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Note: This page contains sample records for the topic "light columbia water" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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1

Columbia Water and Light- Solar Rebates  

Broader source: Energy.gov [DOE]

Columbia Water and Light (CWL) offers rebates to its commercial and residential customers for the purchase of solar water heaters and solar photovoltaic systems. These rebates are available for...

2

Columbia Water and Light- HVAC and Lighting Efficiency Rebates  

Broader source: Energy.gov [DOE]

Columbia Water and Light (CWL) offers rebates to its commercial and industrial customers for the purchase of high efficiency HVAC installations and efficient lighting. Incentives for certain...

3

Columbia Water and Light- Residential Super Saver Loans  

Broader source: Energy.gov [DOE]

The Columbia Water and Light (CWL) Home Performance Super Saver Loan allows Columbia residents to finance energy improvements to homes with affordable, low interest loans with five to ten year...

4

Columbia Water and Light- Residential HVAC Rebate Program  

Broader source: Energy.gov [DOE]

Columbia Water and Light (CWL) provides an HVAC incentive for residential customers that are replacing an older heating and cooling system. Customers should submit the mechanical permit from a...

5

Columbia Water and Light- Commercial Super Saver Loans  

Broader source: Energy.gov [DOE]

Columbia Water and Light (CWL) provides Commercial Super Saver Loans, which allow C&I rate customers to replace a furnace along with a new central air conditioner or heat pump with an...

6

University of the District of Columbia District of Columbia Drinking Water Blind Taste  

E-Print Network [OSTI]

University of the District of Columbia District of Columbia Drinking Water Blind Taste Testing for Nutrition, Diet and Health Cooperative Extension Service University of the District of Columbia Dawanna University of the District of Columbia Date: May 2005 Prepared for the DC Water Resources Research Institute

District of Columbia, University of the

7

Light Water Reactor Sustainability  

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

3 Light Water Reactor Sustainability Program ACCOMPLISHMENTS REPORT 2013 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

8

Light Water Reactor Sustainability  

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

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

9

Independent External Evaluation of The Columbia Basin Water Transactions Program  

E-Print Network [OSTI]

three objectives since its inception in 2003: 1) Experimenting with open market transactions a market for instream water (153 open-market transactions have been made to date), and QLEs have beenIndependent External Evaluation of The Columbia Basin Water Transactions Program (2003

10

Light Water Reactor Sustainability Newsletter  

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

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

11

Light Water Reactor Sustainability Newsletter  

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

30-35, August 2012. Clayton, D. A. and M. S. Hileman, 2012, Light Water Reactor Sustainability Non-Destructive Evaluation for Concrete Research and Development Roadmap, ORNLTM-...

12

WRRC Report No. 163 The Water Resources Research Center (WRRC) of the University of the District of Columbia  

E-Print Network [OSTI]

, and program reports. The Universities and Colleges within the District of Columbia which are eligible College, Trinity College, University of the District of Columbia. The research projects are based: D.C. Water Resources Research Center University of the District of Columbia 4200 Connecticut Ave. N

District of Columbia, University of the

13

LIGHT WATER REACTOR SUSTAINABILITY PROGRAM: INTRODUCTION  

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

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

14

Coastal Upwelling Supplies Oxygen-Depleted Water to the Columbia River Estuary  

E-Print Network [OSTI]

extent and duration of exposure to low DO water. Strong upwelling during neap tides produced the largestCoastal Upwelling Supplies Oxygen-Depleted Water to the Columbia River Estuary G. Curtis Roegner1 States of America Abstract Low dissolved oxygen (DO) is a common feature of many estuarine and shallow-water

15

Upper Middle Mainstem Columbia River Subbasin Water Quality Parameters Affected by Hydropower Production  

E-Print Network [OSTI]

Appendix E Upper Middle Mainstem Columbia River Subbasin Water Quality Parameters Affected have reappeared as management agencies have reinstituted spill as a means of aiding downstream fish passage throughout the system. The WDOE has set a TDG standard of 110 percent of saturation for all

16

Light Water Reactor Sustainability (LWRS) Program  

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

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

17

WATER, PROPERTIES D Hillel, Columbia University, New York, NY, USA  

E-Print Network [OSTI]

with an abundance of it, even with a surfeit, so that often the problem is how to dispose of excess water. Arid, inert liquid, water is a highly reactive substance, a solvent and a transporter of numerous substances. In the Middle Ages, people believed that fresh water emanated magically from the bowels of the earth. They could

18

Light-Water Breeder Reactor  

DOE Patents [OSTI]

Described is a light-water-moderated and -cooled nuclear breeder reactor of the seed-blanket type characterized by core modules comprising loosely packed blanket zones enriched with fissile fuel and axial zoning in the seed and blanket regions within each core module. Reactivity control over lifetime is achieved by axial displacement of movable seed zones without the use of poison rods in the embodiment illustrated. The seed is further characterized by a hydrogen-to-uranium-233 atom ratio in the range 10 to 200 and a uranium-233-to-thorium-232 atom ratio ranging from 0.012 to 0.200. The seed occupies from 10 to 35 percent of the core volume in the form of one or more individual islands or annuli. (NSA 26: 55130)

Beaudoin, B. R.; Cohen, J. D.; Jones, D. H.; Marier, Jr, L. J.; Raab, H. F.

1972-06-20T23:59:59.000Z

19

Light Water Reactor Sustainability Program Contact Information  

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

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

20

Light Water Reactor Sustainability Newsletter  

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

and nuclear waste disposal. Dr. Corradini has extensive research experience in the phenomenology of beyond design basis Meet the New LWRS Program Pathway Lead accidents in light...

Note: This page contains sample records for the topic "light columbia water" 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

Literature and data review for the surface-water pathway: Columbia River and adjacent coastal areas  

SciTech Connect (OSTI)

As part of the Hanford Environmental Dose Reconstruction Project, Pacific Northwest Laboratory reviewed literature and data on radionuclide concentrations and distribution in the water, sediment, and biota of the Columbia River and adjacent coastal areas. Over 600 documents were reviewed including Hanford reports, reports by offsite agencies, journal articles, and graduate theses. Certain radionuclide concentration data were used in preliminary estimates of individual dose for the 1964--1966 time period. This report summarizes the literature and database review and the results of the preliminary dose estimates.

Walters, W.H.; Dirkes, R.L.; Napier, B.A.

1992-04-01T23:59:59.000Z

22

Immobilization of U(VI) from Oxic Groundwater by Hanford 300 Area Sediments and Effects of Columbia River Water  

SciTech Connect (OSTI)

Regions within the U.S. Department of Energy Hanford 300 Area (300 A) site experience periodic hydrologic influences from the nearby Columbia River as a result of changing river stage, which causes changes in groundwater elevation, flow direction and water chemistry. An important question is the extent to which the mixing of Columbia River water and groundwater impacts the speciation and mobility of uranium (U). In this study, we designed experiments to mimic interactions among U, oxic groundwater or Columbia River water, and 300 A sediments in the subsurface environment of Hanford 300 A. The goals were to investigate mechanisms of: 1) U immobilization in 300 A sediments under bulk oxic conditions and 2) U remobilization from U-immobilized 300 A sediments exposed to oxic Columbia River water. Initially, 300 A sediments in column reactors were fed with U(VI)-containing oxic 1) synthetic groundwater (SGW), 2) organic-amended SGW (OA-SGW), and 3) de-ionized (DI) water to investigate U immobilization processes. After that, the sediments were exposed to oxic Columbia River water for U remobilization studies. The results reveal that U was immobilized by 300 A sediments predominantly through reduction (80-85%) when the column reactor was fed with oxic OA-SGW. However, U was immobilized by 300 A sediments through adsorption (100%) when the column reactors were fed with oxic SGW or DI water. The reduced U in the 300 A sediments fed with OA-SGW was relatively resistant to remobilization by oxic Columbia River water. Oxic Columbia River water resulted in U remobilization (?7%) through desorption, and most of the U that remained in the 300 A sediments fed with OA-SGW (?93%) was in the form of uraninite nanoparticles. These results reveal that: 1) the reductive immobilization of U through OA-SGW stimulation of indigenous 300 A sediment microorganisms may be viable in the relatively oxic Hanford 300 A subsurface environments and 2) with the intrusion of Columbia River water, desorption may be the primary process resulting in U remobilization from OA-SGW-stimulated 300 A sediments at the subsurface of the Hanford 300 A site.

Ahmed, B.; Cao, Bin; Mishra, Bhoopesh; Boyanov, Maxim I.; Kemner, Kenneth M.; Fredrickson, Jim K.; Beyenal, Haluk

2012-09-23T23:59:59.000Z

23

Water Quality Sampling Locations Along the Shoreline of the Columbia River, Hanford Site, Washington  

SciTech Connect (OSTI)

As environmental monitoring evolved on the Hanford Site, several different conventions were used to name or describe location information for various sampling sites along the Hanford Reach of the Columbia River. These methods range from handwritten descriptions in field notebooks to the use of modern electronic surveying equipment, such as Global Positioning System receivers. These diverse methods resulted in inconsistent archiving of analytical results in various electronic databases and published reports because of multiple names being used for the same site and inaccurate position data. This document provides listings of sampling sites that are associated with groundwater and river water sampling. The report identifies names and locations for sites associated with sampling: (a) near-river groundwater using aquifer sampling tubes; (b) riverbank springs and springs areas; (c) pore water collected from riverbed sediment; and (d) Columbia River water. Included in the listings are historical names used for a particular site and the best available geographic coordinates for the site, as of 2009. In an effort to create more consistency in the descriptive names used for water quality sampling sites, a naming convention is proposed in this document. The convention assumes that a unique identifier is assigned to each site that is monitored and that this identifier serves electronic database management requirements. The descriptive name is assigned for the convenience of the subsequent data user. As the historical database is used more intensively, this document may be revised as a consequence of discovering potential errors and also because of a need to gain consensus on the proposed naming convention for some water quality monitoring sites.

Peterson, Robert E.; Patton, Gregory W.

2009-12-14T23:59:59.000Z

24

Columbia River System Operation Review : Final Environmental Impact Statement, Appendix F: Irrigation, Municipal and Industrial/Water Supply.  

SciTech Connect (OSTI)

Since the 1930`s, the Columbia River has been harnessed for the benefit of the Northwest and the nation. Federal agencies have built 30 major dams on the river and its tributaries. Dozens of non-Federal projects have been developed as well. The dams provide flood control, irrigation, navigation, hydro-electric power generation, recreation, fish and wildlife, and streamflows for wildlife, anadromous fish, resident fish, and water quality. This is Appendix F of the Environmental Impact Statement for the Columbia River System, focusing on irrigation issues and concerns arrising from the Irrigation and Mitigation of impacts (M&I) working Group of the SOR process. Major subheadings include the following: Scope and process of irrigation/M&I studies; Irrigation/M&I in the Columbia Basin Today including overview, irrigated acreage and water rights, Irrigation and M&I issues basin-wide and at specific locations; and the analysis of impacts and alternative for the Environmental Impact Statement.

Columbia River System Operations Review (U.S.); United States. Bonneville Power Administration; United States. Army. Corps of Engineers. North Pacific Division; United States. Bureau of Reclamation. Pacific Northwest Region.

1995-11-01T23:59:59.000Z

25

Sustained water cleavage by visible light  

SciTech Connect (OSTI)

Sustained cleavage of water by 4 quanta of visible light is achieved in aqueous solutions by using a bifunctional redox catalyst composed of Pt and RuO/sub 2/ cosupported by colloidal TiO/sub 2/ particles. A photochemical model system containing Ru(bpy)/sub 3//sup 2 +/ as a sensitizer and methyl viologen (MV/sup 2 +/) as an electron relay is used to test the effect of catalyst composition, sensitizer concentration, pH, and temperature on the efficiency of light-induced water decomposition. Electron relay free systems also exhibit high photoactivity. Direct band gap irradiation by uv light leads to efficient water cleavage in the absence of sensitizer and relay.

Borgarello, E.; Kiwi, J.; Pelizzetti, E.; Visca, M.; Graetzel, M.

