining a safe end and a low alloy metal nozzle. In this paper, the development and the actual application of the laser peening system for PWR power plants will be described. (authors)

Masaki Yoda; Itaru Chida; Satoshi Okada; Makoto Ochiai; Yuji Sano; Naruhiko Mukai; Gaku Komotori; Ryoichi Saeki [Toshiba Corporation (Japan); Toshimitsu Takagi; Masanori Sugihara; Hirokata Yoriki [Shikoku Electric Co., Inc. (Japan)

2006-07-01T23:59:59.000Z

123

Griffiss Air Force Base integrated resource assessment. Volume 3, Electric resource assessment  

SciTech Connect

The US Air Force Air Combat Command (ACC) has tasked the US Department of Energy (DOE) Federal Energy Management Program (FEMP) to identify, evaluate, and assist in acquiring all cost-effective energy projects at Griffiss Air Force Base (AFB). FEMP, with support from the Pacific Northwest Laboratory (PNL), is designing this model program for federal customers served by the Niagara Mohawk Power Company. The program with Griffiss AFB will (1) identify and evaluate all cost-effective electric energy projects; (2) develop a schedule for project acquisition considering project type, size, timing, capital requirements, as well as energy and dollar savings; and (3) secure 100% of the financing required to implement electric energy efficiency projects from Niagara Mohawk and have them procure the necessary contractors to perform detailed audits and install the technologies. This report provides the results of the electric energy resource opportunity (ERO) assessments performed by PNL at one of Niagara Mohawk`s primary federal facilities, the ACC Griffiss AFB facility located near Rome, New York. The results of the analyses of EROs are presented in seven common energy end-use categories. A narrative description of each ERO provides information on the initial cost, energy and dollar savings; impacts on operations and maintenance (O&M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. The evaluation methodology and technical and cost assumptions are also described for each ERO. Summary tables present the operational performance of energy end-use equipment before and after the implementation of each ERO and the results of the life-cycle cost analysis indicating the net present value (NPV) and savings-to-investment ratio (SIR) of each ERO.

Armstrong, P.R.; Shankle, S.A.; Elliott, D.B.; Stucky, D.J.; Keller, J.M.; Wahlstrom, R.R.; Dagle, J.E.; Gu, A.Y.

1993-09-01T23:59:59.000Z

124

Assessment of molten debris freezing in a severe RIA in-pile test. [PWR; BWR  

SciTech Connect

An understanding of the freezing of molten debris on cold core structures following a hypothetical core meltdown accident in a light water reactor (LWR) is of importance to reactor safety analysis. The purpose of the present investigation was to analyze the transient freezing of the molten debris produced in a severe reactivity initiated accident (RIA) scoping test, designated RIA-ST-4, which was performed in the Power Burst Facility and simulated a BWR control rod drop accident. In the RIA-ST-4 experiment, a single, unirradiated, 20 wt % enriched, UO/sub 2/ fuel rod contained within a Zircaloy flow shroud was subjected to a single power burst which deposited a total energy of about 700 cal/g UO/sub 2/. This energy deposition is well above what is possible in a commercial LWR during a hypothetical control rod drop (BWR) or ejection (PWR) accident. However, the performance of such an in-pile test has provided important information regarding molten debris movement, relocation, and freezing on cold walls.

El-Genk, M.S.; Moore, R.L.

1980-01-01T23:59:59.000Z

125

Numerical simulation of a blanket cooling system for fusion reactor based on PWR conditions  

Science Journals Connector (OSTI)

The simulations of a blanket cooling system were presented to address the choice of cooling channel geometry and coolant input data which are related to blanket engineering implementation. This work was performed using computer aided design (CAD) and computational fluid dynamics (CFD) technology. Simulations were carried out for the blanket module with a size of 0.6mנ0.45m in toroidal plane, and the nuclear heat was applied on the cooling system at Pn (neutron wall load) of 5MW/m2. The structure factors and input data of hydraulics were investigated to explore the optimal parameters to match the PWR condition. It was found that the inlet velocity of first wall (FW) channel should be within the range of 2.483.34m/s. As a result, the temperature rise (TR) of the coolant in the FW channel would be 2425K. This leads to the remaining space for TR within the range of 15K in the piping circuits. It also indicated that the FW plays an important role in TR (reaches 60% of the whole cooling system) due to its high level of Pn and heat flux in the zones. It was predicted that the nuclear heat inside blanket module could be removed completely by the piping circuits with an acceptable pipe bore and the related input data. Finally, a possible design range of cooling parameters was proposed in view of engineering feasibility and blanket neutronics design.

Changle Liu; Jianzhong Zhang; Yinfeng Zhu; Songlin Liu; Xuebin Ma; Peiming Chen

2013-01-01T23:59:59.000Z

126

Severe accident modeling of a PWR core with different cladding materials  

SciTech Connect

The MAAP v.4 software has been used to model two severe accident scenarios in nuclear power reactors with three different materials as fuel cladding. The TMI-2 severe accident was modeled with Zircaloy-2 and SiC as clad material and a SBO accident in a Zion-like, 4-loop, Westinghouse PWR was modeled with Zircaloy-2, SiC, and 304 stainless steel as clad material. TMI-2 modeling results indicate that lower peak core temperatures, less H 2 (g) produced, and a smaller mass of molten material would result if SiC was substituted for Zircaloy-2 as cladding. SBO modeling results indicate that the calculated time to RCS rupture would increase by approximately 20 minutes if SiC was substituted for Zircaloy-2. Additionally, when an extended SBO accident (RCS creep rupture failure disabled) was modeled, significantly lower peak core temperatures, less H 2 (g) produced, and a smaller mass of molten material would be generated by substituting SiC for Zircaloy-2 or stainless steel cladding. Because the rate of SiC oxidation reaction with elevated temperature H{sub 2}O (g) was set to 0 for this work, these results should be considered preliminary. However, the benefits of SiC as a more accident tolerant clad material have been shown and additional investigation of SiC as an LWR core material are warranted, specifically investigations of the oxidation kinetics of SiC in H{sub 2}O (g) over the range of temperatures and pressures relevant to severe accidents in LWR 's. (authors)

Johnson, S. C. [Westinghouse Electric Company LLC, 5801 Bluff Road, Columbia, SC 29209 (United States); Henry, R. E.; Paik, C. Y. [Fauske and Associates, Inc., 16W070 83rd Street, Burr Ridge, IL 60527 (United States)

2012-07-01T23:59:59.000Z

127

A safety and regulatory assessment of generic BWR and PWR permanently shutdown nuclear power plants  

SciTech Connect

The long-term availability of less expensive power and the increasing plant modification and maintenance costs have caused some utilities to re-examine the economics of nuclear power. As a result, several utilities have opted to permanently shutdown their plants. Each licensee of these permanently shutdown (PSD) plants has submitted plant-specific exemption requests for those regulations that they believe are no longer applicable to their facility. This report presents a regulatory assessment for generic BWR and PWR plants that have permanently ceased operation in support of NRC rulemaking activities in this area. After the reactor vessel is defueled, the traditional accident sequences that dominate the operating plant risk are no longer applicable. The remaining source of public risk is associated with the accidents that involve the spent fuel. Previous studies have indicated that complete spent fuel pool drainage is an accident of potential concern. Certain combinations of spent fuel storage configurations and decay times, could cause freshly discharged fuel assemblies to self heat to a temperature where the self sustained oxidation of the zircaloy fuel cladding may cause cladding failure. This study has defined four spent fuel configurations which encompass all of the anticipated spent fuel characteristics and storage modes following permanent shutdown. A representative accident sequence was chosen for each configuration. Consequence analyses were performed using these sequences to estimate onsite and boundary doses, population doses and economic costs. A list of candidate regulations was identified from a screening of 10 CFR Parts 0 to 199. The continued applicability of each regulation was assessed within the context of each spent fuel storage configuration and the results of the consequence analyses.

Travis, R.J.; Davis, R.E.; Grove, E.J.; Azarm, M.A. [Brookhaven National Lab., Upton, NY (United States)

1997-08-01T23:59:59.000Z

128

Design, Feasibility, and Testing of Instrumented Rod Bundles to Improve Heat Transfer Knowledge in PWR Fuel Assemblies  

SciTech Connect

Two 5 x 5 test rod bundles mimicking the PWR fuel assembly have been adapted into two suitable test loop facilities, respectively, to carry out sufficiently detailed hydraulic and thermal measurements in identical geometric configuration. The objective is to investigate heat transfer phenomena in single-phase as well as with onset of nucleate boiling (ONB). The accuracy and reproducibility of the temperature measurements using the sliding-traversing thermocouple device under typical PWR conditions has been demonstrated in the thermal test facility. In the hydraulic loop, a Laser Doppler Velocimetry (LDV) system to precisely scan the local axial velocity component in each sub-channel has been implemented. The approach is to utilize mean sub-channel axial velocity distributions and pressure drop data from the hydraulic loop and the global boundary conditions (Pressure, Temperature, flow rate) from the thermal loop to simulate sub-channels in appropriate T/H codes. This permits computation of sub-channel averaged fluid temperatures (as well as mass velocity) in various subchannels within the test bundle. Subsequently, in conjunction with the wall temperatures and applied heat flux values from the thermal loop, it is possible to develop a complete map of heat transfer coefficients along the 9 instrumented central heater rods. Locations downstream of spacer grids would be of special interest. Depending on pressure, mass velocity and heat flux conditions of a given test, the inlet temperature will be a parameter to be varied so that the ONB boundary can be observed within the bundle. Detailed designs of the test section, required loop modifications, and adaptation of specialized instrumentation and data acquisition systems have been accomplished in both test loops. Further we have established that based on such detailed rod surface temperature and sub-channel axial velocity measurements, it is possible to achieve sufficient accuracy in the temperature measurements to meet the objective of improving the heat transfer correlations applicable to PWR cores. (authors)

Bergeron, A. [CEA, Saclay (France); Chataing, T.; Garnier, J. [CEA, Genoble (France); Decossin, E.; Peturaud, P. [EDF/R and D, Chatou (France); Yagnik, S.K. [Electric Power Research Institute - EPRI (United States)

2007-07-01T23:59:59.000Z

129

Investigation of the behaviour of high burn-up PWR fuel under RIA conditions in the CABRI test reactor  

SciTech Connect

Performance, reliability and economics are the goal criteria for fuel pin design and development. For steady state behaviour and operational transients, the demonstration is made worldwide that burn-up of more than 60 GWd/t can be reached reliably with improved PWR fuel. It has however not been demonstrated yet that safety criteria, related to design basis accident scenarios, are still respected at these high burn-up levels. In particular, for the reactivity initiated accident (RIA), resulting from a postulated, rapid removal of control rod elements, the amount of energy injection must be limited by design such that no severe damage to the core and its structures might occur.

Schmitz, F.; Papin, J.; Haessler, M.; Nervi, J.C. [Institut de Protection et de Surete Nucleaire (France); Permezel, P. [Electricite de France, Septen (France)

1994-10-01T23:59:59.000Z

130

Analysis of a Defected Dissimilar Metal Weld in a PWR Power Plant  

SciTech Connect

During the refueling outage 2000, inspections of the RC-loops of one of the Ringhals PWR-units, Ringhals 4, indicated surface breaking defects in the axial direction of the piping in a dissimilar weld between the Low alloy steel nozzle and the stainless safe end in the hot leg. In addition some indications were found that there were embedded defects in the weld material. These defects were judged as being insignificant to the structural integrity. The welds were inspected in 1993 with the result that no significant indications were found. The weld it self is a double U weld, where the thickness of the material is ideally 79,5 mm. Its is constructed by Inconel 182 weld material. At the nozzle a buttering was applied, also by Inconel 182. The In-service inspection, ISI, of the object indicated four axial defects, 9-16 mm deep. During fabrication, the areas where the defects are found were repaired at least three times, onto a maximum depth of 32 mm. To evaluate the defects, 6 boat samples from the four axial defects were cut from the perimeter and shipped to the hot-cell laboratory for further examination. This examination revealed that the two deep defects had been under sized by the ISI outside the requirement set by the inspection tolerances, while the two shallow defects were over sized, but within the tolerances of the detection system. When studying the safety case it became evident that there were several missing elements in the way this problems is handled with respect to the Swedish safety evaluation code. Among these the most notable at the beginning was the absence of reliable fracture mechanical data such as crack growth laws and fracture toughness at elevated temperature. Both these questions were handled by the project. The fracture mechanical evaluation has focused on a fit for service principal. Thus defects both in the unaffected zones and the disturbed zones, boat sample cutouts, of the weld have been analyzed. With reference to the Swedish safety evaluation system in accordance to the regulatory demands, a safety evaluation was performed using the R6-method. The failure assessment diagram is modified by the addition of the ASME XI safety factors both for limit load analysis and fracture assessment. This results in a very high conservatism since the secondary stresses such as residual stresses are high in the area. In order to quantify this effect an analysis in accordance to ASME IWB-3640, App. C was performed. This analysis provides the decision-makers with a sensitivity study; important to have to value the real risk of any missed defects in the area. (authors)

Efsing, P. [Barseback Kraft AB, P.O. Box 524, Loddekopinge SE-246 25 (Sweden); Lagerstrom, J. [Vattenfall AB, Ringhals, 430 22 Vaeroebacka (Sweden)

2002-07-01T23:59:59.000Z

131

TOPICAL REPORT ON ACTINIDE-ONLY BURNUP CREDIT FOR PWR SPENT NUCLEAR FUEL PACKAGES  

SciTech Connect

A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay. A set of chemical assay benchmarks is presented for this purpose as well as a method for assessing the calculational bias and uncertainty, and conservative correction factors for each isotope. (2) Validate a computer code system to predict the subcritical multiplication factor, k{sub eff}, of a spent nuclear fuel package. Fifty-seven UO{sub 2}, UO{sub 2}/Gd{sub 2}O{sub 3}, and UO{sub 2}/PuO{sub 2} critical experiments have been selected to cover anticipated conditions of SNF. The method uses an upper safety limit on k{sub eff} (which can be a function of the trending parameters) such that the biased k{sub eff}, when increased for the uncertainty is less than 0.95. (3) Establish bounding conditions for the isotopic concentration and criticality calculations. Three bounding axial profiles have been established to assure the ''end effect'' is accounted for conservatively. (4) Use the validated codes and bounding conditions to generate package loading criteria (burnup credit loading curves). Burnup credit loading curves show the minimum burnup required for a given initial enrichment. The utility burnup record is compared to this requirement after the utility accounts for the uncertainty in its record. Separate curves may be generated for each assembly design, various minimum cooling times and burnable absorber histories. (5) Verify that SNF assemblies meet the package loading criteria and confirm proper assembly selection prior to loading. A measurement of the average assembly burnup is required and that measurement must be within 10% of the utility burnup record for the assembly to be accepted. The measurement device must be accurate to within 10%. Each step is described in detail for use with any computer code system and is then demonstrated with the SCALE 4.2 computer code package using 27BURNUPLIB cross sections.

DOE

1997-04-01T23:59:59.000Z

132

Development of a Safeguards Verification Method and Instrument to Detect Pin Diversion from Pressurized Water Reactor (PWR) Spent Fuel Assemblies  

SciTech Connect

A technical safeguards challenge has remained for decades for the IAEA to identify possible diversion of nuclear fuel pins from Light Water Reactor (LWR) spent fuel assemblies. In fact, as modern nuclear power plants are pushed to higher power levels and longer fuel cycles, fuel failures (i.e., ''leakers'') as well as the corresponding fuel assembly repairs (i.e., ''reconstitutions'') are commonplace occurrences within the industry. Fuel vendors have performed hundreds of reconstitutions in the past two decades, thus, an evolved know-how and sophisticated tools exist to disassemble irradiated fuel assemblies and replace damaged pins with dummy stainless steel or other type rods. Various attempts have been made in the past two decades to develop a technology to identify a possible diversion of pin(s) and to determine whether some pins are missing or replaced with dummy or fresh fuel pins. However, to date, there are no safeguards instruments that can detect a possible pin diversion scenario to the requirements of the IAEA. The FORK detector system [1-2] can characterize spent fuel assemblies using operator declared data, but it is not sensitive enough to detect missing pins from spent fuel assemblies. Likewise, an emission computed tomography system [3] has been used to try to detect missing pins from a spent fuel assembly, which has shown some potential for identifying possible missing pins but this capability has not yet been fully demonstrated. The use of such a device in the future would not be envisaged, especially in an inexpensive, easy to handle setting for field applications. In this article, we describe a concept and ongoing research to help develop a new safeguards instrument for the detection of pin diversions in a PWR spent fuel assembly. The proposed instrument is based on one or more very thin radiation detectors that could be inserted within the guide tubes of a Pressurized Water Reactor (PWR) assembly. Ultimately, this work could lead to the development of a detector cluster and corresponding high-precision driving system to collect radiation signatures inside PWR spent fuel assemblies. The data obtained would provide the spatial distribution of the neutron and gamma flux fields within the spent fuel assembly, while the data analysis would be used to help identify missing or replaced pins. Monte Carlo simulations have been performed to help validate this concept using a realistic 17 x 17 PWR spent fuel assembly [4-5]. The initial results of this study show that neutron profile in the guide tubes, when obtained in the presence of missing pins, can be identifiably different from the profiles obtained without missing pins, Our latest simulations have focused upon a specific type of fission chamber that could be tested for this application.

Ham, Y S; Maldonado, G I; Burdo, J; He, T

2006-10-10T23:59:59.000Z

133

Record of Decision on the Disposal of the S3G and D1G Prototype Reactor Plants  

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

5 5 Federal Register / Vol. 63, No. 18 / Wednesday, January 28, 1998 / Notices owned by Basin Electric Power Cooperative, Bonneville Power Administration, Citizens Utilities, Detroit Edison Company, Eastern Maine Electric Cooperative, Joint Owners of the Highgate Project, Maine Electric Power Company, Maine Public Service Company, Minnesota Power and Light Company, Minnkota Power Cooperative, New York Power Authority, Niagara Mohawk Power Corporation, Northern States Power, and Vermont Electric Transmission Company. Each of these transmission facilities, as more fully described in the application, has previously been authorized by a Presidential permit issued pursuant to Executive Order 10485, as amended. Procedural Matters Any persons desiring to become a party to this proceeding or to be heard

134

HTS Cable Projects  

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

Superconductivity Superconductivity Partnerships with Industry ANL Air Liquide DOE Golden LANL AEP ORNL Nexans Niagara Mohawk Super Power American Superconductor NYSERDA BOC Praxair W ? tion systems. This is the most the nation. W superconductivity? HTS Cable Projects www.oe.energy.gov Phone: 202 \ 586-1411 Office of Electricity Delivery and Energy Reliability, OE-1 U.S. Department of Energy - 1000 Independence Avenue, SW - Washington, DC 20585. Plugging America Into the Future of Power "A National Effort to Introduce New Technology into

135

PWR blowdown heat transfer separate-effects program - Thermal-Hydraulic Test Facility experimental data report for test 177. [Contains microfiche data  

SciTech Connect

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 177, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. Objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 177 was conducted at the request of Idaho National Engineering Laboratory ''for use in the independent assessment of RELAP4/MOD6.'' Primary purpose of this report is to make the reduced instrument responses during test 177 available. The responses are presented in graphical form in engineering units and have been analyzed only to the extent necessary to assure reasonableness and consistency. The data are presented in microfiche form.

Clemons, V.D.; Flanders, R.M.; Craddick, W.G.

1980-08-01T23:59:59.000Z

136

Evaluation of storing Shippingport Core II spent blanket fuel assemblies in the T Plant PWR Core II fuel pool without active cooling  

SciTech Connect

PWR Core II fuel pool chiller-off test was conducted because it appeared possible that acceptable pool-water temperatures could be maintained without operating the chillers, thus saving hundreds of thousands of dollars in maintenance and replacement costs. Test results showed that the water-cooling capability is no longer needed to maintain pool temperature below 38{degrees}C (100{degrees}F).

Gilbert, E.R.; Lanning, D.D. [Pacific Northwest Lab., Richland, WA (United States); Dana, C.M.; Hedengren, D.C. [Westinghouse Hanford Co., Richland, WA (United States)

1994-10-01T23:59:59.000Z

137

Technical basis for the initiation and cessation of environmentally-assisted cracking of low-alloy steels in elevated temperature PWR environments  

SciTech Connect

The Section 11 Working Group on Flaw Evaluation of the ASME B and PV Code Committee is considering a Code Case to allow the determination of the conditions under which environmentally-assisted cracking of low-alloy steels could occur in PWR primary environments. This paper provides the technical support basis for such an EAC Initiation and Cessation Criterion by reviewing the theoretical and experimental information in support of the proposed Code Case.

James, L.A.

1997-10-01T23:59:59.000Z

138

An assessment of the core degradation frequency in a typical large LMFBR design for internal accident initiators-a comparison with PWR predictions  

SciTech Connect

A comparative assessment of the core degradation frequency due to internal accident initiators between a typical large liquid-metal fast breeder reactor (LMFBR) design and pressurized water reactors (PWRs) has been performed. For the PWR system, existing analyses have been utilized. For the reference LMFBR, an extensive analysis has been performed for two accident initiators, i.e., loss of off-site power and loss of main feedwater. Based on this analysis an estimate of about1 X 10/sup -6//reactor X yr has been obtained for the core degradation frequency of the reference LMFBR. This estimate is significantly smaller than the PWR core degradation frequency ( about 6 X 10/sup -5//yr). A sensitivity analysis shows that the parameters having the largest impact on the unavailability of decay heat removal are (a) for the ''loss of off-site power'' initiator: human error and failure to restore off-site power, and (b) for the ''loss of main feedwater'' initiator: the leakage rates of the passive decay heat removal system and the adoption of the policy to repair the Na-NaK heat exchanger only during normal shutdowns. The results indicate that the LMFBR system has the potential of higher resistance than the PWR system to the accident initiators considered. The lower core degradation frequency estimated for the LMFBR system is due to the presence of two redundant and diverse reactor shutdown systems, with a self-actuated feature included in one of them, the incorporation of a passive decay heat removal system, and the significantly lower sensitivity of the reference LMFBR to primary system pipe breaks.

Tzanos, C.P.; Adamantiades, A.G.; Hanan, N.A.

1983-12-01T23:59:59.000Z

139

PWR FLECHT SEASET 163-Rod Bundle Flow Blockage Task data report. NRC/EPRI/Westinghouse report No. 13, August-October 1982  

SciTech Connect

This report presents data from the 163-Rod Bundle Blow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Systems Effects and Separate Effects Test Program (FLECHT SEASET). The task consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. These tests were designed to determine effects of flow blockage and flow bypass on reflooding behavior and to aid in the assessment of computational models in predicting the reflooding behavior of flow blockage in rod bundle arrays.

Loftus, M J; Hochreiter, L E; McGuire, M F; Valkovic, M M

1983-10-01T23:59:59.000Z

140

Fuel cycle cost, reactor physics and fuel manufacturing considerations for Erbia-bearing PWR fuel with > 5 wt% U-235 content  

SciTech Connect

The efforts to reduce fuel cycle cost have driven LWR fuel close to the licensed limit in fuel fissile content, 5.0 wt% U-235 enrichment, and the acceptable duty on current Zr-based cladding. An increase in the fuel enrichment beyond the 5 wt% limit, while certainly possible, entails costly investment in infrastructure and licensing. As a possible way to offset some of these costs, the addition of small amounts of Erbia to the UO{sub 2} powder with >5 wt% U-235 has been proposed, so that its initial reactivity is reduced to that of licensed fuel and most modifications to the existing facilities and equipment could be avoided. This paper discusses the potentialities of such a fuel on the US market from a vendor's perspective. An analysis of the in-core behavior and fuel cycle performance of a typical 4-loop PWR with 18 and 24-month operating cycles has been conducted, with the aim of quantifying the potential economic advantage and other operational benefits of this concept. Subsequently, the implications on fuel manufacturing and storage are discussed. While this concept has certainly good potential, a compelling case for its short-term introduction as PWR fuel for the US market could not be determined. (authors)

Franceschini, F.; Lahoda, E. J.; Kucukboyaci, V. N. [Westinghouse Electric Co. LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2012-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Niagara Falls, New York: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

0944999°, -79.0567111° 0944999°, -79.0567111° 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":43.0944999,"lon":-79.0567111,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

142

Niagara County, New York: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

3119496°, -78.7476208° 3119496°, -78.7476208° 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":43.3119496,"lon":-78.7476208,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

143

GROUND LEVEL INVESTIGATION OF ANOMALOUS RADIATION LEVELS IN NIAGARA...  

Office of Legacy Management (LM)

Oak Ridge, Tennessee 37630 O&J. 2,7 +, 7&y' March 1979 operated by UNION CARBIDE CORPORATIOII for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-...

144

MHK Projects/Niagara Community | Open Energy Information  

Open Energy Info (EERE)

Community Community < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":5,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"350px","centre":false,"title":"","label":"","icon":"File:Aquamarine-marker.png","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":43.0643,"lon":-79.0278,"alt":0,"address":"","icon":"http:\/\/prod-http-80-800498448.us-east-1.elb.amazonaws.com\/w\/images\/7\/74\/Aquamarine-marker.png","group":"","inlineLabel":"","visitedicon":""}]}

145

RETRAN-02: a program for transient thermal-hydraulic analysis of complex fluid flow systems. Volume 1. Theory and numerics (Revision 2). [PWR; BWR  

SciTech Connect

RETRAN-02 represents a significant achievement in the development of a versatile and reliable computer program for use in best-estimate transient thermal-hydraulic analysis of LWR systems. The RETRAN-02 computer program is an extension of the RETRAN-01 program designed to provide analysis capabilities for: (1) BWR and PWR transients; (2) small-break loss-of-coolant accidents; (3) balance of plant modeling; and (4) anticipated transients without scram, while maintaining the analysis capabilities of the predecessor code. This report (the first of a four-volume computer code manual) describes the theory and numerical algorithms of the RETRAN-02 code. The three companion volumes describe the programming aspects, the programming details, and the verification and qualification performed with RETRAN.

McFadden, J.H.; Narum, R.E.; Peterson, C.E.; Noble, C.; Farman, R.F.; McClure, J.A.; Paulsen, M.P.; Richert, K.D.; Hughes, E.D.; Gose, G.C.

1984-11-01T23:59:59.000Z

146

PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report. NRC/EPRI/Westinghouse Report No. 11. Appendices K-P  

SciTech Connect

This report presents data and limited analysis from the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). The tests consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. Steam cooling and hydraulic characteristics tests were also conducted. These tests were utilized to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 163-rod flow blockage bundle tests.

Loftus, M.J.; Hochreiter, L.E.; Lee, N.; McGuire, M.F.; Wenzel, A.H.; Valkovic, M.M.

1982-09-01T23:59:59.000Z

147

Crack growth rates and metallographic examinations of Alloy 600 and Alloy 82/182 from field components and laboratory materials tested in PWR environments.  

SciTech Connect

In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C. These data were used to determine the activation energy for crack growth in Alloy 182 welds. The tests were performed by measuring the changes in the stress corrosion CGR as the temperatures were varied during the test. The difference in electrochemical potential between the specimen and the Ni/NiO line was maintained constant at each temperature by adjusting the hydrogen overpressure on the water supply tank. The CGR data as a function of temperature yielded activation energies of 252 kJ/mol for a double-J weld and 189 kJ/mol for a deep-groove weld. These values are in good agreement with the data reported in the literature. The data reported here and those in the literature suggest that the average activation energy for Alloy 182 welds is on the order of 220-230 kJ/mol, higher than the 130 kJ/mol commonly used for Alloy 600. The consequences of using a larger value of activation energy for SCC CGR data analysis are discussed.

Alexandreanu, B.; Chopra, O. K.; Shack, W. J.

2008-05-05T23:59:59.000Z

148

ORNL rod-bundle heat-transfer test data. Volume 3. Thermal-hydraulic test facility experimental data report for test 3. 06. 6B - transient film boiling in upflow. [PWR  

SciTech Connect

Reduced instrument responses are presented for Thermal-Hyraulic Test Facility (THTF) Test 3.06.6B. This test was conducted by members of the Oak Ridge National Laboratory Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer (BDHT) Separate-Effects Program on August 29, 1980. The objective of the program was to investigate heat transfer phenomena believed to occur in PWR's during accidents, including small and large break loss-of-coolant accidents. Test 3.06.6B was conducted to obtain transient film boiling data in rod bundle geometry under reactor accident-type conditions. The primary purpose of this report is to make the reduced instrument responses for THTF Test 3.06.6B available. Included in the report are uncertainties in the instrument responses, calculated mass flows, and calculated rod powers.

Mullins, C.B.; Felde, D.K.; Sutton, A.G.; Gould, S.S.; Morris, D.G.; Robinson, J.J.

1982-05-01T23:59:59.000Z

149

The French codes RCC-M and RSE-M -- Design, construction and in-service inspection rules for the mechanical components of PWR nuclear islands: An overview and a comparison to the ASME codes  

SciTech Connect

The RCC-M, ``Regles de Conception et de Construction des Materiels Mecaniques des Ilots Nucleaires REP`` or, in English, ``Design and Construction Rules for the Mechanical Components of PWR Nuclear Islands`` and the RSE-M, ``Regles de Surveillance en Exploitation des Materiels Mecaniques des Ilots Nucleaires REP`` or, in English, ``In-Service Inspection Rules for the Mechanical Components of PWR Nuclear Islands`` gather all design, construction and operating practices relating to the mechanical components of French PWR nuclear islands. This paper is a presentation of these two codes. Throughout this presentation the specific aspects of the French approach will be underlined and will be compared to that of the ASME codes--mainly Section 3 and Section 11. The broad general technical scopes of the French codes are similar to those of the ASME codes. However, in some important areas of design, material specifications, procurement and manufacturing, the provisions of the RCC-M and RSE-M deviate from those of a strict mechanical Code and are more self-sustaining than those of ASME.

Journet, J.; Masson, S.H.; Morel, A.; Remond, A.; Grandemange, J.M.

1995-12-01T23:59:59.000Z

150

Application of MELCOR Code to a French PWR 900 MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results  

SciTech Connect

In the ambit of the Severe Accident Network of Excellence Project (SARNET), funded by the European Union, 6. FISA (Fission Safety) Programme, one of the main tasks is the development and validation of the European Accident Source Term Evaluation Code (ASTEC Code). One of the reference codes used to compare ASTEC results, coming from experimental and Reactor Plant applications, is MELCOR. ENEA is a SARNET member and also an ASTEC and MELCOR user. During the first 18 months of this project, we performed a series of MELCOR and ASTEC calculations referring to a French PWR 900 MWe and to the accident sequence of 'Loss of Steam Generator (SG) Feedwater' (known as H2 sequence in the French classification). H2 is an accident sequence substantially equivalent to a Station Blackout scenario, like a TMLB accident, with the only difference that in H2 sequence the scram is forced to occur with a delay of 28 seconds. The main events during the accident sequence are a loss of normal and auxiliary SG feedwater (0 s), followed by a scram when the water level in SG is equal or less than 0.7 m (after 28 seconds). There is also a main coolant pumps trip when {delta}Tsat < 10 deg. C, a total opening of the three relief valves when Tric (core maximal outlet temperature) is above 603 K (330 deg. C) and accumulators isolation when primary pressure goes below 1.5 MPa (15 bar). Among many other points, it is worth noting that this was the first time that a MELCOR 1.8.5 input deck was available for a French PWR 900. The main ENEA effort in this period was devoted to prepare the MELCOR input deck using the code version v.1.8.5 (build QZ Oct 2000 with the latest patch 185003 Oct 2001). The input deck, completely new, was prepared taking into account structure, data and same conditions as those found inside ASTEC input decks. The main goal of the work presented in this paper is to put in evidence where and when MELCOR provides good enough results and why, in some cases mainly referring to its specific models (candling, corium pool behaviour, etc.) they were less good. A future work will be the preparation of an input deck for the new MELCOR 1.8.6. and to perform a code-to-code comparison with ASTEC v1.2 rev. 1. (author)

De Rosa, Felice [ENEA, Italian National Agency for New Technologies, Energy and the Environment (Italy)

2006-07-01T23:59:59.000Z

151

Experimental Investigation on the Effects of Coolant Concentration on Sub-Cooled Boiling and Crud Deposition on Reactor Cladding at Prototypical PWR Operating Conditions  

SciTech Connect

Increasing demand for energy necessitates nuclear power units to increase power limits. This implies significant changes in the design of the core of the nuclear power units, therefore providing better performance and safety in operations. A major hindrance to the increase of nuclear reactor performance especially in Pressurized Deionized water Reactors (PWR) is Axial Offset Anomaly (AOA)--the unexpected change in the core axial power distribution during operation from the predicted distribution. This problem is thought to be occur because of precipitation and deposition of lithiated compounds like boric acid (H{sub 2}BO{sub 3}) and lithium metaborate (LiBO{sub 2}) on the fuel rod cladding. Deposited boron absorbs neutrons thereby affecting the total power distribution inside the reactor. AOA is thought to occur when there is sufficient build-up of crud deposits on the cladding during subcooled nucleate boiling. Predicting AOA is difficult as there is very little information regarding the heat and mass transfer during subcooled nucleate boiling. An experimental investigation was conducted to study the heat transfer characteristics during subcooled nucleate boiling at prototypical PWR conditions. Pool boiling tests were conducted with varying concentrations of lithium metaborate (LiBO{sub 2}) and boric acid (H{sub 2}BO{sub 3}) solutions in deionized water. The experimental data collected includes the effect of coolant concentration, subcooling, system pressure and heat flux on pool the boiling heat transfer coefficient. The analysis of particulate deposits formed on the fuel cladding surface during subcooled nucleate boiling was also performed. The results indicate that the pool boiling heat transfer coefficient degrades in the presence of boric acid and lithium metaborate compared to pure deionized water due to lesser nucleation. The pool boiling heat transfer coefficients decreased by about 24% for 5000 ppm concentrated boric acid solution and by 27% for 5000 ppm lithium metaborate solution respectively at the saturation temperature for 1000 psi (68.9 bar) coolant pressure. Boiling tests also revealed the formation of fine deposits of boron and lithium on the cladding surface which degraded the heat transfer rates. The boron and lithium metaborate precipitates after a 5 day test at 5000 ppm concentration and 1000 psi (68.9 bar) operating pressure reduced the heat transfer rate 21% and 30%, respectively for the two solutions.

Schultis, J., Kenneth; Fenton, Donald, L.

2006-10-20T23:59:59.000Z

152

Sliding mode observer design for a PWR to estimate the xenon concentration & delayed neutrons precursor density based on the two point nuclear reactor model  

Science Journals Connector (OSTI)

Abstract One of the important operations in nuclear power plants is load-following in which imbalance of axial power distribution induces xenon oscillations. These oscillations must be maintained within acceptable limits otherwise the nuclear power plant could become unstable. Therefore, bounded xenon oscillation considered to be a constraint for the load-following operation. In other hands, precursors produce delayed neutrons which are most important in control of nuclear reactor, but xenon concentration & precursor density cannot be measured directly. In this paper, non-linear sliding mode observer which has the robust characteristics facing the parameters uncertainties and disturbances is proposed based on the two point nuclear reactor model to estimate the xenon concentration & delayed neutron precursor density of the Pressurized-Water Nuclear Reactor (PWR) using reactor power measurement. The stability analysis is given by means Lyapunov approach, thus the system is guaranteed to be stable within a large range. The employed method is easy to implement in practical applications. This estimation is done taking into account the effects of reactivity feedback due to temperature and xenon concentration. Simulation results clearly show that the sliding mode observer follows the actual system variables accurately and is satisfactory in the presence of the parameters uncertainties & disturbances.

G.R. Ansarifar; M.H. Esteki; M. Arghand

2015-01-01T23:59:59.000Z

153

Estimation of the xenon concentration and delayed neutrons precursors densities in the pressurized-water nuclear reactors (PWR) with sliding mode observer considering xenon oscillations  

Science Journals Connector (OSTI)

Abstract One of the important operations in nuclear power plants is load-following in which the imbalance in axial power distribution induces xenon oscillations. These oscillations must be maintained within acceptable limits otherwise the nuclear power plant could become unstable. Therefore, bounded xenon oscillation is considered to be a constraint for the load-following operation. On the other hands, precursors produce delayed neutrons which are important with respect to reactor period and control, but xenon concentration and precursors densities cannot be measured directly. In this paper, the non-linear sliding mode observer which has the robust characteristics facing the parameters uncertainties and disturbances is proposed based on the two point nuclear reactor model equations with three groups of the delayed neutrons to estimate the xenon concentration and delayed neutrons precursor densities of the pressurized-water nuclear reactor (PWR) using reactor power measurements. The stability analysis is provided by means of the Lyapunov approach, thus the system is guaranteed to be stable over a wide range. The employed method is easy to implement. This estimation is done taking into account the effects of reactivity feedback due to temperature and xenon concentration. Simulation results clearly show that the sliding mode observer follows the actual system variables accurately and is satisfactory in the presence of the parameter uncertainties and disturbances.

M.H. Esteki; G.R. Ansarifar; M. Arghand

2015-01-01T23:59:59.000Z

154

MOTION TO INTERVENE OF THE NEW YORK TRANSMISSION OWNERS PP-230-4 |  

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

MOTION TO INTERVENE OF THE NEW YORK TRANSMISSION OWNERS PP-230-4 MOTION TO INTERVENE OF THE NEW YORK TRANSMISSION OWNERS PP-230-4 MOTION TO INTERVENE OF THE NEW YORK TRANSMISSION OWNERS PP-230-4 Pursuant to Rules 212 and 214 of the Rules of Practice and Procedure, 18 C.F.R. §§ 385.212 and 385.214 (2010), Central Hudson Gas & Electric Corporation, Consolidated Edison Company of New York, Inc., Long Island Power Authority, New York Power Authority, New York State Electric & Gas Corporation, Niagara Mohawk Power Corporation d/b/a National Grid, Orange and Rockland Utilities, Inc., and Rochester Gas and Electric Corporation (referred to herein as the "New York Transmission Owners"), individually and collectively move to intervene in the above-captioned proceeding and request an opportunity to comment on International Transmission Company's d/b/a/ ITCTransmission

155

O:ELECTRICEA-148-A.PDF  

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

8-A 8-A I. BACKGROUND Exports of electricity from the United States to a foreign country are regulated and require authorization under section 202(e) of the Federal Power Act (FPA) (16 U.S.C. §824a(e)). On August 13, 1997, the Office of Fossil Energy (FE) of the Department of Energy (DOE) authorized Aquila Energy Marketing Corporation (AEM) to transmit electric energy from the United States to Canada as a power marketer using the international electric transmission facilities of Basin Electric Power Cooperative, Bonneville Power Administration, Citizens Utilities, Detroit Edison, Eastern Maine Electric Cooperative, Joint Owners of the Highgate Project, Maine Electric Power Company, Maine Public Service Company, Minnesota Power, Inc., Minnkota Power, New York Power Authority, Niagara Mohawk Power Corp., Northern States

156

O:ELECTRICORDERSEA-168-B.PDF  

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

8-B 8-B I. BACKGROUND Exports of electricity from the United States to a foreign country are regulated and require authorization under section 202(e) of the Federal Power Act (FPA) (16 U.S.C. §824a(e)). On February 25, 1998, the Office of Fossil Energy (FE) of the Department of Energy (DOE) authorized PG&E Energy Trading-Power, L.P. (PGET-Power) to transmit electric energy as a power marketer from the United States to Canada using the international transmission facilities of Detroit Edison, Minnesota Power, Niagara Mohawk and New York Power Authority. On August 25, 1998, in Order EA-168-A, DOE amended PGET-Power's electricity export authorization to add the remaining major transmission interconnections with Canada. That two- year authorization expired on August 25, 2000. On July 6, 2000, PGET-Power filed an

157

Page not found | Department of Energy  

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

51 - 560 of 31,917 results. 51 - 560 of 31,917 results. Download WA_96_018_NIAGARA_MOHAWK__POWER_CORPORATION_Waiver_of_U.S._a.pdf http://energy.gov/gc/downloads/wa96018niagaramohawkpowercorporationwaiverofusapdf Download WA_00_008_PLUG_POWER_Waiver_of_Patent_Rights_in_Performance_.pdf http://energy.gov/gc/downloads/wa00008plugpowerwaiverofpatentrightsinperformancepdf Download WA_06_015_PPG_INDUSTRIES_Waiver_of_Patent_Rights_Under_a_DOE.pdf http://energy.gov/gc/downloads/wa06015ppgindustrieswaiverofpatentrightsunderadoepdf Download WA_1995_001_US_AUTO_MATERIALS_PARTNERSHIPS_Waiver_of_Patent_.pdf http://energy.gov/gc/downloads/wa1995001usautomaterialspartnershipswaiverofpatentpdf Download WA_00_005_GENERAL_ELECTRIC_Waiver_of_Government_US_and_Forei.pdf http://energy.gov/gc/downloads/wa00005generalelectricwaiverofgovernmentusandforeipdf

158

Wethersfield Wind Power Wind Farm | Open Energy Information  

Open Energy Info (EERE)

Wethersfield Wind Power Wind Farm Wethersfield Wind Power Wind Farm Facility Wethersfield Wind Power Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Enel North America Developer Western NY Wind Power Partners Energy Purchaser Niagara Mohawk Location WY County NY Coordinates 42.667741°, -78.219803° 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":42.667741,"lon":-78.219803,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

159

Review of consolidated Edison`s integrated resource bidding program  

SciTech Connect

Competitive bidding has emerged as the dominant method for procuring new resources by US utilities. In New York, the Public Service Commission (NYPSC) ordered the state`s seven investor-owned utilities to develop bidding programs to acquire supply and DSM resource options. Utilities were allowed significant discretion in program design in order to encourage experimentation. Competitive bidding programs pose formidable policy, design, and management challenges for utilities and their regulators. Yet, there have been few detailed case studies of bidding programs, particularly of those utilities that take on the additional challenge of having supply and DSM resources compete head-to-head for a designated block of capacity. To address that need, the New York State Energy Research and Development Authority (NYSERDA), the New York Department of Public Service, and the Department of Energy`s Integrated Resource Planning program asked Lawrence Berkeley Laboratory (LBL) to review the bidding programs of two utilities that tested the integrated ``all-sources`` approach. This study focuses primarily on Consolidated Edison Company of New York`s (Con Edison) bidding program; an earlier report discusses our review of Niagara Mohawk`s program (Goldman et al 1992). We reviewed relevant Commission decisions, utility filings and signed contracts, interviewed utility and regulatory staff, surveyed DSM bidders and a selected sample of DSM non-bidders, and analyzed the bid evaluation system used in ranking bids based on detailed scoring information on individual bids provided by Con Edison.

Goldman, C.A.; Busch, J.F.; Kahn, E.P.; Baldick, R.; Milne, A.

1993-07-01T23:59:59.000Z

160

TRAC methods and models. [PWR  

SciTech Connect

The numerical methods and physical models used in the Transient Reactor Analysis Code (TRAC) versions PD2 and PF1 are discussed. Particular emphasis is placed on TRAC-PF1, the version specifically designed to analyze small-break loss-of-coolant accidents (LOCAs).

Mahaffy, J.H.; Liles, D.R.; Bott, T.F.

1981-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Death of a carbonate basin: The Niagara-Salina transition in the Michigan basin  

SciTech Connect

The A-O Carbonate in the Michigan basin comprises a sequence of laminated calcite/anhydrite layers intercalated with bedded halite at the transition between normal marine Niagaran carbonates and lower Salina Group evaporites. The carbonate/anhydrite interbeds represent freshing events during initial evaporative concentration of the Michigan basin. Recent drilling in the Michigan basin delineates two distinct regions of A-O Carbonate development: a 5 to 10 m thick sequence of six 'laminites' found throughout most of the western and northern basin and a 10 to 25 m thick sequence in the southeastern basin containing both thicker 'laminates' and thicker salt interbeds. Additionally, potash deposits of the overlying A-1 evaporite unit are restricted to the northern and western basin regions. The distribution of evaporite facies in these two regions is adequately explained by a source of basin recharge in the southeast-perhaps the 'Clinton Inlet' of earlier workers. This situation suggest either that: (1) the source of basin recharge is alternately supplying preconcentrated brine and more normal marine water, or (2) that the basin received at least two distinct sources of water during A-O deposition.

Leibold, A.W.; Howell, P.D. (Univ. of Michigan, Ann Arbor (United States))

1991-03-01T23:59:59.000Z

162

DOE/OR/20722-133 POST-REMEDIAL ACTION REPORT FOR THE NIAGARA...  

Office of Legacy Management (LM)

h e LOOW to store uranium ore processing residues from a ceramics plant operated by Linde Air Products in Tonawanda, New York. By 1948, 6,000 acres of the LOOW had been transferred...

163

PWR cores with silicon carbide cladding  

SciTech Connect

The feasibility of using silicon carbide rather than Zircaloy cladding, to reach higher power levels and higher discharge burnups in PWRs has been evaluated. A preliminary fuel design using fuel rods with the same dimensions as in the Westinghouse Robust Fuel Assembly but with fuel pellets having 10 vol% central void has been adopted to mitigate the higher fuel temperatures that occur due to the lower thermal conductivity of the silicon carbide and to the persistence of the open clad-pellet gap over most of the fuel life. With this modified fuel design, it is possible to achieve 18 month cycles that meet present-day operating constraints on peaking factor, boron concentration, reactivity coefficients and shutdown margin, while allowing batch average discharge burnups up to 80 MWD/kgU and peak rod burnups up to 100 MWD/kgU. Power uprates of 10% and possibly 20% also appear feasible. For non-uprated cores, the silicon carbide-clad fuel has a clear advantage that increases with increasing discharge burnup. Even for comparable discharge burnups, there is a savings in enriched uranium. Control rod configuration modifications may be required to meet the shutdown margin criterion for the 20% up-rate. Silicon carbide's ability to sustain higher burnups than Zircaloy also allows the design of a licensable two year cycle with only 96 fresh assemblies, avoiding the enriched uranium penalty incurred with use of larger batch sizes due to their excessive leakage. (authors)

Dobisesky, J. P.; Carpenter, D.; Pilat, E.; Kazimi, M. S. [Center for Advanced Nuclear Energy Systems, Dept. of Nuclear Science and Engineering, Massachusetts Inst. of Technology, 77 Massachusetts Avenue 24-215, Cambridge, MA 02139-4307 (United States)

2012-07-01T23:59:59.000Z

164

Soft computing systems applied to PWR's xenon  

Science Journals Connector (OSTI)

The present work intends to introduce a soft computing technique as an effective and robust tool available to deal with nuclear engineering problems. This goal is reached by the presentation of an application: a genetic programming system (GP) able to automatically design a controller for the axial xenon oscillations in a pressurized water reactors (PWRs). The axial xenon oscillations control methodology is based on three axial offsets: the xenon axial offset (AOx), the iodine axial offset (AOi) and the neutron flux axial offset (AOf), effectively used in former work. Simulations were made using a two-point xenon oscillation model which employs the non-linear xenon and iodine balance equations and the one group, one-dimensional neutron diffusion equation, with non-linear power reactivity feedback, also proposed in the literature. Obtained results showed the ability of the GP in finding a strategy which can effectively control the axial xenon oscillations.

Roberto P. Domingos; Roberto Schirru; Aquilino Senra Martinez

2005-01-01T23:59:59.000Z

165

Impact of the Demand-Side Management (DSM) Program structure on the cost-effectiveness of energy efficiency projects  

SciTech Connect

Pacific Northwest Laboratory (PNL) analyzed the cost-effective energy efficiency potential of Fort Drum, a customer of the Niagara Mohawk Power Corporation (NMPC) in Watertown, New York. Significant cost-effective investments were identified, even without any demand-side management (DSM) incentives from NMPC. Three NMPC DSM programs were then examined to determine the impact of participation on the cost-effective efficiency potential at the Fort. The following three utility programs were analyzed: (1) utility rebates to be paid back through surcharges, (2) a demand reduction program offered in conjunction with an energy services company, and (3) utility financing. Ultimately, utility rebates and financing were found to be the best programs for the Fort. This paper examines the influence that specific characteristics of the DSM programs had on the decision-making process of one customer. Fort Drum represents a significant demand-side resource, whose decisions regarding energy efficiency investments are based on life-cycle cost analysis subject to stringent capital constraints. The structures of the DSM programs offered by NMPC affect the cost-effectiveness of potential efficiency investments and the ability of the Fort to obtain sufficient capital to implement the projects. This paper compares the magnitude of the cost-effective resource available under each program, and the resulting level of energy and demand savings. The results of this analysis can be used to examine how DSM program structures impact the decision-making process of federal and large commercial customers.

Stucky, D.J.; Shankle, S.A.; Dixon, D.R.; Elliott, D.B.

1994-12-01T23:59:59.000Z

166

Impact of the demand-side management (DSM) Program structure on the cost-effectiveness of energy efficiency projects  

SciTech Connect

Pacific Northwest Laboratory (PNL) analyzed the cost-effective energy efficiency potential of Fort Drum, a customer of the Niagara Mohawk Power Corporation (NMPC) in Watertown, New York. Significant cost-effective investments were identified, even without any demand-side management (DSM) incentives from NMPC. Three NMPC DMS programs were then examined to determine the impact of participation on the cost-effective efficiency potential at the Fort. The following three utility programs were analyzed: (1) utility rebates to be paid back through surcharges; (2) a demand reduction program offered in conjunction with an energy services company; and (3) utility financing. Ultimately, utility rebates and financing were found to be the best programs for the Fort. This paper examines the influence that specific characteristics of the DSM programs had on the decision-making process of one customer. Fort Drum represents a significant demand-side resource, whose decisions regarding energy efficiency investments are based on life-cycle cost analysis subject to stringent capital constraints. The structures of the DSM programs offered by NMPC affect the cost-effectiveness of potential efficiency investments and the ability of the Fort to obtain sufficient capital to implement the projects. This paper compares the magnitude of the cost-effective resource available under each program, and the resulting level of energy and demand savings. The results of this analysis can be used to examine how DSM program structures impact the decision-making process of federal and large commercial customers.

Stucky, D.J.; Shankle, S.A.; Dixon, D.R.; Elliott, D.B.

1995-06-01T23:59:59.000Z

167

Report on discussions with utility engineers about superconducting generators  

SciTech Connect

This report relates to a series of discussions with electric utility engineers concerning the integration of high-temperature superconducting (HTS) generators into the present electric power system. The current and future interest of the utilities in the purchase and use of HTS generators is assessed. Various performance and economic factors are also considered as part of this inspection of the utility prospects for HTS generators. Integration of HTS generators into the electric utility sector is one goal of the Superconductivity Partnership Initiative (SPI). The SPI, a major part of the Department of Energy (DOE) Superconductivity Program for Electric Systems, features vertical teaming of a major industrial power apparatus manufacturers, a producer of HTS wire, and an end-user with assistance and technical support for the national laboratories. The SPI effort on HTS generators is headed by a General Electric Corporation internal team comprised of the Corporate Research Laboratories, Power Generation Engineering, and Power Systems Group. Intermagnetics General corporation, which assisted in the development of the superconducting coils, is the HTS wire and tape manufacturer. Additional technical support is provided by the national laboratories: Argonne, Los Alamos, and Oak Ridge, and the New York State Institute on Superconductivity. The end-user is represented by Niagara-Mohawk and the Electric Power Research Institute.

none,

1996-03-01T23:59:59.000Z

168

Mandated Collaboration as a Strategy of Environmental Governance? A Case Study of the Niagara Peninsula Source Protection Area in Ontario.  

E-Print Network (OSTI)

??Government (state) command and control strategies for addressing the complexities, uncertainties, and conflicts associated with ecological issues are no longer adequate. This is particularly true (more)

Vaughan, Katelyn Suzanne

2012-01-01T23:59:59.000Z

169

Notice of Intent to prepare an Environmental Impact Statement for the Construction and Operation of the Proposed Wellton-Mohawk Generating Facility, Yuma County, AZ (5/19/03)  

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

056 056 Federal Register / Vol. 68, No. 96 / Monday, May 19, 2003 / Notices 3 The ALJ report will not be an initial decision, so we will not entertain the filing of briefs on or opposing exceptions. Further, we do not anticipate the need for cross-examination of witnesses. The Judge need not create an exhaustive record, but may work with the parties to create the record that provides a thorough picture of the facts, problems, and opportunities, and lessons to be learned. date of this order. 3 State Commission ALJs or expert staff that participate in the fact-finding may offer written comments or conclusions that will be appended to the Commission ALJ's report. The Commission Orders (A) The Secretary is hereby directed to publish this order in the Federal Register.

170

PWR Fuel Shipping Limits & RNP Core Design  

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

Fuel Fuel Transportation Experience Steven Edwards, Progress Energy September 21, 2005 2 Discussion Topics Progress Energy Transportation History Success Factors Shipment Security Dedicated Trains Emergency Response Public Communication/Participation Summary 3 Brunswick Harris Crystal River Robinson Progress Energy Nuclear Plants 4 Spent Fuel Management Strategy Maintain operating reserve at all nuclear units Spent fuel shipping program to reduce inventories at Brunswick and Robinson Maximize use of Harris spent fuel pools 5 Transportation Experience 191 shipments 1,000 MTU transported 4,541 spent fuel assemblies transported 6 Transportation Experience First Shipment - 1977 Active spent fuel transportation program since 1989 12 to 15 shipments per year

171

Stanton County Public Pwr Dist | Open Energy Information  

Open Energy Info (EERE)

Place Stanton, Nebraska Place Stanton, Nebraska Utility Id 17979 Utility Location Yes Ownership P NERC Location SPP NERC SPP Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] SGIC[2] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Stanton County Public Power District Smart Grid Project was awarded $397,000 Recovery Act Funding with a total project value of $794,000. Utility Rate Schedules Grid-background.png Commercial Pumping Single Phase Commercial Commercial Pumping Three Phase Commercial Commercial Single Phase Commercial Commercial Three Phase Commercial Discounted Small Public Authority Services Single Phase Commercial Discounted Small Public Authority Services Three Phase Commercial

172

Sam Rayburn Municipal Pwr Agny | Open Energy Information  

Open Energy Info (EERE)

Id 16821 Utility Location Yes Ownership P NERC Location SERC NERC SERC Yes Activity Wholesale Marketing Yes This article is a stub. You can help OpenEI by expanding it. Utility...

173

Arizona Electric Pwr Coop Inc | Open Energy Information  

Open Energy Info (EERE)

Plant Yes Activity Generation Yes Activity Buying Transmission Yes Activity Wholesale Marketing Yes This article is a stub. You can help OpenEI by expanding it. Utility...

174

Central Montana E Pwr Coop Inc | Open Energy Information  

Open Energy Info (EERE)

Id 40301 Utility Location Yes Ownership C NERC Location WECC NERC WECC Yes Activity Wholesale Marketing Yes This article is a stub. You can help OpenEI by expanding it. Utility...

175

Nuclear reactor cooling system decontamination reagent regeneration. [PWR; BWR  

DOE Patents (OSTI)

An improved method for decontaminating the coolant system of water-cooled nuclear power reactors and for regenerating the decontamination solution is described. A small amount of one or more weak-acid organic complexing agents is added to the reactor coolant, and the pH is adjusted to form a decontamination solution which is circulated throughout the coolant system to dissolve metal oxides from the interior surfaces and complex the resulting metal ions and radionuclide ions. The coolant containing the complexed metal ions and radionuclide ions is passed through a strong-base anion exchange resin bed which has been presaturated with a solution containing the complexing agents in the same ratio and having the same pH as the decontamination solution. As the decontamination solution passes through the resin bed, metal-complexed anions are exchanged for the metal-ion-free anions on the bed, while metal-ion-free anions in the solution pass through the bed, thus removing the metal ions and regenerating the decontamination solution.

Anstine, L.D.; James, D.B.; Melaika, E.A.; Peterson, J.P. Jr.

1980-06-06T23:59:59.000Z

176

Stress-corrosion cracking in BWR and PWR piping  

SciTech Connect

Intergranular stress-corrosion cracking of weld-sensitized wrought stainless steel piping has been an increasingly ubiquitous and expensive problem in boiling-water reactors over the last decade. In recent months, numerous cracks have been found, even in large-diameter lines. A number of potential remedies have been developed. These are directed at providing more resistant materials, reducing weld-induced stresses, or improving the water chemistry. The potential remedies are discussed, along with the capabilities of ultrasonic testing to find and size the cracks and related safety issues. The problem has been much less severe to date in pressurized-water reactors, reflecting the use of different materials and much lower coolant oxygen levels.

Weeks, R.W.

1983-07-01T23:59:59.000Z

177

Wire wrapped fuel pin hexagonal arrays for PWR service  

E-Print Network (OSTI)

This work contributes to the Hydride Fuels Project, a collaborative effort between UC Berkeley and MIT aimed at investigating the potential benefits of hydride fuel use in light water reactors (LWRs). Core design is ...

Diller, Peter Ray

2005-01-01T23:59:59.000Z

178

Annular burnout data from rod-bundle experiments. [PWR  

SciTech Connect

Burnout data for annular flow in a rod bundle are presented for both transient and steady-state conditions. Tests were performed at the Oak Ridge National Laboratory in the Thermal Hydraulic Test Facility (THTF), a pressurized-water loop containing an electrically heated 64-rod bundle. The bundle configuration is typical of later generation pressurized-water reactors with 17 x 17 fuel arrays. Both axial and radial power profiles are flat. All experiments were carried out in upflow with subcooled inlet conditions, insuring accurate flow measurement. Conditions within the bundle were typical of those which could be encountered during a nuclear reactor loss-of-coolant accident.

Yoder, G.L.; Morris, D.G.; Mullins, C.B.

1983-01-01T23:59:59.000Z

179

Steam generator sludge pile model boiler testing: sludge characterization. [PWR  

SciTech Connect

As part of a program to understand the thermal and hydraulic transport process that can lead to chemical concentration in sludge piles on the tubesheet in a steam generator, the chemical composition and physical properties of eight sludges and several simulants were determined. Analyses performed by emission and x-ray fluorescence spectroscopy indicated that most of the sludges were mainly composed of iron oxides, copper, and other elements at trace levels. X-ray diffraction measurements identified iron to exist in the form of magnetite and copper to exist in the form of a metal. The densities, porosity, particle size, surface area, pore size distribution, and hydrodynamic permeabilities were determined on all plant sludges and selected simulants. Wide variations were observed in the physical measurements of the different plant sludges.

Becker, L.F. Jr.; Esposito, J.N.

1981-09-01T23:59:59.000Z

180

Structure of high-burnup-fuel Zircaloy cladding. [PWR; BWR  

SciTech Connect

Zircaloy cladding from high-burnup (> 20 MWd/kg U) fuel rods in light-water reactors is characterized by a high density of irradiation-induced defects (RID), compositional changes (e.g., oxygen and hydrogen uptake) associated with in-service corrosion, and geometrical changes produced by creepdown, bowing, and irradiation-induced growth. During a reactor power transient, the cladding is subject to localized stress imposed by thermal expansion of the cracked fuel pellets and to mechanical constraints imposed by pellet-cladding friction. As part of a program to provide a better understanding of brittle-type failure of Zircaloy fuel cladding by pellet-cladding interaction (PCI) phenomenon, the stress-rupture properties and microstructural characteristics of high-burnup spent fuel cladding have been under investigation. This paper reports the results of the microstructural examinations by optical microscopy, scanning (SEM), 100-keV transmission (TEM), and 1 MeV high-voltage (HVEM) electron microscopies of the fractured spent fuel cladding with a specific empahsis on a correlation of the structural characteristics with the fracture behavior.

Chung, H.M.

1983-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Selection of clc, cba, andfcb Chlorobenzoate-Catabolic Genotypes from Groundwater and Surface Waters Adjacent to the Hyde Park, Niagara Falls, Chemical Landfill  

Science Journals Connector (OSTI)

...Elements Dioxygenases Fresh Water microbiology Hydrolases...Restriction Fragment Length Water Microbiology georef...enrichment geochemistry ground water Hyde Park New York industrial...North America pollution remediation sediments transport United...

Michelle C. Peel; R. Campbell Wyndham

1999-04-01T23:59:59.000Z

183

Multilocus Sequence Typing Supports the Hypothesis that Cow- and Human-Associated Salmonella Isolates Represent Distinct and Overlapping Populations  

Science Journals Connector (OSTI)

...Golden, CO). County codes are as follows...Nia, Niagara; One, Oneida; Ono, Onondaga...farm) (Table 1). c Counties are depicted in Fig. 1. County codes are as follows...Nia, Niagara; One, Oneida; Ono, Onondaga...

S. D. Alcaine; Y. Soyer; L. D. Warnick; W.-L. Su; S. Sukhnanand; J. Richards; E. D. Fortes; P. McDonough; T. P. Root; N. B. Dumas; Y. Grhn; M. Wiedmann

2006-10-06T23:59:59.000Z

184

niagarastoragesite  

Office of Legacy Management (LM)

Niagara Falls Storage Site, New York, is a Niagara Falls Storage Site, New York, is a 191-acre site located on Pletcher Road in the towns of Lewiston and Porter, Niagara County, in northwestern New York. It is approximately 10 miles north of the city of Niagara Falls and 19 miles northwest of Buffalo, New York. The site is a remnant of the U.S. Army's 7,500-acre Lake Ontario Ordnance Works. The property includes a 10-acre interim waste

185

Customer Strategies for Responding to Day-Ahead Market HourlyElectricity Pricing  

SciTech Connect

Real-time pricing (RTP) has been advocated as an economically efficient means to send price signals to customers to promote demand response (DR) (Borenstein 2002, Borenstein 2005, Ruff 2002). However, limited information exists that can be used to judge how effectively RTP actually induces DR, particularly in the context of restructured electricity markets. This report describes the second phase of a study of how large, non-residential customers' adapted to default-service day-ahead hourly pricing. The customers are located in upstate New York and served under Niagara Mohawk, A National Grid Company (NMPC)'s SC-3A rate class. The SC-3A tariff is a type of RTP that provides firm, day-ahead notice of hourly varying prices indexed to New York Independent System Operator (NYISO) day-ahead market prices. The study was funded by the California Energy Commission (CEC)'s PIER program through the Demand Response Research Center (DRRC). NMPC's is the first and longest-running default-service RTP tariff implemented in the context of retail competition. The mix of NMPC's large customers exposed to day-ahead hourly prices is roughly 30% industrial, 25% commercial and 45% institutional. They have faced periods of high prices during the study period (2000-2004), thereby providing an opportunity to assess their response to volatile hourly prices. The nature of the SC-3A default service attracted competitive retailers offering a wide array of pricing and hedging options, and customers could also participate in demand response programs implemented by NYISO. The first phase of this study examined SC-3A customers' satisfaction, hedging choices and price response through in-depth customer market research and a Constant Elasticity of Substitution (CES) demand model (Goldman et al. 2004). This second phase was undertaken to answer questions that remained unresolved and to quantify price response to a higher level of granularity. We accomplished these objectives with a second customer survey and interview effort, which resulted in a higher, 76% response rate, and the adoption of the more flexible Generalized Leontief (GL) demand model, which allows us to analyze customer response under a range of conditions (e.g. at different nominal prices) and to determine the distribution of individual customers' response.

Goldman, Chuck; Hopper, Nicole; Bharvirkar, Ranjit; Neenan,Bernie; Boisvert, Dick; Cappers, Peter; Pratt, Donna; Butkins, Kim

2005-08-25T23:59:59.000Z

186

The design of a compact integral medium size PWR : the CIRIS  

E-Print Network (OSTI)

The International Reactor Innovative and Secure (IRIS) is an advanced medium size, modular integral light water reactor design, rated currently at 1000 MWt. IRIS design has been under development by over 20 organizations ...

Shirvan, Koroush

2010-01-01T23:59:59.000Z

187

Pre-Phase 1 Aging Assessment of the BWR and PWR Accumulators  

SciTech Connect

Accumulators are important components used in many systems at commercial boiling water reactors (BWRs) and pressurized water reactors in the United States. The accumulators are vessels attached to fluid systems to provide 1) a limited backup source of stored fluid energy for hydraulic/pneumatic mechanical equipment, 2) a damping effect on pressure pulses in fluid systems, and 3) a volume of fluid to be injected passively into a fluid system. Accumulators contain a gas that is compressed or expanded as the fluid from the system enters or exits the accumulator. The gas and fluid in accumulators are usually separated from each other by a piston or bladder. In support of the U.S. Nuclear Regulatory Commission's Nuclear Aging Research Program (NPAR), the Pacific Northwest Laboratory conducted an analysis of available industry databases to determine if accumulator components already had been studied in other NPAR assessments and to evaluate each accumulator type for applicable aging issues. The results of this preliminary study indicate that two critical uses of accumulators have been previously evaluated by the NPAR program. NUREGICR-5699, Aging and Service Wear of Control Rod Drive Mechanisms for BUT Nuclear Plants (Greene 199 I), identified two hydraulic control unit components subject to aging failures: accumulator nitrogen-charging cartridge valves and the scram water accumulator. In addition, NUREGICR-6001, Aging Assessment of BWR Standby Liquid Control Systems (Buckley et al. 1992), identified two predominant aging-related accumulator failures that result in a loss of the nitrogen blanket pressure: (charging) valve wear and failure of the gas bladder. The present study has identified five prevalent aging-related accumulator failures: rupture of the accumulator bladder separation of the metal disc from the bottom of the bladder leakage of the gas from the charging valve leakage past the safety injection tank manway cover gasket leakage past O-rings. An additional study of the accumulator subcomponents associated with these failures is recommended, including an evaluation of current inspection programs to verify that they are detecting the aging degradation effects. The study may also provide beneficial input to the design of passive accumulator applications in advanced reactor designs.

Buckely, G. D.

1995-08-01T23:59:59.000Z

188

Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR  

E-Print Network (OSTI)

An analysis and comparison of Unit Conventional UO2 Fuel-Assemblies and proposed Plutonium Recycle Fuel Assemblies for the Yankee (Rowe) Reactor has been made. The influence of spectral effects, at the watergaps -and ...

Mertens, Paul Gustaaf

1971-01-01T23:59:59.000Z

189

Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor  

SciTech Connect

This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemical assay data and the use of the data to validate computer code predictions of isotopic composition for spent nuclear fuel, to establish the uncertainty and bias associated with code predictions. The experimental data analyzed in the current report were acquired from a high-burnup fuel program coordinated by Spanish organizations. The measurements included extensive actinide and fission product data of importance to spent fuel safety applications, including burnup credit, decay heat, and radiation source terms. Six unique spent fuel samples from three uranium oxide fuel rods were analyzed. The fuel rods had a 4.5 wt % {sup 235}U initial enrichment and were irradiated in the Vandellos II pressurized water reactor operated in Spain. The burnups of the fuel samples range from 42 to 78 GWd/MTU. The measurements were used to validate the two-dimensional depletion sequence TRITON in the SCALE computer code system.

Ilas, Germina [ORNL; Gauld, Ian C [ORNL

2011-01-01T23:59:59.000Z

190

Propagation of Isotopic Bias and Uncertainty to Criticality Safety Analyses of PWR Waste Packages  

SciTech Connect

Burnup credit methodology is economically advantageous because significantly higher loading capacity may be achieved for spent nuclear fuel (SNF) casks based on this methodology as compared to the loading capacity based on a fresh fuel assumption. However, the criticality safety analysis for establishing the loading curve based on burnup credit becomes increasingly complex as more parameters accounting for spent fuel isotopic compositions are introduced to the safety analysis. The safety analysis requires validation of both depletion and criticality calculation methods. Validation of a neutronic-depletion code consists of quantifying the bias and the uncertainty associated with the bias in predicted SNF compositions caused by cross-section data uncertainty and by approximations in the calculational method. The validation is based on comparison between radiochemical assay (RCA) data and calculated isotopic concentrations for fuel samples representative of SNF inventory. The criticality analysis methodology for commercial SNF disposal allows burnup credit for 14 actinides and 15 fission product isotopes in SNF compositions. The neutronic-depletion method for disposal criticality analysis employing burnup credit is the two-dimensional (2-D) depletion sequence TRITON (Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion)/NEWT (New ESC-based Weighting Transport code) and the 44GROUPNDF5 crosssection library in the Standardized Computer Analysis for Licensing Evaluation (SCALE 5.1) code system. The SCALE 44GROUPNDF5 cross section library is based on the Evaluated Nuclear Data File/B Version V (ENDF/B-V) library. The criticality calculation code for disposal criticality analysis employing burnup credit is General Monte Carlo N-Particle (MCNP) Transport Code. The purpose of this calculation report is to determine the bias on the calculated effective neutron multiplication factor, k{sub eff}, due to the bias and bias uncertainty associated with predicted spent fuel compositions (i.e., determine the penalty in reactivity due to isotopic composition bias and uncertainty) for use in disposal criticality analysis employing burnup credit. The method used in this calculation to propagate the isotopic bias and bias-uncertainty values to k{sub eff} is the Monte Carlo uncertainty sampling method. The development of this report is consistent with 'Test Plan for: Isotopic Validation for Postclosure Criticality of Commercial Spent Nuclear Fuel'. This calculation report has been developed in support of burnup credit activities for the proposed repository at Yucca Mountain, Nevada, and provides a methodology that can be applied to other criticality safety applications employing burnup credit.

Radulescu, Georgeta [ORNL

2010-06-01T23:59:59.000Z

191

Decommissioning of Large Components as an Example of Steam Generator from PWR Nuclear Power Plants  

SciTech Connect

This paper describes the procedure for the qualification of large components (Steam Generators) as an IP-2 package, the ship transport abroad to Sweden and the external treatment of this components to disburden the Nuclear Power Plant from this task, to assure an accelerated the deconstruction phase and to minimize the amount of waste. In conclusion: The transport of large components to an external treatment facility is linked with many advantages for a Nuclear Power Plant: - Disburden of the Nuclear Power Plant from the treatment of such components, - no timely influence on the deconstruction phase of the power reactor and therewith an accelerated deconstruction phase and - minimization of the waste to be returned and therewith less demand of required waste storage capacity. (authors)

Beverungen, M. [GNS Gesellschaft fur Nuklear-Service mbH, Hollestrabe 7A (Germany)

2008-07-01T23:59:59.000Z

192

Monitoring system for a liquid-cooled nuclear fission reactor. [PWR  

DOE Patents (OSTI)

The invention provides improved means for detecting the water levels in various regions of a water-cooled nuclear power reactor, viz., in the downcomer, in the core, in the inlet and outlet plenums, at the head, and elsewhere; and also for detecting the density of the water in these regions. The invention utilizes a plurality of exterior gamma radiation detectors and a collimator technique operable to sense separate regions of the reactor vessel to give respectively, unique signals for these regions, whereby comparative analysis of these signals can be used to advise of the presence and density of cooling water in the vessel.

DeVolpi, A.

1984-07-20T23:59:59.000Z

193

Comparison of BALON2 with cladding ballooning strain tables in NUREG-0630. [PWR; BWR  

SciTech Connect

For this comparison study, the two computer models used for calculating fuel rod cladding failure and the resulting permanent strains were compared against experiment data. The two models considered were the mechanistic BALON2 model and the empirical model described in the NUREG-0630 report. The purpose for making this comparison was simply to gain insight into the relative strengths and weaknesses of each model. The experiment data sample consisted of data from both single and bundle tests conducted sometimes in in-pile facilities, but mostly in out-of-pile facilities. Comparisons between models indicated that the empirical NUREG-0630 model more accurately calculated the local cladding temperature and pressure conditions at rupture, but the mechanistic BALON2 model more accurately calculated the resulting cladding permanent strain at the rupture location.

Resch, S.C.; Laats, E.T.

1982-01-01T23:59:59.000Z

194

Dynamic system characterization of an integral test facility of an advanced PWR  

E-Print Network (OSTI)

series of tests to generate data for code assessment against AP600 relevant phenomena. The AP600 design relies only on passive safety features such as gravity driven draining pressurized tanks, and battery power logic and actuators for its safety...

Smith, Simon Gregory

2012-06-07T23:59:59.000Z

195

Microsoft PowerPoint - MISO-SPP Market Impacts HydPwrConf 2014  

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

Changing Energy Markets- Effects of Day 2 and Real Time Markets in the S th t P P l d Mid C ti t I d d t S t O t Southwest Power Pool and Mid-Continent Independent System Operator...

196

Development of a new flux map processing code for moveable detector system in PWR  

SciTech Connect

This paper presents an introduction to the development of the flux map processing code MAPLE developed by China Nuclear Power Technology Research Institute (CNPPJ), China Guangdong Nuclear Power Group (CGN). The method to get the three-dimensional 'measured' power distribution according to measurement signal has also been described. Three methods, namely, Weight Coefficient Method (WCM), Polynomial Expand Method (PEM) and Thin Plane Spline (TPS) method, have been applied to fit the deviation between measured and predicted results for two-dimensional radial plane. The measured flux map data of the LINGAO nuclear power plant (NPP) is processed using MAPLE as a test case to compare the effectiveness of the three methods, combined with a 3D neutronics code COCO. Assembly power distribution results show that MAPLE results are reasonable and satisfied. More verification and validation of the MAPLE code will be carried out in future. (authors)

Li, W.; Lu, H.; Li, J.; Dang, Z.; Zhang, X. [China Nuclear Power Technology Research Institute, 47 F/A Jiangsu Bldg., Yitian Road, Futian District, Shenzhen 518026 (China); Wu, Y.; Fan, X. [Information Technology Center, China Guangdong Nuclear Power Group, Shenzhen 518000 (China)

2013-07-01T23:59:59.000Z

197

CFD Analysis of Nuclear Fuel Bundles and Spacer Grids for PWR Reactors  

E-Print Network (OSTI)

4.3 The Numerical Approach ......................................................... 95 viii 4.4 Implementation in CFD Codes ................................................. 99 4... Total standard error refinement 3 ................................................................... 56 xii Figure 62 Experimental results plane B1 axial velocity (a), KER 138M mesh constant inlet (b), SST138M mesh periodic inlet (c...

Capone, Luigi

2012-10-19T23:59:59.000Z

198

Advances in steam turbine technology for the power generation industry. PWR-Volume 26  

SciTech Connect

This is a collection of the papers on advances in steam turbine technology for the power generation industry presented at the 1994 International Joint Power Generation Conference. The topics include advances in steam turbine design, application of computational fluid dynamics to turbine aerodynamic design, life extension of fossil and nuclear powered steam turbine generators, solid particle erosion control technologies, and artificial intelligence, monitoring and diagnostics.

Moore, W.G. [ed.