1981-10-21T23:59:59.000Z

26

Dissolved and particulate aluminum in the Columbia River and coastal waters of Oregon and Washington: behavior in near-field and far-field plumes  

E-Print Network [OSTI]

1 Dissolved and particulate aluminum in the Columbia River and coastal waters of Oregon) and particulate (leachable and total) aluminum was examined in the Columbia River and estuary, in near Influence on Shelf Ecosystems (RISE) cruise of May/June 2006. Dissolved and particulate aluminum (Al

Hickey, Barbara

27

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

SciTech Connect (OSTI)

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

L. C. Hulstrom

2009-09-28T23:59:59.000Z

28

Cedarburg Light and Water Utility- Commercial Energy Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

Cedarburg Light and Water Utility provides incentives for commercial, industrial and agricultural customers to increase the energy efficiency of eligible facilities. Upon request, Cedarburg Light...

29

Missoula flood dynamics and magnitudes inferred from sedimentology of slack-water deposits on the Columbia Plateau, Washington  

SciTech Connect (OSTI)

Sedimentological study of late Wisconsin, Missoula-flood slack-water sediments deposited along the Columbia and Tucannon Rivers in southern Washington reveals important aspects of flood dynamics. Most flood facies were deposited by energetic flood surges (velocities>6 m/sec) entering protected areas along the flood tract, or flowing up and then directly out of tributary valleys. True still-water facies are less voluminous and restricted to elevations below 230 m. High flood stages attended the initial arrival of the flood wave and were not associated with subsequent hydraulic ponding upslope from channel constrictions. Among 186 flood beds studied in 12 sections, 57% have bioturbated tops, and about half of these bioturbated beds are separated from overlying flood beds by nonflood sediments. A single graded flood bed was deposited at most sites during most floods. Sequences in which 2-9 graded beds were deposited during a single flood are restricted to low elevations. These sequences imply complex, multi-peaked hydrographs in which the first flood surge was generally the largest, and subsequent surges were attenuated by water already present in slack-water areas. Slack-water - sediment stratigraphy suggests a wide range of flood discharges and volumes. Of >40 documented late Wisconsin floods that inundated the Pasco Basin, only about 20 crossed the Palouse-Snake divide. Floods younger than the set-S tephras from Mount St.Helens were generally smaller than earlier floods of late Wisconsin age, although most still crossed the Palouse-Snake divide. These late floods primarily traversed the Cheney-Palouse scabland because stratigraphy of slack-water sediment along the Columbia River implies that the largest flood volumes did not enter the Pasco Basin by way of the Columbia River. 47 refs., 17 figs., 2 tabs.

Smith, G.A. (Univ. of New Mexico, Albuquerque (United States))

1993-01-01T23:59:59.000Z

30

Zircaloy performance in light water reactors  

SciTech Connect (OSTI)

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

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

1992-12-31T23:59:59.000Z

31

Light water reactor lower head failure analysis  

SciTech Connect (OSTI)

This document presents the results from a US Nuclear Regulatory Commission-sponsored research program to investigate the mode and timing of vessel lower head failure. Major objectives of the analysis were to identify plausible failure mechanisms and to develop a method for determining which failure mode would occur first in different light water reactor designs and accident conditions. Failure mechanisms, such as tube ejection, tube rupture, global vessel failure, and localized vessel creep rupture, were studied. Newly developed models and existing models were applied to predict which failure mechanism would occur first in various severe accident scenarios. So that a broader range of conditions could be considered simultaneously, calculations relied heavily on models with closed-form or simplified numerical solution techniques. Finite element techniques-were employed for analytical model verification and examining more detailed phenomena. High-temperature creep and tensile data were obtained for predicting vessel and penetration structural response.

Rempe, J.L.; Chavez, S.A.; Thinnes, G.L. [EG and G Idaho, Inc., Idaho Falls, ID (United States)] [and others

1993-10-01T23:59:59.000Z

32

austenitic light water: Topics by E-print Network  

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

First, a solid SiC-coated ... Hejzlar, P. 26 Overview of light waterhydrogen-base low energy nuclear reactions CiteSeer Summary: This paper reviews light water and hydrogen-based...

33

Water Cooling of High Power Light Emitting Diode Henrik Srensen  

E-Print Network [OSTI]

Water Cooling of High Power Light Emitting Diode Henrik Sørensen Department of Energy Technology and product lifetime. The high power Light Emitting Diodes (LED) belongs to the group of electronics

Berning, Torsten

34

Environmentally assisted cracking in light water reactors  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from April 1995 to December 1995. Topics that have been investigated include fatigue of carbon and low-alloy steel used in reactor piping and pressure vessels, EAC of Alloy 600 and 690, and irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS. Fatigue tests were conducted on ferritic steels in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during different portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Crack-growth-rate tests were conducted on compact-tension specimens from several heats of Alloys 600 and 690 in simulated LWR environments. Effects of fluoride-ion contamination on susceptibility to intergranular cracking of high- and commercial- purity Type 304 SS specimens from control-tensile tests at 288 degrees Centigrade. Microchemical changes in the specimens were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements may contribute to IASCC of these materials.

Chopra, O.K.; Chung, H.M.; Gruber, E.E. [and others

1996-07-01T23:59:59.000Z

35

Duquesne Light Company- Residential Solar Water Heating Program  

Broader source: Energy.gov [DOE]

Duquesne Light provides rebates to its residential customers for purchasing and installing qualifying solar water heating systems. Eligible systems may receive a flat rebate of $286 per qualifying...

36

Light Water Reactor Sustainability Newsletter Kathryn McCarthy  

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

Technical Integration Office T he Light Water Reactor Sustainability (LWRS) Pro- gram Integrated Program Plan was released on January 31, 2012; it can be downloaded at https:...

37

Light Water Reactor Sustainability Newsletter Rebecca Smith-Kevern  

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

Rebecca Smith-Kevern Director, Office of Light Water Reactor Technologies. I am often asked why the Federal Government should fund a program that supports the continued operation...

38

Light Water Reactor Sustainability Program - Non-Destructive...  

Energy Savers [EERE]

for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants Light Water Reactor Sustainability Program - Non-Destructive Evaluation R&D Roadmap for...

39

Light Water Reactor Sustainability Newsletter By Rich Reister  

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

the safety, and extend the life of current reactors. The Light Water Re- actor Sustainability (LWRS) program is NE's principal means of achieving this objective. We have...

40

Light Water Reactor Sustainability Newsletter Thomas M. Rosseel  

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

Laboratory (ORNL), through the Department of Energy's (DOE) Light Water Reactor Sustainability (LWRS) Program, is coordinating and contracting with Zion Solutions, LLC (a...

Note: This page contains sample records for the topic "light columbia water" 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

Light Water Reactor Sustainability Newsletter By John Gaertner  

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

Year 2011 LWRS Program funding is very clear: "Regarding the Light Water Reactor Sustainability program, (Congress) expects a high cost share from industry." Cost sharing is...

42

City Water Light and Power- Residential Energy Efficiency Rebate Programs  

Broader source: Energy.gov [DOE]

City Water Light and Power (CWLP) offers rebates to Springfield residential customers for increasing the energy efficiency of participating homes. Rebates are available for geothermal heat pumps,...

43

City Water Light and Power- Commercial Energy Efficiency Rebate Programs  

Broader source: Energy.gov [DOE]

City Water Light and Power (CWLP) offers rebates to help commercial customers increase the energy efficiency of participating facilities. Energy efficient air-to-air, geothermal and water-loop...

44

Importance of vertical mixing for additional sources of nitrate and iron to surface waters of the Columbia River plume  

E-Print Network [OSTI]

of the Columbia River plume: Implications for biology Maeve C. Lohan a,*, Kenneth W. Bruland b a Institute

Hickey, Barbara

45

Future Water Supply and Demand in the Okanagan Basin, British Columbia: A Scenario-Based Analysis  

E-Print Network [OSTI]

. An integrated water management model (Water Evaluation and Planning system, WEAP) was used to consider future . Reservoir management . Instream flows . Mountain Pine Beetle Water Resour Manage (2012) 26:667­689 DOI 10 misperception of an abundance of renewable freshwater has inhibited integrated planning for water management

46

Safety of light water reactor fuel with silicon carbide cladding  

E-Print Network [OSTI]

Structural aspects of the performance of light water reactor (LWR) fuel rod with triplex silicon carbide (SiC) cladding - an emerging option to replace the zirconium alloy cladding - are assessed. Its behavior under accident ...

Lee, Youho

2013-01-01T23:59:59.000Z

47

Light Water Reactor Sustainability Newsletter Kathryn A. McCarthy  

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

S ome of the Light Water Reactor Sustainability (LWRS) Program managers have changed; therefore, I would like to provide a brief introduction to all of the LWRS program managers:...

48

Reduced heat flow in light water (H2O) due to heavy water (D2O)  

E-Print Network [OSTI]

The flow of heat, from top to bottom, in a column of light water can be decreased by over 1000% with the addition of heavy water. A column of light water cools from 25 C to 0 C in 11 hours, however, with the addition of heavy water it takes more than 100 hours. There is a concentration dependence where the cooling time increases as the concentration of added (D2O) increases, with a near maximum being reached with as little as 2% of (D2O) added. This phenomenon will not occur if the water is mixed after the heavy water is added.

William R. Gorman; James D. Brownridge

2008-09-04T23:59:59.000Z

49

COLUMBIA UNIVERSITY AN OVERVIEW  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY AN OVERVIEW #12;COLUMBIA COLLEGE www.college.columbia.edu Columbia College UNIVERSITY SCHOOLS, #12;COLLEGES, AND AFFILIATES SCHOOL OF LAW www.law.columbia.edu Columbia Law School, philosophy, history, music, art, and science. THE FU FOUNDATION SCHOOL OF ENGINEERING AND APPLIED SCIENCE www.engineering.columbia

Yang, Junfeng

50

Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels  

E-Print Network [OSTI]

Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

51

Near-infrared light scattering by particles in coastal waters  

E-Print Network [OSTI]

Near-infrared light scattering by particles in coastal waters David Doxaran* , Marcel Babin extend over the near-infrared spectral region to up to 870 nm. The measurements were conducted in three in the near-infrared very closely matched a - spectral dependence, which is expected when the particle size

Babin, Marcel

52

Literature and data review for the surface-water pathway: Columbia River and adjacent coastal areas. Hanford Environmental Dose Reconstruction Project  

SciTech Connect (OSTI)

As part of the Hanford Environmental Dose Reconstruction Project, Pacific Northwest Laboratory reviewed literature and data on radionuclide concentrations and distribution in the water, sediment, and biota of the Columbia River and adjacent coastal areas. Over 600 documents were reviewed including Hanford reports, reports by offsite agencies, journal articles, and graduate theses. Certain radionuclide concentration data were used in preliminary estimates of individual dose for the 1964--1966 time period. This report summarizes the literature and database review and the results of the preliminary dose estimates.

Walters, W.H.; Dirkes, R.L.; Napier, B.A.

1992-04-01T23:59:59.000Z

53

Calculation of heat capacities of light and heavy water by path-integral molecular dynamics  

E-Print Network [OSTI]

Calculation of heat capacities of light and heavy water by path-integral molecular dynamics-integral molecular dynamics has been used to calculate the constant-volume heat capacities of light and heavy water

Nielsen, Steven O.

54

Assessment of innovative fuel designs for high performance light water reactors  

E-Print Network [OSTI]

To increase the power density and maximum allowable fuel burnup in light water reactors, new fuel rod designs are investigated. Such fuel is desirable for improving the economic performance light water reactors loaded with ...

Carpenter, David Michael

2006-01-01T23:59:59.000Z

55

Columbia River PUD- Commercial Energy Efficiency Rebate Programs  

Broader source: Energy.gov [DOE]

Columbia River PUD offers a variety of rebates to commercial and industrial customers who make energy saving improvements to facilities. Rebates are available for lighting retrofits, weatherization...