1994-12-31T23:59:59.000Z

199

Comparison of nuclear data uncertainty propagation methodologies for PWR burn-up simulations  

E-Print Network (OSTI)

Several methodologies using different levels of approximations have been developed for propagating nuclear data uncertainties in nuclear burn-up simulations. Most methods fall into the two broad classes of Monte Carlo approaches, which are exact apart from statistical uncertainties but require additional computation time, and first order perturbation theory approaches, which are efficient for not too large numbers of considered response functions but only applicable for sufficiently small nuclear data uncertainties. Some methods neglect isotopic composition uncertainties induced by the depletion steps of the simulations, others neglect neutron flux uncertainties, and the accuracy of a given approximation is often very hard to quantify. In order to get a better sense of the impact of different approximations, this work aims to compare results obtained based on different approximate methodologies with an exact method, namely the NUDUNA Monte Carlo based approach developed by AREVA GmbH. In addition, the impact of different covariance data is studied by comparing two of the presently most complete nuclear data covariance libraries (ENDF/B-VII.1 and SCALE 6.0), which reveals a high dependency of the uncertainty estimates on the source of covariance data. The burn-up benchmark Exercise I-1b proposed by the OECD expert group "Benchmarks for Uncertainty Analysis in Modeling (UAM) for the Design, Operation and Safety Analysis of LWRs" is studied as an example application. The burn-up simulations are performed with the SCALE 6.0 tool suite.

Carlos Javier Diez; Oliver Buss; Axel Hoefer; Dieter Porsch; Oscar Cabellos

2014-11-04T23:59:59.000Z

200

Prediction of departure from nucleate boiling in PWR fast power transients  

E-Print Network (OSTI)

An assessment is conducted of the differences in predicted results between use of steady state versus transient Departure from Nucleate Boiling (DNB) models, for fast power transients under forced convective heat exchange ...

Lenci, Giancarlo

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Pwr fuel assembly optimization using adaptive simulated annealing coupled with translat  

E-Print Network (OSTI)

assembly to be used in an operating nuclear power reactor. The two main cases of optimization are: one that finds the optimal 235U enrichment layout of the fuel pins in the assembly and another that finds both the optimal 235U enrichments where gadolinium...

Rogers, Timothy James

2009-05-15T23:59:59.000Z

202

Aggressive fuel designs minimize fuel costs for the ANO-1 PWR  

SciTech Connect

Fuel cycle design objectives are influenced by the desire of utilities to attain top performer status in the industry and to become more cost competitive. At Energy, we are seeking aggressive fuel designs and core management schemes that reduce costs without compromising operating margins. Recent efforts at the Arkansas Nuclear One (ANO-1) plant demonstrated the effectiveness of this approach and led to important benefits for both the utility and the fuel vendor, Babcock Wilcox. With our acquisition of the CASMO-3/SIMULATE-3 advanced physics code, we initiated a proactive approach to the design of cycle 12 of ANO-1. The primary goal was to explore the use of advanced designs to reduce front-end fuel cycle costs for cycle 12. A secondary goal was to incorporate those features into cycle 12 that could lead to further cost or margin improvements in later cycles.

Ober, T.G.; Megehee, K.B.; Bencheikh, A.; Thompson, R.A. (Entergy Operations, Jackson, MS (United States))

1993-01-01T23:59:59.000Z

203

The comparison of available data on PWR assembly thermal behavior with analytical predictions  

E-Print Network (OSTI)

The comparison of available data with analytical predictions has been illustrated in this report. Since few data on the cross flow are available, a study of parameters in the transverse momentum equation were performed to ...

Liu, Jack S. H.

204

Analysis of the FLECHT SEASET unblocked bundle steam-cooling and boiloff tests. [PWR  

SciTech Connect

A series of forced convection steam cooling tests at low Reynolds numbers and bundle boiloff tests were conducted in the unblocked bundle task of the FLECHT SEASET program. The COBRA-IV-I computer code was utilized to simulate the steam cooling tests, so that the effects of the housing, disconnected heater rods in the bundle, and subchannel mixing were accurately accounted for. After careful data screening, a steady-state forced convection steam cooling heat transfer correlation was developed using the measured heater rod power, heater rod surface temperatures calculated from the measured cladding inner surface temperature by an inverse conduction code, and the vapor temperatures at various subchannels calculated by the COBRA-IV-I code The new correlation was found to give higher heat transfer than the conventional Dittus-Boelter correlation in the low Reynolds number region. At higher Reynolds numbers, the data begin to merge with the Dittus-Boelter correlation.

Wong, S.; Hochreiter, L.E.

1981-05-01T23:59:59.000Z

205

Evaluation of nonequilibrium effects in bundle dispersed-flow film boiling. [PWR; BWR  

SciTech Connect

The effects of thermodynamic nonequilibrium in dispersed flow film boiling heat transfer are examined. Steady-state and transient rod-bundle data are used to evaluate several empirical heat-transfer models commonly employed to predict post-CHF behavior. The models that account for thermodynamic nonequilibrium perform adequately, while those that ignore nonequilibrium effects incur errors in wall superheat as high as 190/sup 0/K. Nonequilibrium effects can also be treated by explicitly modeling the phenomena. The thermal-hydraulic code COBRA-TF employs this approach. Using bundle data, the models in the code are evaluated. Analysis suggests that the interfacial heat transfer is overpredicted.

Morris, D.G.; Mullins, C.B.; Yoder, G.L.

1983-01-01T23:59:59.000Z

206

Multi-Recycling of Transuranic Elements in a Modified PWR Fuel Assembly  

E-Print Network (OSTI)

production/destruction, and radiotoxicity reduction as compared to a UOX and MOX assembly. It is found that the most beneficial recycling strategy is the one where all of the transuranics are recycled. The inclusion of Cm reduces the required U-235...

Chambers, Alex

2012-10-19T23:59:59.000Z

207

Evaluation of fission product worth margins in PWR spent nuclear fuel burnup credit calculations.  

SciTech Connect

Current criticality safety calculations for the transportation of irradiated LWR fuel make the very conservative assumption that the fuel is fresh. This results in a very substantial overprediction of the actual k{sub eff} of the transportation casks; in certain cases, this decreases the amount of spent fuel which can be loaded in a cask, and increases the cost of transporting the spent fuel to the repository. Accounting for the change of reactivity due to fuel depletion is usually referred to as ''burnup credit.'' The US DOE is currently funding a program aimed at establishing an actinide only burnup credit methodology (in this case, the calculated reactivity takes into account the buildup or depletion of a limited number of actinides). This work is undergoing NRC review. While this methodology is being validated on a significant experimental basis, it implicitly relies on additional margins: in particular, the absorption of neutrons by certain actinides and by all fission products is not taken into account. This provides an important additional margin and helps guarantee that the methodology is conservative provided these neglected absorption are known with reasonable accuracy. This report establishes the accuracy of fission product absorption rate calculations: (1) the analysis of European fission product worth experiments demonstrates that fission product cross-sections available in the US provide very good predictions of fission product worth; (2) this is confirmed by a direct comparison of European and US cross section evaluations; (3) accuracy of Spent Nuclear Fuel (SNF) fission product content predictions is established in a recent ORNL report where several SNF isotopic assays are analyzed; and (4) these data are then combined to establish in a conservative manner the fraction of the predicted total fission product absorption which can be guaranteed based on available experimental data.

Blomquist, R.N.; Finck, P.J.; Jammes, C.; Stenberg, C.G.

1999-02-17T23:59:59.000Z

208

WAPD-SC-545 HYDROGEN FLAMMABILITY DATA AND APPLICATION TO PWR  

Office of Scientific and Technical Information (OSTI)

and results of a major loss-of-coolant accident in RVR (the Shippingport Atomic Power Station). There it is shown that a zirconium-water (or steam) reaction is a possible...

209

Verification of Optimal Control Strategy Search Using a Simplest 3-D PWR Xenon Oscillation Simulator  

SciTech Connect

Power spatial oscillations due to the transient xenon spatial distribution are well known as xenon oscillation in large PWRs. When the reactor size becomes larger than the current design, then even radial oscillations can be also divergent. Even if the radial oscillation is convergent, when some control rods malfunction occurs, it is necessary to suppress the oscillation in as short time as possible. In such cases, optimal control strategy is required. Generally speaking the optimality search based on the modern control theory requires a lot of calculation for the evaluation of state variables. In the case of control rod malfunctions the xenon oscillation could be three dimensional. In such case, direct core calculations would be inevitable. From this point of view a very simple model, only four point reactor model, has been developed and verified. In this paper, an example of a procedure and the validity of the results for optimal control strategy search are presented by comparing it with the result by a three dimensional nuclear design code The simplest simulator can predict optimal strategy in less than 10 seconds on a PC. Thus it is recommended that a strategy generator, which is quick in analyzing and easy to use, might be installed in a monitoring system or in an operator guiding system. (author)

Shimazu, Yoichiro [Graduate School of Engineering, Hokkaido University, Kita13, Nishi8, Kita-ku, Sapporo (Japan)

2006-07-01T23:59:59.000Z

210

PWR's xenon oscillation control through a fuzzy expert system automatically designed by means of genetic programming  

Science Journals Connector (OSTI)

This work proposes the use of genetic programming (GP) for automatic design of a fuzzy expert system aimed to provide the control of axial xenon oscillations in pressurized water reactors (PWRs). The control methodology is based on three axial offsets of xenon (AOx), iodine (AOi) and neutron flux (AOf), effectively used in former work. Simulations were made using a two-point xenon oscillation model, which employs the non-linear xenon and iodine balance equations and the one group, one-dimensional neutron diffusion equation, with non-linear power reactivity feedback, also proposed in the literature. Results have demonstrated the ability of the GP in finding a good fuzzy strategy, which can effectively control the axial xenon oscillations.

Roberto P. Domingos; Gustavo H.F. Caldas; Cludio M.N.A. Pereira; Roberto Schirru

2003-01-01T23:59:59.000Z

211

PWR's xenon oscillation control through a fuzzy expert system automatically designed by means of genetic programming  

Science Journals Connector (OSTI)

This work proposes the use of genetic programming (GP) for automatic design of a fuzzy expert system aimed to provide the control of axial xenon oscillations in pressurized water reactors (PWRs). The control methodology is based on three axial offsets ... Keywords: Axial xenon oscillations control, Fuzzy logic, Genetic programming

Roberto P. Domingos; Gustavo H. F. Caldas; Cludio M. N. A. Pereira; Roberto Schirru

2003-12-01T23:59:59.000Z

212

Optimal Control Strategy Search Using a Simplest 3-D PWR Xenon Oscillation Simulator  

SciTech Connect

Power spatial oscillations due to the transient xenon spatial distribution are well known as xenon oscillation in large PWRs. When the reactor size becomes larger than the current design, then even radial oscillations can be also divergent. Even if the radial oscillation is convergent, when some control rods malfunction occurs, it is necessary to suppress the oscillation in as short time as possible. In such cases, optimal control strategy is required. Generally speaking the optimality search based on the modern control theory requires a lot of calculation for the evaluation of state variables. In the case of control rod malfunctions the xenon oscillation could be three dimensional. In such case, direct core calculations would be inevitable. From this point of view a very simple model, only four point reactor model, has been developed and verified. In this paper, an example of a procedure and the results for optimal control strategy search are presented. It is shown that we have only one optimal strategy within a half cycle of the oscillation with fixed control strength. It is also shown that a 3-D xenon oscillation introduced by a control rod malfunction can not be controlled by only one control step as can be done for axial oscillations. They might be quite strong limitations to the operators. Thus it is recommended that a strategy generator, which is quick in analyzing and easy to use, might be installed in a monitoring system or operator guiding system. (author)

Yoichiro, Shimazu [Graduate School of Engineering, Hokkaido University, Kita13, Nishi8, Kita-ku, Sapporo (Japan)

2004-07-01T23:59:59.000Z

213

Impact of PWR spent fuel variations on TRU-fueled VHTRS  

E-Print Network (OSTI)

of legacy spent fuel that is given in the Yucca Mountain Safety Assessment Report. Chapter III discusses the details of the study. The concluding study was accomplished through the use of ORNL SCALE5.1 code system. The detailed whole-core 3-D models were...

Alajo, Ayodeji Babatunde

2009-05-15T23:59:59.000Z

214

TMI-2 - A Case Study for PWR Instrumentation Performance during a Severe Accident  

SciTech Connect

The accident at the Three Mile Island Unit 2 (TMI-2) reactor provided a unique opportunity to evaluate sensors exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during this accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This new effort focussed upon a set of sensors that provided critical data to TMI-2 operators for assessing the condition of the plant and the effects of mitigating actions taken by these operators. In addition, the effort considered sensors providing data required for subsequent accident simulations. Over 100 references related to instrumentation performance and post-accident evaluations of TMI-2 sensors and measurements were reviewed. Insights gained from this review are summarized within this report. For each sensor, a description is provided with the measured data and conclusions related to the sensors survivability, and the basis for conclusions about its survivability. As noted within this document, several techniques were invoked in the TMI-2 post-accident evaluation program to assess sensor status, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design but more easily removed from the TMI-2 plant for evaluations. Conclusions from this review provide important insights related to sensor survivability and enhancement options for improving sensor performance. In addition, this document provides recommendations related to the sensor survivability and data evaluation process that could be implemented in upcoming Fukushima Daiichi recovery efforts.

Joy L. Rempe; Darrell L. Knudson

2014-05-01T23:59:59.000Z

215

Analysis of operating data related to power and flow distribution in a PWR  

E-Print Network (OSTI)

The analysis of the effects of the uncertainties associated with temperature and power measurements in the Connecticut Yankee Reactor leads to the evaluation of the uncertainty associated with the effective flow factor. ...

Herbin, Henry Christophe

1974-01-01T23:59:59.000Z

216

Parametric calculations of fatigue-crack growth in piping. [PWR; BWR  

SciTech Connect

A major objective of this program is to provide data that can be used to formulate recommended revisions to ASME Section XI and regulatory requirements for inservice inspection of piping and pressure vessels. This study presents calculations of the growth of piping flaws produced by fatigue. Flaw growth was predicted as a function of the initial flaw size, the level and number of stress cycles, the piping material, and environmental factors.

Simonen, F.A.; Goodrich, C.W.

1983-03-01T23:59:59.000Z

217

Experimental facility for containment sump reliability studies (Generic Task A-43). [PWR; BWR  

SciTech Connect

On July 3, 1979, Sandia National Laboratories (Sandia) contracted the Alden Research Laboratory (ARL) to conduct tests on unresolved safety issues associated with containment sump performance during the recirculation mode (Generic Task A-43). This report describes the test facility constructed and completed under Phase I, Task III of the contract. Sump performance is determined through the observation of vortex formation in the main tank and the measurement of swirl, pressure gradient, and entrained air in the suction pipes. The use of electrically operated valves and a sophisticated data acquisition system, with computer interface, allows the test flow parameters to be set and test data to be taken (with the exception of vortex observations) from a single central office.

Durgin, W. W.; Padmanabhan, M.; Janik, C. R.

1980-12-01T23:59:59.000Z

218

Status of verification and validation of AREVA's ARCADIA{sup R} code system for PWR applications  

SciTech Connect

In March 2010 the submittal of Topical Reports for ARCADIA{sup R} and COBRA-FLX, the thermal-hydraulic module of ARCADIA{sup R}, to the U.S. Nuclear Regulatory Commission (NRC) concluded a major step in the development of AREVA's new code system for core design and safety analyses. This submittal was dedicated to the application of the code system to uranium fuel in pressurized water reactors. The submitted information comprised results for plants operated in the US (France)) and Germany and provided uncertainties for in-core measuring systems with traveling in-core detectors and for the aero-ball system of the EPR. A reduction of the uncertainties in the prediction of F{sub AH} and F{sub Q} of > 1 % (absolute) was derived compared to the current code systems. This paper extents the verification and validation base for uranium based fuel and demonstrates the basic capabilities of ARCADIA{sup R} of describing MOX. The achieved status of verification and validation is described in detail. All applications followed the same standard without any specific calibration. The paper gives also insight in the new capability of 3D full core steady-state and transient pin-by-pin/sub-channel-by-sub-channel calculations and the opportunities offered by this feature. The gain of margins with increasing detail of the representation is outlined. Currently, the strategies for worldwide implementation of ARCADIA{sup R} are developed. (authors)

Porsch, D. [AREVA, AREVA NP GmbH (Germany); P.O.Box 1109, 91001 Erlangen (Germany); Leberig, M.; Kuch, S. [AREVA, AREVA NP GmbH (Germany); Magat, P. [AREVA, AREVA NP SAS, Paris (France); Segard, K. [AREVA, AREVA NP Inc., Lynchburg (United States)

2012-07-01T23:59:59.000Z

219

Thermal and hydraulic code verification: ATHOS2 and Model Boiler No. 2 data. Final report. [PWR  

SciTech Connect

As part of the EPRI/Westinghouse Project S168-1, Westinghouse was contracted to conduct steady-state and transient tests on the Westinghouse Model Boiler No. 2 (MB-2) steam genertor test model at the Engineering Test Facility in Tampa, Florida, and to use the data obtained in these tests for the verification of the ATHOS2 (an updated version of URSULA2) code developed for EPRI by CHAM of North America, Inc. This document presents a description of: (1) the model boiler and the associated test facility; (2) the ATHOS2 code analytical model of MB-2; (3) the tests performed for the code verification program; (4) the comparisons of the test data with ATHOS2 calculations; and (5) recommendations for improving the ATHOS2 code.

Hopkins, G.W.; Lee, A.Y.; Mendler, O.J.

1983-02-01T23:59:59.000Z

220

Thermal and hydraulic code verification: ATHOS2 and Model Boiler No. 2 data. Final report. [PWR  

SciTech Connect

As part of the EPRI/Westinghouse Project S168-1, Westinghouse was contracted to conduct steady-state and transient tests on the Westinghouse Model Boiler No. 2 (MB-2) steam generator test model at the Engineering Test Facility in Tampa, Florida, and to use the data obtained in these tests for the verification of the ATHOS2 (an updated version of URSULA2) code developed for EPRI by CHAM of North America, Inc. This document presents a description of (1) the model boiler and the associated test facility, (2) the ATHOS2 code analytical model of MB-2, (3) the tests performed for the code verification program, (4) the comparisons of the test data with ATHOS2 calculations, and (5) recommendations for improving the ARHOS2 code.

Hopkins, G.W.; Lee, A.Y.; Mendler, O.J.

1983-02-01T23:59:59.000Z

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


221

Effect of calcium hydroxide and carbonates on IGA and SCC of Alloy 600. Final report. [PWR  

SciTech Connect

A series of five tests was conducted at the Westinghouse Forest Hills Single Tube Model Boiler (STMB) Facility under this project. The objective of the project was to determine if alkaline earth carbonates and/or hydroxides are key ingreidents in causing intergranular attack (IGA) or stress corrosion cracking (SCC) of mill-annealed Alloy 600. Also as part of this program a report was written and issued detailing the earlier related STMB work Westinghouse conducted that led to reproducible SCC. The work reported here was an extension of that work.

Balavage, J.R.

1983-05-01T23:59:59.000Z

222

Experimental study of the deformation of Zircaloy PWR fuel rod cladding under mainly convective cooling  

SciTech Connect

Zircaloy-4 cladding specimens 450 mm long were filled with alumina pellets and tested at temperatures between 630 and 915 degree C in flowing steam at atmospheric pressure. Internal test pressures were in the range 0.69 to 11.0 MPa. The length of cladding strained 33 percent or more was greatest (about 20 times the original diameter) when the initial pressure was 1.38/plus or minus/0.17MPa. This results from oxidation strengthening of the surface layers acting as an additional mechanism for stabilizing the deformation or partial superplastic deformation, or both. For adjacent rods in a fuel assembly not to touch at any temperature, the pressure would have to be less than about 1 MPa. These results are compared with those form multirod tests elsewhere, and it is suggested that heat transfer has a dominant effect in determining deformation. The implications for the behavior of fuel elements in a loss-of-coolant accident are outlined. 37 refs.

Hindle, E.D.; Mann, C.A.

1982-01-01T23:59:59.000Z

223

Experiment operations plan for the MT-4 experiment in the NRU reactor. [PWR  

SciTech Connect

A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal operations plan for MT-4 - the fourth materials deformation experiment conducted in the National Research Universal (NRU) reactor, Chalk River, Ontario, Canada. A major objective of MT-4 was to simulate a pressurized water reactor LOCA that could induce fuel rod cladding deformation and rupture due to a short-term adiabatic transient and a peak fuel cladding temperature of 1200K (1700/sup 0/F).

Russcher, G.E.; Wilson, C.L.; Parchen, L.J.; Marshall, R.K.; Hesson, G.M.; Webb, B.J.; Freshley, M.D.

1983-06-01T23:59:59.000Z

224

Experiment operations plan for the TH-2 experiment in the NRU reactor. [PWR; BWR  

SciTech Connect

A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal operations plan for TH-2--the second experiment in the series of thermal-hydraulic tests conducted in the National Research Universal (NRU) reactor, Chalk River, Ontario, Canada. The major objective of TH-2 was to develop the experiment reflood control parameters and the procedures to be used in subsequent experiments in this program. In this experiment, the data acquisition and control system was used to control the fuel cladding temperature during a simulated LOCA by using variable reflood coolant flow.

Russcher, G.E.; Wilson, C.L.; Parchen, L.J.; Freshley, M.D.

1983-06-01T23:59:59.000Z

225

SYNTHESE EN FRANAIS TITRE: NEUTRONIC STUDY OF THE MONO-RECYCLING OF AMERICIUM IN PWR  

E-Print Network (OSTI)

AND OF THE CORE CONVERSION IN MNSR USING THE MURE CODE R?SUM? Le code MURE est basé sur le couplage d'un code questions : le mono- recyclage de l'Am dans les réacteurs français de type REP et la conversion du coeur du MNSR (Miniature Neutron Source Reactor) au Ghana d'un combustible à uranium hautement enrichi (HEU

Paris-Sud XI, Université de

226

Reactivity initiated accident test series Test RIA 1-4 fuel behavior report. [PWR; BWR  

SciTech Connect

This report presents and discusses results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4, conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. Nine preirradiated fuel rods in a 3 x 3 bundle configuration were subjected to a power burst while at boiling water reactor hot-startup system conditions. The test resulted in estimated axial peak, radial average fuel enthalpies of 234 cal/g UO/sub 2/ on the center rod, 255 cal/g UO/sub 2/ on the side rods, and 277 cal/g UO/sub 2/ on the corner rods. Test RIA 1-4 was conducted to investigate fuel coolability and channel blockage within a bundle of preirradiated rods near the present enthalpy limit of 280 cal/g UO/sub 2/ established by the US Nuclear Regulatory Commission. The test design and conduct are described, and the bundle and individual rod thermal and mechanical responses are evaluated. Conclusions from this final test and the entire PBF RIA Test Series are presented.

Cook, B.A.; Martinson, Z.R.

1984-09-01T23:59:59.000Z

227

Analysis of molten debris freezing and wall erosion during a severe RIA test. [PWR; BWR  

SciTech Connect

A one-dimensional physical model was developed to study the transient freezing of the molten debris layer (a mixture of UO/sub 2/ fuel and zircaloy cladding) produced in a severe reactivity initiated accident in-pile test and deposited on the inner surface of the test shroud wall. The wall had a finite thickness and was cooled along its outer surface by coolant bypass flow. Analyzed are the effects of debris temperature, radiation cooling at the debris layer surface, zircaloy volume ratio within the debris, and initial wall temperature on the transient freezing of the debris layer and the potential melting of the wall. The governing equations of this two-component, simultaneous freezing and melting problem in a finite geometry were solved using a one-dimensional finite element code based on the method of weighted residuals.

El-Genk, M.S.; Moore, R.L.

1980-01-01T23:59:59.000Z

228

THE CALCULATION OF BURNABLE POISON CORRECTION FACTORS FOR PWR FRESH FUEL ACTIVE COLLAR MEASUREMENTS  

SciTech Connect

Verification of commercial low enriched uranium light water reactor fuel takes place at the fuel fabrication facility as part of the overall international nuclear safeguards solution to the civilian use of nuclear technology. The fissile mass per unit length is determined nondestructively by active neutron coincidence counting using a neutron collar. A collar comprises four slabs of high density polyethylene that surround the assembly. Three of the slabs contain {sup 3}He filled proportional counters to detect time correlated fission neutrons induced by an AmLi source placed in the fourth slab. Historically, the response of a particular collar design to a particular fuel assembly type has been established by careful cross-calibration to experimental absolute calibrations. Traceability exists to sources and materials held at Los Alamos National Laboratory for over 35 years. This simple yet powerful approach has ensured consistency of application. Since the 1980's there has been a steady improvement in fuel performance. The trend has been to higher burn up. This requires the use of both higher initial enrichment and greater concentrations of burnable poisons. The original analytical relationships to correct for varying fuel composition are consequently being challenged because the experimental basis for them made use of fuels of lower enrichment and lower poison content than is in use today and is envisioned for use in the near term. Thus a reassessment of the correction factors is needed. Experimental reassessment is expensive and time consuming given the great variation between fuel assemblies in circulation. Fortunately current modeling methods enable relative response functions to be calculated with high accuracy. Hence modeling provides a more convenient and cost effective means to derive correction factors which are fit for purpose with confidence. In this work we use the Monte Carlo code MCNPX with neutron coincidence tallies to calculate the influence of Gd{sub 2}O{sub 3} burnable poison on the measurement of fresh pressurized water reactor fuel. To empirically determine the response function over the range of historical and future use we have considered enrichments up to 5 wt% {sup 235}U/{sup tot}U and Gd weight fractions of up to 10 % Gd/UO{sub 2}. Parameterized correction factors are presented.

Croft, Stephen [Los Alamos National Laboratory; Favalli, Andrea [Los Alamos National Laboratory; Swinhoe, Martyn T. [Los Alamos National Laboratory

2012-06-19T23:59:59.000Z

229

Review of NRC-funded programs on NDE at Pacific Northwest Laboratory. [PWR; BWR  

SciTech Connect

There are currently four major NDT related programs in progress at PNL which are funded by the US Nuclear Regulatory Commission. These programs are Integration of NDE and Fracture Mechanics Program, Development of a Real-Time SAFT-UT System for the Inservice Inspection of LWRs, Acoustic Emission - Flaw Relationships for Inservice Monitoring of Nuclear Reactor Pressure Boundaries, and Steam Generator Integrity Program/Steam Generator Group Project. This paper will discuss and present an overview of each program and highlight the more significant accomplishments obtained to date. All of these programs have been funded for several years and are scheduled for completion in 1985 or 1986.

Doctor, S.R.

1983-04-01T23:59:59.000Z

230

Approach to fluid-mechanics calculations on serial and parallel computer architectures. [PWR; BWR; TRAC code  

SciTech Connect

The Transient Reactor Analysis Code (TRAC) is a large FORTRAN thermal-hydraulics program designed to solve problems involving internal flows in nuclear reactors. The current versions have been designed for a CDC 7600 and CRAY 1 but benchmarks have been run in parallel simulations. This paper will discuss the methods in use, the reason that these techniques are effective, and their extension to parallel machines.

Liles, D.R.; Mahaffy, J.H.; Giguere, P.T.

1983-01-01T23:59:59.000Z

231

Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety  

SciTech Connect

Utilization of burnup credit in criticality safety analysis for long-term disposal of spent nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile material that will be present in the repository. Burnup-credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents (in terms of criticality potential), followed by criticality calculations to assess the value of the effective neutron multiplication factor (k(sub)eff) for the a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models.

DeHart, M.D.

1999-08-01T23:59:59.000Z

232

Calendar of Patent Records  

Science Journals Connector (OSTI)

... in France on Oct. 24, 1832, under the title of Roue a pression universelle et continue . The original turbines for the Niagara Falls Power Company were of ...

1929-10-19T23:59:59.000Z

233

The Honorable Wlliaq~ S. Cohen  

Office of Legacy Management (LM)

Wayne i . M iddlesex Sampling Plant ' Ashland 1 Ashland 2 Seaway Industrial Park Linde Air Products, Niagara Falls- Storage Site' Colonie Bliss & Laughlin Steel . Luckey...

234

Microsoft Word - Remedial Action Program Update.rtf  

Office of Legacy Management (LM)

District Sites Niagara Falls Storage Site Lewiston, NY Ashland 1, Tonawanda, NY Linde Air Products, Tonawanda, NY Seaway Industrial Park, Tonawanda, NY Former Harshow Chemical...

235

The FIonorable W  

Office of Legacy Management (LM)

Wayne i . M iddlesex Sampling Plant * Ashland 1 Ashland 2 Seaway Industrial Par'k Linde Air Products, -Niagara Falls Storage Site' Colonie Bliss & Laughlin Steel . Luckey...

236

The Honorable W  

Office of Legacy Management (LM)

. Wayne . Middlesex Sampling Plant ' Ashland 1 Ashland 2 Seaway Industrial Park Linde Air Products, -Niagara Falls Storage Site' Colonie Bliss & Laughlin Steel . Luckey...

237

"To Feel the Drumming Earth Come Upward": Indigenizing the American Studies Discipline, Field, Movement  

E-Print Network (OSTI)

two of whom (Rob ert K. Thomas and Shirley Hill Witt) identified as American Indians (Oklahoma Cherokee and Akwesasne Mohawk, Wolf Clan, respectively).17 Finally, the issue's contemporary focus contrasted with the emphasis on the past in most...

Clark, D. Anthony Tyeeme; Yetman, Norman R.

2006-03-01T23:59:59.000Z

238

The Energy Technologist  

E-Print Network (OSTI)

The special need for personnel to assist with energy management in the industrial and commercial/institutional sectors has resulted in a new three year, full-time, engineering program at Mohawk College. The knowledge and skills necessary...

Tumber, A. J.; Molczan, T. J.

1981-01-01T23:59:59.000Z

239

Protecting Elm Trees from Elm Bark Beetle on the Texas High Plains  

E-Print Network (OSTI)

is to grow a Texas native. Several new USDA selections and hybrids look promising. Pecan (native) The state tree of Texas does well in most locations in the state. In the South Plains, ?Pawnee,? Carya illinoinensis ?Caddo,? ?Shoshoni,? ?Maramec,? ?Mohawk...

Porter, Patrick; Baugh, Brant A.; Siders, Kerry; Riley, Cherinell; Young, Stanley

2001-06-27T23:59:59.000Z

240

CX-004898: Categorical Exclusion Determination  

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

Gila-Wellton-Mohawk (Structure Maintenance)CX(s) Applied: B1.3Date: 11/05/2010Location(s): Yuma County, ArizonaOffice(s): Western Area Power Administration-Desert Southwest Region

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Page not found | Department of Energy  

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

81 - 21290 of 31,917 results. 81 - 21290 of 31,917 results. Download Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program (March 2012) http://energy.gov/lm/downloads/evaluation-final-radiological-conditions-areas-niagara-falls-storage Download Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Paper presented at the Waste Management 2012 Conference.February 26 through March 1, 2012, Phoenix, Arizona. http://energy.gov/lm/downloads/evaluation-final-radiological-conditions-areas-niagara-falls-storage-site-remediated

242

The Influence of the In-Situ Clad Staining on the Corrosion of Zircaloy in PWR Water Environment  

SciTech Connect

Zircaloy cladding tubes strain in-situ during service life in the corrosive environment of a Pressurized Water Reactor for a variety of reasons. First, the tube undergoes stress free growth due to the preferential alignment of irradiation induced vacancy loops on basal planes. Positive strains develop in the textured tubes along prism orientations while negative strains develop along basal orientations (Reference (a)). Second, early in life, free standing tubes will often shrink by creep in the diametrical direction under the external pressure of the water environment, but potentially grow later in life in the diametrical direction once the expanding fuel pellet contacts the cladding inner wall (Reference (b)). Finally, the Zircaloy cladding absorbs hydrogen as a by product of the corrosion reaction (Reference (c)). Once above the solubility limit in Zircaloy, the hydride precipitates as zirconium hydride (References (c) through (j)). Both hydrogen in solid solution and precipitated as Zirconium hydride cause a volume expansion of the Zircaloy metal (Reference (k)). Few studies are reported on that have investigated the influence that in-situ clad straining has on corrosion of Zircaloy. If Zircaloy corrosion rates are governed by diffusion of anions through a thin passivating boundary layer at the oxide-to-metal interface (References (l) through (n)), in-situ straining of the cladding could accelerate the corrosion process by prematurely breaking that passivating oxide boundary layer. References (o) through (q) investigated the influence that an applied tensile stress has on the corrosion resistance of Zircaloy. Knights and Perkins, Reference (o), reported that the applied tensile stress increased corrosion rates above a critical stress level in 400 C and 475 C steam, but not at lower temperatures nor in dry oxygen environments. This latter observation suggested that hydrogen either in the oxide or at the oxide-to-metal interface is involved in the observed stress effect. Kim et al. (Reference (p)) and Kim and Kim (Reference (q)) more recently investigated the influence that an applied hoop stress has on the corrosion resistance of Zircaloy tubes in a 400 C steam and in a 350 C concentrated lithia water environment. Both of these studies found the applied tensile hoop stress to have no effect on cladding corrosion rates in the 400 C steam environment but to have accelerated corrosion in the lithiated water environment. In both cases, the corrosion acceleration in the lithiated water environment was attributed to the accumulation of the increased hydrogen picked up in the lithiated environment into the tensile regions of the test specimen. Dense hydride rims have been shown, independent of clad strain, to accelerate the corrosion of Zirconium alloys (References (r) and (s)), suggesting that the primary effect of applied stresses on the corrosion of Zircaloy in the above studies is through the accumulation of hydrogen at the oxide-to-metal interface and not through a direct mechanical breakdown of the passivating boundary layer. To further investigate the potential role of in-situ clad straining (or stress) on Zircaloy corrosion rates, two experimental studies were performed. First, several samples that were irradiated with and without an applied stress were destructively examined for the extent of corrosion occurring in strained and nonstrained regions of the test samples. The extent of corrosion was determined, posttest, by metallographic examination. Second, the corrosion process was monitored in-situ using electrochemical impedance spectroscopy on samples exposed out-of-reactor with and without an applied stress. Post test, these autoclave samples were also metallographically examined.

Kammenzind, B.F., Eklund, K.L. and Bajaj, R.

2001-06-21T23:59:59.000Z

243

Assessment of Biasi and Columbia University CHF correlations with GE 3x3 rod bundle experiment. [PWR; BWR  

SciTech Connect

The critical heat flux (CHF), at which a sudden degradation of heat transfer occurs without corresponding decrease in heat generation, is one of the limiting parameters for safe operation of nuclear reactors. Reactor operation beyond the CHF causes a rapid rise in fuel cladding temperature and thus should be avoided to maintain the fuel element integrity. Reactor power limits are therefore set so that a prescribed safety margin below the CHF is maintained. Two CHF correlations are evaluated for reactor core thermal hydraulic analysis: the Biasi correlation and the Columbia University correlation. The BODYFIT-2PE computer code is used for this assessment. The CHF predicted by the BODYFIT-2PE using the two correlations is compared with GE 3x3 rod bundle CHF experiment.

Chen, B.C.J.; Chien, T.H.; Sha, W.T.; Kim, J.H.

1984-01-01T23:59:59.000Z

244

Critical heat flux predictions based on the BODYFIT-2PE computer code and Columbia University CHF correlation. [PWR; BWR  

SciTech Connect

The BODYFIT-2PE (Boundary-Fitted Coordinate, 2-Phase Flow with Partially Elliptic) computer code has been developed and was employed to simulate the critical heat flux experiment in a General Electric 3 x 3 rod bundle by using a CHF correlation recently developed at Columbia University under EPRI sponsorship. CHF predictions are important in analyzing rod bundle performance in nuclear reactor operation. The results of the BODYFIT calculations compared favorably with the experimental measurements.

Chen, B.C.J.; Chien, T.H.; Sha, W.T.; Kim, J.H.

1983-01-01T23:59:59.000Z

245

Optimization of PWR behavior of stress-relieved Zircaloy-4 cladding tubes by improving the manufacturing and inspection process  

SciTech Connect

With the aim of optimizing the basic properties of stress-relieved Zircaloy-4 cladding tubes, particularly those that make it possible to push back the initial technological limits that may be encountered, and of reducing the scatter of those properties and enhancing tube quality, the role of the main parameters involved in manufacturing the ingot, Trex, and cladding tube has been evaluated on an industrial scale. A series of large-sized tube lots were produced under controlled manufacturing conditions, then characterized by out-of-pile test results (short- and long-term corrosion, stress corrosion cracking (SCC), creep, mechanical, and structural properties) on finished tubes. For the investigated parameters (chemical compositions, number of melt, quench rate, accumulated annealing parameter, the {Sigma}A factor, surface condition (outside and inside diameters), and finished tube quality), this role is indeed important but complex due to the highly interactive nature of the variables investigated. Adjustment of the chemical composition within ASTM limits enables generalized corrosion resistance to be enhanced and irradiation growth to be minimized. A significant decrease of the observed scatter in corrosion and mechanical properties is obtained by optimization of the {Sigma}A range, the quenching rate, and the final heat treatment. The optimum seems to be reached for a final treatment at the highest possible temperature compatible with the stress-relieved state, corresponding to an average precipitate size and {Sigma}A. Moreover, by adding anneals upstream in the process, a further increase in this {Sigma}A no longer seems to have a significant effect on generalized corrosion.