56

Light Water Reactor Sustainability (LWRS) Program | Department of Energy  

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

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

57

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

SciTech Connect (OSTI)

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

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

2002-09-01T23:59:59.000Z

58

Method of burning lightly loaded coal-water slurries  

DOE Patents [OSTI]

In a preferred arrangement of the method of the invention, a lightly loaded coal-water slurry, containing in the range of approximately 40% to 52% + 2% by weight coal, is atomized to strip water from coal particles in the mixture. Primary combustor air is forced around the atomized spray in a combustion chamber of a combustor to swirl the air in a helical path through the combustion chamber. A flame is established within the combustion chamber to ignite the stripped coal particles, and flame temperature regulating means are provided for maintaining the flame temperature within a desired predetermined range of temperatures that is effective to produce dry, essentially slag-free ash from the combustion process.

Krishna, C.R.

1984-07-27T23:59:59.000Z

59

Reduced heat flow in light water (H2O) due to heavy water (D2O) William R. Gormana)  

E-Print Network [OSTI]

Reduced heat flow in light water (H2O) due to heavy water (D2O) William R. Gormana) and James D by over 1000% with the addition of heavy water. A column of light water cools from 25°C to 0°C in 11 hours, however, with the addition of heavy water it takes more than 100 hours. There is a concentration

Suzuki, Masatsugu

60

COLUMBIA UNIVERSITY  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route BTRIC CNMSMethanoliVP-^"^^? COLUMBIA0910W^ 8

Note: This page contains sample records for the topic "light columbia water" 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

Accident Performance of Light Water Reactor Cladding Materials  

SciTech Connect (OSTI)

During a loss of coolant accident as experienced at Fukushima, inadequate cooling of the reactor core forces component temperatures ever higher where they must withstand aggressive chemical environments. Conventional zirconium cladding alloys will readily oxidize in the presence of water vapor at elevated temperatures, rapidly degrading and likely failing. A cladding breach removes the critical barrier between actinides and fission products and the coolant, greatly increasing the probability of the release of radioactivity in the event of a containment failure. These factors have driven renewed international interest in both study and improvement of the materials used in commercial light water reactors. Characterization of a candidate cladding alloy or oxidation mitigation technique requires understanding of both the oxidation kinetics and hydrogen production as a function of temperature and atmosphere conditions. Researchers in the MST division supported by the DOE-NE Fuel Cycle Research and Development program are working to evaluate and quantify these parameters across a wide range of proposed cladding materials. The primary instrument employed is a simultaneous thermal analyzer (STA) equipped with a specialized water vapor furnace capable of maintaining temperatures above 1200 C in a range of atmospheres and water vapor contents. The STA utilizes thermogravimetric analysis and a coupled mass spectrometer to measure in situ oxidation and hydrogen production of candidate materials. This capability is unprecedented in study of materials under consideration for reactor cladding use, and is currently being expanded to investigate proposed coating techniques as well as the effect of coating defects on corrosion resistance.

Nelson, Andrew T. [Los Alamos National Laboratory

2012-07-24T23:59:59.000Z

62

Multi-Applications Small Light Water Reactor - NERI Final Report  

SciTech Connect (OSTI)

The Multi-Application Small Light Water Reactor (MASLWR) project was conducted under the auspices of the Nuclear Energy Research Initiative (NERI) of the U.S. Department of Energy (DOE). The primary project objectives were to develop the conceptual design for a safe and economic small, natural circulation light water reactor, to address the economic and safety attributes of the concept, and to demonstrate the technical feasibility by testing in an integral test facility. This report presents the results of the project. After an initial exploratory and evolutionary process, as documented in the October 2000 report, the project focused on developing a modular reactor design that consists of a self-contained assembly with a reactor vessel, steam generators, and containment. These modular units would be manufactured at a single centralized facility, transported by rail, road, and/or ship, and installed as a series of self-contained units. This approach also allows for staged construction of an NPP and ''pull and replace'' refueling and maintenance during each five-year refueling cycle.

S. Michale Modro; James E. Fisher; Kevan D. Weaver; Jose N. Reyes, Jr.; John T. Groome; Pierre Babka; Thomas M. Carlson

2003-12-01T23:59:59.000Z

63

Issues affecting advanced passive light-water reactor safety analysis  

SciTech Connect (OSTI)

Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented.

Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

1992-01-01T23:59:59.000Z

64

Issues affecting advanced passive light-water reactor safety analysis  

SciTech Connect (OSTI)

Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented.

Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

1992-08-01T23:59:59.000Z

65

Energy - Water Nexus -- Meeting the Energy and Water Needs of the Snake/Columbia River Basin in the 21st CenturyScience and Technology SummitConference Results  

SciTech Connect (OSTI)

In June 2007, representatives from federal, state, and academic institutions met to discuss the role of innovative science, technology, and policy in meeting future energy and water demands in the Snake-Columbia River Basin. Conference members assessed the state-of-the-science, technology, and associated research to develop cost-effective and environmentally sound methodologies and technologies to maximize the production of energy and availability of water and to minimize the consumption of both water and energy in the Snake-Columbia River system. Information on all phases of science and technology development, theoretical analysis, laboratory experiments, pilot tests, and field applications were relevant topics for discussion. An overview of current management needs was presented the first day. On the second day, five focus groups were created: ? Energy Generation and Use ? Water Allocation and Use ? Energy/Water Storage ? Environmental Considerations ? Social, Economic, Political, and Regulatory Considerations. Each group started with a list of status items and trends, and discussed the future challenges and research needed to reach four goals: ? Balance energy production and resource consumption ? Balance water availability and competing needs ? Balance water consumption/energy production and competing needs ? Balance environmental impacts and water use/energy production ? Balance costs and benefits of water use. The resulting initiatives were further broken down into three categories of importance: critical, important, and nice to do but could be delayed. Each initiative was assigned a number of dots to show a more refined ranking. The results of each focus group are given in the pages that follow. These results are intended to help local and regional researchers 1. Develop a technical strategy for developing cost-effective science and technology to predict, measure, monitor, purify, conserve, and store water and to maximize power generation, storage, and efficiency in the region 2. Evaluate methods and technologies for reducing the impacts of energy and water development and use on the environment.

Paul L. Wichlacz; Gerald Sehlke

2008-02-01T23:59:59.000Z

66

The Consortium for Advanced Simulation of Light Water Reactors  

SciTech Connect (OSTI)

The Consortium for Advanced Simulation of Light Water Reactors (CASL) is a DOE Energy Innovation Hub for modeling and simulation of nuclear reactors. It brings together an exceptionally capable team from national labs, industry and academia that will apply existing modeling and simulation capabilities and develop advanced capabilities to create a usable environment for predictive simulation of light water reactors (LWRs). This environment, designated as the Virtual Environment for Reactor Applications (VERA), will incorporate science-based models, state-of-the-art numerical methods, modern computational science and engineering practices, and uncertainty quantification (UQ) and validation against data from operating pressurized water reactors (PWRs). It will couple state-of-the-art fuel performance, neutronics, thermal-hydraulics (T-H), and structural models with existing tools for systems and safety analysis and will be designed for implementation on both today's leadership-class computers and the advanced architecture platforms now under development by the DOE. CASL focuses on a set of challenge problems such as CRUD induced power shift and localized corrosion, grid-to-rod fretting fuel failures, pellet clad interaction, fuel assembly distortion, etc. that encompass the key phenomena limiting the performance of PWRs. It is expected that much of the capability developed will be applicable to other types of reactors. CASL's mission is to develop and apply modeling and simulation capabilities to address three critical areas of performance for nuclear power plants: (1) reduce capital and operating costs per unit energy by enabling power uprates and plant lifetime extension, (2) reduce nuclear waste volume generated by enabling higher fuel burnup, and (3) enhance nuclear safety by enabling high-fidelity predictive capability for component performance.

Ronaldo Szilard; Hongbin Zhang; Doug Kothe; Paul Turinsky

2011-10-01T23:59:59.000Z

67

Fuel Summary Report: Shippingport Light Water Breeder Reactor  

SciTech Connect (OSTI)

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

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

1999-01-01T23:59:59.000Z

68

Columbia University Postdoctoral Officers  

E-Print Network [OSTI]

Columbia University Postdoctoral Officers Handbook 2013 #12;Greetings! I am excited to welcome you to the Columbia University community of scholars and investigators. The Columbia University Office of Postdoctoral Director, Office of Postdoctoral Affairs Columbia University in the city of new york office of postdoctoral

Grishok, Alla

69

?engineering columbia university  

E-Print Network [OSTI]

?engineering why engineeri columbia university engineering engineering why engineering for the world to use. The images below represent technological innovations pioneered by Columbia engineers. Can Parsons graduated from Columbia in 1882. 2.) Flat panel TV--Columbia Professor James Im developed

70

Columbia University Postdoctoral Officers  

E-Print Network [OSTI]

Columbia University Postdoctoral Officers Handbook 2011 #12;Greetings! I am excited to welcome you to the Columbia University community of scholars and investigators. The Columbia University Office of Postdoctoral of Postdoctoral Affairs Columbia university in the City of new york offiCe of postdoCtoral affairs 840 Interchurch

Grishok, Alla

71

Tidal-Fluvial and Estuarine Processes in the Lower Columbia River: I. Along-channel Water Level Variations, Pacific Ocean to Bonneville Dam  

SciTech Connect (OSTI)

This two-part paper provides comprehensive time and frequency domain analyses and models of along-channel water level variations in the 234km-long Lower Columbia River and Estuary (LCRE) and documents the response of floodplain wetlands thereto. In Part I, power spectra, continuous wavelet transforms, and harmonic analyses are used to understand the influences of tides, river flow, upwelling and downwelling, and hydropower operations ("power-peaking") on the water level regime. Estuarine water levels are influenced primarily by astronomical tides and coastal processes, and secondarily by river flow. The importance of coastal and tidal influences decreases in the landward direction, and water levels are increasingly controlled by river flow variations at periods from ?1day to years. Water level records are only slightly non-stationary near the ocean, but become increasingly irregular upriver. Although astronomically forced tidal constituents decrease above the estuary, tidal fortnightly and overtide variations increase for 80-200km landward, both relative to major tidal constituents and in absolute terms.

Jay, D. A.; Leffler, K.; Diefenderfer, Heida L.; Borde, Amy B.

2014-06-07T23:59:59.000Z

72

Commercial Light Water Reactor Tritium Extraction Facility Geotechnical Summary Report  

SciTech Connect (OSTI)

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

Lewis, M.R.

2000-01-11T23:59:59.000Z

73

Materials Inventory Database for the Light Water Reactor Sustainability Program  

SciTech Connect (OSTI)

Scientific research involves the purchasing, processing, characterization, and fabrication of many sample materials. The history of such materials can become complicated over their lifetime materials might be cut into pieces or moved to various storage locations, for example. A database with built-in functions to track these kinds of processes facilitates well-organized research. The Material Inventory Database Accounting System (MIDAS) is an easy-to-use tracking and reference system for such items. The Light Water Reactor Sustainability Program (LWRS), which seeks to advance the long-term reliability and productivity of existing nuclear reactors in the United States through multiple research pathways, proposed MIDAS as an efficient way to organize and track all items used in its research. The database software ensures traceability of all items used in research using built-in functions which can emulate actions on tracked items fabrication, processing, splitting, and more by performing operations on the data. MIDAS can recover and display the complete history of any item as a simple report. To ensure the database functions suitably for the organization of research, it was developed alongside a specific experiment to test accident tolerant nuclear fuel cladding under the LWRS Advanced Light Water Reactor Nuclear Fuels Pathway. MIDAS kept track of materials used in this experiment from receipt at the laboratory through all processes, test conduct and, ultimately, post-test analysis. By the end of this process, the database proved to be right tool for this program. The database software will help LWRS more efficiently conduct research experiments, from simple characterization tests to in-reactor experiments. Furthermore, MIDAS is a universal tool that any other research team could use to organize their material inventory.

Kazi Ahmed; Shannon M. Bragg-Sitton

2013-08-01T23:59:59.000Z

74

Water cooled metal optics for the Advanced Light Source  

SciTech Connect (OSTI)

The program for providing water cooled metal optics for the Advanced Light Source at Berkeley is reviewed with respect to fabrication and metrology of the surfaces. Materials choices, surface figure and smoothness specifications, and metrology systems for measuring the plated metal surfaces are discussed. Results from prototype mirrors and grating blanks will be presented, which show exceptionally low microroughness and mid-period error. We will briefly describe out improved version of the Long Trace Profiler, and its importance to out metrology program. We have completely redesigned the mechanical, optical and computational parts of the profiler system with the cooperation of Peter Takacs of Brookhaven, Continental Optical, and Baker Manufacturing. Most important is that one of our profilers is in use at the vendor to allow testing during fabrication. Metrology from the first water cooled mirror for an ALS beamline is presented as an example. The preplating processing and grinding and polishing were done by Tucson Optical. We will show significantly better surface microroughness on electroless nickel, over large areas, than has been reported previously.

McKinney, W.R.; Irick, S.C. [Lawrence Berkeley Lab., CA (United States); Lunt, D.L.J. [Tucson Optical Research Corp., AZ (United States)

1991-10-28T23:59:59.000Z

75

Columbia Gas of Virginia- Business Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

Columbia Gas of Virginia offers rebates to commercial customers for the purchase and installation of energy efficient equipment. Water heaters, furnaces, boilers and controls, laundromat clothes...

76

Columbia Gas of Kentucky- Home Savings Rebate Program (Kentucky)  

Broader source: Energy.gov [DOE]

Columbia Gas of Kentucky offers rebates to residential customers for the purchase and installation of energy efficient appliances and equipment. Water heaters, furnaces and space heating equipment...

77

Columbia River Component Data Gap Analysis  

SciTech Connect (OSTI)

This Data Gap Analysis report documents the results of a study conducted by Washington Closure Hanford (WCH) to compile and reivew the currently available surface water and sediment data for the Columbia River near and downstream of the Hanford Site. This Data Gap Analysis study was conducted to review the adequacy of the existing surface water and sediment data set from the Columbia River, with specific reference to the use of the data in future site characterization and screening level risk assessments.

L. C. Hulstrom

2007-10-23T23:59:59.000Z

78

Light Water Reactor Sustainability Constellation Pilot Project FY13 Summary Report  

SciTech Connect (OSTI)

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

R. Johansen

2013-09-01T23:59:59.000Z

79

Lansing Board of Water and Light- Hometown Energy Savers Commercial Rebates  

Broader source: Energy.gov [DOE]

Franklin Energy Services and the Lansing Board of Water and Light (LBWL) partner together to offer the Hometown Energy Savers Commercial and Industrial Energy Efficiency Rebate Program. Eligible...

80

Light Water Reactor Sustainability Constellation Pilot Project FY12 Summary Report  

SciTech Connect (OSTI)

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

R. Johansen

2012-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Light-water-reactor safety research program. Quarterly progress report, July to September 1981  

SciTech Connect (OSTI)

Information is presented concerning environmentally assisted cracking in light water reactors; transient fuel response and fission-product release; and clad properties for code verification.

Not Available

1982-02-01T23:59:59.000Z

82

McMinnville Water and Light- Residential Energy Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

McMinnville Water and Light (MWL) offers rebates on energy efficient homes, appliances and equipment to their residential customers. Rebates are valid on refrigerators, freezers, clothes washer,...

83

COLUMBIA UNIVERSITY Computer Engineering Program  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY Computer Engineering Program The Fu Foundation School of Engineering Zukowski (caz@columbia.edu) Acting Chair, Computer Engineering Program #12;COLUMBIA UNIVERSITY Computer interdepartmental major within Engineering School #12;COLUMBIA UNIVERSITY Computer Engineering Program The Fu

Yang, Junfeng

84

Physics methods for calculating light water reactor increased performances  

SciTech Connect (OSTI)

The intensive use of light water reactors (LWRs) has induced modification of their characteristics and performances in order to improve fissile material utilization and to increase their availability and flexibility under operation. From the conceptual point of view, adequate methods must be used to calculate core characteristics, taking into account present design requirements, e.g., use of burnable poison, plutonium recycling, etc. From the operational point of view, nuclear plants that have been producing a large percentage of electricity in some countries must adapt their planning to the need of the electrical network and operate on a load-follow basis. Consequently, plant behavior must be predicted and accurately followed in order to improve the plant's capability within safety limits. The Belgonucleaire code system has been developed and extensively validated. It is an accurate, flexible, easily usable, fast-running tool for solving the problems related to LWR technology development. The methods and validation of the two computer codes LWR-WIMS and MICROLUX, which are the main components of the physics calculation system, are explained.

Vandenberg, C.; Charlier, A.

1988-11-01T23:59:59.000Z

85

Technologies for Upgrading Light Water Reactor Outlet Temperature  

SciTech Connect (OSTI)

Nuclear energy could potentially be utilized in hybrid energy systems to produce synthetic fuels and feedstocks from indigenous carbon sources such as coal and biomass. First generation nuclear hybrid energy system (NHES) technology will most likely be based on conventional light water reactors (LWRs). However, these LWRs provide thermal energy at temperatures of approximately 300C, while the desired temperatures for many chemical processes are much higher. In order to realize the benefits of nuclear hybrid energy systems with the current LWR reactor fleets, selection and development of a complimentary temperature upgrading technology is necessary. This paper provides an initial assessment of technologies that may be well suited toward LWR outlet temperature upgrading for powering elevated temperature industrial and chemical processes during periods of off-peak power demand. Chemical heat transformers (CHTs) are a technology with the potential to meet LWR temperature upgrading requirements for NHESs. CHTs utilize chemical heat of reaction to change the temperature at which selected heat sources supply or consume thermal energy. CHTs could directly utilize LWR heat output without intermediate mechanical or electrical power conversion operations and the associated thermodynamic losses. CHT thermal characteristics are determined by selection of the chemical working pair and operating conditions. This paper discusses the chemical working pairs applicable to LWR outlet temperature upgrading and the CHT operating conditions required for providing process heat in NHES applications.

Daniel S. Wendt; Piyush Sabharwall; Vivek Utgikar

2013-07-01T23:59:59.000Z

86

Chemical and light-stable isotope characteristics of waters from...  

Open Energy Info (EERE)

water; (2) there is a single deep hot water, and the range of chloride concentrations is produced by the water passing through a zone of highly soluble materials (most likely in...

87

Guillaume Bal Columbia University  

E-Print Network [OSTI]

Guillaume Bal Columbia University 500 W. 120th St, New York, NY 10027, U.S.A. (212) 854 4731 - 1993 Professional Experience · Professor, Columbia University, 2008-present. · Associate Professor, Columbia University, 2003-2008. · Visiting scholar, Institute for Pure and Applied Mathematics, UCLA campus

Bal, Guillaume

88

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to declineeven with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energys Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administrations energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Programs plans.

McCarthy, Kathryn A. [INL; Busby, Jeremy [ORNL; Hallbert, Bruce [INL; Bragg-Sitton, Shannon [INL; Smith, Curtis [INL; Barnard, Cathy [INL

2014-04-01T23:59:59.000Z

89

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline - even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy's Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program's plans.

George Griffith; Robert Youngblood; Jeremy Busby; Bruce Hallbert; Cathy Barnard; Kathryn McCarthy

2012-01-01T23:59:59.000Z

90

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to declineeven with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energys Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administrations energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Programs plans.

Kathryn McCarthy; Jeremy Busby; Bruce Hallbert; Shannon Bragg-Sitton; Curtis Smith; Cathy Barnard

2013-04-01T23:59:59.000Z

91

Multi-Application Small Light Water Reactor Final Report  

SciTech Connect (OSTI)

The Multi-Application Small Light Water Reactor (MASLWR) project was conducted under the auspices of the Nuclear Energy Research Initiative (NERI) of the U.S. Department of Energy (DOE). The primary project objectives were to develop the conceptual design for a safe and economic small, natural circulation light water reactor, to address the economic and safety attributes of the concept, and to demonstrate the technical feasibility by testing in an integral test facility. This report presents the results of the project. After an initial exploratory and evolutionary process, as documented in the October 2000 report, the project focused on developing a modular reactor design that consists of a self-contained assembly with a reactor vessel, steam generators, and containment. These modular units would be manufactured at a single centralized facility, transported by rail, road, and/or ship, and installed as a series of self-contained units. This approach also allows for staged construction of an NPP and ''pull and replace'' refueling and maintenance during each five-year refueling cycle. Development of the baseline design concept has been sufficiently completed to determine that it complies with the safety requirements and criteria, and satisfies the major goals already noted. The more significant features of the baseline single-unit design concept include: (1) Thermal Power--150 MWt; (2) Net Electrical Output--35 MWe; (3) Steam Generator Type--Vertical, helical tubes; (4) Fuel UO{sub 2}, 8% enriched; (5) Refueling Intervals--5 years; (6) Life-Cycle--60 years. The economic performance was assessed by designing a power plant with an electric generation capacity in the range of current and advanced evolutionary systems. This approach allows for direct comparison of economic performance and forms a basis for further evaluation, economic and technical, of the proposed design and for the design evolution towards a more cost competitive concept. Applications such as cogeneration, water desalination or district heating were not addressed directly in the economic analyses since these depend more on local conditions, demand and economy and can not be easily generalized. Current economic performance experience and available cost data were used. The preliminary cost estimate, based on a concept that could be deployed in less than a decade, is: (1) Net Electrical Output--1050 MWe; (2) Net Station Efficiency--23%; (3) Number of Power Units--30; (4) Nominal Plant Capacity Factor--95%; (5) Total capital cost--$1241/kWe; and (6) Total busbar cost--3.4 cents/kWh. The project includes a testing program that has been conducted at Oregon State University (OSU). The test facility is a 1/3-height and 1/254.7 volume scaled design that will operate at full system pressure and temperature, and will be capable of operation at 600 kW. The design and construction of the facility have been completed. Testing is scheduled to begin in October 2002. The MASLWR conceptual design is simple, safe, and economical. It operates at NSSS parameters much lower than for a typical PWR plant, and has a much simplified power generation system. The individual reactor modules can be operated as on/off units, thereby limiting operational transients to startup and shutdown. In addition, a plant can be built in increments that match demand increases. The ''pull and replace'' concept offers automation of refueling and maintenance activities. Performing refueling in a single location improves proliferation resistance and eliminates the threat of diversion. Design certification based on testing is simplified because of the relatively low cost of a full-scale prototype facility. The overall conclusion is that while the efficiency of the power generation unit is much lower (23% versus 30%), the reduction in capital cost due to simplification of design more than makes up for the increased cost of nuclear fuel. The design concept complies with the safety requirements and criteria. It also satisfies the goals for modularity, standard plant design, certification before construction, c

Modro, S.M.; Fisher, J.E.; Weaver, K.D.; Reyes, J.N.; Groome, J.T.; Babka, P.; Carlson, T.M.

2003-12-01T23:59:59.000Z

92

Cross section generation strategy for high conversion light water reactors  

E-Print Network [OSTI]

High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR), are being designed with axial heterogeneity of alternating fissile and blanket zones to achieve a conversion ratio of ...

Herman, Bryan R. (Bryan Robert)

2011-01-01T23:59:59.000Z

93

1 Columbia University--The University Seminars COLUMBIA UNIVERSITY  

E-Print Network [OSTI]

1 Columbia University--The University Seminars COLUMBIA UNIVERSITY T H E U N I V E R S I T Y S E M. Belknap Professor Emeritus of Russian, Columbia University, Director Emeritus of The University Seminars, Columbia University Susan Boynton Associate Professor of Music, Columbia University Ester Fuchs Professor

Champagne, Frances A.