Mardon, J.P. [FRAMATOME, Lyon (France). Nuclear Fuel Division; Charquet, D. [CEZUS, Ugine (France); Senevat, J. [ZIRCOTUBE, Paimboeuf (France)

1994-12-31T23:59:59.000Z

246

 

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

energy energy The proposed activity includes implementing the following list of energy efficiency improvements in existing Tribal buildings: * Foam Insulation for the Administration Building * Install new Energy Star oil furnace at the Maintenance Garage * Install new Energy Star oil furnace at the Construction Office * Window replacement at the Family Support Building and Department of Social Services using Energy Star qualified Double Hung Vinyl Windows * Install new Energy Star oil furnace at Terrance House Energy Efficiency and Conservation Block Grants Saint Regis Mohawk Tribe Energy Efficiency Retrofits Saint Regis Mohawk Tribe New York Nov 2, 2009 Jane Summerson Print Form for Records Submit via E-mail Billie Newland Digitally signed by Billie Newland

247

Surplus Facilities Management Program (SFMP) Contract No. DE-AC05-810R20722  

Office of Legacy Management (LM)

'^ l '"17 '^ l '"17 ^' ~/t~ >7~ 6~'1 ~DOE/OR/20722-18 Surplus Facilities Management Program (SFMP) Contract No. DE-AC05-810R20722 NIAGARA FALLS STORAGE SITE ENVIRONMENTAL MONITORING REPORT Calendar Year 1983 July 1984 Bechtel National, Inc. Advanced Technology Division DOE/OR/20722-18 NIAGARA FALLS STORAGE SITE ENVIRONMENTAL MONITORING REPORT CALENDAR YEAR 1983 July 1984 Prepared for U.S. DEPARTMENT OF ENERGY OAK RIDGE OPERATIONS OFFICE Under Contract No. DE-AC05-810R20722 By Bechtel National, Inc. Advanced Technology Division Oak Ridge, Tennessee 37830 Bechtel Job No. 14501 *4:F~~~~ ^ABSTRACT During 1983, an environmental monitoring program was continued at the Niagara Falls Storage Site, a United States Department of Energy (DOE) surplus facility located in Niagara County, New York presently

248

ESTIMATE OF RADIUM-226 CONCENTRATIONS IN RUBBLED PCB WAREHOUSE...  

Office of Legacy Management (LM)

THE NIAGARA FALLS STORAGE SITE MAY 1987 Prepared for UNITED STATES DEPARTMENT OF ENERGY OAK RIDGE OPERATIONS OFFICE Under Contract No. DE-AC05-810R20722 By Bechtel National, Inc....

249

Quantifying the semantics of search behavior before stock market moves  

Science Journals Connector (OSTI)

...administrative, church, slovenia, county, villages, situated...lsu, allegheny, hokkaido, county, markers, syracuse, geograph...shapefiles, niagara, oakwood, oneida, davao, makati, outbuildings...sendaiGeography II Labels rural, county, Geography, cities, Regional...

Chester Curme; Tobias Preis; H. Eugene Stanley; Helen Susannah Moat

2014-01-01T23:59:59.000Z

250

Nikola Tesla  

Science Journals Connector (OSTI)

...Advantages of Polyphase Power The polyphase induction...speed and considerable power. Its insulation and windings were simpler...from fractional horse-power to the 83,000-horsepower...the motor. The Niagara plant helped prove, however...

Kenneth M. Swezey

1958-05-16T23:59:59.000Z

251

,"Plant","Primary Energy Source","Operating Company","Net Summer...  

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

Source","Operating Company","Net Summer Capacity (MW)" 1,"Robert Moses Niagara","Hydroelectric","New York Power Authority",2353.2 2,"Ravenswood","Natural Gas","TC Ravenswood...

252

E-Print Network 3.0 - americium Sample Search Results  

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

thermal response: removal of plutonium, americium... , cesium, and strontium from spent PWR fuel,americium, cesium, and strontium from spent PWR fuel,...

253

E-Print Network 3.0 - americium 241 Sample Search Results  

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

thermal response: removal of plutonium, americium... , cesium, and strontium from spent PWR fuel,americium, cesium, and strontium from spent PWR fuel, recycling...

254

2003 Geological Society of America. For permission to copy, contact Copyright Permissions, GSA, or editing@geosociety.org. Geology; April 2003; v. 31; no. 4; p. 327330; 2 figures; Data Repository item 2003039. 327  

E-Print Network (OSTI)

--Lake Tahoe basin; C--Carson Val- ley; LV--Long Valley; SNFFS--Sierra Nevada frontal fault system; I-- Hat Creek graben; A--Lake Almanor structural basin; MV--Mohawk Valley; HL--Honey Lake fault; T--Independence fault; OV--Owens Valley; IWV--Indian Wells Valley; ECSZ--Eastern California shear zone; DV--Death Valley

Watts, A. B. "Tony"

255

The identity and construction of Wreck Baker: a War of 1812 era Royal Navy frigate  

E-Print Network (OSTI)

for this new command.28 Chauncey immediately undertook to send 170 sailors and marines, 140 ship carpenters, as well as more than 100 cannon and other supplies to 17 Sackets Harbor. The supplies and men traveled up the Hudson River to the Mohawk and from...

Walker, Daniel Robert

2009-06-02T23:59:59.000Z

256

CX-009805: Categorical Exclusion Determination  

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

Maintenance and Wood Pole Replacement along the Gila Wellton Mohawk 161 Kilovolt Transmission Line CX(s) Applied: B1.3 Date: 01/03/2013 Location(s): Arizona Offices(s): Western Area Power Administration-Desert Southwest Region

257

Variation in ecogeographical traits of pecan cultivars and provenances  

E-Print Network (OSTI)

and provenances (i.e., the area of origin of seed). An assessment of leaf anatomical traits of pecan cultivars (Pawnee, Mohawk and Starking Hardy Giant) collected from three locations (Tifton, GA., Chetopa, KS., and Stillwater, OK.) was conducted to provide...

Sagaram, Madhulika

2009-05-15T23:59:59.000Z

258

A review of "The Collected Writings Volume 1: The Voyages" by Pierre-Esprit Radisson, edited by Germaine Warkentin  

E-Print Network (OSTI)

and was soon captured by Mohawks. After living with them long enough to learn the language and earn their trust, Radisson managed to escape. With his newfound knowledge of the geography, language, and cultures of New France, he found work as a guide...

Aune, M. G.

2013-01-01T23:59:59.000Z

259

Centrale nucleaire de production d'electricite. Analyse d'une centrale type P.W.R. du palier 900 MWe.  

E-Print Network (OSTI)

ferm´e, cycle de Hirn-Rankine. F. Ravelet (Lab. DynFluid) Analyse du palier 900 MWe 10 octobre 2013 2Fluid) Analyse du palier 900 MWe 10 octobre 2013 1 / 13 #12;Introduction Eau ordinaire, cycle indirect

Ravelet, Florent

260

Multivariable analysis of the effects of Li, H{sub 2}, and pH on PWR primary water stress corrosion cracking. Final report  

SciTech Connect

The effects of Li, pH and H, on primary water stress corrosion cracking (PWSCC) of Alloy 600 were investigated for temperatures between 320 and 330{degrees}C. Specimens included in the study were reverse U-bends (RUBs) made from several different heats of Alloy 600. The characteristic life, {eta}, which represents the time until 63.2% of the population initiates PWSCC, was computed using a modified Weibull statistical analysis algorithm and was analyzed for effects of the water chemistry variables previously mentioned. It was determined that the water chemistry variables are less sensitive than the metallurgical characteristics defined by the heat, heat treatment and initial stress state of the specimen (diameter and style of RUB); the maximum impact of chemistry effects was 0.13 to 0.59 standard deviations compared to a range of three (3) standard deviations for all variables. A first-order model was generated to estimate the effect of changes in pH, Li and H, concentrations on the characteristic life. The characteristic time to initiate cracks, {eta}, is not sensitive to Li and H{sub 2} concentrations in excess of 3.5 ppm and 25 ml/kg, respectively. Below these values, (1) {eta} decreases by {approximately}20% when [Li] is increased from 0.7 to 3.5 ppm; (2) {eta} decreases by {approximately}9% when [H{sub 2}] is increased from 13.1 to 25.0 ml/kg; and (3) {eta} decreases by {approximately}14% when pH is increased from 7.0 to 7.4, in each case holding the other two variables constant.

Eason, E.D.; Merton, A.A.; Wright, J.E.

1996-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Experimental investigations of uncovered-bundle heat transfer and two-phase mixture-level swell under high-pressure low heat-flux conditions. [PWR  

SciTech Connect

Results are reported from a series of uncovered-bundle heat transfer and mixture-level swell tests. Experimental testing was performed at Oak Ridge National Laboratory in the Thermal Hydraulic Test Facility (THTF). The THTF is an electrically heated bundle test loop configured to produce conditions similar to those in a small-break loss-of-coolant accident. The objective of heat transfer testing was to acquire heat transfer coefficients and fluid conditions in a partially uncovered bundle. Testing was performed in a quasi-steady-state mode with the heated core 30 to 40% uncovered. Linear heat rates varied from 0.32 to 2.22 kW/m.rod (0.1 to 0.68 kW/ft.rod). Under these conditions peak clad temperatures in excess of 1050 K (1430/sup 0/F) were observed, and total heat transfer coefficients ranged from 0.0045 to 0.037 W/cm/sup 2/.K (8 to 65 Btu/h.ft/sup 2/./sup 0/F). Spacer grids were observed to enhance heat transfer at, and downstream of, the grid. Radiation heat transfer was calculated to account for as much as 65% of total heat transfer in low-flow tests.

Anklam, T. M.; Miller, R. J.; White, M. D.

1982-03-01T23:59:59.000Z

262

Design concept and testing of an in-bundle gamma densitometer for subchannel void fraction measurements in the THTF electrically heated rod bundle. [PWR  

SciTech Connect

A design concept is presented for an in-bundle gamma densitometer system for measurement of subchannel average fluid density and void fraction in rod or tube bundles. This report describes (1) the application of the design concept to the Thermal-Hydraulic Test Facility (THTF) electrically heated rod bundle; and (2) results from tests conducted in the THTF.

Felde, D. K.

1982-04-01T23:59:59.000Z

263

Development of a generalized correlation for phase-velocity measurements obtained from impedance-probe pairs in two-phase flow systems. [PWR  

SciTech Connect

A flag type electrical impedance probe has been developed at the Oak Ridge National Lab (ORNL) to measure liquid- and vapor-phase velocities in steam-water mixtures flowing through rod bundles. Measurements are made by utilizing the probes in pairs, installed in line, parallel to the flow direction, and extending out into the flow channel. The present study addresses performance difficulties by examining from a fundamental point of view the two-phase flow system which the impedance probes typically operate in. Specifically, the governing equations (continuity, momentum, energy) were formulated for both air-water and steam-water systems, and then subjected to a scaling analysis. The scaling analysis yielded the appropriate dimensionless parameters of significance in both kinds of systems. Additionally, with the aid of experimental data obtained at ORNL, those parameters of significant magnitude were established. As a result, a generalized correlation was developed for liquid and vapor phase velocities that makes it possible to employ the impedance probe velocity measurement technique in a wide variety of test configurations and fluid combinations.

Hsu, C.T.; Keshock, E.G.; McGill, R.N.

1983-01-01T23:59:59.000Z

264

CX-000219: Categorical Exclusion Determination | Department of Energy  

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

9: Categorical Exclusion Determination 9: Categorical Exclusion Determination CX-000219: Categorical Exclusion Determination United States Army Corps Niagara River, New York Small Hydropower CX(s) Applied: A9, A11 Date: 11/30/2009 Location(s): Niagara River, New York Office(s): Energy Efficiency and Renewable Energy, Golden Field Office The United States Army Corps of Engineering (USACE) would demonstrate the feasibility of low-head hydropower generation along the Niagara River. The work would take place at the USACE offices in Buffalo, New York and Portland, Oregon. The project consists of two steps, Reconnaissance Analysis and Feasibility Study. DOCUMENT(S) AVAILABLE FOR DOWNLOAD CX-000219.pdf More Documents & Publications Dams and Energy Sectors Interdependency Study, September 2011 EIS-0145: Final Environmental Impact Statement

265

# Energy Measuremenfs Group  

Office of Legacy Management (LM)

ri EECE ri EECE # Energy Measuremenfs Group SUMMARY REPORT . AiRIAL R4DIOLOGICAL SURVEY - NIAGARA FALLS AREA NIAGARA FALLS, NEh' YORK DATE OF SURVEY: SEPTEMBER 1979 APPROVED FOR DISTRIBUTION: P Stuart, EC&G, Inc. . . Herbirt F. Hahn, Department of Energy PERFDRflED BY EGtf, INC. UNDER CONTRACT NO. DE-AHO&76NV01163 WITH THE UNITED STATES DEPARTMENT OF ENERGY II'AFID 010 November 30, 1979 - The Aerial Measurements System (A%), operated by EC&t, Inc< for the Un i ted States Department of Energy, was used during November 1976 to conduct an exploratory aerial radiological survey in-the greater Niagara Fails area. The purpose of that survey was to identify locations having concentrations of terrestrial radioactivity not typical of the radiation

266

PDF Document (3851k)  

Office of Legacy Management (LM)

REFERENCES REFERENCES B 1234 1. Bechtel National, Inc. Engineering Evaluation of Alternatives for the Disposition of Niagara Falls Storage Site, Its Residues and Wastes, DOE/OR/20722-1, prepared for U.S. Department of Energy, Oak Ridge Operations, Oak Ridge, TN January 1984. 2. Aerospace Corporation. Background and Resurvey Recommendations for the Atomic Energy Commission Portion of the Lake Ontario Ordinance Works, ATR-82 (7963-04)-1, prepared for U.S. Department of Energy, washington, DC, 1982. 3. Battelle Columbus Laboratories. A Comprehensive Characterization and Hazard Assessment of the DOE Niagara Falls Storage Site, BMI-2074, Columbus, OH, 1981. 4. Battelle Columbus Laboratories. Preliminary Smelting of Afrimet Residues, Columbus, OH, 1983. 5. Bechtel National, Inc. Geologic Report, Niagara Falls Storage Site, DOE/OR/20722-8, prepared for the U.S. Department of

267

/ J8Y.17 I E(DE86008418)  

Office of Legacy Management (LM)

/,, DOE/EIS-0109F /,, DOE/EIS-0109F / J8Y.17 I E(DE86008418) O&4 .48 FINAL Environmental Impact Statement Long-Term Management of the Existing Radioactive Wastes and Residues at the Niagara Falls Storage Site ( Se(42Ho- /,02.F7fro^' t^ K- A~-) April 1986 U. S. Department of Energy Washington, D.C. 20585 DOE/EIS-0109F (DE86008418) Distribution Category UC-70A FINAL ENVIRONMENTAL IMPACT STATEMENT LONG-TERM MANAGEMENT OF THE EXISTING RADIOACTIVE WASTES AND RESIDUES AT THE NIAGARA FALLS STORAGE SITE April 1986 U.S. Department of Energy Washington, D.C. COVER SHEET FINAL ENVIRONMENTAL IMPACT STATEMENT LONG-TERM MANAGEMENT OF EXISTING RADIOACTIVE WASTES AND RESIDUES AT THE NIAGARA FALLS STORAGE SITE a) Lead Agency: U.S. Department of Energy (DOE) b) Proposed Action: Long-term stabilization and control of existing radioactive wastes and residues

268

Microsoft Word - S06246_VP_Report  

Office of Legacy Management (LM)

Formerly Utilized Sites Formerly Utilized Sites Remedial Action Program Niagara Falls Storage Site Vicinity Properties, New York: Review of Radiological Conditions at Six Vicinity Properties and Two Drainage Ditches October 2010 LMS/NFS/S06246 This page intentionally left blank LMS/NFS/S06246 Formerly Utilized Sites Remedial Action Program Niagara Falls Storage Site Vicinity Properties, New York: Review of Radiological Conditions at Six Vicinity Properties and Two Drainage Ditches October 2010 This page intentionally left blank U.S. Department of Energy NFSS Vicinity Property Report October 2010 Doc. No. S06246 Page i Contents Abbreviations .................................................................................................................................. v

269

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINFA;RIOflH;EPORT  

Office of Legacy Management (LM)

ELIMINFA;RIOflH;EPORT ELIMINFA;RIOflH;EPORT FORMER ELECTRO METALLURGICAL COMPANY NIAGARA FALLS, NEW YORK U.S. DEPARTMENT OF ENERGY OFFICE OF NUCLEAR ENERGY OFFICE OF REMEDIAL ACTION AND WASTE TECHNOLOGY DIVISION OF FACILITY AND SITE DECOMMISSIONING PROJECTS CONTENTS INTRODUCTION BACKGROUND Site Function Site Description Radiological History and Status ELIMINATION ANALYSIS SUMMARY OF FINDINGS REFERENCES Page 1 : 3 5 7 8 ELIMINATION REPORT FORMER ELECTRO METALLURGICAL COMPANY NIAGARA FALLS, NEW YORK INTRODUCTION From 1942 through 1953, the Electra Metallurgical' Company ("Electromet"), a subsidiary of Union Carbide and Carbon Corporation (now Umetco Minerals Corporation, a subsidiary of Union Carbide Corporation) performed work with radioactive materials under contract to the Manhattan

270

Categorical Exclusion Determinations: Office of Energy Efficiency and  

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

2, 2009 2, 2009 CX-000172: Categorical Exclusion Determination Minnesota City St. Paul CX(s) Applied: A9, A11, B5.1 Date: 11/02/2009 Location(s): St. Paul, Minnesota Office(s): Energy Efficiency and Renewable Energy, Golden Field Office November 2, 2009 CX-000035: Categorical Exclusion Determination Washington's Energy Efficiency Retrofits CX(s) Applied: B5.1 Date: 11/02/2009 Location(s): Washington, Utah Office(s): Energy Efficiency and Renewable Energy November 2, 2009 CX-000034: Categorical Exclusion Determination Saint Regis Mohawk Tribe Energy Efficiency Retrofits CX(s) Applied: B5.1, B2.5 Date: 11/02/2009 Location(s): New York Office(s): Energy Efficiency and Renewable Energy November 2, 2009 CX-000033: Categorical Exclusion Determination Saint Regis Mohawk Tribe Energy Efficiency and Conservation Programs for

271

Microsoft Word - EMDA_Volume_5_-_Cable_volume_Final.docx  

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

... 71 Table 7.5. Reactor building dose for a Westinghouse ice condenser PWR ... 72 Table A.1: Summary of...

272

British Association Meeting in Toronto  

Science Journals Connector (OSTI)

... the centre of the city, and within less than five minutes' walk from the electric car line which communicates with all parts of the city, the selection offers every convenience ... Company, which ascend the Niagara River to a point connected with the Falls by two electric car lines. This excursion may be made on any day, and an opportunity will be ...

A. B. MACALLUM

1897-02-04T23:59:59.000Z

273

Tectonic and Eustatic Signals in the Sequence Stratigraphy of the Upper Devonian Canadaway Group, New York State  

Science Journals Connector (OSTI)

...global sea level curve bears little resem-blance to the relative sea level curve for Allegany...final report: Albany, New York State Energy Research and Development Authority, 2106...1970, Geologic map of New York, Niagara sheet; New York State Museum and Science Service...

Gerald J. Smith; Robert D. Jacobi

274

Snapping Turtles (Chelydra serpentina) as Bioindicators in Canadian Areas of Concern in the Great Lakes Basin. 1. Polybrominated Diphenyl Ethers, Polychlorinated Biphenyls, and Organochlorine Pesticides in Eggs  

Science Journals Connector (OSTI)

Eggs from Lyons Creek (Niagara River AOC) reflected a local PCB source over a range of 7.5 km (3.2 ? 10.8) from the Welland Canal. ... AOC ... Mean ?PBDEs concentrations in turtle eggs ranged from 3.8 ng/g ww (Algonquin Park) to 73.3 ng/g (Hamilton Harbour AOC; Figure 2). ...

S. R. de Solla; K. J. Fernie; R. J. Letcher; S. G. Chu; K. G. Drouillard; S. Shahmiri

2007-10-04T23:59:59.000Z

275

Mining Large Graphs And Streams Using Matrix And Tensor Tools  

E-Print Network (OSTI)

RESULTS The graphs at right show overall variability distribution estimated for the Pentium D 800 where a core no longer works properly. In the Sun T1 Niagara cores this is done with a built-in- self processors we record the temperature at which the failure occurred and adjust to the frequencies

Kolda, Tamara G.

276

Recent Changes in Greenland & Antarctica  

E-Print Network (OSTI)

lake drainage her height ?5 = old water level Lake used to be 8m (24 ft) deep Flow rate Niagara Falls depth: Volume of water in lake over time Field project: If meltwater reaches the bed, does it affect ice the ability to make accurate projections (IPCC, 2007). From ice sheets /glaciers: 0.04 to 0.23 meters #12;IPCC

Bitz, Cecilia

277

New Method Gives Precise Control in Air Conditioning  

Science Journals Connector (OSTI)

The Niagara "Controlled Humidity Method" is a new system of air conditioning giving complete control of temperature and relative humidity, holding constant conditions or varying them at the will of the user. ... A condition of 15 grains o f moisture per pound of air at 85 dcg. ...

1950-01-09T23:59:59.000Z

278

New Method Gives Precise Control in Air Conditioning  

Science Journals Connector (OSTI)

The Niagara "Controlled Humidity Method" is a new system of air conditioning giving complete control of temperature and relative humidity, holding constant conditions or varying them at the will of the user. ... A condition of 15 grains of moisture per pound of air at 85 deg. ...

1950-02-13T23:59:59.000Z

279

PLEAEERUSH ANALYTICAL DA-~-A SHEET  

Office of Legacy Management (LM)

for F Alpham Remarks NIAGARA pALI+S* N.Y. U Beta Bldg. 103 - furnace room - -NO, Ra Oil PH Be Th Sample No. Hour Sample Description I I I--- R ) T 1 Q I I I 7392 1100 GA...

280

operation_tbl1_October_2011M.xlsx  

Gasoline and Diesel Fuel Update (EIA)

2009 Summer 2009 Summer Capacity 2010 Annual Generation Capacity Factor Net MW(e) 1 Net MWh 2 Percent 3 Arkansas Nuclear One 1 AR PWR 842 6,607,090 90 Arkansas Nuclear One 2 AR PWR 993 8,415,588 97 Beaver Valley 1 PA PWR 892 7,119,413 91 Beaver Valley 2 PA PWR 885 7,874,151 102 Braidwood Generation Station 1 IL PWR 1,178 9,196,689 89 Braidwood Generation Station 2 IL PWR 1,152 10,003,246 99 Browns Ferry 1 AL BWR 1,066 8,072,298 86 Browns Ferry 2 AL BWR 1,104 8,842,513 91 Browns Ferry 3 AL BWR 1,105 7,856,326 81 Brunswick 1 NC BWR 938 6,808,445 83 Brunswick 2 NC BWR 920 8,000,043 99 Byron Generating Station 1 IL PWR 1,164 10,337,288 101 Byron Generating Station 2 IL PWR 1,136 9,518,424 96 Callaway 1 MO PWR 1,190 8,996,033 86 Calvert Cliffs Nuclear Power Plant 1 MD PWR 855 6,755,043 90 Calvert Cliffs Nuclear Power Plant 2 MD PWR 850 7,238,905 97 Catawba 1 SC

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Warped Space Issue 29/30  

E-Print Network (OSTI)

and the Bandersnatchi Press have moved to 2100 N. Halsted, Third Floor, Chicago, IL, 60614. Steve has been in the process of moving and hopes to catch up real soon now on answering all orders and inquiries. The album (Leslie Fish's) and filksong booklet should be out.... But it's done with flair, it hangs to gether. It is for enjoyment. "To the Water and the Wild" Spock and an ersatz unicorn? Amazing how a Vulcan who goes into Pon Farr as often as he does can remain a virgin ... Leslie Fish, 1906 N. Mohawk, rear house...

Multiple Contributors

1977-01-01T23:59:59.000Z

282

Techno-economic evaluation of waste lube oil re-refining in Saudi Arabia  

SciTech Connect

About 80 million gallons of automotive lubricating oils are sold in Saudi Arabia. Much of this oil, after use, is actually contributing to the increased pollution of land because of indiscriminate dumping. Any scheme of secondary use of the waste lube oils would be of interest both for conservation of energy resources and for protection of environment. This paper discusses the secondary use for the used automotive lubricating oils. Process technology of Meinken, Mohawk and KTI were selected for the techno-economic feasibility study for refining used oil. Profitability analysis of each process is worked out and the results are compared.

Ali, M.F.; Hamdan, A.J.; Rahman, F. [King Fahd Univ. of Petroleum & Minerals, Dhahran (Saudi Arabia)

1995-12-31T23:59:59.000Z

283

U.S. Spent Nuclear Fuel Data as of December 31,2002 -Table 2  

Gasoline and Diesel Fuel Update (EIA)

6 6 Table 1 | Table 3 Table 2. Nuclear Power Plant Data as of December 31, 2002 Reactor Name State Reactor Type Reactor Vendor a Core Size (number of assemblies) Startup Date (year)b License Expiration (year) Actual Retirement (year) Arkansas Nuclear 1 AR PWR B&W 177 1974 2034 Arkansas Nuclear 2 AR PWR CE 177 1978 2018 Beaver Valley 1 PA PWR WE 157 1976 2016 Beaver Valley 2 PA PWR WE 157 1987 2027 Big Rock Point MI BWR GE 84 1962 2000 1998 Braidwood 1 IL PWR WE 193 1987 2026 Braidwood 2 IL PWR WE 193 1988 2027 Browns Ferry 1 AL BWR GE 764 1973 2013 Browns Ferry 2 AL BWR GE 764 1974 2014 Browns Ferry 3 AL BWR GE 764 1976 2016 Brunswick 1 NC BWR GE 560 1976 2016

284

DOE - Office of Legacy Management -- Love Canal - NY 24  

Office of Legacy Management (LM)

Love Canal - NY 24 Love Canal - NY 24 FUSRAP Considered Sites Site: LOVE CANAL (NY.24 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None NY.24-1 Location: Region running from Old Military Road from the 16-acre rectangular piece of land in the southeast corner of Niagara Falls into the Township of Lewiston , Niagara Falls , New York NY.24-3 Evaluation Year: 1987 NY.24-1 Site Operations: Chemical storage and disposal. NY.24-1 NY.24-3 Site Disposition: Eliminated - No residual radioactive material found NY.24-1 Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None Indicated Radiological Survey(s): Yes NY.24-5 Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to LOVE CANAL

285

Prepared  

Office of Legacy Management (LM)

Prepared Prepared by Oak Ridge Associated Universities Prepared for Division of Remedial Action Projects U.S. Department of Energy COMPREHENSIVE RADIOLOGICAL SURVEY OFF-SITE PROPERTYM NIAGARA FALLS STORAGE SITE LEWISTON, NEW YORK B.P. ROCCO Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT May 1983 B.P. Rocco FINAL REPORT Prepared for A.M. pitt T.J. Sowell C.F. Weaver T.S. Yoo Project Staff Prepared by J.D. Berger R.D. Condra R.C. Gosslee J.A. Mattina OFF-SITE PROPERTY M NIAGARA FALLS STORAGE SITE LEWISTON, NEW YORK CO~WREHENSIVE RADIOLOGICAL SURVEY Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37830 U.S. Department of Energy as part of the Formerly Utilized Sites -- Remedial Action Program May 1983 -- til - This

286

Natural Gas - U.S. Energy Information Administration (EIA) - U.S. Energy  

Gasoline and Diesel Fuel Update (EIA)

9, 2013 | Release Date: October 10, 9, 2013 | Release Date: October 10, 2013 | Next Release: October 17, 2013 Previous Issues Week: 01/19/2014 (View Archive) JUMP TO: In The News | Overview | Prices/Demand/Supply | Storage In the News: Northeast net imports from Canada plummet, driven by export growth at Niagara Falls Northeast U.S. net natural gas imports from Canada declined by more than half for the first nine months of 2013 compared to the same period in 2012, from 939 million cubic feet per day (MMcf/d) to 438 MMcf/d, according to U.S. Energy Information Administration (EIA) calculations using data from Bentek Energy LLC. Most of this 502 MMcf/d decrease resulted from a 433 MMcf/d decrease in net imports at Kinder Morgan's Tennessee Gas Pipeline (TGP) and TransCanada Pipeline's border crossing between Niagara Falls,

287

DOE - Office of Legacy Management -- Titanium Alloys Manufacturing Co Div  

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

Titanium Alloys Manufacturing Co Titanium Alloys Manufacturing Co Div of National Lead of Ohio - NY 41 FUSRAP Considered Sites Site: TITANIUM ALLOYS MANUFACTURING CO., DIV. OF NATIONAL LEAD OF OHIO (NY.41) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Titanium Alloy Metals Titanium Alloy Manufacturing Division Titanium Alloy Manufacturing (TAM) Division of National Lead Company The Titanium Pigment Co. NL Industries ICD/Niagara NY.41-1 NY.41-2 NY.41-3 Location: Niagara Falls , New York NY.41-1 Evaluation Year: 1993 NY.41-4 Site Operations: Produced commercial grade zirconium tetrachloride; conducted research and development relating to solid metallic hydride moderators; and experimental work relative to the conversion of thorium scrap to anhydrous tetrachloride. NY.41-5

288

Page not found | Department of Energy  

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

81 - 19090 of 26,764 results. 81 - 19090 of 26,764 results. Download CX-000219: Categorical Exclusion Determination United States Army Corps Niagara River, New York Small Hydropower CX(s) Applied: A9, A11 Date: 11/30/2009 Location(s): Niagara River, New York Office(s): Energy Efficiency and Renewable Energy, Golden Field Office http://energy.gov/nepa/downloads/cx-000219-categorical-exclusion-determination Download CX-000098: Categorical Exclusion Determination Churchill County's Heating, Ventilating, and Air Conditioning Retrofit CX(s) Applied: B5.1 Date: 11/24/2009 Location(s): Churchill County, Nevada Office(s): Energy Efficiency and Renewable Energy http://energy.gov/nepa/downloads/cx-000098-categorical-exclusion-determination Download CX-000091: Categorical Exclusion Determination Cheektowaga's Installation of Photovoltaic Solar Panels

289

Page not found | Department of Energy  

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

01 - 610 of 29,416 results. 01 - 610 of 29,416 results. Download Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Paper presented at the Waste Management 2012 Conference.February 26 through March 1, 2012, Phoenix, Arizona. http://energy.gov/lm/downloads/evaluation-final-radiological-conditions-areas-niagara-falls-storage-site-remediated Download EIS-0463: Amended Notice of Intent To Modify the Scope of the EIS and Conduct Additional Public Scoping Meetings, Notice of Floodplains and Wetlands Involvement Department of Energy - Presidential Permit Application for Northern Pass Transmission, New Hampshire http://energy.gov/nepa/downloads/eis-0463-amended-notice-intent-modify-scope-eis-and-conduct-additional-public-scoping

290

ORO-845 REV.  

Office of Legacy Management (LM)

ORO-845 ORO-845 REV. 1 SUPPLEMENT Surplus Facilities Management Program (SFMP) Contract No. DE-AC05-810R20722 NIAGARA FALLS STORAGE SITE PROJECT MANAGEMENT INFORMATION SUPPLEMENT Prepared by U.S. DEPARTMENT OF ENERGY OAK RIDGE OPERATIONS OFFICE .....- - - - - - - - - - LEGAL NonCE - - - - - - - - - - - - . This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Department of Energy, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. I I I I I " +..'."~ I I * * * * * * * * * * * * ORO-845 Rev. 1 NIAGARA FALLS

291

IE  

Office of Legacy Management (LM)

/ / / / / ORAU 89/J-178 IE Prepared by Oak Ridge Associated VERIFICATION Universities OF Prepared for the Division of 1983 AND 1984 REMEDIAL ACTIONS Facility and Site Decommissioning NIAGARA FALLS STORAGE SITE I P rojets VICINITY PROPERTIES U.S. Department of Energy LEWISTON, NEW YORK I~~~| ~S. A. WICAL, M. R. LANDIS, and A. J. BOERNER I I I I I Environmental Survey and Site Assessment Program l3*~~~~~~~ ~~~Energy/Environment Systems Division FINAL REPORT DECEMBER 1989 I VERIFICATION OF 1983 AND 1984 REMEDIAL ACTIONS NIAGARA FALLS STORAGE SITE VICINITY PROPERTIES LEWISTON, NEW YORK 3~~ ~~~~~~1 ~Prepared by S.A. Wical, M.R. Landis, and A.J. Boerner Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117

292

OAK RIDGE NATIONAL LABORATORY RESULTS OF RADIOLOGICAL  

Office of Legacy Management (LM)

2 7% 2 7% d &y / 7 ORNL/TM- 10076 OAK RIDGE NATIONAL LABORATORY RESULTS OF RADIOLOGICAL ~-T-m -~=- -~ w-~- -"" * ,<.~- ~w&$UREMENTs: TAKEN IN THE NIAGARA FALLS, NEW YORK, AREA (NF002) J. K. Williams B. A. Berven ~.~~;:;-~~~ ~. -,' - ~~ 7, OPERATED BY MARTIN MARIDTA ENERGY SYSTEMS, INC, FOR THE UNITED STATES DEPARTMENT OF ENERGY --... ORNL/TM-10076 HEALTH AND SAFETY RESEARCH DIVISION Nuclear and Chemical Waste Programs (Activity No. AH 10 05 00 0; ONLWCOI) RESULTS OF RADIOLOGICAL MEASUREMENTS TAKEN IN THE NIAGARA FALLS, NEW YORK, AREA (NFOO2) J. K. Williams* and B. A. Berven *Biology Division Date Published November 1986 Investigation Team B. A. Berven - RASA Program Manager W. D. Cottrell - FUSRAP Project Director W. H. Shinpaugh - Field Survey Supervisor

293

I I~ I~~" Oak Ridge As.slJj:iatea I Universities Prepared  

Office of Legacy Management (LM)

I~ I~ I~~" Oak Ridge As.slJj:iatea I Universities Prepared for Division of ;' ' 'I Remedial A'ci';on Projects " , : I u.S. Department of Ener'1N I '. I I 'I I I I I [(-24194 COMPREHENSIVE RAOIOLOGYe.AL~\iAVEY , . ~,- ... . -" . OFF-SITE PROPE~tV,i~~ , . NIAGARA FALLS STORA~ESJt~; LEWISTON, NEW YORK A. J. BOERNER Radiological Site Assessment Program Manpower Educatiou t Research, and Training Division FINAL REPORT March 1984 . .. '~-".".'''~'''.;:-- .. ~ -, , I A. J. Boerner FINAL REPORT March 1984 W.O. Helton T.J. Sowell C.F. Weaver B.S. Zacharek Prepared by Project Staff Prepared for OFF-SITE PROPERTY K NIAGARA FALLS STORAGE SITE LEWISTON, NEW YORK J.D. Berger M.J. Brennan R.D. Condra P.W. Frame R.C. Goss1ee COMPREHENSIVE RADIOLOGICAL SURVEY Radiological Site Assessment Program

294

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT  

Office of Legacy Management (LM)

FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT FOR OCCIDENTAL CHEMICAL CORPORATION ( FORMER HOOKER ELECTROCHEMICAL COMPANY ) NIAGARA FALLS, NEW YORK SEP 30 1985 Department of Energy Office of Nuclear Energy Office of Remedial Action and Waste Technology Division of Facility and Site Decommissioning Projects ELIMINATION REPORT FOR OCCIDENTAL CHEMICAL CORPORATION (FORMER HOOKER ELECTROCHEMICAL COMPANY) L NIAGARA FALLS, NEW YORK- INTRODUCTION The Department ' of Energy (DDE), Office of Nuclear Energy, Office of Remedial Action and Waste Technology, Division of Facility and Site Decommissioning Projects (and/or the predecessor agencies, offices, and divisions), has reviewed the past activities of the Manhattan Engineer District (MED) and the Atomic Energy Commission (MED/AEC) at

295

Steuben Rural Elec Coop, Inc | Open Energy Information  

Open Energy Info (EERE)

Rural Elec Coop, Inc Rural Elec Coop, Inc Jump to: navigation, search Name Steuben Rural Elec Coop, Inc Place New York Utility Id 18102 Utility Location Yes Ownership C NERC Location NPCC NERC NPCC Yes ISO NY Yes Operates Generating Plant Yes Activity Generation Yes Activity Buying Transmission Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Electric Thermal Storage-TOU Commercial Electric Thermal Storage-TOU(Niagara Hydro Plus Program Participant) Commercial Industrial Industrial Industrial(Niagara Hydro Plus Program Participant) Industrial Residential Seasonal Residential

296

Oak Ridge Associated  

Office of Legacy Management (LM)

])\D ])\D Oak Ridge ,.(\\~ Associated ru~ Universities Post Office Box 11 7 Oak Ridge, Tennessee 37831-0117 October 21, 1986 Manpower Education, Research, and Training Division Mr. Edward G. Delaney, Director Division of Facility and Site Decommissioning Projects Office of Nuclear Energy U.S. Department of Energy Washington, DC 20545 Subject: VERIFICATION OF NIAGARA FALLS STORAGE SITE VICINITY PROPERTIES - 1983/1984 REMEDIAL ACTIONS Dear Mr. Delaney: Oak Ridge Associated Universities Niagara Falls Storage Site, which were remediated during the 1983 and 1984 construction seasons. Based on the results of document reviews, confirmatory sample analyses, and independent site surveys it is ORAU's opinion that the remedial actions have been effective in meeting the DOE radiological

297

OE/EV-0005/2 Formerly Utilized MED/AEC Sites Remedial Action Program  

Office of Legacy Management (LM)

OE/EV-0005/2 OE/EV-0005/2 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Hooker Chemical Company Niagara Falls, New York January 1977 Final Report Prepared for U.S. Department of Energy Division of Environmental Control Technology Washington, D.C. 20545 DOE/EV-0005/2 UC-70 Formerly Utilized MED/AEC Sites Remedial Action Program Radiological Survey of the Hooker Chemical Company Niagara Falls, New York January 1977 Final Report Prepared for U.S. Department of Energy Division of Environmental Control Technology Washing-ton, D.C. 20545 Under Contract No. W-7405-ENE-26 Oak Ridge National Laboratory Oak Ridge, Tennessee 3783C NOTICE This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United

298

Microsoft Word - NY.17-16.doc  

Office of Legacy Management (LM)

Printed with soy ink on recycled paper Printed with soy ink on recycled paper Department of Energy Washington, DC 20585 Ms. Judith Leithner Project Manager, Buffalo District U.S. Army Corps of Engineers Department of the Army 1776 Niagara Street Buffalo, New York 14207-3199 Dear Ms. Leithner: This is in reference to the Niagara Falls Storage Site (NFSS) Vicinity Properties E', E, and G located in Lewiston, New York. In accordance with the terms of the March 1999 Memorandum of Understanding (MOU) between the Department of Energy (DOE) and the U.S. Army Corps of Engineers (U.S. ACE), DOE is in the process of completing closure documentation for several sites remediated by DOE prior to assignment of the Formerly Utilized Sites Remedial Action Program (FUSRAP) to the U.S. ACE. Under contract to the U.S. ACE (U.S. ACE Contract

299

Canrom Photovoltaics Inc | Open Energy Information  

Open Energy Info (EERE)

Canrom Photovoltaics Inc Canrom Photovoltaics Inc Jump to: navigation, search Name Canrom Photovoltaics Inc Place Niagara Falls, New York Zip 14305 Sector Solar Product Developer of a thin-film CdTe based solar electric module. References Canrom Photovoltaics Inc[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Canrom Photovoltaics Inc is a company located in Niagara Falls, New York . References ↑ "Canrom Photovoltaics Inc" Retrieved from "http://en.openei.org/w/index.php?title=Canrom_Photovoltaics_Inc&oldid=343203" Categories: Clean Energy Organizations Companies Organizations Stubs What links here Related changes Special pages Printable version Permanent link Browse properties

300

OBITUARIES  

Science Journals Connector (OSTI)

Born in Decatur, Ill., Herring received a B.S. in chemistry from the University of Illinois, Urbana-Champaign, in 1942, and an M.S. in chemical engineering from Pennsylvania State University in 1946. ... At DuPont, he worked as a process design engineer at plants in Wilmington, Del., and Niagara Falls, N.Y., before being transferred to Newark, Del., where he focused on market research. ... Robert J. Huoni, 93, a retired Dow Chemical researcher, died on Sept. 19. ...

2011-12-19T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Suit filed to block sale of Love Canal homes  

Science Journals Connector (OSTI)

Suit filed to block sale of Love Canal homes ... New York's attorney general has filed suit against the Love Canal Area Revitalization Agency and its chairman to block the sale or lease of six of the 450 homes in Ring 3, the so-called Emergency Declaration Area around the Love Canal hazardous waste dump in Niagara Falls. ... Folly or not, in May the revitalization agency decided that no harm would result from the rehabilitation and reoccupancy of the six homes. ...

1985-07-15T23:59:59.000Z

302

Westinghouse-CASL team wins major computing award for reactor...  

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

throughout the world. In 1957 the company supplied the world's first PWR in Shippingport, Pennsylvania. Today, Westinghouse technology is the basis for approximately...

303

CILC Studies with Comparative Analysis to Existing Plants L2...  

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

Materials Performance Optimization Focus Area NDA non-disclosure agreement NPP nuclear power plant PWR pressurized water reactor Re Reynolds number STAR-CCM+ Simulation of...

304

Computational evaluation of two reactor benchmark problems.  

E-Print Network (OSTI)

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

Cowan, James Anthony

2012-01-01T23:59:59.000Z

305

Object Management Systems  

E-Print Network (OSTI)

Object-Oriented Database Management Systems for EngineeringR. Cassel. Distribution Management Systems: Functions and8-PWR 1988. Network Management Systems 52 Subodh Bapat.

Gollu, Aleks Ohannes

1995-01-01T23:59:59.000Z

306

Microsoft Word - NURETH14-337 Ver11.docx  

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

become available, further PWR rod bundle testing is being performed to obtain advanced data which has high spatial and temporal resolution. This paper presents the advanced...

307

TRACE Code Validation for Natural Circulation During Small Break LOCA in EPR-Type Reactor.  

E-Print Network (OSTI)

?? The PWR PACTEL test facility was built in Lappeenranta (Finland) to gain experience in thermal-hydraulics behavior of vertical steam generators used by EPR (European (more)

Bertran Morancho, Joan

2011-01-01T23:59:59.000Z

308

Westinghouse Test Stand Report  

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

2014 Westinghouse Electric Company LLC. All Rights Reserved MT-14-12 Westinghouse VERA Test Stand Zero Power Physics Test Simulations for the AP1000 PWR Fausto Franceschini,...

309

V  

Office of Scientific and Technical Information (OSTI)

for feedwater lines at five PWR plants; the analysis is based on probabilistic fracture mechanics. On the basis of observed pipe cracks in these feedwater lines, the crack...

310

March 2014 Most Viewed Documents for Fission And Nuclear Technologies...  

Office of Scientific and Technical Information (OSTI)

J. (1978) 30 > Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Executive summary: main report. PWR and BWR Not Available (1975)...

311

CASL Milestone L2.VRI.P6.01  

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

Ridge National Laboratory PCI pellet-cladding interaction PWR pressurized water reactor RIA reactivity insertion accident RSICC Radiation Safety Information Computational Center...

312

CNS 2008 Template  

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

for PWR design calculations, including options of fuel boiling duty calculation, a grid heat transfer model and data interface with ANC and BOA for CIPS risk assessment. The...

313

A review of the secondary plant modifications on steam generator performance  

SciTech Connect

This paper provides recommendations for modifications in the secondary system of existing pressurized water reactor (PWR) plants for the purpose of arresting the problem of steam generator corrosion.

Asarpota, A.; Snaith, R.

1983-01-01T23:59:59.000Z

314

Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors  

E-Print Network (OSTI)

of hydride fueled BWRs. Nuclear Engineering and Design, 239:Fueled PWR Cores. Nuclear Engineering and Design, 239:1489Hydride Fueled LWRs. Nuclear Engineering and Design, 239:

Terrani, Kurt Amir

2010-01-01T23:59:59.000Z

315

Assessment of uranium-free nitride fuels for spent fuel transmutation in fast reactor systems  

E-Print Network (OSTI)

. ....................................................................................... 18 Fig. 4. Standard PWR core model with fresh, once- and twice-burned fuel, and the location of MOX fuel assemblies with respect to original layout, 32% MOX loading................................................................................................................ 21 Fig. 5. Control rod locations......................................................................................... 21 Fig. 6. Net change of U, Pu and Am for PWR and 1/3 MOX fueled whole cores, 360 day burn...

Szakaly, Frank Joseph

2004-09-30T23:59:59.000Z

316

Practical implications of neutron survey instrument performance  

Science Journals Connector (OSTI)

......252Cf 241Am-Be GCR PWR Spent fuel flask PuO2 store Fuel processing R H (10) (90...incidence through the electronics and batteries, and the connections to the detector...252Cf 241Am-Be GCR PWR Spent fuel flask PuO2 store Fuel processing......

R. J. Tanner; D. T. Bartlett; L. G. Hager; L. N. Jones; C. Molinos; N. J. Roberts; G. C. Taylor; D. J. Thomas

2004-08-01T23:59:59.000Z

317

Nuclear reactor characteristics and operational history  

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

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

318

Comparison of Pratt and Whitney Rocketdyne IGCC and commercial IGCC performance  

SciTech Connect

This report compares the performance and cost of commercial Integrated Gasification Combined Cycle (IGCC) plants using General Electric Energy (GEE) and Shell gasifiers with conceptual IGCC plant designs using the Pratt and Whitney Rocketdyne (PWR) compact gasifier. the PWR gasifier is also compared with the GEEE gasifier in hydrogen production and carbon capture mode. With the exception of the PWR gasifier, the plants are designed with commercially available equipment to be operational in approximately 2010. All results should be considered preliminary and dictated in large part by the selected design basis. 10 refs., 54 exhibits

Jeffrey Hoffmann; Jenny Tennant; Gary J. Stiegel [Office of Systems Analysis and Planning (United States)

2006-06-15T23:59:59.000Z

319

LBNL-6349E  

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

349E 349E ERNEST ORLANDO LAWRENCE BERKELEY NATIONAL LABORATORY Assessing the Costs and Benefits of the Superior Energy Performance Program Peter Therkelsen and Aimee McKane Environmental Energy Technologies Division Lawrence Berkeley National Laboratory Ridah Sabouni and Tracy Evans Energetics Incorporated Paul Scheihing Advanced Manufacturing Office United States Department of Energy Reprint version of conference paper presented at American Council for an Energy-Efficient Economy Summer Study on Energy Efficiency in Industry, please cite as: Peter Therkelsen, Ridah Sabouni, Aimee McKane, and Paul Scheihing. (2013). Assessing the Costs and Benefits of the Superior Energy Performance Program, 2013 ACEEE Summer Study on Energy Efficiency in Industry, Niagara Falls, NY

320

Kylteknik ("KYL")Kylteknik ("KYL") RefrigerationRefrigerationRefrigerationRefrigeration  

E-Print Network (OSTI)

+ moisture a_Falls.jpg For the range -10 ~ +50°C, dry air can be treated as an ideal gas with c i 1 005 kJ/(kg· K) _Mist-Niagara cp,air 1.005 kJ/(kg K) The saturation pressure of water at 50°C is 12.3 k.3 kJ/kg c t 1.82 kJ/(kg· K) Picture:http:// 8.11.2012 ?bo Akademi Univ - Thermal and Flow

Zevenhoven, Ron

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Page not found | Department of Energy  

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

71 - 31080 of 31,917 results. 71 - 31080 of 31,917 results. Download EIS-0169-SA-04: Supplement Analysis Yakima Fisheries Project-Construction/modification upgrades to the Prosser Hatchery and the Marion Drain Hatchery Facilities http://energy.gov/nepa/downloads/eis-0169-sa-04-supplement-analysis Download EIS-0355: Amended Record of Decision Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, UT http://energy.gov/nepa/downloads/eis-0355-amended-record-decision Download EIS-0358: Notice of Intent to Prepare an Environmental Impact Statement Construction and Operation of the Proposed Wellton-Mohawk Generating Facility, Yuma County, Arizona http://energy.gov/nepa/downloads/eis-0358-notice-intent-prepare-environmental-impact-statement Download UMore Park Wind Turbine Project Loggerhead Shrike Survey,

322

Categorical Exclusion Determinations: Western Area Power  

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

November 23, 2010 November 23, 2010 CX-004887: Categorical Exclusion Determination Cable and Conduit Addition Within the Fenced Area of the Buck Boulevard Substation CX(s) Applied: B4.6 Date: 11/23/2010 Location(s): Riverside County, California Office(s): Western Area Power Administration-Desert Southwest Region November 23, 2010 CX-007129: Categorical Exclusion Determination Buck Boulevard Substation CX(s) Applied: B4.6 Date: 11/23/2010 Location(s): Ripley, California Office(s): Western Area Power Administration-Desert Southwest Region November 5, 2010 CX-004898: Categorical Exclusion Determination Gila-Wellton-Mohawk (Structure Maintenance) CX(s) Applied: B1.3 Date: 11/05/2010 Location(s): Yuma County, Arizona Office(s): Western Area Power Administration-Desert Southwest Region

323

Page not found | Department of Energy  

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

171 - 1180 of 9,640 results. 171 - 1180 of 9,640 results. Download US-China Clean Energy Forum 2010 China Clean Energy http://energy.gov/pi/office-policy-and-international-affairs/downloads/us-china-clean-energy-forum-2010 Download EIS-0358: Notice of Intent to Prepare an Environmental Impact Statement Construction and Operation of the Proposed Wellton-Mohawk Generating Facility, Yuma County, Arizona http://energy.gov/nepa/downloads/eis-0358-notice-intent-prepare-environmental-impact-statement Download EA-1485: Finding of No Significant Impact Nisqually Transmission Line Relocation Project http://energy.gov/nepa/downloads/ea-1485-finding-no-significant-impact Download CX-008701: Categorical Exclusion Determination Spring Basin Wilderness Land Exchange CX(s) Applied: B1.25 Date: 06/05/2012

324

Microsoft Word - Cover Page - Exhibit 7  

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

7 7 Northern Pass Project General Area Map of North Section ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . ! . # * # * # * # * # * CANADA White Mountain National Forest White Mountain National Forest VERMONT COOS COUNTY GRAFTON COUNTY CARROLL COUNTY Smith S/S Berlin S/S Littleton S/S Whitefield S/S Lost Nation S/S § ¨ ¦ 93 £ ¤ 3 £ ¤ 2 £ ¤ 302 £ ¤ 3 ! ( 26 ! ( 102 ! ( 16 ! ( 105 ! ( 110 ! ( 135 ! ( 115 ! ( 145 ! ( 142 ! ( 114 ! ( 117 ! ( 253 ! ( 1 ! ( 111 ! ( 147 ! ( 116 ! ( 142 ! ( 114 ! ( 116 ! ( 26 ! ( 16 ! ( 142 ! ( 16 White Mountain National Forest 13 Mile Woods Pond of Safety Tract Appalachian Trail Tract 161-01 Pondicherry Unit of Silvio O Conte NFWR Lake Umbagog National Wildlife Refuge Steady Easement Appalachian Trail Tract 164-03 Jahoda CE SILVIO O. CONTE NATIONAL FISH AND WILDLIFE Appalachian Trail Tract 164-05 Mohawk Div. of Silvio O Conte NFWR Jahoda-Johnson CE Wilfong

325

MHK Technologies/RED HAWK | Open Energy Information  

Open Energy Info (EERE)

RED HAWK RED HAWK < MHK Technologies Jump to: navigation, search << Return to the MHK database homepage RED HAWK.jpg Technology Profile Primary Organization Natural Currents Energy Services Project(s) where this technology is utilized *MHK Projects/Avalon Tidal *MHK Projects/BW2 Tidal *MHK Projects/Cape Cod Tidal Energy Project *MHK Projects/Cape May Tidal Energy *MHK Projects/Cohansey River Tidal Energy *MHK Projects/Dorchester Maurice Tidal *MHK Projects/Fishers Island Tidal Energy Project *MHK Projects/Gastineau Channel Tidal *MHK Projects/Highlands Tidal Energy Project *MHK Projects/Killisnoo Tidal Energy *MHK Projects/Margate Tidal *MHK Projects/Maurice River Tidal *MHK Projects/Mohawk MHK Project *MHK Projects/Orient Point Tidal *MHK Projects/Rockaway Tidal Energy Plant

326

Oil-Free Centrifugal Hydrogen Compression Technology Demonstration - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

0 0 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Hooshang Heshmat Mohawk Innovative Technology, Inc. (MiTi) 1037 Watervliet Shaker Road Albany, NY 12205 Phone: (518) 862-4290 Email: HHeshmat@miti.cc DOE Managers HQ: Erika Sutherland Phone: (202) 586-3152 Email: Erika.Sutherland@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-FG36-08GO18060 Subcontractor: Mitsubishi Heavy Industries, Ltd, Compressor Corporation, Hiroshima, Japan Project Start Date: September 25, 2008 Project End Date: May 30, 2013 Fiscal Year (FY) 2012 Objectives Design a reliable and cost-effective centrifugal compressor for hydrogen pipeline transport and delivery: Eliminate sources of oil/lubricant contamination * Increase efficiency by using high rotational speeds *

327

U.S. Department of Energy Hydrogen and Fuel Cells Program 2013 Annual Merit Review (AMR) and Peer Evaluation Report  

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

D: PROJECTS NOT REVIEWED D: PROJECTS NOT REVIEWED 552 | FY 2013 Merit Review and Peer Evaluation Report List of Projects Not Reviewed Project ID Project Title Principal Investigator Name Organization PD-004 Distributed Bio-Oil Reforming Stefan Czernik National Renewable Energy Laboratory PD-013 Electrolyzer Development for the Copper-Chlorine Thermochemical Cycle Michele Lewis Argonne National Laboratory PD-016 Oil-Free Centrifugal Hydrogen Compression Technology Demonstration Hooshang Heshmat Mohawk Innovative Technology PD-017 Development of a Centrifugal Hydrogen Pipeline Gas Compressor Frank Di Bella Concepts NREC PD-021 Development of High-Pressure Hydrogen Storage Tank for Storage and Gaseous Truck Delivery Don Baldwin Hexagon Lincoln PD-027 Solar High-Temperature Water Splitting

328

CX-000033: Categorical Exclusion Determination | Department of Energy  

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

3: Categorical Exclusion Determination 3: Categorical Exclusion Determination CX-000033: Categorical Exclusion Determination Saint Regis Mohawk Tribe Energy Efficiency and Conservation Programs for Buildings and Facilities CX(s) Applied: B5.1, A9 Date: 11/02/2009 Location(s): New York Office(s): Energy Efficiency and Renewable Energy Energy Efficiency and Conservation Block Grant Program. Construction of the "Center for Excellence for Diabetes Care and Prevention" (Diabetes Center). Funds will specifically be used to cover costs of incorporating green technologies and energy efficiency components/features/processes into separately funded new facility. DOCUMENT(S) AVAILABLE FOR DOWNLOAD CX-000033.pdf More Documents & Publications CX-000034: Categorical Exclusion Determination CX-000019: Categorical Exclusion Determination

329

Page not found | Department of Energy  

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

61 - 13270 of 28,905 results. 61 - 13270 of 28,905 results. Download CX-004401: Categorical Exclusion Determination The Use of Scrap Tires for Oil Well Stimulation CX(s) Applied: B3.6 Date: 11/08/2010 Location(s): Waynesburg, Pennsylvania Office(s): Fossil Energy, National Energy Technology Laboratory http://energy.gov/nepa/downloads/cx-004401-categorical-exclusion-determination Download CX-004898: Categorical Exclusion Determination Gila-Wellton-Mohawk (Structure Maintenance) CX(s) Applied: B1.3 Date: 11/05/2010 Location(s): Yuma County, Arizona Office(s): Western Area Power Administration-Desert Southwest Region http://energy.gov/nepa/downloads/cx-004898-categorical-exclusion-determination Download CX-004389: Categorical Exclusion Determination CX-004389: Categorical Exclusion Determination

330

Page not found | Department of Energy  

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

21 - 14030 of 28,905 results. 21 - 14030 of 28,905 results. Download CX-000030: Categorical Exclusion Determination Orutsararmuit Native Village Energy Efficiency and Conservation Programs for Buildings and Facilities CX(s) Applied: B5.1, A9 Date: 11/02/2009 Location(s): Alaska Office(s): Energy Efficiency and Renewable Energy http://energy.gov/nepa/downloads/cx-000030-categorical-exclusion-determination Download CX-000031: Categorical Exclusion Determination Pueblo de Cochiti Energy Efficiency Retrofits CX(s) Applied: B5.1, B2.5, A1 Date: 11/02/2009 Location(s): Pueblo de Cochiti, New Mexico Office(s): Energy Efficiency and Renewable Energy http://energy.gov/nepa/downloads/cx-000031-categorical-exclusion-determination Download CX-000033: Categorical Exclusion Determination Saint Regis Mohawk Tribe Energy Efficiency and Conservation Programs for

331

Data:22dfb476-09ef-4c77-b731-2151bae15623 | Open Energy Information  

Open Energy Info (EERE)

22dfb476-09ef-4c77-b731-2151bae15623 22dfb476-09ef-4c77-b731-2151bae15623 No revision has been approved for this page. It is currently under review by our subject matter experts. Jump to: navigation, search Loading... 1. Basic Information 2. Demand 3. Energy << Previous 1 2 3 Next >> Basic Information Utility name: Wellton-Mohawk Irr & Drain Dist Effective date: 2012/01/01 End date if known: Rate name: General Service Sector: Commercial Description: Source or reference: ISU Documentation Source Parent: Comments Applicability Demand (kW) Minimum (kW): Maximum (kW): History (months): Energy (kWh) Minimum (kWh): Maximum (kWh): History (months): Service Voltage Minimum (V): Maximum (V): Character of Service Voltage Category: Phase Wiring: << Previous 1 2 3 Next >> << Previous 1 2 3 Next >>

332

Categorical Exclusion Determinations: Arizona | Department of Energy  

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

April 4, 2013 April 4, 2013 CX-010095: Categorical Exclusion Determination Casa Grande Substation, CAG 262 Breaker Replacement CX(s) Applied: B1.3 Date: 04/04/2013 Location(s): Arizona Offices(s): Western Area Power Administration-Desert Southwest Region January 3, 2013 CX-009805: Categorical Exclusion Determination Maintenance and Wood Pole Replacement along the Gila Wellton Mohawk 161 Kilovolt Transmission Line CX(s) Applied: B1.3 Date: 01/03/2013 Location(s): Arizona Offices(s): Western Area Power Administration-Desert Southwest Region December 10, 2012 CX-009555: Categorical Exclusion Determination Assisting the Tooling and Machining Industry to Become Energy Efficient CX(s) Applied: A9 Date: 12/10/2012 Location(s): Arizona Offices(s): Golden Field Office December 4, 2012 CX-009554: Categorical Exclusion Determination

333

Techno-economic evaluation of waste lube oil re-refining in Saudi Arabia  

SciTech Connect

About 80 million gallons of automotive lubricating oils are sold in Saudi Arabia. Much of this oil, after use, is actually contributing to the increased pollution of land because of indiscriminate dumping. Any scheme of secondary use of the waste lube oils would be of interest both for conservation of energy resources and for protection of environment. This paper discusses the secondary use for the used automotive lubricating oils. Process technology of Meinken, Mohawk and KTI were selected for the techno-economic feasibility study for re-refining used oil. Profitability analysis for each process is worked out and the results are compared. In many countries, the re-refining of used oils has become an important industry. The objective of recovering high quality raffinates is attained through the use of widely differing techniques. The processes concerned can be classified according to the chemical or physical method of used-oil pretreatment selected. Meinken process is based on chemical pretreatment, whereas both Mohawk and KTI processes employ physical methods involving distillation and eliminate the use of sulfuric acid, thus providing a facility for safer operation than Meinken. The plant capacity of two existing units in Jeddah are 10,000 TPA and 80,000 TPA re-refining of waste oil. We selected a plant of 50,000 TPA waste oil re-refining for economic study of these three processes. The authors wish to acknowledge the support from King Fahd University of Petroleum & Minerals and King Abdulaziz City for Science & Technology for this work.

Ali, F.M.; Hamdan, A.J.; Rahman, F. [King Fahd Univ. of Petroleum & Minerals, Dharan (Saudi Arabia)] [and others

1995-12-31T23:59:59.000Z

334

Initial Modeling of a Pressurized Water Reactor Completed Using RELAP-7 |  

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

Initial Modeling of a Pressurized Water Reactor Completed Using Initial Modeling of a Pressurized Water Reactor Completed Using RELAP-7 Initial Modeling of a Pressurized Water Reactor Completed Using RELAP-7 January 29, 2013 - 12:06pm Addthis Schematic of the OECD PWR benchmark used in the initial RELAP-7 demonstration Schematic of the OECD PWR benchmark used in the initial RELAP-7 demonstration RELAP-7 is a nuclear reactor system safety analysis code. Development started in October 2011, and during the past quarter the initial capabilities of RELAP-7 were demonstrated by simulating a steady-state single-phase pressurized water reactor (PWR) with two parallel loops and multiple reactor core flow channels (Fig. 1). The PWR configuration matched that of the Three Mile Island 1 LWR, which is a benchmark problem from the

335

Linear Extrusion 400 Tons/Day Dry Solids Pump  

SciTech Connect

Pratt & Whitney Rocketdyne (PWR) has developed an innovative gasifier concept that uses rocket engine experience to significantly improve gasifier performance, life, and cost compared to current state-of-the-art systems. The PWR gasifier concept uses a compact and highly efficient (>50%) dry solids pump that has excellent availability (>99.5%). PWR is currently developing this dry solids pump under a U.S. Department of Energy (DOE) cooperative agreement. The conceptual design on two dry solids pumps were completed under this agreement and one pump concept was selected for preliminary design. A preliminary design review (PDR) of the selected pump was presented on September 20, 2007 to PWR management and numerous technical specialists. Feedback from the PDR review team has been factored into the design and a Delta-PDR was held on April 9, 2008.

Kenneth Sprouse; David Matthews

2008-04-30T23:59:59.000Z

336

Rl*-M-2413 LIST OF SELECTED PUBLICATIONS 1982  

E-Print Network (OSTI)

Cour, A Model of the Ringhals 3 PWR Power Plant. In: 10th IMACS World Congress on System Simulation. Lagerstrom, B. Lehnert, B. P. Peregud, A. Sillesen, and A. A. Semenov, Use of Thermal Imaging in Experiments

337

Most Viewed Documents for Fission And Nuclear Technologies: September...  

Office of Scientific and Technical Information (OSTI)

PWR and BWR Not Available (1975) 27 Sloshing analysis of viscous liquid storage tanks Uras, R.Z. (1995) 22 Flow-induced vibration of circular cylindrical structures Chen,...

338

E-Print Network 3.0 - abwr feedwater pump Sample Search Results  

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

Gases, Summary: 610 2011 China, Taiwan (2) Lungmen 1 ABWR 1,300 A Lungmen 2 ABWR 1,300 A Finland (1) Olkiluoto 3 PWR 1... Agency PRIS database http:www.iaea.orgprogrammesa2...

339

Nuclear power plants: structure and function  

SciTech Connect

Topics discussed include: steam electric plants; BWR type reactors; PWR type reactors; thermal efficiency of light water reactors; other types of nuclear power plants; the fission process and nuclear fuel; fission products and reactor afterheat; and reactor safety.

Hendrie, J.M.

1983-01-01T23:59:59.000Z

340

Three-Dimensional Velocity Measurement Reconstruction for a Rod Bundle Array using Matched Refractive Index Particle Tracking Velocimetry  

E-Print Network (OSTI)

In a pressurized water reactor (PWR), pressurized water flows over fuel rods containing radioactive uranium. Potential failure of these nuclear fuel rods is a primary concern, as fuel rod failure typically results in power generation losses...

Reyes, Denny L

2013-08-09T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

CASL-U-2014-0069-001  

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

an iPWR Startup Core Cycle with VERA Progress Report 2 Milestone L4:AMA.APP.P10.04 Kelly Kenner University of Tennessee - Knoxville Advisors: Ivan Maldonado, UTK Rose...

342

Flooding Experiments with Steam and Water in a Large Diameter Vertical Tube  

E-Print Network (OSTI)

An experimental study on flooding with steam and water in a large diameter vertical tube was conducted. This research has been performed to provide a better prediction of flooding in a pressurized water reactor (PWR) pressurizer surge line...

Williams, Susan Nicole

2010-10-12T23:59:59.000Z

343

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

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

PWR Fuel CRUD," Proceedings of the TMS 2013 142nd Annual Meeting and Exhibition, March 3-7, 2013, San Antonio, TX, 2013. Tryggvason, G., S. Dabiri, B. Aboulhasanzadeh, J. Lu.,...

344

SAFEGUARDS EXPERIENCE ON THE DUPIC FUEL CYCLE PROCESS  

SciTech Connect

Safeguards have been applied to the R and D process for directly fabricating CANDU fuel with PWR spent fuel material. Safeguards issues to be resolved were identified in the areas such as international cooperation on handling foreign origin nuclear material, technology development of operator's measurement system of the bulk handling process of spent fuel material, and a built-in C/S system for independent verification of material flow. The fuel cycle concept (Direct Use of PWR spent fuel in CANDU, DUPIC) was developed in consideration of reutilization of over-flowing spent fuel resources at PWR sites and a reduction of generated high level wastes. All those safeguards issues have been finally resolved, and the first batch of PWR spent fuel material was successfully introduced in the DUPIC lab facility and has been in use for routine process development.

J. HONG; H. KIM; ET AL

2001-02-01T23:59:59.000Z

345

Two-phase flow interfacial drag for once through steam generators  

E-Print Network (OSTI)

transient analysis code that can be used for simulation of a wide variety of PWR system transients of interest in LWR safety. The primary system, secondary system, feedwater train, system controls, and core neutronics can be simulated. The code modeling... are separated rather than agglomerated. 28 CHAPTER V RELAP5/MOD2 CODE MODIFICATIONS V. 1 Introduction Recent analyses of experiments in PWR-type fuel bundles have revealed that RELAP5/MOD2 overpredicts void fraction below the mixture level, leading...

Rais, Omar Tahar

2012-06-07T23:59:59.000Z

346

Analysis of the Simplified Boiling Water Reactor using the code Ramona-4B  

E-Print Network (OSTI)

of the macroscopic cross sections using General Electric fuel bundle design standard parameters and the powerful code CASMO-3 which is multigroup two-dimensional transport theory code for burnup calculations on BWR or PWR assemblies. This strategy results in a one... is a multigroup two-dimensional code for burnup and nuclear parameter calculation on BWR and PWR assemblies. It handles a geometry consisting of cylindrical fuel rods of varying composition in a square pitch anay with allowance for fuel rods loaded...

Cuevas Vivas, Gabriel Francisco

2012-06-07T23:59:59.000Z

347

Spent Nuclear Fuel Self-Induced XRF to Predict Pu to U Content  

E-Print Network (OSTI)

area of interest, would improve input accountability and shipper/receiver differences. XRF measurements were made on individual PWR fuel rods with varying fuel ages and final burn-ups at Oak Ridge National Laboratory (ORNL) in July 2008 and January... Committee NRF Nuclear Resonance Fluorescence viii ORNL Oak Ridge National Laboratory Pu Plutonium PUREX Plutonium and Uranium Recovery by Extraction PWR Pressurized Water Reactor RPP Reprocessing Plant SNM Special Nuclear Material...

Stafford, Alissa Sarah

2010-10-12T23:59:59.000Z

348

Application of the lattice code DRAGON to CANDU analysis  

SciTech Connect

Most lattice codes initially designed for pressurized water reactor (PWR) or boiling water reactor (BWR) assembly analysis can only treat approximately two-dimensional (2-D) Canadian deuterium uranium (CANDU) reactor cluster geometries. Moreover, they generally lack the three-dimensional (3-D) supercell option required for CANDU control device analysis. The lattice code DRAGON has all the features that are necessary for a combined CANDU cell and supercell calculations as well as for PWR or BWR lattice analysis.

Hebert, A.; Marleau, G.; Roy, R. [Ecole Polytechnique, Montreal (Canada)

1995-12-31T23:59:59.000Z

349

operation_tbl3_October_2011M.xlsx  

Gasoline and Diesel Fuel Update (EIA)

Arkansas Nuclear One Arkansas Nuclear One 1 PWR Babcock&Wilcox, Lower Loop 10/1/1968 8/17/1974 5/20/2014 2/1/2000 6/20/2001 5/20/2034 Arkansas Nuclear One 2 PWR Combustion Eng. 7/1/1971 12/26/1978 7/17/2018 10/15/2003 6/30/2005 7/17/2038 Beaver Valley 1 PWR Westinghouse, 3 Loop 6/1/1970 6/14/1976 1/29/2016 8/28/2007 11/5/2009 1/29/2036 Beaver Valley 2 PWR Westinghouse, 3 Loop 5/1/1974 8/17/1987 5/27/2027 8/28/2007 11/5/2009 5/27/2047 Braidwood Generation Station 1 PWR Westinghouse, 4 Loop 8/1/1975 7/12/1987 10/17/2026 N/A N/A N/A Braidwood Generation Station 2 PWR Westinghouse, 4 Loop 8/1/1975 5/25/1988 12/18/2027 N/A N/A N/A Browns Ferry 1 BWR General Electric, Mark 1 5/1/1967 10/15/1973 12/20/2013 1/6/2004 5/4/2006 12/20/2033 Browns Ferry 2 BWR General Electric, Mark 1 5/1/1967 8/28/1974 6/28/2014 1/6/2004 5/4/2006 6/28/2034 Browns Ferry

350

Rffi  

Office of Legacy Management (LM)

Rffi Rffi Prepared by s l/s r Oak Ridge Associated Universities Prepared for Division of Remedial Action Projects U.S. Department of Energy CO]IIPREHENSIVE RADIOLOGICAL SURVEY O F F - S I T E P R O P E R T Y S NIAGARA FALLS STORAGE SITE L E W T S T O N , N E W Y O R K J . D . B E R G E R R a d i o l o g i c a l . S i t e A s s e s s m e n t P r o g r a m Idanpower Education, Research, and Trai.ning Division FINAL REPORT February 1984 COMPREIIENSIVE RADIOLOGICAL SI'RVEY OFF-SITE PROPERTY S NIAGARA FALLS STORAGE SITE LEWTSTON, NEW YORK u. s. Fornerly Utllized R.D. Condra R . C . G o s s l e e W.O. Helton T.J. Sowell Radiological Manpower Educatlon' Oak ltldge Oak Ridge' Prepared for Department of EnergY as part of the Sttes - Renedial Actlon Program J . D . B e r g e r Project Staff M.W. Stafford G.11. St,ePhens C.F. Weaver B.S. Zacharek Prepared bY Site Assessment Program

351

A Parametric Study of the DUPIC Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy  

SciTech Connect

For both pressurized water reactor (PWR) and Canada deuterium uranium (CANDU) tandem analysis, the Direct Use of spent PWR fuel In CANDU reactor (DUPIC) fuel cycle in a CANDU 6 reactor is studied using the DRAGON/DONJON chain of codes with the ENDF/B-V and ENDF/B-VI libraries. The reference feed material is a 17 x 17 French standard 900-MW(electric) PWR fuel. The PWR spent-fuel composition is obtained from two-dimensional DRAGON assembly transport and depletion calculations. After a number of years of cooling, this defines the initial fuel nuclide field in the CANDU unit cell calculations in DRAGON, where it is further depleted with the same neutron group structure. The resulting macroscopic cross sections are condensed and tabulated to be used in a full-core model of a CANDU 6 reactor to find an optimized channel fueling rate distribution on a time-average basis. Assuming equilibrium refueling conditions and a particular refueling sequence, instantaneous full-core diffusion calculations are finally performed with the DONJON code, from which both the channel power peaking factors and local parameter effects are estimated. A generic study of the DUPIC fuel cycle is carried out using the linear reactivity model for initial enrichments ranging from 3.2 to 4.5 wt% in a PWR. Because of the uneven power histories of the spent PWR assemblies, the spent PWR fuel composition is expected to differ from one assembly to the next. Uneven mixing of the powder during DUPIC fuel fabrication may lead to uncertainties in the composition of the fuel bundle and larger peaking factors in CANDU. A mixing method for reducing composition uncertainties is discussed.

Rozon, Daniel; Shen Wei [Institut de Genie Nucleaire (Canada)

2001-05-15T23:59:59.000Z

352

Multirecycling of Plutonium from LMFBR Blanket in Standard PWRs Loaded with MOX Fuel  

SciTech Connect

It is now well-known that, from a physics standpoint, Pu, or even TRU (i.e. Pu+M.A.), originating from LEU fuel irradiated in PWRs can be multirecycled also in PWRs using MOX fuel. However, the degradation of the isotopic composition during irradiation necessitates using enriched U in conjunction with the MOX fuel either homogeneously or heterogeneously to maintain the Pu (or TRU) content at a level allowing safe operation of the reactor, i.e. below about 10%. The study is related to another possible utilization of the excess Pu produced in the blanket of a LMFBR, namely in a PWR(MOX). In this case the more Pu is bred in the LMFBR, the more PWR(MOX) it can sustain. The important difference between the Pu coming from the blanket of a LMFBR and that coming from a PWR(LEU) is its isotopic composition. The first one contains about 95% of fissile isotopes whereas the second one contains only about 65% of fissile isotopes. As it will be shown later, this difference allows the PWR fed by Pu from the LMFBR blanket to operate with natural U instead of enriched U when it is fed by Pu from PWR(LEU)

Sonat Sen; Gilles Youinou

2013-02-01T23:59:59.000Z

353

Page not found | Department of Energy  

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

51 - 13660 of 28,905 results. 51 - 13660 of 28,905 results. Download TEC Working Group Topic Groups Rail Key Documents Planning Subgroup Planning Subgroup http://energy.gov/em/downloads/tec-working-group-topic-groups-rail-key-documents-planning-subgroup Download Fuel Assembly Shaker Test for Determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport R0.1 Results of testing employing surrogate instrumented rods (non-high-burnup, 17 x 17 PWR fuel assembly) to capture the response to the loadings experienced during normal conditions of transport indicate that strain- or stress-based failure of fuel rods seems unlikely; performance of high-burnup fuels continues to be assessed. http://energy.gov/ne/downloads/fuel-assembly-shaker-test-determining-loads-pwr-assembly-under-surrogate-normal

354

Natural convection phenomena in a nuclear power plant during a postulated TMLB' accident  

SciTech Connect

After the TMI (Three Mile Island) accident, there has been significant interest in analyzing and understanding the phenomena that may occur in a PWR (Pressurized Water Reactor) accident which may lead to partial or total core meltdown and degradation. Natural convection is one of the important phenomena. In the present paper the results of two numerical simulations of (1) four-loop PWR and (2) three-loop PWR are presented. The simulations were performed with the COMMIX(2) computer code. Our analysis shows that in severe accident scenarios, natural convection phenomena does occur and that it helps to delay core degradation by transferring decay heat from the reactor core to other internal structures of the reactor system. The amount of heat transfer and delay in core degradation depends on the geometry and internal structures of the system and on the events of an accident.