94

Sustained Recycle in Light Water and Sodium-Cooled Reactors  

SciTech Connect (OSTI)

From a physics standpoint, it is feasible to sustain recycle of used fuel in either thermal or fast reactors. This paper examines multi-recycle potential performance by considering three recycling approaches and calculating several fuel cycle parameters, including heat, gamma, and neutron emission of fresh fuel; radiotoxicity of waste; and uranium utilization. The first recycle approach is homogeneous mixed oxide (MOX) fuel assemblies in a light water reactor (LWR). The transuranic portion of the MOX was varied among Pu, NpPu, NpPuAm, or all-TRU. (All-TRU means all isotopes through Cf-252.) The Pu case was allowed to go to 10% Pu in fresh fuel, but when the minor actinides were included, the transuranic enrichment was kept below 8% to satisfy the expected void reactivity constraint. The uranium portion of the MOX was enriched uranium. That enrichment was increased (to as much as 6.5%) to keep the fuel critical for a typical LWR irradiation. The second approach uses heterogeneous inert matrix fuel (IMF) assemblies in an LWR - a mix of IMF and traditional UOX pins. The uranium-free IMF fuel pins were Pu, NpPu, NpPuAm, or all-TRU. The UOX pins were limited to 4.95% U-235 enrichment. The number of IMF pins was set so that the amount of TRU in discharged fuel from recycle N (from both IMF and UOX pins) was made into the new IMF pins for recycle N+1. Up to 60 of the 264 pins in a fuel assembly were IMF. The assembly-average TRU content was 1-6%. The third approach uses fast reactor oxide fuel in a sodium-cooled fast reactor with transuranic conversion ratio of 0.50 and 1.00. The transuranic conversion ratio is the production of transuranics divided by destruction of transuranics. The FR at CR=0.50 is similar to the CR for the MOX case. The fast reactor cases had a transuranic content of 33-38%, higher than IMF or MOX.

Steven J. Piet; Samuel E. Bays; Michael A. Pope; Gilles J. Youinou

2010-11-01T23:59:59.000Z

95

advanced light water: Topics by E-print Network  

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

SM top properties such as the cross-section has been suggested to give a handle for this stealth stop' scenario. We present an estimate of the potential impact a light stop may...

96

COLUMBIA UNIVERSITY Radiation Safety Program  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY Radiation Safety Program Medical Center - T: 212-305-0303 F: 212-305-0318 rso-clinical@columbia by more than 50 percent. #12;COLUMBIA UNIVERSITY Radiation Safety Program Medical Center - T: 212 ________________________________________________________ ________________________________________________________ #12;COLUMBIA UNIVERSITY Radiation Safety Program Medical Center - T: 212-305-0303 F: 212-305-0318 rso-clinical@columbia

Jia, Songtao

97

The impact of passive safety systems on desirability of advanced light water reactors  

E-Print Network [OSTI]

This work investigates whether the advanced light water reactor designs with passive safety systems are more desirable than advanced reactor designs with active safety systems from the point of view of uncertainty in the ...

Eul, Ryan C

2006-01-01T23:59:59.000Z

98

Memphis Light, Gas and Water (Electric)- Commercial Efficiency Advice and Incentives Program  

Broader source: Energy.gov [DOE]

Memphis Light, Gas and Water (MLGW), in partnership with the Tennessee Valley Authority (TVA), offers a variety of energy efficient incentives to non-residential customers. The program provides...

99

E-Print Network 3.0 - advanced light-water nuclear Sample Search...  

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

by Explorit Topic List Advanced Search Sample search results for: advanced light-water nuclear Page: << < 1 2 3 4 5 > >> 1 1 Managed by UT-Battelle for the U.S. Department...

100

INL/EXT-14-33257 Light Water Reactor Sustainability Program  

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

57 Light Water Reactor Sustainability Program 3D J-Integral Capability in Grizzly September 2014 DOE Office of Nuclear Energy DISCLAIMER This information was prepared as an account...

Note: This page contains sample records for the topic "light columbia water" 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

Assessment of light water reactor power plant cost and ultra-acceleration depreciation financing  

E-Print Network [OSTI]

Although in many regions of the U.S. the least expensive electricity is generated from light-water reactor (LWR) plants, the fixed (capital plus operation and maintenance) cost has increased to the level where the cost ...

El-Magboub, Sadek Abdulhafid.

102

McMinnville Water and Light- Commercial Energy Efficiency Rebate Programs  

Broader source: Energy.gov [DOE]

McMinnville Water and Light Company offers a variety of rebates for commercial and industrial customers to make energy efficient improvements to eligible facilities. MW&L offers rebates in...

103

EIS-0288: Production of Tritium in a Commercial Light Water Reactor  

Broader source: Energy.gov [DOE]

This Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor (CLWR EIS) evaluates the environmental impacts associated with producing tritium at one or more...

104

Visible Light Water Splitting Using Dye-Sensitized Oxide Semiconductors  

E-Print Network [OSTI]

- ical energy in the form of fuels. Hydrogen is a key solar fuel because it can be used directly. This Account describes our approach to two problems in solar water splitting: the organization of molecules in photochemistry.1,2 Efficient photocatalytic water-splitting systems could have practical value for solar energy

105

Columbia River Treaty  

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

an understanding of the implications for post-2024 Treaty planning and Columbia River operations. The joint effort by the Entities to conduct initial post-2024 modeling and...

106

COLUMBIA UNIVERSITY DEPARTMENT OF NEUROLOGY  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY DEPARTMENT OF NEUROLOGY RESEARCH RESOURCES GUIDE Prepared by Minu Chaudhuri, Ph.edu/research/gcp.htm. The Columbia University Health Sciences Division requirement is the demonstration of knowledge ............................................................................. 3 IV ) Columbia Funding Resources

Pullman, Seth L.

107

The predicted impacts to the groundwater and Columbia River from ammoniated water discharges to the 216-A-36B crib  

SciTech Connect (OSTI)

Impact from past and potential future discharges of ammoniated water to the 216-A-36B crib have on groundwater and river concentrations of hazardous chemical constitutents are studied. Until August 1987, the 216-A-36B crib, located in the 200-East Area of the Hanford Site, accepted ammoniated water discharges. Although this study addresses known hazardous chemical constituents associated with such discharges, the primary concern is the discharge of NH/sub 4/OH because of its microbiological conversion to NO/sub 2//sup /minus// and NO/sub 3//sup /minus//. As a result of fuel decladding operations, material balance calculations indicate that NH/sub 4/OH has been discharged to the 216-A-36B crib in amounts that exceed reportable quantities under the Comprehensive Environmental Response, Compensation and Liability Act of 1980. Although flow to the crib is relatively constant, the estimated NH/sub 4/OH discharge varies from negligible to a maximum of 10,000 g-molesh. Because these discharges are intermittent, the concentration delivered to the groundwater is a function of soil sorption, microbiological conversion rates of NH/sub 4//sup +/ to NO/sub 2//sup /minus// and NO/sub 3//sup /minus//, and groundwater dispersion. This report provides results based on the assumptions of maximum, nominal, and discountinued NH/sub 4/OH discharges to the crib. Consequently, the results show maximum and realistic estimates of NH/sub 4//sup +/, NO/sub 2//sup /minus// and NO/sub 3//sup /minus// concentrations in the groundwater.

Buelt, J.L.; Conbere, W.; Freshley, M.D.; Hicks, R.J.; Kuhn, W.L.; Lamar, D.A.; Serne, R.J.; Smoot, J.L.

1988-03-01T23:59:59.000Z

108

Fatigue and environmentally assisted cracking in light water reactors  

SciTech Connect (OSTI)

Fatigue and stress corrosion cracking (SCC) for low-alloy steel used in piping and in steam generator and reactor pressure vessels have been investigated. Fatigue data were obtained on medium-sulfur-content A533-Gr B and A106-Gr B steels in high-purity (HP) deoxygenated water, in simulated pressurized water reactor water, and in air. Analytical studies focused on the behavior of carbon steels in boiling water reactor (BWR) environments. Crack-growth rates of composite fracture-mechanics specimens of A533-Gr B/Inconel-182/Inconel-600 (plated with nickel) and homogeneous specimens of A533-Gr B steel were determined under small-amplitude cyclic loading in HP water with {approx}300 pbb dissolved oxygen. Radiation-induced segregation and irradiation-assisted SCC of Type 304 SS after accumulation of relatively high fluence also have been investigated. Microchemical and microstructural changes in HP and commercial-purity Type 304 SS specimens from control-blade absorber tubes used in two operating BWRs were studied by Auger electron spectroscopy and scanning electron microscopy, and slow-strain-rate tensile tests were conducted on tubular specimens in air and in simulated BWR water at 289{degrees}C.

Kassner, T.F.; Ruther, W.E.; Chung, H.M.; Hicks, P.D.; Hins, A.G.; Park, J.Y.; Shack, W.J.

1992-03-01T23:59:59.000Z

109

Materials science division light-water-reactor safety research program. Quarterly progress report, October - December 1981  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during October, November, and December 1981 on water-reactor-safety problems. The research and development areas covered are environmentally assisted cracking in light water reactors, transient fuel response and fission-product release, and clad properties for code verification.

Not Available

1982-05-01T23:59:59.000Z

110

Light-water-reactor safety research program. Quarterly progress report, April-June 1981  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1981 on water-reactor-safety problems. The research and development areas covered are transient fuel response and fission-product release and environmentally assisted cracking in light water reactors.

Not Available

1981-01-01T23:59:59.000Z

111

The Columbia River System Inside Story  

SciTech Connect (OSTI)

The Columbia River is one of the greatest natural resources in the western United States. The river and its tributaries touch the lives of nearly every resident of the Pacific Northwestfrom fostering world-famous Pacific salmon to supplying clean natural fuel for 50 to 65 percent of the regions electrical generation. Since early in the 20th century, public and private agencies have labored to capture the benefits of this dynamic river. Today, dozens of major water resource projects throughout the region are fed by the waters of the Columbia Basin river system.

none,

2001-04-01T23:59:59.000Z

112

Database of radionuclide measurements in Columbia River water, fish, waterfowl, gamebirds, and shellfish downstream of Hanford`s single-pass production reactors, 1960--1970. Hanford Environmental Dose Reconstruction Project  

SciTech Connect (OSTI)

This report is a result of the Hanford Environmental Dose Reconstruction (HEDR) Project. The goal of the HEDR Project is to estimate the radiation dose that individuals could have received from radionuclide emissions since 1944 at the Hanford Site near Richland, Washington. The HEDR Project is conducted by Battelle, Pacific Northwest Laboratories. The time periods of greatest interest to the HEDR study vary depending on the type of environmental media concerned. Concentrations of radionuclides in Columbia River media from 1960--1970 provide the best historical data for validation of the Columbia River pathway computer models. This report provides the historical radionuclide measurements in Columbia River water (1960--1970), fish (1960--1967), waterfowl (1960--1970), gamebirds (1967--1970), and shellfish (1960--1970). Because of the large size of the databases (845 pages), this report is being published on diskette. A diskette of this report is available from the Technical Steering Panel (c/o K. CharLee, Office of Nuclear Waste Management, Department of Ecology, Technical Support and Publication Information Section, P.O. Box 47651, Olympia, Washington 98504-7651).

Thiede, M.E.; Duncan, J.P.

1994-03-01T23:59:59.000Z

113

Impact of Pilot Light Modeling on the Predicted Annual Performance of Residential Gas Water Heaters: Preprint  

SciTech Connect (OSTI)

Modeling residential water heaters with dynamic simulation models can provide accurate estimates of their annual energy consumption, if the units? characteristics and use conditions are known. Most gas storage water heaters (GSWHs) include a standing pilot light. It is generally assumed that the pilot light energy will help make up standby losses and have no impact on the predicted annual energy consumption. However, that is not always the case. The gas input rate and conversion efficiency of a pilot light for a GSWH were determined from laboratory data. The data were used in simulations of a typical GSWH with and without a pilot light, for two cases: 1) the GSWH is used alone; and 2) the GSWH is the second tank in a solar water heating (SWH) system. The sensitivity of wasted pilot light energy to annual hot water use, climate, and installation location was examined. The GSWH used alone in unconditioned space in a hot climate had a slight increase in energy consumption. The GSWH with a pilot light used as a backup to an SWH used up to 80% more auxiliary energy than one without in hot, sunny locations, from increased tank losses.

Maguire, J.; Burch, J.

2013-08-01T23:59:59.000Z

114

The Columbia River System : the Inside Story.  

SciTech Connect (OSTI)

The Columbia Ricer is one of the greatest natural resources in the western United States. The river and its tributaries touch the lives of nearly every resident of the Northwest-from providing the world-famous Pacific salmon to supplying the clean natural fuel for over 75 percent of the region's electrical generation. Since early in the century, public and private agencies have labored to capture the benefits of this dynamic river. Today, dozens of major water resource projects throughout the region are fed by the waters of the Columbia Basin river system. And through cooperative efforts, the floods that periodically threaten developments near the river can be controlled. This publication presents a detailed explanation of the planning and operation of the multiple-use dams and reservoirs of the Columbia River system. It describes the river system, those who operate and use it, the agreements and policies that guide system operation, and annual planning for multiple-use operation.