Domanus, H.M.; Schmitt, R.C.; Sha, W.T.; Shah, V.L.; Han, J.T.

1987-01-01T23:59:59.000Z

355

A framework for the assessment of severe accident management strategies  

SciTech Connect

Severe accident management can be defined as the use of existing and/or altemative resources, systems and actors to prevent or mitigate a core-melt accident. For each accident sequence and each combination of severe accident management strategies, there may be several options available to the operator, and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrumentation behavior during an accident. A framework based on decision trees and influence diagrams has been developed which incorporates such criteria as feasibility, effectiveness, and adverse effects, for evaluating potential severe accident management strategies. The framework is also capable of propagating both data and model uncertainty. It is applied to several potential strategies including PWR cavity flooding, BWR drywell flooding, PWR depressurization and PWR feed and bleed.

Kastenberg, W.E. [ed.; Apostolakis, G.; Dhir, V.K. [California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering] [and others

1993-09-01T23:59:59.000Z

356

National Transportation Stakeholders Forum  

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

Transportation Stakeholders Forum Transportation Stakeholders Forum May 14-16, 2013 Tuesday, May 14 7:00 am - 5:00 pm Registration Niagara Foyer 7:00 am - 7:45 am Breakfast and Networking Grand A 8:00 am - 10:00 am National Updates for Transportation Stakeholder Groups and Guests - Panel Grand BC Moderator: John Giarrusso Jr., MA Emergency Management Agency / Northeast High-Level Radioactive Waste Transportation Task Force Co-Chair US Department of Energy, Office of Environmental Management - Steve O'Connor, Director, Office of Packaging & Transportation US Nuclear Regulatory Commission - Earl P. Easton, Senior Level Advisor (retired) and David W. Pstrak, Transportation and Storage Specialist, Division of Spent Fuel Storage and Transportation

357

Microsoft Word - S06246_VP_Report  

Office of Legacy Management (LM)

NFSS Vicinity Property S NFSS Vicinity Property S This page intentionally left blank Assessment Data Excerpt from Comprehensive Radiological Survey Off-Site Property S Niagara Falls Storage Site Appendix C NFSS Vicinity Property S Page C-1 This page intentionally left blank Appendix C NFSS Vicinity Property S Page C-2 Appendix C NFSS Vicinity Property S Page C-3 Appendix C NFSS Vicinity Property S Page C-4 Appendix C NFSS Vicinity Property S Page C-5 Appendix C NFSS Vicinity Property S Page C-6 Appendix C NFSS Vicinity Property S Page C-7 Appendix C NFSS Vicinity Property S Page C-8 Appendix C NFSS Vicinity Property S Page C-9 Appendix C NFSS Vicinity Property S Page C-10 Appendix C NFSS Vicinity Property S Page C-11 Appendix C NFSS Vicinity Property S Page C-12 Appendix C NFSS Vicinity Property S Page C-13

358

a J. C. Clarke, Contract FEOM 8 J. P. Morgan, Assist tor, Pznduction Division  

Office of Legacy Management (LM)

J. C. Clarke, Contract J. C. Clarke, Contract FEOM 8 J. P. Morgan, Assist tor, Pznduction Division SUBJECT: CONTRACT PROPCX3AL OF r) ELECTRO MXTALLURGICAL DIVISION SYMBOL: PADtJPM UNION CARBIDE & CAFLBON CORPORATION i' .:' CONTRACT NO. W-7405 EN&14 4. . A; BACKGROUND 18 The vacuum casting facilities at the Electra ~etallnrgical Division at Niagara Falls, New York, currently in standby, are needed for the vacuum casting of slrconium sponge to ingot for subsequent con- version to zirconium shapes for the Naval Critical hequiremento . The program has been approved by the &shington Division of heactor Development through the Washington Production Division, Monies are available from operations budget for FY 1950 and FY 1951 under the Titanium Alloy Manufacturing Division of National &ad Company

359

Microsoft Word - S06246_VP_Report  

Office of Legacy Management (LM)

Drainages Drainages This page intentionally left blank Assessment Data Excerpt from: Background and Resurvey Recommendations for the Atomic Energy Commission Portion of the Lake Ontario Ordnance Works and A Comprehensive Characterization and Hazard Assessment of the DOE-Niagara Falls Storage Site Appendix G Drainages Page G-1 This page intentionally left blank Appendix G Drainages Page G-2 Aerospace Report No. ATR-82(7963-04)-1 Background and ~I Resurvey Recommendations for the Atomic Energy Commission Portion of the I Lake Ontario Ordnance Works November 1982 ~~~~~~I ~Prepared for Public Safety Division Office of Operational Safety Assistant Secretary for Environmental Protection, ~~~~I ~Safety, and Energy Prepardness U.S. DEPARTMENT OF ENERGY *|I~~~ ~~Prepared by

360

ORNL/RASA-85/l OAK RIDGE NATIONAL LABORATORY RESULTS OF THE MOBILE GAMMA SCANNING  

Office of Legacy Management (LM)

d-I. 17-9 d-I. 17-9 d &y-?-T /,' k~:" , q ORNL/RASA-85/l OAK RIDGE NATIONAL LABORATORY RESULTS OF THE MOBILE GAMMA SCANNING ACTIVITIES IN NIAGARA FALLS, NEW YORK AREA ,. OPERATED BY MARTIN MARIEITA ENERGY SYSTEMS, INC. FOR THE UNITED STATES 'DEPARTMENT OF ENERGY ACCeSS t0 the information in this rePoti is limited (o those indicated on the distribution list and to Depanment of &ergy and Department of Energy Contractors Health and Safety Research Division EESULTS OFTBEMlBILEGAJMA SCANNING ACTIVITIES IN NIAGABAFALLS. NBR YOBKARBA W. B. Sbinpaugh, B. A. Berven, and W. D. Cottrell hQUBARANDrEEUICALWASlEWOGBA&5 (Activity No. AB 10 05 00 0; ONLWCOl) Manuscript Completed - February 1985 Date of Issue - August 1985 Investigation Team B. A. Berven - BASA Program Manager

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

New York | Department of Energy  

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

March 30, 2012 March 30, 2012 Information Notice -- Champlain Hudson Project, March 30, 2012 Champlain Hudson Power Express Transmission Line Project, New York March 25, 2012 Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Paper presented at the Waste Management 2012 Conference. February 26 through March 1, 2012, Phoenix, Arizona. Christopher Clayton, Vijendra Kothari, and Ken Starr, U.S. Department of Energy Office of Legacy Management Michael Widdop and Joey Gillespie, S.M. Stoller Corporation, Contractor to the U.S. Department of Energy Office of Legacy Management March 23, 2012 Brookhaven researchers Etsuko Fujita, Jonathan Hull, and James Muckerman developed a new catalyst that reversibly converts hydrogen gas and carbon dioxide to a liquid under very mild conditions. Their findings were published in the March 18th issue of Nature Chemistry. | Photo courtesy of Brookhaven National Lab.

362

Natural Gas - U.S. Energy Information Administration (EIA) - U.S. Energy  

Gasoline and Diesel Fuel Update (EIA)

14, 2012 | Release Date: November 15, 14, 2012 | Release Date: November 15, 2012 | Next Release: November 29, 2012 Previous Issues Week: 12/22/2013 (View Archive) JUMP TO: In The News | Overview | Prices/Demand/Supply | Storage In the News: New pipeline expansions come online in the Northeast. Two major northeast pipeline infrastructure expansion projects came into service at the beginning of this month. The Tennessee Gas Pipeline (TGP) Supply Diversification Project and the National Fuel Gas Northern Access Project together will add about 0.4 billion cubic feet per day of incremental volumes to TransCanada's Niagara export trading point, according to recent reports by BENTEK Energy LLC (Bentek). The National Fuel Gas Northern Access Project included 320 million cubic feet (MMcf) per day of capacity, while the TGP Supply Diversification Project included 250

363

U.S. Total Exports  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

364

U.S. Liquefied Natural Gas Exports to United Kingdom  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

365

United States Government Department of Energy  

Office of Legacy Management (LM)

Department of Energy Department of Energy memorandum DATE: SEP 2 5 l= REPLY TO A-RN OF: EM-421 (W. A. Williams, 903-8149) SUBJECT: Authorization for Remedial Action at Bliss 81 Laughlin Steel Company Site in Buffalo, New York TO: L. Price, OR The former Bliss & Laughlin Steel Company site located at 110 Hopkins Street in Buffalo, New York, is designated for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The site is owned by Niagara Cold Drawn Corporation. This designation is based on the results of a radiological survey and conclusions from an authority review as noted in the attached Designation Summary (8/4/92). Copies of the radiological survey report and authority determination are provided for information. The site has been assigned a low priority under FUSRAP protocol. The

366

DOE - Office of Legacy Management -- Hooker Chemical Co - NY 05  

Office of Legacy Management (LM)

Hooker Chemical Co - NY 05 Hooker Chemical Co - NY 05 FUSRAP Considered Sites Site: Hooker Chemical Co. (NY.05) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Occidental Chemical Corporation Hooker Electrochemical Corporation NY.05-1 NY.05-2 Location: Niagara Falls , New York NY.05-3 Evaluation Year: 1985 NY.05-1 NY.05-2 Site Operations: Design, engineering, construction, equipping and operation of a plant for the manufacture of Product 45 (xylene hexachloride); MFL (Miller's fluorolubricant); P-45Cl; and recovered P-45Cl2 from residues produced in the manufacture of P-45Cl; used hydrochloric acid (a byproduct of the P-45 Program) in the chemical processing of uranium-bearing slag as a precursor to recovery. NY.05-2 NY.05-4 Site Disposition: Eliminated - Radiation levels below criteria NY.05-1

367

PLEAEERUSH ANALYTICAL DA-~-A SHEET  

Office of Legacy Management (LM)

' ' PLEAEERUSH ANALYTICAL DA-~-A SHEET ' ANALYTICAL DEPT. - HEALTH AhD SAFETY DlVlSlON 1956 Industrial Hygiene or Medical Dept. 1. H.#~~Sample Nos. 3 --Date Collected~~by-CESS-.Route to CBS LocationTITANIUM Type of Sample airnalyzed for F Alpham Remarks NIAGARA pALI+S* N.Y. U Beta Bldg. 103 - furnace room - -NO, Ra Oil PH Be Th Sample No. Hour Sample Description I I I--- R ) T 1 Q I I I 7392 1100 GA Induction furnace area duri-nn ----l----- mDeriod;.02; 151 .3 while furnace was charged with UOT_- and carbon, and under heat. 7393 / GA Continuation of 7392 I I 7394 GA Continuation of 7393 -I- ----J -___-_-- - ___(_-- I- -~----~ -- ~- __ __ ___ -----.A ri --- - ----_' ---p. ----- __- -. -~-- -~ - 1 - .- -__ -___ -_--__ -___-- I -__-- -- --' II--T---

368

The Honorable'Anthony Mosillo .'  

Office of Legacy Management (LM)

Departmerit of Enei@y Departmerit of Enei@y Vi/ashington, DC 20585 " NC 1 s~lz34~: ' / ' 8 The Honorable'Anthony Mosillo .' 6500 Niagara Square Buffalo, New York. 14202 Dear.Mayor Mosi~llo: , ;' "i,' . \ ;& ~ ,., Secretary of Energy Hazel O'Leary,has'announced~a new approach to openness in the Department'of Energy (POE) and,its communications'with the ,publ'ic. In support of this initiative, we are, pleased to forward the enclosed information related to the fo,rmer Buflovak Co. site in your jurisdiction that performed work for,DOE or its predecessor agencies. This. information is provided for your information,.use, and retention \ ,.." ,. DOE!s Formerly Util$ied Sites Remediai Action Program is responsible for identification, of /vites used by DOE's predecessor agencies,.determining their

369

Microsoft Word - S06246_VP_Report  

Office of Legacy Management (LM)

NFSS Vicinity Property W NFSS Vicinity Property W This page intentionally left blank Assessment Data Excerpt from Comprehensive Radiological Survey Off-Site Property W Niagara Falls Storage Site Appendix E NFSS Vicinity Property W Page E-1 This page intentionally left blank Appendix E NFSS Vicinity Property W Page E-2 Appendix E NFSS Vicinity Property W Page E-3 Appendix E NFSS Vicinity Property W Page E-4 Appendix E NFSS Vicinity Property W Page E-5 Appendix E NFSS Vicinity Property W Page E-6 Appendix E NFSS Vicinity Property W Page E-7 Appendix E NFSS Vicinity Property W Page E-8 Appendix E NFSS Vicinity Property W Page E-9 Appendix E NFSS Vicinity Property W Page E-10 Appendix E NFSS Vicinity Property W Page E-11 Appendix E NFSS Vicinity Property W Page E-12 Appendix E NFSS Vicinity Property W Page E-13

370

U.S. Natural Gas Exports to China  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

371

U.S. Liquefied Natural Gas Exports to India  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

372

U.S. Natural Gas Exports to Russia  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

373

Microsoft Word - non-graphics title pages.doc  

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

43 43 Prepared by: U.S. Department of Energy Natural Gas Imports and Exports First Quarter Report 2011 LNG LNG Japan Trinidad and Tobago Canada Yemen Egypt Mexico Peru India South Korea Norway Qatar Spain United Kingdom POINTS OF IMPORT 1. Sumas, Washington 2. Eastport, Idaho 3. Whitlash / Babb / Port of Del Bonita / Sweetgrass, Montana 4. Port of Morgan, Montana / Portal, North Dakota 5. Sherwood, North Dakota 6. Noyes / Warroad, Minnesota 7. Detroit / St. Clair / Marysville, Michigan 8. Niagara Falls / Grand Island, New York 9. Waddington, New York 10. Massena / Champlain, New York 11. Highgate Springs, Vermont 12. Pittsburg, New Hampshire 13. Calais, Maine 14. Ogilby, California 15. Alamo / Hidalgo, Texas 16. McAllen / Galvan Ranch, Texas 17. Northeast Gateway Deepwater Port 18.

374

ACEEE_LBNL_Role-of-Industry_Paper-38_Final  

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

37E 37E Demand Response Opportunities in Industrial Refrigerated Warehouses in California Sasank Goli, Aimee McKane, Daniel Olsen Environmental Energy Technologies Division July 2011 Presented at the 2011 ACEEE Summer Study on Energy Efficiency in Industry, Niagara Falls, NY, July 26-29, 2011, and to be published in the Proceedings DISCLAIMER This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor The Regents of the University of California, nor any of their employees, makes any warranty, express or implied, or assumes any legal responsibility for the accuracy, completeness, or usefulness of any information,

375

FRONTC~1.ai  

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

3 3 Prepared by: U.S. Department of Energy Natural Gas Imports and Exports Fourth Quarter Report 2012 LNG LNG Japan Trinidad and Tobago Canada Mexico Qatar Brazil Norway Yemen Portugal POINTS OF IMPORT 1. Sumas, Washington 2. Eastport, Idaho 3. Whitlash / Babb / Port of Del Bonita / Sweetgrass, Montana 4. Port of Morgan, Montana / Portal, North Dakota 5. Sherwood, North Dakota 6. Noyes / Warroad, Minnesota 7. Detroit / St. Clair / Marysville, Michigan 8. Niagara Falls / Grand Island, New York 9. Waddington, New York 10. Massena / Champlain, New York 11. Highgate Springs, Vermont 12. Pittsburg, New Hampshire 13. Calais, Maine 14. Ogilby, California 15. Alamo / Hidalgo, Texas 16. McAllen / Galvan Ranch, Texas 17. Northeast Gateway Deepwater Port 18. Neptune Deepwater Port 19. Everett,

376

DOE/FE-0552  

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

2 2 Prepared by: U.S. Department of Energy Natural Gas Imports and Exports Second Quarter Report 2011 LNG LNG Japan Trinidad and Tobago Canada Yemen Egypt Mexico Peru India South Korea Qatar Spain China Brazil POINTS OF IMPORT 1. Sumas, Washington 2. Eastport, Idaho 3. Whitlash / Babb / Port of Del Bonita / Sweetgrass, Montana 4. Port of Morgan, Montana / Portal, North Dakota 5. Sherwood, North Dakota 6. Noyes / Warroad, Minnesota 7. Detroit / St. Clair / Marysville, Michigan 8. Niagara Falls / Grand Island, New York 9. Waddington, New York 10. Massena / Champlain, New York 11. Highgate Springs, Vermont 12. Pittsburg, New Hampshire 13. Calais, Maine 14. Ogilby, California 15. Alamo / Hidalgo, Texas 16. McAllen / Galvan Ranch, Texas 17. Northeast Gateway Deepwater Port 18. Neptune Deepwater

377

Microsoft Word - 12184b.doc  

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

 Stakeholder interaction must be open and transparent, and DOE must respond promptly to  Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns.  DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk.  DOE must continue to maintain constructive relationships with the U.S. Army Corps of Engineers and state and federal regulators. INTRODUCTION The Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs)occupy approximately 607 hectares (1,500 acres) of the original 3036-hectare (7,500-acre) Lake Ontario Ordnance Works (LOOW), a former trinitrotoluene manufacturing facility built during the 1940s. In 1944, the LOOW was reassigned to the Manhattan Engineer District (MED) for use as

378

ESS 2012 Peer Review - NYSERDA Energy Storage Projects - Dhruv Bhatnagar, SNL  

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

NYSERDA Energy Storage Projects NYSERDA Energy Storage Projects Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. SAND No. 2011-XXXXP NaS Battery at MTA Long Island Bus Depot Beacon Flywheel Plant at Stephentown, NY 4 Demonstration Project Sites 1) Beacon Flywheel Plant at Stephentown, NY * Ancillary services in NYISO 2) NaS Battery at MTA Long Island Bus Depot * Time of day load shifting to avoid TOU rates 3) Flow Battery at Niagara Falls State Park * Renewables integration/firming &

379

UNION CARBIDE MZALS DIVISION tiiAGARA FALLS, NEW YDRK  

Office of Legacy Management (LM)

PRELIF",INARY SURVEY 0' PRELIF",INARY SURVEY 0' ELECTRDMET iORPDF.&TiCIN UNION CARBIDE MZALS DIVISION tiiAGARA FALLS, NEW YDRK Work performed by the Health and Safety Research Division Dak Ridge National Laboratory Oak Ridge, Tennessee 37830 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Fornierly Utilized Sites-- Remedial Action Program ,ELECTRD?'ISi 60RPOR:TION UNiON CARBIDE METALS DIVlSIOti NiASARA FALLS, NEA YORK At the requests o f the Department of Energy (DOE, then ERDA), a preliminary survey was performed at the former Electromet Plant (cur- rently Union Carbide Corporation - Metals Division plant) in Niagara Falls, Neh' York (see Fig. l), on August 24, 1976, to assess the radio- logical status 0 f those facilities utilized under~Manhattan Engineer

380

Microsoft Word - S06246_VP_Report  

Office of Legacy Management (LM)

NFSS Vicinity Property R NFSS Vicinity Property R This page intentionally left blank Assessment Data Excerpt from Comprehensive Radiological Survey Off-Site Property R Niagara Falls Storage Site Appendix B NFSS Vicinity Property R Page B-1 This page intentionally left blank Appendix B NFSS Vicinity Property R Page B-2 Appendix B NFSS Vicinity Property R Page B-3 Appendix B NFSS Vicinity Property R Page B-4 Appendix B NFSS Vicinity Property R Page B-5 Appendix B NFSS Vicinity Property R Page B-6 Appendix B NFSS Vicinity Property R Page B-7 Appendix B NFSS Vicinity Property R Page B-8 Appendix B NFSS Vicinity Property R Page B-9 Appendix B NFSS Vicinity Property R Page B-10 Appendix B NFSS Vicinity Property R Page B-11 Appendix B NFSS Vicinity Property R Page B-12 Appendix B NFSS Vicinity Property R Page B-13

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Dr. Wm. E. Mott, Director Environmental 8 Safety Eng. Div.  

Office of Legacy Management (LM)

Wm. E. Mott, Director Wm. E. Mott, Director Environmental 8 Safety Eng. Div. 0f.f ice of Environment (EU- 14) Dept. of Energy Washington, DC 20545 Dear Dr. Mott: MED Warehousing Location The sites listed in your letter of Febru; to determine present utilization and ownershi] the information available at this time: 1. Utica Street Warehouse 240 W. Utica Street Buffalo, ?pI The area of 240 and 242 W. Utica St, drive to a 4-story parking garage for Ch The ramp is about 4 years old and previol there was a paved parking lot on the sit 1960' s. The warehouse structure was denI unknown previous date. 2. West Genesee Street Warehouse Buffalo, NY The W. Genesee area is currently abc in .length. About half of the streets prc eliminated to make way for the Niagara E: the remaining streets there is one old bl

382

EM-421  

Office of Legacy Management (LM)

NY-W] NY-W] ' qc-,p,,4 ,P -pIj i; ,./&+e~--- ,jJs AIJG 0 2 130 EM-421 Addition of Sites to FUSRAP Lester K. Price, Director Technical Services,Division Oak Ridge Operations Office Attached is a memorandum approving transfer of responsibility for the Niagara Falls Storage Site (NFSS) in New York and the New Brunswick Laboratory (NBL) Site in New Jersey to FUSRAP. Please incorporate these sites in the FUSRAP rebaselining effort now underway. As we previously discussed, funding for NBL will provide for continued surveillance and maintenance activities at the site and will be borne by FUSRAP beginning in FY 1991. Funding for NFSS will be provided under B&R AH1020 for FY 1991 and will be borne by FUSRAP thereafter. If you have any questions in this regard, call me at FTS 233-4937.

383

I  

Office of Legacy Management (LM)

*, *, m *~ :~; Ff I ;,,,: . ?"? L. ,I .,m / ,; t-1 7 1," i i h , 13' 1. ~,. / ,,.. .e c _-. F c > ., *z . . - : ,, ,. ,i :,_:,, ., ,. _ ,: w:,,,, RADIOLOGICAL SURVEY OF BUILDINGS UOlA, 402,416, AND 429 NIAGARA FALLS STORAGE SITE LEWISTON, NEW YORK Prepared by T.J. Vitkus Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Institute for Science and Education Oa$ Ridge, TN 37831-0117 ORISE 92/J-40 Project Staff S. F. Bamett S. E. Potter R. ,D. Condra D. A. Gibson R. B. Slaten' T. D. Herrera Prepared for Office of Environmental Restoration Department of Energy FINAL REPORT OCTOBER 1992 This report is b&d on work performed under contract number DE-AC-05760R00033 with the ' XI. S . Departmefif'

384

Mr. James Schaus Vice President  

Office of Legacy Management (LM)

Mr. James Schaus Mr. James Schaus Vice President Finance and Administration Niagara Cold Drawn Corp. 110 Hopkins Street P.O. Box 399 Buffalo, New York 14240 Dear Mr. Schaus: This is to notify you that the U.S. Department of Energy (DOE) has designated the former Bliss & Laughlin Steel Company facility for remedial action as a part of the Formerly Utilized Sites Remedial Action Program. Remedial activities are managed by the DOE Oak Ridge Field Office, and Mr. Ron Kirk (615-576-7477) will be the site manager. As a result of the designation decision, Mr. Kirk will be the appropriate point of contact in the future. If you have any questions, please call me at 301-903-8149. Sincerely, /' /f-j , f-i 4 /fi /C q--1 - ,i/ -' uj %I&//& L' /< 1 i&x.-:,

385

buffalo  

Office of Legacy Management (LM)

Buffalo, New Buffalo, New York, Site (formerly the Bliss & Laughlin Steel site) is located at 110 Hopkins Street in the southern portion of Buffalo, New York. The site consists of a single, approximately 129,600-square-foot building surrounded by approximately 161,460 square feet of grounds. Used for finishing steel products, the facility is currently owned by the Niagara LaSalle Corporation. In September and October of 1952, the Bliss & Laughlin Steel Company machined and straightened uranium rods under subcontract to National Lead of Ohio (NLO), who operated the Fernald Site in Ohio under contract to the U.S. Atomic Energy Commission (AEC). These activities at the Buffalo site generated 53 drums of uranium waste cuttings, which AEC shipped to the Lake Ontario Ordnance

386

Microsoft Word - S06246_VP_Report  

Office of Legacy Management (LM)

NFSS Vicinity Property X NFSS Vicinity Property X This page intentionally left blank Assessment Data Excerpt from Comprehensive Radiological Survey Off-Site Property X Niagara Falls Storage Site Appendix F NFSS Vicinity Property X Page F-1 This page intentionally left blank Appendix F NFSS Vicinity Property X Page F-2 Appendix F NFSS Vicinity Property X Page F-3 Appendix F NFSS Vicinity Property X Page F-4 Appendix F NFSS Vicinity Property X Page F-5 Appendix F NFSS Vicinity Property X Page F-6 Appendix F NFSS Vicinity Property X Page F-7 Appendix F NFSS Vicinity Property X Page F-8 Appendix F NFSS Vicinity Property X Page F-9 Appendix F NFSS Vicinity Property X Page F-10 Appendix F NFSS Vicinity Property X Page F-11 Appendix F NFSS Vicinity Property X Page F-12 Appendix F NFSS Vicinity Property X Page F-13

387

Microsoft Word - S06246_VP_Report  

Office of Legacy Management (LM)

NFSS Vicinity Property Q NFSS Vicinity Property Q This page intentionally left blank Assessment Data Excerpt from Comprehensive Radiological Survey Off-Site Property Q Niagara Falls Storage Site Appendix A NFSS Vicinity Property Q Page A-1 This page intentionally left blank Appendix A NFSS Vicinity Property Q Page A-2 Appendix A NFSS Vicinity Property Q Page A-3 Appendix A NFSS Vicinity Property Q Page A-4 Appendix A NFSS Vicinity Property Q Page A-5 Appendix A NFSS Vicinity Property Q Page A-6 Appendix A NFSS Vicinity Property Q Page A-7 Appendix A NFSS Vicinity Property Q Page A-8 Appendix A NFSS Vicinity Property Q Page A-9 Appendix A NFSS Vicinity Property Q Page A-10 Appendix A NFSS Vicinity Property Q Page A-11 Appendix A NFSS Vicinity Property Q Page A-12 Appendix A NFSS Vicinity Property Q Page A-13

388

The Honorable Anthony Mosillo'  

Office of Legacy Management (LM)

D&aitment of Encjrgy .~ ' D&aitment of Encjrgy .~ ' , Washington,, DC 20585 The Honorable Anthony Mosillo' ', ' 6500 Niagara Square. 'Buffalo, New York 14202 Dear Mayor Mosillo: ~, ' ", Secretary of Energy Hazel, O'Leary has announced a.new approach to openness in the Department of Energy (DOE) and its communications with the public. In ., support of this initiative, we are pleased to forward the enclosed information related to the,Curtiss Wright Metal's.Processing Division;site in your / jurisdiction that performed work, for DOE or its predecessor agencies. Th'is information is provided for your information, use, and- retention., ,..,,I ., ; DOE's Formerly Utilized Sites Remedial ActionProgram is responsible for 1 identification of sites used by DOE's predecessor agencies, determining their

389

Microsoft Word - NY17-15 01-50.rtf  

Office of Legacy Management (LM)

OR/20722-84 OR/20722-84 Formerly Utilized Sites Remedial Action Program (FUSRAP) Contract No. DE-ACO5-810R20722 POST-REMEDIAL ACTION REPORT FOR THE NIAGARA FALLS STORAGE SITE VICINITY PROPERTIES - 1983 AND 1984 Lewiston, New York December 1986 Bechtel National, Inc. This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Department of Energy, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product disclosed, or represents that its use would not infringe privately owned rights.

390

THE AEROSPACE CORPORATION ,'  

Office of Legacy Management (LM)

,' ,' 20030 Century Blvd., Germantown, Maryland 20767, Telephone: (301) 428-2700 7848-02.80.aw.35 11 August 1980 Dr. William E. Mott Acting Director Environmental § Safety Engineering Division U.S. Department of Energy Germantown, MD 20767 Dear Dr. Mott: RESTRICTIONS ON THE LEWISTON LAND FORMERLY OWNED BY THE FEDERAL GOVERNMENT Enclosed please find copies of the restrictions placed on properties that were formerly part of the Atomic Energy Commission portion of the Lake Ontario ordnance works. The restrictions, in the form of Orders, were based on the Atomic Energy Commission surveys and were issued on April 27, 1972 by the New York State Commissioner of Health for: 1. Certain property of the town of Lewiston, Niagara County 2. Certain property of Monroe W. Frank, located in the town of

391

I  

Office of Legacy Management (LM)

6 6 I oRNL/Tit-10076 RESULTS OF RADIOLOGICAL MEASUREMENTS TAKEN IN THE NIAGARA FALLS, NEW YORK, AREA (NFOO2) J. K. Williams B. A. Berven Printed in the United States of America. Available from National Technical Information Service U.S. DePartment of Commerce 5285 Port Royal Road, Springfield, Virginia 22161 NTIS price codes-Printed Copy: A04; Microfiche A01 This report was prepared as an account of work sponsored by an agency of the United StatesGovernment. Neith€r the U nited StatesGovernment nor any agency thereof, noJ any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accurscy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not inf ringe

392

DOE/FE-0558  

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

58 58 Prepared by: U.S. Department of Energy Natural Gas Imports and Exports First Quarter Report 2012 LNG LNG Japan Trinidad and Tobago Canada Yemen Mexico Qatar Brazil Egypt Norway India POINTS OF IMPORT 1. Sumas, Washington 2. Eastport, Idaho 3. Whitlash / Babb / Port of Del Bonita / Sweetgrass, Montana 4. Port of Morgan, Montana / Portal, North Dakota 5. Sherwood, North Dakota 6. Noyes / Warroad, Minnesota 7. Detroit / St. Clair / Marysville, Michigan 8. Niagara Falls / Grand Island, New York 9. Waddington, New York 10. Massena / Champlain, New York 11. Highgate Springs, Vermont 12. Pittsburg, New Hampshire 13. Calais, Maine 14. Ogilby, California 15. Alamo / Hidalgo, Texas 16. McAllen / Galvan Ranch, Texas 17. Northeast Gateway Deepwater Port 18. Neptune Deepwater Port 19. Everett,

393

U.S. Natural Gas Exports to Portugal  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

394

Completed Sites Listing  

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

Hallam Nuclear Power Facility, NE Hallam Nuclear Power Facility, NE 1969 1998 2. Piqua Nuclear Power Facility, OH 1969 1998 3. Bayo Canyon, NM 1982 1998 4. Kellex/Pierpont, NJ 1982 1998 5. University of California, CA 1982 1998 6. Acid/Pueblo Canyons, NM 1984 1999 7. Chupadera Mesa, NM 1984 1999 8. Canonsburg, PA 1986 1999 9.Shiprock, NM 1987 2000 10. Middlesex Municipal Landfill, NJ 1987 2000 11. Niagara Falls Storage Site Vicinity Properties, NY 1987 2001 12. Salt Lake City, UT 1989 2001 13. Spook, WY 1989 2001 14. National Guard Armory, IL 1989 2002 15. University of Chicago, IL 1989 2005 16. Green River, UT 1990 2005 17. Lakeview, OR 1990 2006 18. Riverton, WY 1990 2006 19. Tuba City, AZ 1990 2006 20 Durango, CO 1991 2007 21. Lowman, ID 1992 2007 22. Pagano Salvage Yard, NM 1992 2007 23. Elza Gate, TN 1992 2007 24. Albany Research Center, OR

395

U.S. Natural Gas Exports to Mexico  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

396

Weatherization Provides Boost for New Jersey Business | Department of  

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

Provides Boost for New Jersey Business Provides Boost for New Jersey Business Weatherization Provides Boost for New Jersey Business April 9, 2010 - 5:11pm Addthis Joshua DeLung Although supplying weatherization professionals with the materials they need to make homes more energy efficient has been a part of Niagara Conservation Corp.'s business since it was founded in 1977, Rich Wagner admits that sales have slumped over the last decade. The Recovery Act is reversing that, says Wagner, the Director of Business Development-Weatherization for Cedar Knolls, N.J. The company makes and sells caulking and weatherstripping, duct sealing products, and window sealant kits to hundreds of local weatherization agencies and providers throughout the country, Wagner says. The company provides other high efficiency products, such as

397

DOE - Office of Legacy Management -- Buffalo NY Site - NY 54  

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

Buffalo NY Site - NY 54 Buffalo NY Site - NY 54 FUSRAP Considered Sites Buffalo, NY Alternate Name(s): Bliss & Laughlin Steel Company Niagara Cold Drawn Steel Corporation Ramco Steel Incorporated NY.54-1 NY.54-4 Location: 110 Hopkins Street, Buffalo, New York NY.54-1 Historical Operations: Machined and straightened uranium rods as subcontracted work from National Lead Company, an AEC contractor. NY.54-3 NY.54-4 LTSM012601 Eligibility Determination: Eligible NY.54-4 Radiological Survey(s): Assessment Surveys, Verification Surveys NY.54-6 NY.54-7 NY.54-8 LTSM012601 Site Status: Certified- Certification Basis and Certification Statement BLS000001 LTSM012152 LTSM012584 Long-term Care Requirements: Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites S07566_FUSRAP

398

Microsoft Word - Continual Improvement GSEP.doc  

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

9E 9E International Approaches to Measurement and Verification of Continual Improvement in Industrial Facilities Aimee McKane Environmental Energy Technologies Division Lawrence Berkeley National Laboratory Miriam Goldberg and Julia Vetromile DNV KEMA July 2013 To be presented at the ACEEE Summer Study on Energy Efficiency in Industry Niagara Falls, NY July 24-26, 2013 and to be published online at ACEEE.org DISCLAIMER This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor The Regents of the University of California, nor any of their employees, makes any warranty, express

399

INSIDE COVER MAP (JUNE 2012).pdf  

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

60 60 Prepared by: U.S. Department of Energy Natural Gas Imports and Exports Second Quarter Report 2012 LNG LNG Japan Trinidad and Tobago Canada Yemen Mexico Qatar POINTS OF IMPORT 1. Sumas, Washington 2. Eastport, Idaho 3. Whitlash / Babb / Port of Del Bonita / Sweetgrass, Montana 4. Port of Morgan, Montana / Portal, North Dakota 5. Sherwood, North Dakota 6. Noyes / Warroad, Minnesota 7. Detroit / St. Clair / Marysville, Michigan 8. Niagara Falls / Grand Island, New York 9. Waddington, New York 10. Massena / Champlain, New York 11. Highgate Springs, Vermont 12. Pittsburg, New Hampshire 13. Calais, Maine 14. Ogilby, California 15. Alamo / Hidalgo, Texas 16. McAllen / Galvan Ranch, Texas 17. Northeast Gateway Deepwater Port 18. Neptune Deepwater Port 19. Everett, Massachusetts 20.

400

Microsoft Word - 12184b  

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

* Stakeholder interaction must be open and transparent, and DOE must respond promptly to * Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. * DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. * DOE must continue to maintain constructive relationships with the U.S. Army Corps of Engineers and state and federal regulators. INTRODUCTION The Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs)occupy approximately 607 hectares (1,500 acres) of the original 3036-hectare (7,500-acre) Lake Ontario Ordnance Works (LOOW), a former trinitrotoluene manufacturing facility built during the 1940s. In 1944, the LOOW was reassigned to the Manhattan Engineer District (MED) for use as

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Issues and Trends: Natural Gas - Energy Information Administration  

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

Issues and Trends: Natural Gas Issues and Trends: Natural Gas Updated: November 25, 2013 For prior report data see Natural Gas Year-in-Review archives EIA's Natural Gas Issues and Trends highlights timely information and analyses on natural gas markets. Natural gas prices reflect decreasing seasonality. Today in Energy, November 20, 2013 Increased Northeast natural gas production reduces net inflow of supply from other areas. Today in Energy, November 19, 2013 Gas pipeline expansions reduce Marcellus backup, New York gas prices. Natural Gas Weekly Update, November 13, 2013 EIA projects lower natural gas use this winter. Natural Gas Weekly Update, October 31, 2013 Northeast net imports from Canada plummet, driven by export growth at Niagara Falls. Natural Gas Weekly Update, October 10, 2013

402

U.S. Liquefied Natural Gas Exports to Japan  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

403

U.S. Natural Gas Exports to Russia  

Gasoline and Diesel Fuel Update (EIA)

Babb, MT Havre, MT Port of Morgan, MT Pittsburg, NH Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Kenai, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Sabine Pass, LA Period: Monthly Annual

404

DOE/FE-0554  

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

4 4 Prepared by: U.S. Department of Energy Natural Gas Imports and Exports Third Quarter Report 2011 LNG LNG Japan Trinidad and Tobago Canada Yemen Mexico Nigeria Qatar China Brazil POINTS OF IMPORT 1. Sumas, Washington 2. Eastport, Idaho 3. Whitlash / Babb / Port of Del Bonita / Sweetgrass, Montana 4. Port of Morgan, Montana / Portal, North Dakota 5. Sherwood, North Dakota 6. Noyes / Warroad, Minnesota 7. Detroit / St. Clair / Marysville, Michigan 8. Niagara Falls / Grand Island, New York 9. Waddington, New York 10. Massena / Champlain, New York 11. Highgate Springs, Vermont 12. Pittsburg, New Hampshire 13. Calais, Maine 14. Ogilby, California 15. Alamo / Hidalgo, Texas 16. McAllen / Galvan Ranch, Texas 17. Northeast Gateway Deepwater Port 18. Neptune Deepwater Port 19. Everett,

405

FRONTCOVER (3rd Qtr 2012).pdf  

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

1 1 Prepared by: U.S. Department of Energy Natural Gas Imports and Exports Third Quarter Report 2012 LNG LNG Japan Trinidad and Tobago Canada Mexico Qatar POINTS OF IMPORT 1. Sumas, Washington 2. Eastport, Idaho 3. Whitlash / Babb / Port of Del Bonita / Sweetgrass, Montana 4. Port of Morgan, Montana / Portal, North Dakota 5. Sherwood, North Dakota 6. Noyes / Warroad, Minnesota 7. Detroit / St. Clair / Marysville, Michigan 8. Niagara Falls / Grand Island, New York 9. Waddington, New York 10. Massena / Champlain, New York 11. Highgate Springs, Vermont 12. Pittsburg, New Hampshire 13. Calais, Maine 14. Ogilby, California 15. Alamo / Hidalgo, Texas 16. McAllen / Galvan Ranch, Texas 17. Northeast Gateway Deepwater Port 18. Neptune Deepwater Port 19. Everett, Massachusetts 20. Cove

406

FRONTCOVER (4Q11).pdf  

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

6 6 Prepared by: U.S. Department of Energy Natural Gas Imports and Exports Fourth Quarter Report 2011 LNG LNG Japan Trinidad and Tobago Canada Yemen Mexico Qatar China Brazil Chile Egypt South Korea Norway POINTS OF IMPORT 1. Sumas, Washington 2. Eastport, Idaho 3. Whitlash / Babb / Port of Del Bonita / Sweetgrass, Montana 4. Port of Morgan, Montana / Portal, North Dakota 5. Sherwood, North Dakota 6. Noyes / Warroad, Minnesota 7. Detroit / St. Clair / Marysville, Michigan 8. Niagara Falls / Grand Island, New York 9. Waddington, New York 10. Massena / Champlain, New York 11. Highgate Springs, Vermont 12. Pittsburg, New Hampshire 13. Calais, Maine 14. Ogilby, California 15. Alamo / Hidalgo, Texas 16. McAllen / Galvan Ranch, Texas 17. Northeast Gateway Deepwater Port 18. Neptune Deepwater

407

Overview of the U.S. Department of Energy Formerly Utilized Sites Remedial  

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

Overview of the U.S. Department of Energy Formerly Utilized Sites Overview of the U.S. Department of Energy Formerly Utilized Sites Remedial Action Program Overview of the U.S. Department of Energy Formerly Utilized Sites Remedial Action Program Paper presented at the Waste Management 2012 Conference. February 26 through March 1, 2012, Phoenix, Arizona. Christopher Clayton, Vijendra Kothari, and Ken Starr, U.S. Department of Energy Office of Legacy Management Joey Gillespie and Michael Widdop, S.M. Stoller Corporation, Contractor for the U.S. Department of Energy Office of Legacy Management 12189a.pdf More Documents & Publications Overview of the U.S. Department of Energy Formerly Utilized Sites Remedial Action Program Recent Developments in DOE FUSRAP Evaluation of Final Radiological Conditions at Areas of the Niagara Falls

408

REPLY TO AmN OF: EM-421  

Office of Legacy Management (LM)

gy5.t3 CIy ( 1 IG-. 14-l gy5.t3 CIy ( 1 IG-. 14-l \ United States Government L/d &J~f,j-o p-1 memoratwJum h:3. I q Department of Energy DATE: fi\jfS 0 2 1990 REPLY TO AmN OF: EM-421 SUwECT: Addition of Sites to FUSRAP To' Lester K. Price, Director Technical Services Division Oak Ridge Operations Office Attached is a memorandum approving transfer of responsibility for the Niagara Falls Storage Site (NFSS) in New York and the New Brunswick Laboratory (NBL) Site in New Jersey to FUSRAP. Please incorporate these sites in the FUSRAP rebaselining effort now underway. As we previously discussed, fundinq for NBL will provide for continued surveillance and maintenance activities at the site and will be borne FUSRAP beginning in FY 1991. Funding for NFSS will be provided under

409

I.  

Office of Legacy Management (LM)

' ' ,' Ll ' _ ' ' - ' , - __ r_: I. x 7 , !i-,f, :- :. .' ,... . . Hr. Jay Cull, Technical Manager Special Environmental Programs Occidental Chemical Corporation Box 728 Eiagara Falls, New York 14302 L ;' DeLa ll//:. Dear tir. 0~11: The Department of Energy (DOE), as part of its Formerly Utilized Sites Remedial Action Program (FUSRAP), has reviewed information cn the Occidental Chemical Facility in Niagara Falls, New York (formerly Hooker Electrochemical Company), to determine whether it contains residual radioactivity traceable to activities conducted on behalf of the Manhattan Engineer District or the Atomic Energy C o m m ission (predecessors to DOE). A radiological survey indicated that the radiation levels are equal to natural background. Therefore, no remedial action is required, and DOE is

410

UNITED STATES GOVERNMENT  

Office of Legacy Management (LM)

'.... '|le , * f C. '.... '|le , * f C. Office Memorandum · UNITED STATES GOVERNMENT .-- J TO ' Leo Graup, Chief, DATE: September 29, 1958 Property Management Branch rFi0 : M. S. Weinstein Industrial Hygiene Branch, HASL SUBJBT: SURVEY AT HAIST PROPETIY SYMBOL: HSH:MSW. Thisl property was purchased during MED operation and used as a dumping ground for refinery residues generated by Linde Air Products during their period of participation in the refinery operations program. \It 2 consists of 10 acres in addition to a perpetual .ease- ment right to a strip of land, 10 feet wide and 3600 feet long. The area is located in North Tonawanda, New York near the Niagara River. Because of the growth of adjacent industries, this particular piece of property has appreciated in value. During its tenure as responsible property management office, Oak

411

L,."  

Office of Legacy Management (LM)

- - ' .,:a " i, j ,Jz,2 " &., L,." p" a 4 r. UI R -! " r,.> .p" mm --n "7 :E i"l i_d f-7 i:;i ,. _* T. L. BMI-2074(Revised) _: * ,(4.# -_, FINAL REPORT on A COMPREHENSIVE CHARACTERIZATION AND HAZARD ASSESSMENT OF THE DOE-NIAGARA FALLS STORAGE SITE prepared for U.S. DEPARTMENT OF ENERGY REMEDIAL ACTION PROGRAM June 1981 Anderson, J. F. Dettorre, D. R. Jackson, and B. S. Ausmus" prepared by BATTELLE Columbus Laboratories 505 King Avenue Columbus, Ohio 43201 Under Subcontract for .National Lead Company of Ohio *Cixrently eihployed by B&cht&l N&&al Corporation, Oak Rid&, TN. - - - NOTICE - This report was prepared as an account of work sponsored by the United States Government. Neither the United States Government nor the Depart-

412

- United States Government  

Office of Legacy Management (LM)

8 8 my EFG (07.90) . - United States Government . * Department of. Energy * inemorandum DATE: DEC :! ;j 1993 REPLY TO ATTN OF: EM-421 (W.'A. W illiams, 903-8149) : NY 41 I .' 41 G I? SUBJECT: Elimination of the T itanium Alloy Manufacturing Co., Niagara Falls, New York TO: The F ile I have reviewed the attached site. summary and elimination recommendation for the T itanium Alloy Manufacturing Company. I have determined that the potential for radiological contamination is low because of the lim ited duration of the activities at the site. Further, at least some of the contractual activities at the site were licensed under the Atomic Energy Act, and the licensed activities are thereby disqualified from further consideration under the Department of Energy's Formerly Utilized Sites

413

Microsoft Word - AppendixH_CommentResponse.doc  

Office of Legacy Management (LM)

NFSS Vicinity Property Report NFSS Vicinity Property Report October 2010 Doc. No. S06246 Page H-1 Responsiveness Summary The U.S. Department of Energy (DOE) released the Formerly Utilized Sites Remedial Action Program Niagara Falls Storage Site Vicinity Properties, New York: Review of Radiological Conditions at Six Vicinity Properties and Two Drainage Ditches on April 23, 2010, for public comment. Report availability was announced through a message to stakeholders sent on behalf of DOE by USACE. The announcement provided a 30-day comment period, closing on March 19, 2010. DOE extended the comment period to June 14, 2010, in response to multiple requests for additional time to review FUSRAP documentation. Twenty comments were received, of which five were from one stakeholder and two from

414

LICENSEE  

Office of Legacy Management (LM)

LICENSEE LICENSEE -----e-m LICENSE # _ - - - - - - - 16. Oregon fletallurgical Corp. SNM-144 Albany, OR (Ammended) 17. Pennsylvania Salt Mfg. Company C-3440 Three Penn Center Plaza Philadelphia, PA 8. Southern Research Institute 917 South 20th Street Birmingham, AL 9. Titanium Alloy Mfg. Division National Lead Company Niagara Falls, NY 1 20. Wright Air Development Center Air Research and Development Cormand Wright-Patterson Air Force Bane, Ohio ,, 'r C-3417 C-3413 ,- il i" REMARKS ----_.-- License issued l/28/58 - expired 11/30/62; iOf maximura quantity of 18 Kg of U-235 contained in uranium, as metal, enriched up to 20% in the U-235 isotope. For use in the alloying of uranium and zirconium metal. Authorized for use in the Corporations's plant in Albany, Oregon. Document

415

I  

Office of Legacy Management (LM)

_I _I .' -' ' , I IJ b2 MAR 21 19% ' .I I \i !' The Honorable Anthony Masiello ,65 Niagara Square Buffalo, New ,York 14202 Dear Mayor Masiello: '. Secretary of Energy,Hazel O'Leary has announced a new approach to openness in the Department of Energy (DOE) and its coauiiunications with,the p,ublic. In support of thins initiative, we are pleased tq'forward!the enclosed information related to the-former Linde Air.Products site,in your'jurisdiction that performed work for DOE or its predecessor agencies. This information is provided for your information, use, and,retention. DOE's Formerly Utilized Sites Remedial Action Program is.responsible for. identification of sites used tiy DOE!s predecessor agencies, determining their current radiological condition and,.where it has authority,,.performing

416

ORNL/RASA-85/  

Office of Legacy Management (LM)

e?Ll e?Ll ( U o't /u/ / ORNL/RASA-85/ 4I 4 RESULTS 0FRADI0L0GICALMEASUREMENTSTMENNEA OF BUFFALO AVENUE A'ID HYffi PARK BLVD. IN NIAGARA FALLS' NET{ YORK Access to the inlormation in thit rtport ir limitcd to tho!' ino-icateo on tha distribution list and to oepartmsnt of Encrgy tnd Oepartment ol Enoqy Contracton F This report was prepared as an accountof work sponsored by an agency of the UnitedstatesGovernment.NeithertheUnitedstatesGovernmentnoranyagency thereo|, nor any o| the.r employees, makes any warranty, express or. imp|ied' or "rart". any legal liability or responsibility for the accuracy' completeness' or usefulness of any information, apparatui, product, or process disclosed' or represents that its use wo;ilnoiintting" ptivately-owned

417

Microsoft Word - S06246_VP_Report  

Office of Legacy Management (LM)

NFSS Vicinity Property T NFSS Vicinity Property T This page intentionally left blank Assessment Data Excerpt from Comprehensive Radiological Survey Off-Site Property T Niagara Falls Storage Site Appendix D NFSS Vicinity Property T Page D-1 This page intentionally left blank Appendix D NFSS Vicinity Property T Page D-2 Appendix D NFSS Vicinity Property T Page D-3 Appendix D NFSS Vicinity Property T Page D-4 Appendix D NFSS Vicinity Property T Page D-5 Appendix D NFSS Vicinity Property T Page D-6 Appendix D NFSS Vicinity Property T Page D-7 Appendix D NFSS Vicinity Property T Page D-8 Appendix D NFSS Vicinity Property T Page D-9 Appendix D NFSS Vicinity Property T Page D-10 Appendix D NFSS Vicinity Property T Page D-11 Appendix D NFSS Vicinity Property T Page D-12 Appendix D NFSS Vicinity Property T Page D-13

418

DOE - Office of Legacy Management -- Electromet Corporation - NY 04  

Office of Legacy Management (LM)

Electromet Corporation - NY 04 Electromet Corporation - NY 04 FUSRAP Considered Sites Site: Electromet Corporation (NY.04 ) Eliminated from consideration under FUSRAP - Referred to US EPA and New York State Designated Name: Not Designated Alternate Name: None Location: 4625 Royal Avenue , Niagara Falls , New York NY.04-1 Evaluation Year: 1985 NY.04-2 NY.04-3 Site Operations: Cast zirconium sponge into ingots in the 1950s. NY.04-4 Site Disposition: Eliminated - No Authority NY.04-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium, Zirconium NY.04-4 Radiological Survey(s): Yes NY.04-6 Site Status: Eliminated from consideration under FUSRAP - Referred to US EPA and New York State NY.04-2 Also see Documents Related to Electromet Corporation

419

U.S. DEPARTMENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DETERMINATION  

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

PMC * F F2. et PMC * F F2. et .14)6.02) U.S. DEPARTMENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DETERMINATION RECIPIENT:U.S. ARMY CORPS OF ENGINEERS STATE: NY PROJECT TITLE : NIAGARA RIVER, NY - SMALL HYDROPOWER Funding Opportunity Announcement Number Procurement instrument Number NEPA Control Number CID Number DE-EE0001304 10-049 0 Based on my review of the information concerning the proposed action, as NEPA Compliance Officer (authorized under DOE Order 451.1A), I have made the following determination: CX, EA, EIS APPENDIX AND NUMBER: Description: All Technical advice and planning assistance to international, national, state, and local organizations. A9 Information gathering (including, but not limited to, literature surveys, inventories, audits), data analysis (including

420

Analysis of a 4-inch small-break loss-of-coolant accident in a Westinghouse Pressurized Water Reactor using TRAC-PF1/MOD1  

E-Print Network (OSTI)

the transient response of a Westinghouse 4- loop PWR using 17x17 fuel assemblies in a 14-ft. long reactor core to a 4-inch diameter SBLOCA with the computer code TRAC-PF1/MOD1, This is unique in that there are only two Westinghouse PWRs with 14-ft. cores (The... 4-inch SBLOCAs 65 XI. Comparison of RESAR-3S, TRAC and RELAP SBLOCAs . . 70 LIST OF ACRONYMS Acronym Name CCFL CVCS ECCS EPRI FSAR HPI INEL LB LOCA LOCA LPI MSIV NRC PCT PORV PWR RCP RCS RESAR RHR SI SBLOCA Argonne National...

Knippel, Kimberley I.R.

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

The case for endurance testing of sodium-heated steam generators  

SciTech Connect

After operating pressurized water reactor (PWR) steam generators in U.S. nuclear plants during the past 33 years and plugging thousands of tubes and replacing numerous steam generators at immense costs, utility and steam generator designers are now confident that they can design, build, and operate PWR steam generators successfully. Deployment of liquid-metal fast breeder reactors (LMFBRs) will likely follow the same scenario if long-term testing is not performed and development completed prior to commercial deployment. A case is made for endurance testing of steam generators to be used in future LMFBRs.

Onesto, A.T.; Zweig, H.R.; Gibbs, D.C. (Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Division.); Carlson, R.D. (Argonne National Lab., IL (United States)); Rodwell, E. (Electric Power Research Inst., Palo Alto, CA (United States)); Kakarala, C.R. (Babcock and Wilcox Co., Barberton, OH (United States))

1993-08-01T23:59:59.000Z

422

Investigation of valve failure problems in LWR power plants  

SciTech Connect

An analysis of component failures from information in the computerized Nuclear Safety Information Center (NSIC) data bank shows that for both PWR and BWR plants the component category most responsible for approximately 19.3% of light water reactor (LWR) power plant shutdowns. This investigation by Burns and Roe, Inc. shows that the greatest cause of shutdowns in LWRs due to valve failures is leakage from valve stem packing. Both BWR plants and PWR plants have stem leakage problems (BWRs, 21% and PWRs, 34%).

None

1980-04-01T23:59:59.000Z

423

Oxygen control in makeup water for PWRs  

SciTech Connect

This study describes the oxygen control program and improvements to the make-up water system components of PWR nuclear plants with the ultimate goal of reducing corrosion related problems in the steam generators and other secondary system components. A PWR plant that has a vacuum degasifier has been selected to establish the basis for the program. Following the investigation of the make-up water system components, the report presents instrumentation developed for the program. Recommendations are provided for improvements to the various make-up water system components to lower the dissolved oxygen levels. 5 refs., 23 figs., 3 tabs.

Silaghy, F. (Burns and Roe, Inc., Oradell, NJ (USA))

1990-08-01T23:59:59.000Z

424

Workbook Contents  

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

Propane Weekly Heating Oil and Propane Prices (October - March)" Propane Weekly Heating Oil and Propane Prices (October - March)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Wholesale Propane Weekly Heating Oil and Propane Prices (October - March)",21,"Weekly","12/16/2013","10/7/2013" ,"Release Date:","12/18/2013" ,"Next Release Date:","12/27/2013" ,"Excel File Name:","pet_pri_wfr_a_epllpa_pwr_dpgal_w.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/pet/pet_pri_wfr_a_epllpa_pwr_dpgal_w.htm" ,"Source:","Energy Information Administration"

425

94-A13 Native American Initiative Short Course Management Plan  

SciTech Connect

A training program conducted in Bartlesville by BDM-Oklahoma technical staff, which included geologists, geophysicists, exploration and drilling specialists, and environmental policy experts. The proposed training schedule offered four courses per year and included those coursed identified by the tribes in the survey. The training program was outlined for members of Native American Tribes whose lands have oil and gas resources. The proposed program contributed to meeting the goals of the U.S. Department of Energy's (DOE) Domestic Oil and Gas Initiative to help Native American tribes become more self-sufficient in developing and managing their resources through training in cost-effective, improved technologies for hydrocarbon production that will meet environmental regulations. The training program outlined was for adult tribal representatives who are responsible for managing tribal mineral holdings or setting policy, or who work in the oil and gas industry. The course content is in response to a survey that was developed by BDM-Oklahoma and sent in the Spring of 1995 to 26 tribal agencies identified through previous contact with DOE. Tribes were asked to indicate course content needs, levels, preferred time of year, and location. Six tribes responded with specific recommendations and needs. These tribes, were the Creek, Pueblo, Cherokee, St. Regis Mohawk, Northern Arapho, and Ute Mountain Ute.

Carroll, Herbert B.; Johnson, William I.; Kokesh, Judith H.

1999-04-27T23:59:59.000Z

426

Co-combustion feasibility study. Final report  

SciTech Connect

This report investigates the technical and economic feasibility of co-combusting municipal sewage sludge produced by the Saratoga County Sewer District No. 1 with paper mill sludge produced by the Cottrell Paper Company, Encore Paper Company, International Paper Company, Mohawk Paper Mills, and TAGSONS Papers at the Saratoga County Sewer District No. 1`s secondary wastewater treatment plant and recovering any available energy products. The co-combustion facility would consist of sludge and wood chip storage and conveying systems, belt filter presses, screw presses, fluidized-bed incinerators, venturi scrubbers and tray cooling systems, ash dewatering facilities, heat recovery steam generators, gas-fired steam superheaters, and a back-pressure steam turbine system. Clean waste wood chips would be used as an auxiliary fuel in the fluidized-bed incinerators. It is recommended that the ash produced by the proposed facility be beneficially used, potentially as a raw material in the manufacture of cement and/or as an interim barrier layer in landfills.

Handcock, D.J. [Clough, Harbour and Associates, Albany, NY (United States)

1995-01-01T23:59:59.000Z

427

Wear damage resulting from sliding impact kinematics in pressurized high temperature water: energetical and  

E-Print Network (OSTI)

1 Wear damage resulting from sliding impact kinematics in pressurized high temperature water and Cecile Langlade2,3 1 FRAMATOME-ANP Technical Center, Avenue B. Marcet, Porte Magenta, 71200 Le Creusot.bec@ec-lyon.fr Abstract Specific wear of Rod Cluster Control Assemblies (RCCA) in Pressurized Water nuclear Reactors (PWR

Paris-Sud XI, Université de

428

Expert assessments of the cost of light water small modular reactors  

Science Journals Connector (OSTI)

...viability of SMRs as an energy source. These include...variable and intermittent renewable power into systems...likely evolution of the energy system over the next...25-150 26 2 FBNR FURGS Brazil iPWR 72 26 3 ACP100...HTR 240 26 20 G4M Gen 4 Energy USA LMR 25 26 21 SMR-160...

Ahmed Abdulla; Ins Lima Azevedo; M. Granger Morgan

2013-01-01T23:59:59.000Z

429

Nuclear Regulatory Commission issuances, January 1995. Volume 41, Number 1  

SciTech Connect

This book contains issuances of the Atomic Safety and Licensing Boards for January 1995. The issuances include Babcock and Wilcox Company materials license; Hydro Resources, Inc. application for uranium mining; low-level waste storage in Utah; communication of emerging and existing generic, technical issues with PWR owners groups; and radioactive waste management by Sierra Nuclear Corporation.

NONE

1995-01-01T23:59:59.000Z

430

A Preliminary Study to Assess Model Uncertainties in Fluid Flows  

E-Print Network (OSTI)

. . . . . . . . . . . . . . . . . . . . . . . . 22 E. Convergence criteria, scaling and preconditioner . . . . . . 25 F. Numerical flux . . . . . . . . . . . . . . . . . . . . . . . . . 26 G. Complete form of the discretized equations . . . . . . . . . 27 V CODE VERIFICATION... REACTOR (PWR) EXAMPLE . . . 40 A. Characteristic data for PWRs . . . . . . . . . . . . . . . . 40 B. Steady-state and transient . . . . . . . . . . . . . . . . . . 42 1. Steady-state . . . . . . . . . . . . . . . . . . . . . . . 42 2. Pseudo...

Delchini, Marc Olivier

2011-08-08T23:59:59.000Z

431

Numerical Simulation of Enhanced Mixing in Scramjet Combustor Using Ramp, Tabs and Suction Collar  

E-Print Network (OSTI)

Projects Agency (DARPA), NASA, Pratt & Whitney Rocketdyne (PWR), and Boeing X-51A Scramjet Engine Demonstrator-WaveRider (SED) vehicle, has been developed and started to test in a series of 4 flight test beginning in August 2009. Developing scramjet...

Hwang, Seung-Jae

2011-06-09T23:59:59.000Z

432

Study of the burning capability of the los alamos ATW system  

Science Journals Connector (OSTI)

The aim of calculations is to evaluate the evolution of the infinite multiplication factor (k inf) during the irradiation of minor actinides High Level Waste (HLW) and Plutonium. The most important results are independently verified with Monte Carlo calculations. The relative importance of the main parameters affecting the k inf was investigated by performing calculations with several minor actinide and plutonium concentrations as well as different 238U decontamination factors for HLW. The merit figure value for minor actinide alone considering a constant neutron flux indicates that the best results are reached for minor actinide concentration equal to PWR spent fuel. The best plutonium burning results are obtained for a concentration (50.23 g/l) equal to the half of PWR spent fuel one. The simulations lead to two different reactor concepts: one for HLW burning and the other for plutonium burning purposes. To burn the HLW the most suitable reactor is an homogeneous one. This kind of reactor can effectively be utilised to burn minor actinide in low concentration (namely the PWR spent fuel). On the other hand an heterogeneous reactor with channels filled by all actinides present in PWR spent fuel with the exclusion of U isotopes with a concentration of 50 g/l can be studied.

P. A. Landeyro; A. Buccafurni; A. Orazi

1995-01-01T23:59:59.000Z

433

Non-Intrusive Experiemental Investigation of Multi-Scale Flow Behavior in Rod Bundle with Spacer-Grids  

E-Print Network (OSTI)

5 x 5 rod bundle with spacer-grids. Measurements were performed using two different grid designs. One typical of Boiling Water Reactors (BWR) with swirl type mixing vanes and the other typical of Pressurized Water Reactors (PWR) with split type...

Dominguez Ontiveros, Elvis Efren

2011-08-08T23:59:59.000Z

434

Department of Energy's team's analyses of Soviet designed VVERs (water-cooled water-moderated atomic energy reactors)  

SciTech Connect

This document contains apprendices A through P of this report. Topics discussed are: a cronyms and technical terms, accident analyses reactivity control; Soviet safety regulations; radionuclide inventory; decay heat; operations and maintenance; steam supply system; concrete and concrete structures; seismicity; site information; neutronic parameters; loss of electric power; diesel generator reliability; Soviet codes and standards; and comparisons of PWR and VVER features. (FI)

Not Available

1989-09-01T23:59:59.000Z

435

Research Collaboration with local Centers of  

E-Print Network (OSTI)

Faculty 2014 Enrollment 2013 Graduates Brief History For more information, see our Annual Report at www.engr.utk.edu/nuclear, and Control Laboratory · PWR Simulator (hardware and software) · Radiochemistry and Nuclear Forensics in the past 56 years · 85 MW High Flux Isotope Reactor (HFIR) · Spallation Neutron Source (SNS) · Nuclear

Tennessee, University of

436

Safety Aspects of Nuclear Desalination with Innovative Systems; the EURODESAL Project  

SciTech Connect

The proposed paper reports the results of a preliminary investigation on safety impact deriving from the coupling of a desalination plant with a 600 MWe Passive Design PWR like the AP600 Nuclear Power Plant. This evaluation was performed in the frame of the EURODESAL Project of the 5. EURATOM Framework Programme. (authors)

Alessandroni, C.; Cinotti, L.; Mini, G. [Ansaldo Nucleare, C.so Perrone, 25 - Genova (Italy); Nisan, S. [CEA-CEN Cadarache, F-13108 Saint Paul-lez-Durance (France)

2002-07-01T23:59:59.000Z

437

SIGNAL GROUPING FOR CONDITION MONITORING OF NUCLEAR POWER PLANT COMPONENTS  

E-Print Network (OSTI)

between those used to monitor the reactor coolant pump of a Pressurized Water Reactor (PWR) is considered signal result in a hal-00721033,version1-26Jul2012 Author manuscript, published in "Reliability and Risk measured in different subsystems having the same function). A preliminary analysis has identified: 1

Paris-Sud XI, Université de

438

Brief History Degrees Offered  

E-Print Network (OSTI)

Testing and Analysis Center · Y-12 National Security Complex · Reliability and Maintainability Center Laboratory · Prognostics, Reliability, and Control Laboratory · PWR Simulator (hardware and software · Expenditures = $8.2 million: ($635K per FTE) · 85 MW High Flux Isotope Reactor (HFIR) · Spallation Neutron

Wang, Xiaorui "Ray"

439

An ensemble approach to sensor fault detection and signal reconstruction for nuclear system control  

E-Print Network (OSTI)

within an ensemble of Principal Component Analysis (PCA) models whose outcomes are aggregated by means Reactor (PWR). The obtained results show the possibility to achieve an adequate control of the process to assess the reliability of the measurement and to opportunely plan the sensor maintenance. Additionally

Paris-Sud XI, Université de

440

Pharmacokinetics and Virological Efficacy after Switch to Once-Daily Lopinavir-Ritonavir in Treatment-Experienced HIV-1-Infected Children  

Science Journals Connector (OSTI)

...drug monitoring data, so no informed...levels, or viral loads, in blood samples...of LPV/r. The data were analyzed using...individual. The PWR (power) exponents may...88.9) Viral load 1.7 log10 HIV...pharmacokinetics. The data were best described...using the fixed power exponents 0.75...

Frantz Foissac; Sak Urien; Dborah Hirt; Pierre Frange; Marie-Laure Chaix; Jean-Marc Treluyer; Stphane Blanche

2011-07-11T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Flat Quartz-Crystal X-ray Spectrometer for Nuclear Forensics Applications  

E-Print Network (OSTI)

bulk Pu in SNF is measuring the self-induced x-ray fluorescence (XRF). Previous XRF measurements of Three Mile Island (TMI) PWR SNF taken in July 2008 and January 2009 at Oak Ridge National Laboratory (ORNL) successfully illustrated the ability...

Goodsell, Alison

2012-10-19T23:59:59.000Z

442

Genetic algorithm-based wrapper approach for grouping condition monitoring signals of  

E-Print Network (OSTI)

) of a Pressurized Water Reactor (PWR). The optimization results are evaluated with respect to the accuracy monitoring of nuclear power plants requires to optimally group the usually very large number of signals- proach to optimally group the signals. We use a Genetic Algorithm (GA) for the optimization of the groups

Boyer, Edmond

443

Recent results on the RIA test in IGR reactor  

SciTech Connect

At the 23d WRSM meeting the data base characterizing results of VVER high burnup fuel rods tests under reactivity-initiated accident (RIA) conditions was presented. Comparison of PWR and VVER failure thresholds was given also. Additional analysis of the obtained results was being carried out during 1996. The results of analysis show that the two different failure mechanisms were observed for PWR and VVER fuel rods. Some factors which can be as the possible reasons of these differences are presented. First of them is the state of preirradiated cladding. Published test data for PWR high burnup fuel rods demonstrated that the PWR high burnup fuel rods failed at the RIA test are characterized by very high level of oxidation and hydriding for the claddings. Corresponding researches were performed at Institute of Atomic Reactors (RLAR, Dimitrovgrad, Russia) for large set of VVER high burnup fuel rods. Results of these investigations show that preirradiated commercial Zr-1%Nb claddings practically keep their initial levels of oxidation and H{sub 2} concentration. Consequently the VVER preirradiated cladding must keep the high level of mechanical properties. The second reason leading to differences between failure mechanisms for two types of high burnup fuel rods can be the test conditions. Now such kind of analysis have been performed by two methods.

Asmolov, V.; Yegorova, L. [Nuclear Safety Institute, Moscow (Russian Federation)

1997-01-01T23:59:59.000Z

444

Conceptual design of spectrum changeable neutron calibration fields in JAERI/FRS  

Science Journals Connector (OSTI)

......PWR, HTGR, FBR), accelerators (48 cases; cyclotron...production, processing), nuclear fuel processing plants...means other than using accelerator-produced neutrons...a Van-de-Graaff accelerator. In the SCNCF, neutron...target, which was vacuum-evaporated on 0......

J. Saegusa; Y. Tanimura; M. Yoshizawa; M. Yoshida

2004-08-01T23:59:59.000Z

445

DEVELOPMENT OF ALTERNATE METHODS OF DETERMINING INTEGRATED SMR SOURCE TERMS  

SciTech Connect

The Nuclear Energy Institute (NEI) Small Modular Reactor (SMR) Licensing Task Force (TF) has been evaluating licensing issues unique and important to iPWRs, ranking these issues, and developing NEI position papers for submittal to the U.S. Nuclear Regulatory Commission (NRC) during the past three years. Papers have been developed and submitted to the NRC in a range of areas including: Price- Anderson Act, NRC annual fees, security, modularity, and staffing. In December, 2012, NEI completed a draft position paper on SMR source terms and participated in an NRC public meeting presenting a summary of this paper, which was subsequently submitted to the NRC. One important conclusion of the source term paper was the evaluation and selection of high importance areas where additional research would have a significant impact on source terms. The highest ranked research area was iPWR containment aerosol natural deposition. The NRC accepts the use of existing aerosol deposition correlations in Regulatory Guide 1.183, but these were developed for large light water reactor (LWR) containments. Application of these correlations to an iPWR design has resulted in greater than a ten-fold reduction of containment airborne aerosol inventory as compared to large LWRs. Development and experimental justification of containment aerosol natural deposition correlations specifically for the unique iPWR containments is expected to result in a large reduction of design basis and beyond-design-basis accident source terms with concomitantly smaller dose to workers and the public. Therefore, NRC acceptance of iPWR containment aerosol natural deposition correlations will directly support the industrys goal of reducing the Emergency Planning Zone (EPZ) for SMRs. Based on the results in this work, it is clear that thermophoresis is relatively unimportant for iPWRs. Gravitational settling is well understood, and may be the dominant process for a dry environment. Diffusiophoresis and enhanced settling by particle growth are the dominant processes for determining DFs for expected conditions in an iPWR containment. These processes are dependent on the areato- volume (A/V) ratio, which should benefit iPWR designs because these reactors have higher A/Vs compared to existing LWRs.

Barry, Kenneth

2014-06-10T23:59:59.000Z

446

U.S. Department of Energy Categorical Exclusion Determination Form  

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

Pratt & Whitney Rocketdyne - Pratt & Whitney Rocketdyne - Continuous Detonation Engine Combustor for Natural Gas Turbine Program or Field Office: Advanced Research Project Agency- Energy Location(s) (CitvJCouuty/Statel: Simi Valley, CA; East Hartford, CT Proposed Action Description: Pratt & Whitney Rocketdyne (PWR), in conjunction with United Technologies Research Center (UTRC), will design, build, and test small-scale continuous detonation combustion in a simulated gas turbine environment to establish the feasibility of incorporating this technology into natural- gas-fueled gas turbine electric generator. PWR and UTRC will conduct combustion testing at UTRC's Jet Burner Test Facility in East Hartford, CT, where activities of this nature are routinely conducted and administrative and engineering controls are in place to reduce potential risks. Additional project activities will be carried

447

Page not found | Department of Energy  

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

61 - 11170 of 28,905 results. 61 - 11170 of 28,905 results. Download Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Structural analyses of high-burnup (HBU) fuel require cladding mechanical properties and failure limits to assess fuel behavior during long-term dry-cask storage and transportation. http://energy.gov/ne/downloads/embrittlement-and-dbtt-high-burnup-pwr-fuel-cladding-alloys Download Application to Export Electric Energy OE Docket No. EA-294-B TexMex Energy LLC, Federal Register Notice, Volume 77, No. 162- Aug. 21, 2012 Application from TexMex Energy to export electric energy to Mexico. Federal Register Notice. http://energy.gov/oe/downloads/application-export-electric-energy-oe-docket-no-ea-294-b-texmex-energy-llc-federal Download DOE Reasonable Accommodation Procedures

448

Workbook Contents  

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

Heating Oil Weekly Heating Oil and Propane Prices (October - March)" Heating Oil Weekly Heating Oil and Propane Prices (October - March)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Wholesale Heating Oil Weekly Heating Oil and Propane Prices (October - March)",32,"Weekly","12/16/2013","10/7/2013" ,"Release Date:","12/18/2013" ,"Next Release Date:","12/27/2013" ,"Excel File Name:","pet_pri_wfr_a_epd2f_pwr_dpgal_w.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/pet/pet_pri_wfr_a_epd2f_pwr_dpgal_w.htm" ,"Source:","Energy Information Administration"

449

Nuclear reactor characteristics and operational history  

Gasoline and Diesel Fuel Update (EIA)

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

450

Page not found | Department of Energy  

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

31 - 7840 of 8,172 results. 31 - 7840 of 8,172 results. Download Brine Migration Experimental Studies for Salt Repositories Experiments were used to examine water content in Permian salt samples including impact of variation in thermal regime on water content of evaporites and other mineral species, behavior of brine inclusions in salt, and evolution of the gas/liquid brine/salt system. http://energy.gov/ne/downloads/brine-migration-experimental-studies-salt-repositories Download Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Structural analyses of high-burnup (HBU) fuel require cladding mechanical properties and failure limits to assess fuel behavior during long-term dry-cask storage and transportation. http://energy.gov/ne/downloads/embrittlement-and-dbtt-high-burnup-pwr-fuel-cladding-alloys

451

The Draft of ASME PTC 19  

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

ASME0027 1 Copyright © 2006 Siemens Power Generation, Inc. ASME0027 1 Copyright © 2006 Siemens Power Generation, Inc. Proceedings of PWR2006 2006 Joint Conference of ASME Power and Electric Power May 2-4, 2006, Atlanta, GA, USA PWR2006-88112 TURNING NGCC INTO IGCC: CYCLE RETROFITTING ISSUES Juan Pablo Gutierrez, MSc. Siemens Power Generation 4400 Alafaya Trail Q2-286 Orlando, FL 32826 Juangutierrez@siemens.com Terry B. Sullivan, P.E. Siemens Power Generation 4400 Alafaya Trail Q2-286 Orlando, FL 32826 Terry.Sullivan@siemens.com Gerald J. Feller, Ph.D. Siemens Power Generation 4400 Alafaya Trail Q2-286 Orlando, FL 32826 Gerald.Feller@siemens.com ABSTRACT The increase in price of natural gas and the need for a cleaner technology to generate electricity has motivated the power industry to move towards Integrated

452

Page not found | Department of Energy  

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

41 - 8150 of 26,764 results. 41 - 8150 of 26,764 results. Download 48C Qualifying Advanced Energy Project Credit Questions http://energy.gov/downloads/48c-qualifying-advanced-energy-project-credit-questions Download Slide 1 http://energy.gov/downloads/slide-1-25 Download American Recovery & Reinvestment Act, ARRA, clean energy projects, energy efficiency, smart grid, alternative fuels, geothermal energy http://energy.gov/downloads/american-recovery-reinvestment-act-arra-clean-energy-projects-energy-efficiency-smart-grid Download Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Structural analyses of high-burnup (HBU) fuel require cladding mechanical properties and failure limits to assess fuel behavior during long-term dry-cask storage and transportation. http://energy.gov/ne/downloads/embrittlement-and-dbtt-high-burnup-pwr-fuel-cladding-alloys

453

NETL: Oxy-Fired Pressurized Fluidized Bed Combustor (Oxy-PFBC)  

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

Oxy-Fired Pressurized Fluidized Bed Combustor (Oxy-PFBC) Oxy-Fired Pressurized Fluidized Bed Combustor (Oxy-PFBC) Project No.: DE-FE0009448 Oxy-PFBC Layout. Oxy-PFBC Layout. Pratt and Whitney Rocketdyne (PWR) is developing an oxy-fired pressurized fluidized bed combustor (Oxy-PFBC). Pressurized combustion with oxygen enables high efficiency through staged combustion, which results in reduced oxygen use, as well as through recovery of high quality heat from exhaust water vapor. In addition, the process can result in reduced costs for utilization or storage of CO2 because the CO2 is available at increased pressure, reducing compression requirements. Overall, pressurized fluidized bed combustion can result in electricity production from coal with near-zero emissions. PWR will be testing a novel process for pressurized oxy-combustion in a

454

Five Years of Building the Next Generation of Reactors | Department of  

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

Five Years of Building the Next Generation of Reactors Five Years of Building the Next Generation of Reactors Five Years of Building the Next Generation of Reactors August 15, 2012 - 5:17pm Addthis Simulated three-dimensional fission power distribution of a single 17x17 rod PWR fuel assembly. | Photo courtesy of the Consortium for Advanced Simulation of Light Water Reactors (CASL). Simulated three-dimensional fission power distribution of a single 17x17 rod PWR fuel assembly. | Photo courtesy of the Consortium for Advanced Simulation of Light Water Reactors (CASL). Doug Kothe Director, Consortium for Advanced Simulation of Light Water Reactors What are the key facts? CASL has the virtual capability to look closely at reactor core models. These models operate with 193 fuel assemblies, nearly 51,000 fuel rods, and about 18 million fuel pellets.