United States. Bonneville Power Administration.

1991-09-01T23:59:59.000Z

115

Superior Water, Light and Power Co | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectric Coop, Inc Place: MissouriPrograms |IllinoisCPA CDC1 LLCSunergieWater,

116

Albany Water Gas & Light Comm | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDIT REPORTOpenWende NewSowitecAWSAgri-Energy LLCAir(EC-LEDS) | Open EnergyWater

117

Moose Lake Water & Light Comm | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar Powerstories onFocus Area EnergyMohawk MunicipalMontvale, New Jersey:Water &

118

Two Rivers Water & Light | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov Pty LtdSteen,LtdInformationTulsa,Tuscarawas County,Florida:Creeks,Water &

119

Light-water-reactor safety materials engineering research programs. Quarterly progress report, January-March 1985. Volume 1  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1985 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems. 42 refs.

Not Available

1986-03-01T23:59:59.000Z

120

Light-water-reactor safety materials engineering research programs. Volume 3. Quarterly progress report, October-December 1984  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during October, November, and December 1984 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems.

Not Available

1985-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Environmentally assisted cracking of light-water reactor materials  

SciTech Connect (OSTI)

Environmentally assisted cracking (EAC) of lightwater reactor (LWR) materials has affected nuclear reactors from the very introduction of the technology. Corrosion problems have afflicted steam generators from the very introduction of pressurized water reactor (PWR) technology. Shippingport, the first commercial PWR operated in the United States, developed leaking cracks in two Type 304 stainless steel (SS) steam generator tubes as early as 1957, after only 150 h of operation. Stress corrosion cracks were observed in the heat-affected zones of welds in austenitic SS piping and associated components in boiling-water reactors (BRWs) as early as 1965. The degradation of steam generator tubing in PWRs and the stress corrosion cracking (SCC) of austenitic SS piping in BWRs have been the most visible and most expensive examples of EAC in LWRs, and the repair and replacement of steam generators and recirculation piping has cost hundreds of millions of dollars. However, other problems associated with the effects of the environment on reactor structures and components am important concerns in operating plants and for extended reactor lifetimes. Cast duplex austenitic-ferritic SSs are used extensively in the nuclear industry to fabricate pump casings and valve bodies for LWRs and primary coolant piping in many PWRs. Embrittlement of the ferrite phase in cast duplex SS may occur after 10 to 20 years at reactor operating temperatures, which could influence the mechanical response and integrity of pressure boundary components during high strain-rate loading (e.g., seismic events). The problem is of most concern in PWRs where slightly higher temperatures are typical and cast SS piping is widely used.

Chopra, O.K.; Chung, H.M.; Kassner, T.F.; Shack, W.J.

1996-02-01T23:59:59.000Z

122

Columbia university An Overview  

E-Print Network [OSTI]

, music, art, and science. The Fu FOundATiOn SChOOl OF engineering And Applied SCienCe wwwTS And SCienCeS www.columbia.edu/cu/gsas GSAS is one of the most distinguished graduate schools in the UnitedAduATe SChOOl OF ArChiTeCTure, plAnning And preServATiOn www.arch.columbia.edu GSAPP's international

Shepard, Kenneth

123

Written Testimony of Wes Kelley Executive Director Columbia Power...  

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

serving the City of Columbia and much of Maury County, Tennessee. My utility provides electricity, water, and broadband services to 25,000 homes and businesses. I also serve on...

124

Materials Science Division light-water-reactor safety research program. Quarterly progress report, January-March 1982  

SciTech Connect (OSTI)

Information is presented concerning environmentally assisted cracking in light water reactors; transient fuel response and fission product release; and clad properties for code verification.

Shack, W.J.; Rest, J.; Kassner, T.F.

1982-10-01T23:59:59.000Z

125

Light Water Reactor Sustainability Constellation Pilot Project FY11 Summary Report  

SciTech Connect (OSTI)

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

R. Johansen

2011-09-01T23:59:59.000Z

126

Light Water Reactor Safety Research Program. Semiannual report, April-September 1982  

SciTech Connect (OSTI)

This report documents progress made in Light Water Reactor Safety research conducted by Division 6441 in the period from April 1982 to September 1982. The programs conducted under investigation include Core Concrete Interactions, Core Melt-Coolant Interactions, Containment Emergency Sump Performance, the Hydrogen Program, and Combustible Gas in Containment Program. 50 references.

Berman, M.

1983-10-01T23:59:59.000Z

127

Light water reactor safety research program. Volume 12: quarterly report, Apr-Jun 79  

SciTech Connect (OSTI)

This report summarizes the progress of the Light Water Reactor Safety Research Program during the 2nd quarter of 1979. Specifically, the report summarizes progress in five major areas of research. They are: (1) the molten core/concrete interactions study; (2) steam explosion research phenomena; (3) statistical LOCA analysis; (4) UHI model development; (5) two-phase jet loads.

Berman, M.

1980-05-01T23:59:59.000Z

128

The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel  

E-Print Network [OSTI]

Light water reactors (LWRs) are the worlds dominant nuclear reactor system. Uranium (U)-fuelled LWRs produce long-lived transuranic (TRU) isotopes. TRUs can be recycled in LWRs or fast reactors. The thermal neutron spectrum in LWRs is less suitable...

Lindley, Benjamin A.

2015-02-03T23:59:59.000Z

129

Materials Degradation in Light Water Reactors: Life After 60,???  

SciTech Connect (OSTI)

Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high temperature water, stress, vibration, and an intense neutron field. Degradation of materials in this environment can lead to reduced performance, and in some cases, sudden failure. A recent EPRI-led study interviewed 47 US nuclear utility executives to gauge perspectives on long-term operation of nuclear reactors. Nearly 90% indicated that extensions of reactor lifetimes to beyond 60 years were likely. When polled on the most challenging issues facing further life extension, two-thirds cited plant reliability as the key issue with materials aging and cable/piping as the top concerns for plant reliability. Materials degradation within a nuclear power plant is very complex. There are many different types of materials within the reactor itself: over 25 different metal alloys can be found with can be found within the primary and secondary systems, not to mention the concrete containment vessel, instrumentation and control, and other support facilities. When this diverse set of materials is placed in the complex and harsh environment coupled with load, degradation over an extended life is indeed quite complicated. To address this issue, the USNRC has developed a Progressive Materials Degradation Approach (NUREG/CR-6923). This approach is intended to develop a foundation for appropriate actions to keep materials degradation from adversely impacting component integrity and safety and identify materials and locations where degradation can reasonably be expected in the future. Clearly, materials degradation will impact reactor reliability, availability, and potentially, safe operation. Routine surveillance and component replacement can mitigate these factors, although failures still occur. With reactor life extensions to 60 years or beyond or power uprates, many components must tolerate the reactor environment for even longer times. This may increase susceptibility for most components and may introduce new degradation modes. While all components (except perhaps the reactor vessel) can be replaced, it may not be economically favorable. Therefore, understanding, controlling, and mitigating materials degradation processes are key priorities for reactor operation, power uprate considerations, and life extensions. This document is written to give an overview of some of the materials degradation issues that may be key for extend reactor service life. A detailed description of all the possible forms of degradation is beyond the scope of this short paper and has already been described in other documents (for example, the NUREG/CR-6923). The intent of this document is to present an overview of current materials issues in the existing reactor fleet and a brief analysis of the potential impact of extending life beyond 60 years. Discussion is presented in six distinct areas: (1) Reactor pressure vessel; (2) Reactor core and primary systems; (3) Reactor secondary systems; (4) Weldments; (5) Concrete; and (6) Modeling and simulations. Following each of these areas, some research thrust directions to help identify and mitigate lifetime extension issues are proposed. Note that while piping and cabling are important for extended service, these components are discussed in more depth in a separate paper. Further, the materials degradation issues associated with fuel cladding and fuel assemblies are not discussed in this section as these components are replaced periodically and will not influence the overall lifetime of the reactor.

Busby, Jeremy T [ORNL; Nanstad, Randy K [ORNL; Stoller, Roger E [ORNL; Feng, Zhili [ORNL; Naus, Dan J [ORNL

2008-04-01T23:59:59.000Z

130

Columbia River Treaty History and 2014/2024 Review  

SciTech Connect (OSTI)

The Columbia River, the fourth largest river on the continent as measured by average annual ?ow, generates more power than any other river in North America. While its headwaters originate in British Columbia, only about 15 percent of the 259,500 square miles of the Columbia River Basin is actually located in Canada. Yet the Canadian waters account for about 38 percent of the average annual volume, and up to 50 percent of the peak ?ood waters, that ?ow by The Dalles Dam on the Columbia River between Oregon and Washington. In the 1940s, of?cials from the United States and Canada began a long process to seek a joint solution to the ?ooding caused by the unregulated Columbia River and to the postwar demand for greater energy resources. That effort culminated in the Columbia River Treaty, an international agreement between Canada and the United States for the cooperative development of water resources regulation in the upper Columbia River Basin. It was signed in 1961 and implemented in 1964.

None

2009-02-01T23:59:59.000Z

131

Columbia College and Columbia Engineering Premedical Advisory Committee Evaluation  

E-Print Network [OSTI]

1 Columbia College and Columbia Engineering Premedical Advisory Committee Evaluation Guidelines .....................................................................................................................................................13 Guidelines for Recommendation Letters for Pre-Health Students your request is received, you will be asked to confirm it. This is a security measure to ensure

Hone, James

132

Thermophysical properties of saturated light and heavy water for advanced neutron source applications  

SciTech Connect (OSTI)

The Advanced Neutron Source is an experimental facility being developed by Oak Ridge National Laboratory. As a new nuclear fission research reactor of unprecedented flux, the Advanced Neutron Source Reactor will provide the most intense steady-state beams of neutrons in the world. The high heat fluxes generated in the reactor [303 MW(t) with an average power density of 4.5 MW/L] will be accommodated by a flow of heavy water through the core at high velocities. In support of this experimental and analytical effort, a reliable, highly accurate, and uniform source of thermodynamic and transport property correlations for saturated light and heavy water were developed. In order to attain high accuracy in the correlations, the range of these correlations was limited to the proposed Advanced Neutron Source Reactor's nominal operating conditions. The temperature and corresponding saturation pressure ranges used for light water were 20--300[degrees]C and 0.0025--8.5 MPa, respectively, while those for heavy water were 50--250[degrees]C and 0.012--3.9 MPa. Deviations between the correlation predictions and data from the various sources did not exceed 1.0%. Light water vapor density was the only exception, with an error of 1.76%. The physical property package consists of analytical correlations, SAS codes, and FORTRAN subroutines incorporating these correlations, as well as an interactive, easy-to-use program entitled QuikProp.

Crabtree, A.; Siman-Tov, M.

1993-05-01T23:59:59.000Z

133

Thermophysical properties of saturated light and heavy water for Advanced Neutron Source applications  

SciTech Connect (OSTI)

The Advanced Neutron Source is an experimental facility being developed by Oak Ridge National Laboratory. As a new nuclear fission research reactor of unprecedented flux, the Advanced Neutron Source Reactor will provide the most intense steady-state beams of neutrons in the world. The high heat fluxes generated in the reactor [303 MW(t) with an average power density of 4.5 MW/L] will be accommodated by a flow of heavy water through the core at high velocities. In support of this experimental and analytical effort, a reliable, highly accurate, and uniform source of thermodynamic and transport property correlations for saturated light and heavy water were developed. In order to attain high accuracy in the correlations, the range of these correlations was limited to the proposed Advanced Neutron Source Reactor`s nominal operating conditions. The temperature and corresponding saturation pressure ranges used for light water were 20--300{degrees}C and 0.0025--8.5 MPa, respectively, while those for heavy water were 50--250{degrees}C and 0.012--3.9 MPa. Deviations between the correlation predictions and data from the various sources did not exceed 1.0%. Light water vapor density was the only exception, with an error of 1.76%. The physical property package consists of analytical correlations, SAS codes, and FORTRAN subroutines incorporating these correlations, as well as an interactive, easy-to-use program entitled QuikProp.

Crabtree, A.; Siman-Tov, M.

1993-05-01T23:59:59.000Z

134

Life cycle assessment of buildings technologies: High-efficiency commercial lighting and residential water heaters  

SciTech Connect (OSTI)

In this study the life cycle emissions and energy use are estimated for two types of energy technologies. The first technology evaluated is the sulfur lamp, a high-efficiency lighting system under development by the US Department of Energy (DOE) and Fusion Lighting, the inventor of the technology. The sulfur lamp is compared with conventional metal halide high-intensity discharge lighting systems. The second technology comparison is between standard-efficiency and high-efficiency gas and electric water heaters. In both cases the life cycle energy use and emissions are presented for the production of an equivalent level of service by each of the technologies. For both analyses, the energy use and emissions from the operation of the equipment are found to dominate the life cycle profile. The life cycle emissions for the water heating systems are much more complicated. The four systems compared include standard- and high-efficiency gas water heaters, standard electric resistance water heaters, and heat pump water heaters.

Freeman, S.L.

1997-01-01T23:59:59.000Z

135

Columbia University http://www.columbia.edu/~mem4/  

E-Print Network [OSTI]

Mike Mauel Columbia University http://www.columbia.edu/~mem4/ National Undergraduate Fusion plant · Columbia University's plasma physics experiments 6Friday, June 5, 2009 #12;Forces of Nature, 2009 100-300 s after the "Big-Bang": The Age of Fusion · At 100 sec, the universe cools to 1

Mauel, Michael E.

136

Columbia Blue Furnald MathematicsLewisohn  

E-Print Network [OSTI]

Columbia Blue #12;Furnald MathematicsLewisohn Dodge Miller Theatre Kent International Affairs Columbia Blue Blue View: Part I 4 Exponential Education 10 Columbia Days 26 Common Core, 44 Uncommon 72 Columbia Engineering 78 Community, Columbia Style 84 Columbia Moments: 100 Tried and True Blue

Hone, James

137

Dingzeyu Li LE Schapiro (CEPSR), Columbia University  

E-Print Network [OSTI]

Dingzeyu Li LE Schapiro (CEPSR), Columbia University West th St New York, NY , USA ( ) - dli@cs.columbia.edu http://www.cs.columbia.edu/~dli/ Education Columbia University, New York, USA Sept. - present - PhD Research, Advisor: Changxi Zheng, Columbia Computer Graphics Group, Columbia University, New York, Aug

Grinspun, Eitan

138

Professor Jay Sethuraman Columbia University  

E-Print Network [OSTI]

Professor Jay Sethuraman Columbia University Monday April 2, 2012, Time: 1:00 pm 1 Washington Park Research at Columbia University. His research interests are in scheduling theory, discrete optimization

Lin, Xiaodong

139

Department of Physics Columbia University  

E-Print Network [OSTI]

Department of Physics Columbia University Copyright A. J. Millis 2010 John Hubbard photo Thanks abcd Uabcdd ad bdcdd (d) ab ab()d a()db() ab Habd adb #12;Department of Physics Columbia University to self energy #12;Department of Physics Columbia University Copyright A. J. Millis 2010 Cant treat all

Millis, Andrew

140

Department of Physics Columbia University  

E-Print Network [OSTI]

Department of Physics Columbia University Copyright A. J. Millis 2012 Dynamical Mean Field Theory: Basic ideas and cluster extensions A. J. Millis Department of Physics Columbia University Support: NSF DMR 10006282, DOE ER-046169 and ARO 056032PH #12;Department of Physics Columbia University Copyright A

Millis, Andrew

Note: This page contains sample records for the topic "light columbia water" 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

Department of Physics Columbia University  

E-Print Network [OSTI]

Department of Physics Columbia University Copyright A. J. Millis 2010 Correlated Electron Compounds: from real materials to model systems and back again A. J. Millis Columbia University Boulder 2010 #12;Department of Physics Columbia University Copyright A. J. Millis 2010 Stereotypical theoretical physicist

Millis, Andrew

142

Columbia University THE ITALIAN ACADEMY  

E-Print Network [OSTI]

Columbia University THE ITALIAN ACADEMY FOR ADVANCED STUDIES IN AMERICA Annual Report 2007­2008 #12 for a variety of conferences, concerts, films, and exhibitions. #12;#12;Columbia University THE ITALIAN ACADEMY of Italy and of Columbia University. The Director is the Head of the Acad- emy. The Chairman of the Board

Qian, Ning

143

Department of Physics Columbia University  

E-Print Network [OSTI]

Department of Physics Columbia University Copyright A. J. Millis 2010 `Botany' of correlated fermion physics #12;Department of Physics Columbia University Copyright A. J. Millis 2010 Example: 3He;Department of Physics Columbia University Copyright A. J. Millis 2010 Normal liquid D. Greywall PRB 27 2747

Millis, Andrew

144

Search for Free Decay of Negative Pions in Water and Light Materials  

E-Print Network [OSTI]

We report on a search for the free decay component of pi- stopped in water and light materials. A non-zero value of this would be an indication of anomalous nu_e contamination to the nu_e and nu_mu_bar production at stopped-pion neutrino facilities. No free decay component of pi- was observed in water, Beryllium, and Aluminum, for which upper limits were established at 8.2E-4, 3.2E-3, and 7.7E-3, respectively.

T. Numao; Yu. I. Davydov; J-M. Poutissou; T. C. Awes; V. Cianciolo; S. Berridge; W. Bugg; Yu. Efremenko; R. Gearhart; S. Ovchinnikov

2006-05-30T23:59:59.000Z

145

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

SciTech Connect (OSTI)

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

Not Listed

2011-11-01T23:59:59.000Z

146

Establishment of a Hub for the Light Water Reactor Sustainability Online Monitoring Community  

SciTech Connect (OSTI)

Implementation of online monitoring and prognostics in existing U.S. nuclear power plants will involve coordinating the efforts of national laboratories, utilities, universities, and private companies. Internet-based collaborative work environments provide necessary communication tools to facilitate interaction between geographically diverse participants. Available technologies were considered, and a collaborative workspace was established at INL as a hub for the light water reactor sustainability online monitoring community.

Nancy J. Lybeck; Magdy S. Tawfik; Binh T. Pham

2011-08-01T23:59:59.000Z

147

Fuel assembly for the production of tritium in light water reactors  

DOE Patents [OSTI]

A nuclear fuel assembly is described for producing tritium in a light water moderated reactor. The assembly consists of two intermeshing arrays of subassemblies. The first subassemblies comprise concentric annular elements of an outer containment tube, an annular target element, an annular fuel element, and an inner neutron spectrums shifting rod. The second subassemblies comprise an outer containment tube and an inner rod of either fuel, target, or neutron spectrum shifting neutral.

Cawley, William E. (Richland, WA); Trapp, Turner J. (Richland, WA)

1985-01-01T23:59:59.000Z

148

Fuel assembly for the production of tritium in light water reactors  

DOE Patents [OSTI]

A nuclear fuel assembly is described for producing tritium in a light water moderated reactor. The assembly consists of two intermeshing arrays of subassemblies. The first subassemblies comprise concentric annular elements of an outer containment tube, an annular target element, an annular fuel element, and an inner neutron spectrums shifting rod. The second subassemblies comprise an outer containment tube and an inner rod of either fuel, target, or neutron spectrum shifting neutral.

Cawley, W.E.; Trapp, T.J.

1983-06-10T23:59:59.000Z

149

Overview of the US Department of Energy Light Water Reactor Sustainability Program  

SciTech Connect (OSTI)

The US Department of Energy Light Water Reactor Sustainability Program is focused on the long-term operation of US commercial power plants. It encompasses two facets of long-term operation: (1) manage the aging of plant systems, structures, and components so that nuclear power plant lifetimes can be extended and the plants can continue to operate safely, efficiently, and economically; and (2) provide science-based solutions to the nuclear industry that support implementation of performance improvement technologies. An important aspect of the Light Water Reactor Sustainability Program is partnering with industry and the Nuclear Regulatory Commission to support and conduct the long-term research needed to inform major component refurbishment and replacement strategies, performance enhancements, plant license extensions, and age-related regulatory oversight decisions. The Department of Energy research, development, and demonstration role focuses on aging phenomena and issues that require long-term research and/or unique Department of Energy laboratory expertise and facilities and are applicable to all operating reactors. This paper gives an overview of the Department of Energy Light Water Reactor Sustainability Program, including vision, goals, and major deliverables.

K. A. McCarthy; D. L. Williams; R. Reister

2012-05-01T23:59:59.000Z

150

End-of-life destructive examination of light water breeder reactor fuel rods (LWBR Development Program)  

SciTech Connect (OSTI)

Destructive examination of 12 representative Light Water Breeder Reactor fuel rods was performed following successful operation in the Shippingport Atomic Power Station for 29,047 effective full power hours, about five years. Light Water Breeder Reactor fuel rods were unique in that the thorium oxide and uranium-233 oxide fuel was contained within Zircaloy-4 cladding. Destructive examinations included analysis of released fission gas; chemical analysis of the fuel to determine depletion, iodine, and cesium levels; chemical analysis of the cladding to determine hydrogen, iodine, and cesium levels; metallographic examination of the cladding, fuel, and other rod components to determine microstructural features and cladding corrosion features; and tensile testing of the irradiated cladding to determine mechanical strength. The examinations confirmed that Light Water Breeder Reactor fuel rod performance was excellent. No evidence of fuel rod failure was observed, and the fuel operating temperature was low (below 2580/sup 0/F at which an increased percentage of fission gas is released). 21 refs., 80 figs., 20 tabs.

Richardson, K.D.

1987-10-01T23:59:59.000Z

151

Gas-liquid-liquid equilibria in mixtures of water, light gases, and hydrocarbons  

SciTech Connect (OSTI)

Phase equilibrium in mixtures of water + light gases and water + heavy hydrocarbons has been investigated with the development of new local composition theory, new equations of state, and new experimental data. The preferential segregation and orientation of molecules due to different energies of molecular interaction has been simulated with square well molecules. Extensive simulation has been made for pure square well fluids and mixtures to find the local composition at wide ranges of states. A theory of local composition has been developed and an equation of state has been obtained for square well fluids. The new local composition theory has been embedded in several equations of state. The pressure of water is decoupled into a polar pressure and non-polar pressure according to the molecular model of water of Jorgensen et al. The polar pressure of water is combined with the BACK equation for the general description of polar fluids and their mixtures. Being derived from the steam table, the Augmented BACK equation is particularly suited for mixtures of water + non-polar substances such as the hydrocarbons. The hydrophobic character of the hydrocarbons had made their mixtures with water a special challenge. A new group contribution equation of state is developed to describe phase equilibrium and volumetric behavior of fluids while requiring only to know the molecular structure of the components. 15 refs., 1 fig.

Chao, K.C.

1990-01-01T23:59:59.000Z

152

Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production  

SciTech Connect (OSTI)

The use of supercritical temperature and pressure light water as the coolant in a direct-cycle nuclear reactor offers potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to 46%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type recirculation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed. If a tight fuel rod lattice is adopted, it is possible to significantly reduce the neutron moderation and attain fast neutron energy spectrum conditions. In this project a supercritical water reactor concept with a simple, blanket-free, pancake-shaped core will be developed. This type of core can make use of either fertile or fertile-free fuel and retain the hard spectrum to effectively burn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity.