455

Cavitation and two-phase flow characteristics of SRPR (Savannah River Plant Reactor) pump. Final report  

SciTech Connect

The possible head degradation of the SRPR pumps may be attributable to two independent phenomena, one due to the inception of cavitation and the other due to the two-phase flow phenomena. The head degradation due to the appearance of cavitation on the pump blade is hardly likely in the conventional pressurized water reactor (PWR) since the coolant circulating line is highly pressurized so that the cavitation is difficult to occur even at LOCA (loss of coolant accident) conditions. On the other hand, the suction pressure of SRPR pump is order-of-magnitude smaller than that of PWR so that the cavitation phenomena, may prevail, should LOCA occur, depending on the extent of LOCA condition. In this study, therefore, both cavitation phenomena and two-phase flow phenomena were investigated for the SRPR pump by using various analytical tools and the numerical results are presented herein.

Not Available

1991-07-01T23:59:59.000Z

456

Pressurized water reactor fuel assembly subchannel void fraction measurement  

SciTech Connect

The void fraction measurement experiment of pressurized water reactor (PWR) fuel assemblies has been conducted since 1987 under the sponsorship of the Ministry of International Trade and Industry as a Japanese national project. Two types of test sections are used in this experiment. One is a 5 x 5 array rod bundle geometry, and the other is a single-channel geometry simulating one of the subchannels in the rod bundle. Wide gamma-ray beam scanners and narrow gamma-ray beam computed tomography scanners are used to measure the subchannel void fractions under various steady-state and transient conditions. The experimental data are expected to be used to develop a void fraction prediction model relevant to PWR fuel assemblies and also to verify or improve the subchannel analysis method. The first series of experiments was conducted in 1992, and a preliminary evaluation of the data has been performed. The preliminary results of these experiments are described.

Akiyama, Yoshiei [Mitsubishi Heavy Industries, Ltd., Yokohama (Japan). Nuclear Fuel and Core Engineering Dept.; Hori, Keiichi [Mitsubishi Heavy Industries, Ltd., Hyougo (Japan); Miyazaki, Keiji [Osaka Univ. (Japan). Faculty of Engineering; Mishima, Kaichiro [Kyoto Univ., Osaka (Japan). Research Reactor Inst.; Sugiyama, Shigekazu [Nuclear Power Engineering Corp., Tokyo (Japan). Nuclear Fuel Dept.

1995-12-01T23:59:59.000Z

457

Optimal Coupling of a Nuclear Reactor and a Thermal Desalination Plant  

SciTech Connect

The present study, performed in the framework of the EURODESAL Project (5. EU FWP), deals with the analysis of the 'optimum' coupling of a PWR and of a HTGR plant with a thermal desalination plant, based on the Multiple Effects process. The reference reactors are the AP600 and the PWR900 as Pressurized reactors and the GT-MHR as Gas reactor. The calculations performed show that there are several technical solutions allowing to couple PWRs and GRs to a ME desalination plant. The optimization criteria concern the technical feasibility of the coupling, producing the maximum quantity of fresh water at the lower cost, without unacceptable reduction of the electrical power produced and without undue health hazard for population. (authors)

Caruso, G.; Naviglio, A. [University of Rome 'La Sapienza' - Dince, Corso Vittorio Emanuele II, 244 - 00186 Rome (Italy); Nisan, S. [CEA/CEN Cadarache. DER/SERI, F-13108 Saint Paul-lez-Durance (France); Asuar Alonso, O. [Empresarios Agrupados Internacional, SA (Spain); Bielak, B. [Framatome ANP (France); Cinotti, L. [Ansaldo Nucleare (Italy); Humphries, J.R. [Candesal Technologies (Canada); Martins, N. [Irradiare Lda (Portugal); Volpi, L. [CEA, CEN Cadarache, DER/SERI (France)

2002-07-01T23:59:59.000Z

458

Effect of heat treatment on stress corrosion of Alloy 718 in pressurized-water-reactor primary water  

SciTech Connect

Stress corrosion cracking (SCC) tests were conducted in 360{degrees}C pressurized-water-reactor (PWR) primary water using alloy 718 in various heat treatment conditions. Alloy X-750 in the HTH condition and an experimental heat of an alloy 718 variation, Hicoroy, were also tested for comparison. Fatigue-precracked, 12.5-mm-thick compact fracture specimens were subjected to a constant extension rate of 1.3 x 10{sup {minus}9} m/s. Crack growth rate was measured during testing using a reversing DC potential drop technique. Results in the form of SCC crack growth rate versus applied stress intensity demonstrate that the SCC resistance of alloy 718 in the PWR primary-side environment can be improved by changes in heat treatment.

Miglin, M.T.; Monter, J.V.; Wade, C.S. [Babcock & Wilcox Co., Alliance, OH (United States); Nelson, J.L. [Electric Power Research Institute, Palo Alto, CA (United States)

1992-12-31T23:59:59.000Z

459

SHARP Neutronics Expanded | Department of Energy  

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

SHARP Neutronics Expanded SHARP Neutronics Expanded SHARP Neutronics Expanded January 29, 2013 - 1:28pm Addthis Fully heterogeneous predictions of thermal neutron flux in a hypothetical metal-oxide-fueled PWR Fully heterogeneous predictions of thermal neutron flux in a hypothetical metal-oxide-fueled PWR SHARP neutronics Module Development The SHARP neutronics module, PROTEUS, includes neutron and gamma transport solvers and cross-section processing tools as well as the capability for depletion and fuel cycle analysis. The existing high-fidelity solver package was extended to be independent of reactor technology and demonstrated with 2-D MOC and Sn method simulations of LWR core configurations. Efforts to support verification and validation of the DeCART code, used as one reference solution method by the SHARP code

460

Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - I: DUPIC Fuel Fabrication Cost  

SciTech Connect

A preliminary conceptual design of a Direct Use of spent Pressurized water reactor (PWR) fuel In Canada deuterium uranium (CANDU) reactors (DUPIC) fuel fabrication plant was studied, which annually converts spent PWR fuel of 400 tonnes heavy element (HE) into CANDU fuel. The capital and operating costs were estimated from the viewpoint of conceptual design. Assuming that the annual discount rate is 5% during the construction (5 yr) and operation period (40 yr) and contingency is 25% of the capital cost, the levelized unit cost (LUC) of DUPIC fuel fabrication was estimated to be 616 $/kg HE, which is mostly governed by annual operation and maintenance costs that correspond to 63% of LUC. Among the operation and maintenance cost components being considered, the waste disposal cost has the dominant effect on LUC ({approx}49%). From sensitivity analyses of production capacity, discount rate, and contingency, it was found that the production capacity of the plant is the major parameter that affects the LUC.

Choi, Hangbok; Ko, Won Il; Yang, Myung Seung [Korea Atomic Energy Research Institute (Korea, Republic of)

2001-05-15T23:59:59.000Z

Note: This page contains sample records for the topic "niagara mohawk pwr" 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

Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - III: Spent DUPIC Fuel Disposal Cost  

SciTech Connect

The disposal costs of spent pressurized water reactor (PWR), Canada deuterium uranium (CANDU) reactor, and DUPIC fuels have been estimated based on available literature data and the engineering design of a spent CANDU fuel disposal facility by the Atomic Energy of Canada Limited. The cost estimation was carried out by the normalization concept of total electricity generation. Therefore, the future electricity generation scale was analyzed to evaluate the appropriate capacity of the high-level waste disposal facility in Korea, which is a key parameter of the disposal cost estimation. Based on the total electricity generation scale, it is concluded that the disposal unit costs for spent CANDU natural uranium, CANDU-DUPIC, and PWR fuels are 192.3, 388.5, and 696.5 $/kg heavy element, respectively.

Ko, Won Il; Choi, Hangbok; Roh, Gyuhong; Yang, Myung Seung [Korea Atomic Energy Research Institute (Korea, Republic of)

2001-05-15T23:59:59.000Z

462

TECHNOLOGY DEVELOPMENT ON THE DUPIC SAFEGUARDS SYSTEM  

SciTech Connect

A safeguards system has been developed since 1993 in the course of supporting a fuel cycle process to fabricate CANDU fuel with spent PWR fuel (known as Direct Use of PWR spent fuel In CANDU, DUPIC). The major safeguards technology involved here was to design and fabricate a neutron coincidence counting system for process accountability, and also an unattended continuous monitoring system in association with independent verification by the IAEA. This combined technology was to produce information of nuclear material content and to maintain knowledge of the continuity of nuclear material flow. In addition to hardware development, diagnosis software is being developed to assist data acquisition, data review, and data evaluation based on a neural network system on the IAEA C/S system.

H. KIM; H. CHA; ET AL

2001-02-01T23:59:59.000Z

463

Development of High-Pressure Dry Feed Pump for Gasification Systems  

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

Pressure Dry Feed Pressure Dry Feed Pump for Gasification Systems Background Even though coal-based power generation via Integrated Gasification Combined Cycle (IGCC) is more efficient, cleaner, and uses less water than conventional pulverized coal burning systems, widespread IGCC deployment has not occurred because of its relatively high cost. The Pratt & Whitney Rocketdyne (PWR) high-pressure dry feed pump addresses IGCC cost disparity by enabling lower cost and more reliable coal feed

464

Integrating Energy Markets: Does Sequencing Matter?  

E-Print Network (OSTI)

the nuclear power stations: the aging Magnox stations, the more modern Advanced Gas Cooled Reactors, whose earlier troubled history of delays appeared to have ended around 1990, and one PWR under construction. All these nuclear plant were inflexible and ran... : National Power, PowerGen, and Nuclear Electric. All except Nuclear Electric were privatized, although the modern stations of Nuclear Electric were subse- quently sold as British Energy in 1996. Nuclear Electric, as its name suggests, contained all...

Neuhoff, Karsten; Newbery, David

465

An autonomous long-term fast reactor system and the principal design limitations of the concept  

E-Print Network (OSTI)

Actinides MOX Mixed OXide MSR Molten-Salt Reactors NERI Nuclear Energy Research Initiative vii PWR Pressurized Water Reactor RGPu Reactor-Grade Plutonium SCNES Self-Consistent Nuclear Energy System STAR Secure Transportable Autonomous Reactor... of LWR?s, the drastic increase of Am and Cm inventories are observed after uranium fuel irradiation and the second recycling of MOX fuel.1 Therefore, partitioning and transmutation of the recovered MA?s could significantly reduce the long...

Tsvetkova, Galina Valeryevna

2004-09-30T23:59:59.000Z

466

Radiation Exposure Information Reporting System (REIRS) Update, 2012  

SciTech Connect

A series of graphs gives data through the year 2012 for annual collective doses, collective dose per reactor, number of individuals with measurable doses both in total and per reactor, number of reactors, electricity generated, measurable doses per individual and per megawatt-year, and collective outage hours. Reactors considered include BWR, PWR, and LWR. Also, the total effective dose equivalent for the period 2010-2012 is tabulated for each nuclear power plant considered, and the change over 2009-2011.

none,

2013-01-01T23:59:59.000Z

467

Radiation Exposure Information Reporting System (REIRS) Update, 2012, Presented at the 32nd Annual International Dosimetry and Records Symposium, June 2-6, 2013  

SciTech Connect

A series of graphs gives data through the year 2012 for annual collective doses, collective dose per reactor, number of individuals with measurable doses both in total and per reactor, number of reactors, electricity generated, measurable doses per individual and per megawatt-year, and collective outage hours. Reactors considered include BWR, PWR, and LWR. Also, the total effective dose equivalent for the period 2010-2012 is tabulated for each nuclear power plant considered, and the change over 2009-2011.

none,

2013-01-01T23:59:59.000Z

468

Analysis of tru-fueled vhtr prismatic core performance domains  

E-Print Network (OSTI)

Regulatory Commission ORNL Oak Ridge National Laboratory P&T Partitioning and Transmutation PUREX Plutonium Uranium Reduction and Oxidation PWR Pressurized Water Reactor RGPu Reactor Grade Plutonium SCWCR Super-critical Water Cooled Reactor SFR Sodium.... The neutronics analysis using the 3D, whole-core VHTR model was performed using the ORNL SCALE (Standardized Computer Analysis for Licensing Evaluation) code system. The standard SCALE 5.1 TRITON sequence has been upgraded to allow fuel cycle modeling...

Lewis, Tom Goslee

2009-05-15T23:59:59.000Z

469

32 A. Agung et al. / Nuclear Engineering and Design 257 (2013) 3144 rod bank withdrawal at power, feedwater disturbances, Loss-Of-  

E-Print Network (OSTI)

#12;32 A. Agung et al. / Nuclear Engineering and Design 257 (2013) 31­44 rod bank withdrawal of the Ringhals-3 PWR. A nuclear power plant is a strongly coupled and complex system, in which there is a strong.0 (Downar et al., 2010) and the RELAP5 mod 3.3 (U.S. Nuclear Regulatory Commission: U.S. NRC, 2006) codes

Demazière, Christophe

470

U.S. Spent Nuclear Fuel Data as of December 31,2002 Table 3  

Gasoline and Diesel Fuel Update (EIA)

7 7 Table 1 | Table 2 Table 3. Annual Spent Fuel Discharges and Burnup, 1968 - 2002 Year Number of Assemblies a Initial Uranium Content (Metric Tonnes of Uranium) Average Burnup (GWDt/ MTU) All Discharged Assemblies BWR PWR HTGR Total BWR PWR HTGR Total BWR PWR HTGR 1968 5 0 0 5 0.6 0.6 1.7 1969 97 0 0 97 9.9 9.9 16.6 1970 29 99 0 128 5.6 39.0 44.6 0.3 18.4 1971 413 113 0 526 64.7 44.5 109.2 8.3 23.8 1972 801 282 0 1,083 145.8 99.9 245.7 7.1 22.1 1973 564 165 0 729 93.5 67.1 160.6 13.2 24.2 1974 1,290 575 0 1,865 241.6 207.7 449.3 13.1 18.4 1975 1,223 797 0 2,020 225.9 321.7 547.6 17.1 18.2 1976 1,666 931 0 2,597 298.1 401.0 699.1 13.6 22.4

471

Microsoft PowerPoint - Proceedings Cover Sheets  

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

Hitting the Climate Wall Hitting the Climate Wall Annual Carbon Commitment All Existing Energy Sources 0 1 2 3 4 5 6 7 8 9 10 Annual Lifetime New Pwr 2005 Lifetime New Pwr 2010 Lifetime New Pwr 2015 Billion tonnes C New Coal New Coal New Coal New Gas New Gas New Gas Lifetime Emissions of Annual New Fossil Investment 6.8 6.6 7.9 8.9 Source: new fossil capacity, IEA, WEO 2004 New Coal Build by Decade 0 200 400 600 800 G W C o a l Other Developing 43 90 128 India 16 48 79 China 150 168 226 Transition 1 11 19 OECD 12 184 218 2003-2010 2011-2020 2021-2030 Source: IEA, WEO 2004 221 500 670 Incremental new coal capacity by decade New Coal Plant Emissions Equal All Historic Coal CO 2 145 143 0 50 100 150 1751-2000 Total Coal New Coal Plants Lifetime Emissions Billion tonnes Carbon Source: ORNL, CDIAC; IEA, WEO 2004 27% of remaining budget for 450 ppm Fossil is Pulling Ahead

472

NUREG-1150 risk assessment results  

SciTech Connect

The methodology developed in support of the US Nuclear Regulatory Commission's (NRC's) evaluation of severe accident risks in NUREG-1150 is noted. This paper discusses the results. The principal technical analyses for NUREG-1150 were performed at Sandia National Labs. under the Severe Accident Risk Reduction Program and the Accident Sequence Evaluation Program. The analyses have been completed so far for four reference plants: (a) a pressurized water reactor (PWR) with a dry, subatmospheric containment (Surry Unit 1), (b) a PWR with an ice condenser containment (Sequoyah Unit 1), (c) a boiling water reactor (BWR) with a Mark I containment (Peach Bottom Unit 2), and (d) a BWR with a Mark III containment (Grand Gulf Unit 1). A fifth NUREG-1150 plant, a PWR with a large, dry containment (Zion Unit 1), has been evaluated separately by Brookhaven National Lab. Sample risk results for one of the plants (Surry) are presented. The results for Sequoyah, Peach Bottom, and Grand Gulf are broadly compared with those for Surry.

Benjamin, A.S.; Kunsman, D.M.; Boyd, G.J.; Lewis, S.R.; Amos, C.N.; Smith, L.N.

1987-01-01T23:59:59.000Z

473

Materials Reliability Program Resistance to Primary Water Stress Corrosion Cracking of Alloys 690, 52, and 152 in Pressurized Water Reactors (MRP-111)  

SciTech Connect

Over the last thirty years, stress corrosion cracking in PWR primary water (PWSCC) has been observed in numerous Alloy 600 component items and associated welds, sometimes after relatively long incubation times. Repairs and replacements have generally utilized wrought Alloy 690 material and its compatible weld metals (Alloy 152 and Alloy 52), which have been shown to be very highly resistant to PWSCC in laboratory experiments and have been free from cracking in operating reactors over periods already up to nearly 15 years. It is nevertheless prudent for the PWR industry to attempt to quantify the longevity of these materials with respect to aging degradation by corrosion in order to provide a sound technical basis for the development of future inspection requirements for repaired or replaced component items. This document first reviews numerous laboratory tests, conducted over the last two decades, that were performed with wrought Alloy 690 and Alloy 52 or Alloy 152 weld materials under various test conditions pertinent to corrosion resistance in PWR environments. The main focus of the present review is on PWSCC, but secondary-side conditions are also briefly considered.

H.Xu, S.Fyfitch, P.Scott, M.Foucault, R.Kilian, and M.Winters

2004-03-01T23:59:59.000Z

474

Technology, safety and costs of decommissioning a reference pressurized water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule  

SciTech Connect

Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies on conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference pressurized water reactor (PWR) described in the earlier study; defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs; and completing a study of recent PWR steam generator replacements to determine realistic estimates for time, costs and doses associated with steam generator removal during decommissioning. This report presents the results of recent PNL studies to provide supporting information in four areas concerning decommissioning of the reference PWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; assessing the cost and dose impacts of recent steam generator replacements; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation.

Konzek, G.J.; Smith, R.I.

1988-07-01T23:59:59.000Z

475

Radiological characterization of spent control rod assemblies  

SciTech Connect

This document represents the final report of an ongoing study to provide radiological characterizations, classifications, and assessments in support of the decommissioning of nuclear power stations. This report describes the results of non-destructive and laboratory radionuclide measurements, as well as waste classification assessments, of BWR and PWR spent control rod assemblies. The radionuclide inventories of these spent control rods were determined by three separate methodologies, including (1) direct assay techniques, (2) calculational techniques, and (3) by sampling and laboratory radiochemical analyses. For the BWR control rod blade (CRB) and PWR burnable poison rod assembly (BPRA), {sup 60}Co and {sup 63}Ni, present in the stainless steel cladding, were the most abundant neutron activation products. The most abundant radionuclide in the PWR rod cluster control assembly (RCCA) was {sup 108m}Ag (130 yr halflife) produced in the Ag-In-Cd alloy used as the neutron poison. This radionuclide will be the dominant contributor to the gamma dose rate for many hundreds of years. The results of the direct assay methods agree very well ({+-}10%) with the sampling/radiochemical measurements. The results of the calculational methods agreed fairly well with the empirical measurements for the BPRA, but often varied by a factor of 5 to 10 for the CRB and the RCCA assemblies. If concentration averaging and encapsulation, as allowed by 10CFR61.55, is performed, then each of the entire control assemblies would be classified as Class C low-level radioactive waste.

Lepel, E.A.; Robertson, D.E.; Thomas, C.W.; Pratt, S.L.; Haggard, D.L. [Pacific Northwest Lab., Richland, WA (United States)

1995-10-01T23:59:59.000Z

476

U.S. LNG Imports from Canada  

Gasoline and Diesel Fuel Update (EIA)

Warroad, MN Babb, MT Havre, MT Port of Morgan, MT Sherwood, ND Pittsburg, NH Buffalo, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Freeport, TX Kenai, AK Port Nikiski, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA San Diego, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Kenai, AK Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Freeport, TX Sabine Pass, LA LNG Exports from Cameron, LA LNG Exports from Kenai, AK LNG Exports from Freeport, TX LNG Exports from Nogales, AZ LNG Exports from Otay Mesa, CA LNG Exports from Sabine Pass, LA LNG Exports from Sweetgrass, MT Period: Monthly Annual

477

U.S. Liquefied Natural Gas Exports to India  

Gasoline and Diesel Fuel Update (EIA)

Warroad, MN Babb, MT Havre, MT Port of Morgan, MT Sherwood, ND Pittsburg, NH Buffalo, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Freeport, TX Kenai, AK Port Nikiski, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA San Diego, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Kenai, AK Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Freeport, TX Sabine Pass, LA LNG Exports from Cameron, LA LNG Exports from Kenai, AK LNG Exports from Freeport, TX LNG Exports from Nogales, AZ LNG Exports from Otay Mesa, CA LNG Exports from Sabine Pass, LA LNG Exports from Sweetgrass, MT Period: Monthly Annual

478

U.S. LNG Imports from Other Countries  

Gasoline and Diesel Fuel Update (EIA)

Noyes, MN Warroad, MN Babb, MT Port of Del Bonita, MT Port of Morgan, MT Sweetgrass, MT Whitlash, MT Portal, ND Sherwood, ND Pittsburg, NH Champlain, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Highgate Springs, VT U.S. Pipeline Total from Mexico Ogilby, CA Otay Mesa, CA Galvan Ranch, TX LNG Imports from Algeria LNG Imports from Australia LNG Imports from Brunei LNG Imports from Canada Highgate Springs, VT LNG Imports from Egypt Cameron, LA Elba Island, GA Freeport, TX Gulf LNG, MS LNG Imports from Equatorial Guinea LNG Imports from Indonesia LNG Imports from Malaysia LNG Imports from Nigeria Cove Point, MD LNG Imports from Norway Cove Point, MD Freeport, TX Sabine Pass, LA LNG Imports from Oman LNG Imports from Peru Cameron, LA Freeport, TX LNG Imports from Qatar Elba Island, GA Golden Pass, TX Sabine Pass, LA LNG Imports from Trinidad/Tobago Cameron, LA Cove Point, MD Elba Island, GA Everett, MA Freeport, TX Gulf LNG, MS Lake Charles, LA Sabine Pass, LA LNG Imports from United Arab Emirates LNG Imports from Yemen Everett, MA Freeport, TX Sabine Pass, LA LNG Imports from Other Countries Period: Monthly Annual

479

U.S. LNG Imports from Egypt  

Gasoline and Diesel Fuel Update (EIA)

Noyes, MN Warroad, MN Babb, MT Port of Del Bonita, MT Port of Morgan, MT Sweetgrass, MT Whitlash, MT Portal, ND Sherwood, ND Pittsburg, NH Champlain, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Highgate Springs, VT U.S. Pipeline Total from Mexico Ogilby, CA Otay Mesa, CA Galvan Ranch, TX LNG Imports from Algeria LNG Imports from Australia LNG Imports from Brunei LNG Imports from Canada Highgate Springs, VT LNG Imports from Egypt Cameron, LA Elba Island, GA Freeport, TX Gulf LNG, MS LNG Imports from Equatorial Guinea LNG Imports from Indonesia LNG Imports from Malaysia LNG Imports from Nigeria Cove Point, MD LNG Imports from Norway Cove Point, MD Freeport, TX Sabine Pass, LA LNG Imports from Oman LNG Imports from Peru Cameron, LA Freeport, TX LNG Imports from Qatar Elba Island, GA Golden Pass, TX Sabine Pass, LA LNG Imports from Trinidad/Tobago Cameron, LA Cove Point, MD Elba Island, GA Everett, MA Freeport, TX Gulf LNG, MS Lake Charles, LA Sabine Pass, LA LNG Imports from United Arab Emirates LNG Imports from Yemen Everett, MA Freeport, TX Sabine Pass, LA LNG Imports from Other Countries Period: Monthly Annual

480

U.S. LNG Imports from Malaysia  

Gasoline and Diesel Fuel Update (EIA)

Noyes, MN Warroad, MN Babb, MT Port of Del Bonita, MT Port of Morgan, MT Sweetgrass, MT Whitlash, MT Portal, ND Sherwood, ND Pittsburg, NH Champlain, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Highgate Springs, VT U.S. Pipeline Total from Mexico Ogilby, CA Otay Mesa, CA Galvan Ranch, TX LNG Imports from Algeria LNG Imports from Australia LNG Imports from Brunei LNG Imports from Canada Highgate Springs, VT LNG Imports from Egypt Cameron, LA Elba Island, GA Freeport, TX Gulf LNG, MS LNG Imports from Equatorial Guinea LNG Imports from Indonesia LNG Imports from Malaysia LNG Imports from Nigeria Cove Point, MD LNG Imports from Norway Cove Point, MD Freeport, TX Sabine Pass, LA LNG Imports from Oman LNG Imports from Peru Cameron, LA Freeport, TX LNG Imports from Qatar Elba Island, GA Golden Pass, TX Sabine Pass, LA LNG Imports from Trinidad/Tobago Cameron, LA Cove Point, MD Elba Island, GA Everett, MA Freeport, TX Gulf LNG, MS Lake Charles, LA Sabine Pass, LA LNG Imports from United Arab Emirates LNG Imports from Yemen Everett, MA Freeport, TX Sabine Pass, LA LNG Imports from Other Countries Period: Monthly Annual

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


481

U.S. LNG Imports from Peru  

Gasoline and Diesel Fuel Update (EIA)

Noyes, MN Warroad, MN Babb, MT Port of Del Bonita, MT Port of Morgan, MT Sweetgrass, MT Whitlash, MT Portal, ND Sherwood, ND Pittsburg, NH Champlain, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Highgate Springs, VT U.S. Pipeline Total from Mexico Ogilby, CA Otay Mesa, CA Galvan Ranch, TX LNG Imports from Algeria LNG Imports from Australia LNG Imports from Brunei LNG Imports from Canada Highgate Springs, VT LNG Imports from Egypt Cameron, LA Elba Island, GA Freeport, TX Gulf LNG, MS LNG Imports from Equatorial Guinea LNG Imports from Indonesia LNG Imports from Malaysia LNG Imports from Nigeria Cove Point, MD LNG Imports from Norway Cove Point, MD Freeport, TX Sabine Pass, LA LNG Imports from Oman LNG Imports from Peru Cameron, LA Freeport, TX LNG Imports from Qatar Elba Island, GA Golden Pass, TX Sabine Pass, LA LNG Imports from Trinidad/Tobago Cameron, LA Cove Point, MD Elba Island, GA Everett, MA Freeport, TX Gulf LNG, MS Lake Charles, LA Sabine Pass, LA LNG Imports from United Arab Emirates LNG Imports from Yemen Everett, MA Freeport, TX Sabine Pass, LA LNG Imports from Other Countries Period: Monthly Annual

482

U.S. Liquefied Natural Gas Exports to Japan  

Gasoline and Diesel Fuel Update (EIA)

Warroad, MN Babb, MT Havre, MT Port of Morgan, MT Sherwood, ND Pittsburg, NH Buffalo, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Freeport, TX Kenai, AK Port Nikiski, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA San Diego, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Kenai, AK Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Freeport, TX Sabine Pass, LA LNG Exports from Cameron, LA LNG Exports from Kenai, AK LNG Exports from Freeport, TX LNG Exports from Nogales, AZ LNG Exports from Otay Mesa, CA LNG Exports from Sabine Pass, LA LNG Exports from Sweetgrass, MT Period: Monthly Annual

483

U.S. LNG Imports from Trinidad/Tobago  

Gasoline and Diesel Fuel Update (EIA)

Noyes, MN Warroad, MN Babb, MT Port of Del Bonita, MT Port of Morgan, MT Sweetgrass, MT Whitlash, MT Portal, ND Sherwood, ND Pittsburg, NH Champlain, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Highgate Springs, VT U.S. Pipeline Total from Mexico Ogilby, CA Otay Mesa, CA Galvan Ranch, TX LNG Imports from Algeria LNG Imports from Australia LNG Imports from Brunei LNG Imports from Canada Highgate Springs, VT LNG Imports from Egypt Cameron, LA Elba Island, GA Freeport, TX Gulf LNG, MS LNG Imports from Equatorial Guinea LNG Imports from Indonesia LNG Imports from Malaysia LNG Imports from Nigeria Cove Point, MD LNG Imports from Norway Cove Point, MD Freeport, TX Sabine Pass, LA LNG Imports from Oman LNG Imports from Peru Cameron, LA Freeport, TX LNG Imports from Qatar Elba Island, GA Golden Pass, TX Sabine Pass, LA LNG Imports from Trinidad/Tobago Cameron, LA Cove Point, MD Elba Island, GA Everett, MA Freeport, TX Gulf LNG, MS Lake Charles, LA Sabine Pass, LA LNG Imports from United Arab Emirates LNG Imports from Yemen Everett, MA Freeport, TX Sabine Pass, LA LNG Imports from Other Countries Period: Monthly Annual

484

U.S. LNG Imports from Algeria  

Gasoline and Diesel Fuel Update (EIA)

Noyes, MN Warroad, MN Babb, MT Port of Del Bonita, MT Port of Morgan, MT Sweetgrass, MT Whitlash, MT Portal, ND Sherwood, ND Pittsburg, NH Champlain, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Highgate Springs, VT U.S. Pipeline Total from Mexico Ogilby, CA Otay Mesa, CA Galvan Ranch, TX LNG Imports from Algeria LNG Imports from Australia LNG Imports from Brunei LNG Imports from Canada Highgate Springs, VT LNG Imports from Egypt Cameron, LA Elba Island, GA Freeport, TX Gulf LNG, MS LNG Imports from Equatorial Guinea LNG Imports from Indonesia LNG Imports from Malaysia LNG Imports from Nigeria Cove Point, MD LNG Imports from Norway Cove Point, MD Freeport, TX Sabine Pass, LA LNG Imports from Oman LNG Imports from Peru Cameron, LA Freeport, TX LNG Imports from Qatar Elba Island, GA Golden Pass, TX Sabine Pass, LA LNG Imports from Trinidad/Tobago Cameron, LA Cove Point, MD Elba Island, GA Everett, MA Freeport, TX Gulf LNG, MS Lake Charles, LA Sabine Pass, LA LNG Imports from United Arab Emirates LNG Imports from Yemen Everett, MA Freeport, TX Sabine Pass, LA LNG Imports from Other Countries Period: Monthly Annual

485

C:\Annual\VENTCHAP.V8\NGA02.vp  

Gasoline and Diesel Fuel Update (EIA)

Table. 11 Summary of U.S. Natural Gas Exports By Point of Exit, 1998-2002 (Volumes in Million Cubic Feet, Prices in Dollars per Thousand Cubic Feet) Imports and Exports - Table 11 Pipeline (Canada) East Port, ID.............. NA NA NA NA NA NA NA NA 176 4.40 Detroit, MI.................. 24,908 2.26 25,049 2.30 36,007 3.74 35,644 4.57 7,431 3.03 Marysville, MI ............ 3,377 2.17 691 2.47 5,320 2.91 3,651 3.92 NA NA St. Clair, MI ............... 11,397 2.23 11,258 2.51 29,654 3.73 122,293 3.82 164,084 3.42 Noyes, MN ................ NA NA NA NA NA NA NA NA 71 1.99 Babb, MT................... NA NA NA NA NA NA 549 3.55 143 2.28 Havre, MT ................. NA NA 1,510 2.05 1,606 3.25 2,428 3.40 15,892 2.74 Port of Morgan, MT ... NA NA NA NA NA NA NA NA 1 3.47 Niagara Falls, NY ...... NA NA NA NA NA NA 594 2.49 39 5.04 Sumas, WA ............... 208 2.80 NA NA NA NA 1,529 4.44 1,477 2.59 Total..........................

486

ORNL/RASA-86/ L9  

Office of Legacy Management (LM)

Qq {8 Qq {8 oL'/7 8.-uf*t^* l/fii ORNL/RASA-86/ L9 COMPREHENSIVE MDIOLOGICAL $JRVEY OF OFF-SITE PROPERTY O NIAGARA FALLS STORAGE SITE LEWISTON, NE}J YORK Access to the lnformatlon ln this report ls llmlted to those l n d l c a t e d o n t h e d l s t r l b u t l o n l l s t a n d t o D e p a r t m e n t o f E n e r g y and Departnent of Energy Contractors Thi! roport w!! preprtcd a! an account of wott lponlot€d by an agency ot the Unatcd Stttos Govrrnmant. Naithcr thcU nited StltttGovcrnmrnt nor any agrncy thercot, nor any ol therr cmployod. mtke3 lny wtrrrnty, expross'or implaed, or .33umc3 eny l€gd lirbility or ra3poBability fot thc eccurucy. complelcn.!9. o. usltuln6! of any informtlion, appltttu3, product or procs3! disclo3cd' or reprelant3 thst it3ut€would not inlringaprivetclyown€d tight!. Rslerenceharcan

487

U.S. Natural Gas Exports to Mexico  

Gasoline and Diesel Fuel Update (EIA)

Warroad, MN Babb, MT Havre, MT Port of Morgan, MT Sherwood, ND Pittsburg, NH Buffalo, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Sweetgrass, MT Total to Chile Sabine Pass, LA Total to China Kenai, AK Sabine Pass, LA Total to India Freeport, TX Sabine Pass, LA Total to Japan Cameron, LA Freeport, TX Kenai, AK Port Nikiski, AK Sabine Pass, LA Total to Mexico Douglas, AZ Nogales, AZ Calexico, CA Ogilby Mesa, CA Otay Mesa, CA San Diego, CA Alamo, TX Clint, TX Del Rio, TX Eagle Pass, TX El Paso, TX Hidalgo, TX McAllen, TX Penitas, TX Rio Bravo, TX Roma, TX Total to Portugal Sabine Pass, LA Total to Russia Kenai, AK Total to South Korea Freeport, TX Sabine Pass, LA Total to Spain Cameron, LA Sabine Pass, LA Total to United Kingdom Freeport, TX Sabine Pass, LA LNG Exports from Cameron, LA LNG Exports from Kenai, AK LNG Exports from Freeport, TX LNG Exports from Nogales, AZ LNG Exports from Otay Mesa, CA LNG Exports from Sabine Pass, LA LNG Exports from Sweetgrass, MT Period: Monthly Annual

488

U.S. LNG Imports from Nigeria  

Gasoline and Diesel Fuel Update (EIA)

Noyes, MN Warroad, MN Babb, MT Port of Del Bonita, MT Port of Morgan, MT Sweetgrass, MT Whitlash, MT Portal, ND Sherwood, ND Pittsburg, NH Champlain, NY Grand Island, NY Massena, NY Niagara Falls, NY Waddington, NY Sumas, WA Highgate Springs, VT U.S. Pipeline Total from Mexico Ogilby, CA Otay Mesa, CA Galvan Ranch, TX LNG Imports from Algeria LNG Imports from Australia LNG Imports from Brunei LNG Imports from Canada Highgate Springs, VT LNG Imports from Egypt Cameron, LA Elba Island, GA Freeport, TX Gulf LNG, MS LNG Imports from Equatorial Guinea LNG Imports from Indonesia LNG Imports from Malaysia LNG Imports from Nigeria Cove Point, MD LNG Imports from Norway Cove Point, MD Freeport, TX Sabine Pass, LA LNG Imports from Oman LNG Imports from Peru Cameron, LA Freeport, TX LNG Imports from Qatar Elba Island, GA Golden Pass, TX Sabine Pass, LA LNG Imports from Trinidad/Tobago Cameron, LA Cove Point, MD Elba Island, GA Everett, MA Freeport, TX Gulf LNG, MS Lake Charles, LA Sabine Pass, LA LNG Imports from United Arab Emirates LNG Imports from Yemen Everett, MA Freeport, TX Sabine Pass, LA LNG Imports from Other Countries Period: Monthly Annual