Mac Donald, Philip Elsworth; Buongiorno, Jacopo; Davis, Cliff Bybee; Weaver, Kevan Dean

2002-01-01T23:59:59.000Z

153

Core design study of a supercritical light water reactor with double row fuel rods  

SciTech Connect (OSTI)

An equilibrium core for supercritical light water reactor has been designed. A novel type of fuel assembly with dual rows of fuel rods between water rods is chosen and optimized to get more uniform assembly power distributions. Stainless steel is used for fuel rod cladding and structural material. Honeycomb structure filled with thermal isolation is introduced to reduce the usage of stainless steel and to keep moderator temperature below the pseudo critical temperature. Water flow scheme with ascending coolant flow in inner regions is carried out to achieve high outlet temperature. In order to enhance coolant outlet temperature, the radial power distributions needs to be as flat as possible through operation cycle. Fuel loading pattern and control rod pattern are optimized to flatten power distribution at inner regions. Axial fuel enrichment is divided into three parts to control axial power peak, which affects maximum cladding surface temperature. (authors)

Zhao, C.; Wu, H.; Cao, L.; Zheng, Y. [School of Nuclear Science and Technology, Xi'an Jiaotong Univ., No. 28, Xianning West Road, Xi'an, ShannXi, 710049 (China); Yang, J.; Zhang, Y. [China Nuclear Power Technology Research Inst., Yitian Road, ShenZhen, GuangDong, 518026 (China)

2012-07-01T23:59:59.000Z

154

COLLECTIVE AGREEMENT THE UNIVERSITY OF BRITISH COLUMBIA  

E-Print Network [OSTI]

COLLECTIVE AGREEMENT Between THE UNIVERSITY OF BRITISH COLUMBIA and CANADIAN UNION OF PUBLIC OF BRITISH COLUMBIA #12;COLLECTIVE AGREEMENT Between THE UNIVERSITY OF BRITISH COLUMBIA and CANADIAN UNION) THE UNIVERSITY OF BRITISH COLUMBIA #12;COLLECTIVE AGREEMENT Between THE UNIVERSITY OF BRITISH COLUMBIA

Michelson, David G.

155

Materials Science and Technology Division, light-water-reactor safety research program. Quarterly progress report, October-December 1982  

SciTech Connect (OSTI)

The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Shack, W.J.; Rest, J.; Kassner, T.F.; Ayrault, G.; Chopra, O.K.; Chung, H.M.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.

1983-11-01T23:59:59.000Z

156

Conceptual design of a pressure tube light water reactor with variable moderator control  

SciTech Connect (OSTI)

This paper presents the development of innovative pressure tube light water reactor with variable moderator control. The core layout is derived from a CANDU line of reactors in general, and advanced ACR-1000 design in particular. It should be stressed however, that while some of the ACR-1000 mechanical design features are adopted, the core design basics of the reactor proposed here are completely different. First, the inter fuel channels spacing, surrounded by the calandria tank, contains a low pressure gas instead of heavy water moderator. Second, the fuel channel design features an additional/external tube (designated as moderator tube) connected to a separate moderator management system. The moderator management system is design to vary the moderator tube content from 'dry' (gas) to 'flooded' (light water filled). The dynamic variation of the moderator is a unique and very important feature of the proposed design. The moderator variation allows an implementation of the 'breed and burn' mode of operation. The 'breed and burn' mode of operation is implemented by keeping the moderator tube empty ('dry' filled with gas) during the breed part of the fuel depletion and subsequently introducing the moderator by 'flooding' the moderator tube for the 'burn' part. This paper assesses the conceptual feasibility of the proposed concept from a neutronics point of view. (authors)

Rachamin, R.; Fridman, E. [Reactor Safety Div., Inst. of Resource Ecology, Helmholtz-Zentrum Dresden-Rossendorf, POB 51 01 19, 01314 Dresden (Germany); Galperin, A. [Dept. of Nuclear Engineering, Ben-Gurion Univ. of the Negev, POB 653, Beer Sheva 84105 (Israel)

2012-07-01T23:59:59.000Z

157

Light Water Reactor Sustainability Program Status of Silicon Carbide Joining Technology Development  

SciTech Connect (OSTI)

Advanced, accident tolerant nuclear fuel systems are currently being investigated for potential application in currently operating light water reactors (LWR) or in reactors that have attained design certification. Evaluation of potential options for accident tolerant nuclear fuel systems point to the potential benefits of silicon carbide (SiC) relative to Zr-based alloys, including increased corrosion resistance, reduced oxidation and heat of oxidation, and reduced hydrogen generation under steam attack (off-normal conditions). If demonstrated to be applicable in the intended LWR environment, SiC could be used in nuclear fuel cladding or other in-core structural components. Achieving a SiC-SiC joint that resists corrosion with hot, flowing water, is stable under irradiation and retains hermeticity is a significant challenge. This report summarizes the current status of SiC-SiC joint development work supported by the Department of Energy Light Water Reactor Sustainability Program. Significant progress has been made toward SiC-SiC joint development for nuclear service, but additional development and testing work (including irradiation testing) is still required to present a candidate joint for use in nuclear fuel cladding.

Shannon M. Bragg-Sitton

2013-09-01T23:59:59.000Z

158

Environmentally assisted cracking in light water reactors. Semiannual report July 1996--December 1996  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from July 1996 to December 1996. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Type 304 SS, (c) EAC of Alloy 600, and (d) characterization of residual stresses in welds of boiling water reactor (BWR) core shrouds by numerical models. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen to determine whether a slow strain rate applied during various portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated BWR water at 288 C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from a low-carbon content heat of Alloy 600 in high-purity oxygenated water at 289 C. Residual stresses and stress intensity factors were calculated for BWR core shroud welds.

Chopra, O.K.; Chung, H.M.; Gavenda, D.J. [Argonne National Lab., IL (United States)] [and others

1997-10-01T23:59:59.000Z

159

Environmentally assisted cracking in light water reactors. Semiannual report, April 1994--September 1994, Volume 19  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmentally assisted cracking (EAC) in light water reactors from April to September 1994. Topics that have been investigated include (a) fatigue of carbon and low-alloy steel used in piping and reactor pressure vessels, (b) EAC of austenitic stainless steels (SSs) and Alloy 600, and (c) irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS. Fatigue tests have been conducted on A106-Gr B and A533-Gr B steels in oxygenated water to determine whether a slow strain rate applied during different portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Crack growth data were obtained on fracture-mechanics specimens of SSs and Alloy 600 to investigate EAC in simulated boiling water reactor (BWR) and pressurized water reactor environments at 289{degrees}C. The data were compared with predictions from crack growth correlations developed at ANL for SSs in water and from rates in air from Section XI of the ASME Code. Microchemical changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating BWRs were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements may contribute to IASCC of these materials.

Chopra, O.K.; Chung, H.M.; Gavenda, D.J. [and others

1995-09-01T23:59:59.000Z

160

Environmentally assisted cracking in Light Water Reactors: Semiannual report, April 1993--September 1993. Volume 17  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRS) during the six months from April 1993 to September 1993. EAC and fatigue of piping, pressure vessels, and core components in LWRs are important concerns as extended reactor lifetimes are envisaged. Topics that have been investigated include (a) fatigue of low-alloy steel used in piping, steam generators, and reactor pressure vessels; (b) EAC of cast stainless steels (SSs); and (c) radiation-induced segregation and irradiation-assisted stress corrosion cracking of Type 304 SS after accumulation of relatively high fluence. Fatigue tests were conducted on medium-sulfur-content A106-Gr B piping and A533-Gr B pressure vessel steels in simulated PWR water and in air. Additional crack growth data were obtained on fracture-mechanics specimens of cast austenitic SSs in the as-received and thermally aged conditions in simulated boiling-water reactor (BWR) water at 289{degree}C. The data were compared with predictions based on crack growth correlations for wrought austenitic SS in oxygenated water developed at ANL and rates in air from Section 11 of the ASME Code. Microchemical and microstructural changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating BWRs were studied by Auger electron spectroscopy and scanning electron microscopy.

Chopra, O.K.; Chung, H.M.; Karlsen, T.; Kassner, T.F.; Michaud, W.F.; Ruther, W.E.; Sanecki, J.E.; Shack, W.J.; Soppet, W.K. [Argonne National Lab., IL (United States)

1994-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Environmentally assisted cracking in light water reactors. Semiannual progress report, January 1996--June 1996  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from January 1996 to June 1996. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Type 304 SS, and (c) EAC of Alloys 600 and 690. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during various portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated boiling water reactor (BWR) water at 288{degrees}C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from several heats of Alloys 600 and 690 in air and high-purity, low-DO water. 83 refs., 60 figs., 14 tabs.

Chopra, O.K.; Chung, H.M.; Gruber, E.E. [and others

1997-05-01T23:59:59.000Z

162

Microencapsulated Fuel Technology for Commercial Light Water and Advanced Reactor Application  

SciTech Connect (OSTI)

The potential application of microencapsulated fuels to light water reactors (LWRs) has been explored. The specific fuel manifestation being put forward is for coated fuel particles embedded in silicon carbide or zirconium metal matrices. Detailed descriptions of these concepts are presented, along with a review of attributes, potential benefits, and issues with respect to their application in LWR environments, specifically from the standpoints of materials, neutronics, operations, and economics. Preliminary experiment and modeling results imply that with marginal redesign, significant gains in operational reliability and accident response margins could be potentially achieved by replacing conventional oxide-type LWR fuel with microencapsulated fuel forms.

Terrani, Kurt A [ORNL; Snead, Lance Lewis [ORNL; Gehin, Jess C [ORNL

2012-01-01T23:59:59.000Z

163

General features of direct-cycle, supercritical-pressure, light-water-cooled reactors  

SciTech Connect (OSTI)

The concept of direct-cycle, supercritical-pressure, light-water-cooled reactors is developed. Breeding is possible in the tight lattice core. The power output can be maximized in the fast converter reactor. The gross thermal efficiency of the high temperature reactor adopting Inconel as fuel cladding is expected to be 44.8%. The plant system is similar to the supercritical-fossil-fired power plant which adopts once-through type coolant circulation system. The volume and height of the containment are approximately half of the BWR. The basic safety principles follows those of LWRs. The reactor will solve the economic problems of LWR and LMFBR.

Oka, Y.; Koshizuka, S. [Univ. of Tokyo (Japan). Nuclear Engineering Research Lab.

1996-07-01T23:59:59.000Z

164

Light Water Reactor Safety Research Program. Semiannual report, October 1983-March 1984  

SciTech Connect (OSTI)

This report describes the investigations and analyses conducted at Sandia National Laboratories, Albuquerque, in support of the Light Water Reactor Safety Research Program from October 1983 through March 1984. The Fuel-Coolant Interactions Study investigates the mechanism of concrete erosion by molten core materials, the nature and rate of generation of evolved gases, and the effects of fission-product release. The Hydrogen Behavior and Mitigative and Preventive Schemes Programs investigate the HECTR code for modeling hydrogen deflagration, and the Grand Gulf Igniter System II is being reviewed. All activities are continuing. 53 figs., 11 tabs.

Berman, M.

1986-02-01T23:59:59.000Z

165

Columbia University Office of Global Programs  

E-Print Network [OSTI]

Columbia University Office of Global Programs General Resources for Going Abroad For undergraduate.............................................................................................................................. 3 COLUMBIA CONTACTS Congratulations on your decision to undertake an international experience as part of your Columbia education

Hone, James

166

Columbia University Department of Public Safety  

E-Print Network [OSTI]

Columbia University Department of Public Safety SECURITY ALERT BURGLARY On August 24, 2012 a tenant crime prevention tips and programs offered by Columbia University Public Safety on our website at www.columbia

Lazar, Aurel A.

167

COLLECTIVE AGREEMENT THE UNIVERSITY OF BRITISH COLUMBIA  

E-Print Network [OSTI]

Between THE UNIVERSITY OF BRITISH COLUMBIA and CANADIAN UNION OF PUBLIC EMPLOYEES Local 2278 September 1 __________________________________________________________________ THE UNIVERSITY OF BRITISH COLUMBIA #12;COLLECTIVE AGREEMENT Between THE UNIVERSITY OF BRITISH COLUMBIA

Michelson, David G.

168

Shippingport operations with the Light Water Breeder Reactor core. (LWBR Development Program)  

SciTech Connect (OSTI)

This report describes the operation of the Shippingport Atomic Power Station during the LWBR (Light Water Breeder Reactor) Core lifetime. It also summarizes the plant-oriented operations during the period preceding LWBR startup, which include the defueling of The Pressurized Water Reactor Core 2 (PWR-2) and the installation of the LWBR Core, and the operations associated with the defueling of LWBR. The intent of this report is to examine LWBR experience in retrospect and present pertinent and significant aspects of LWBR operations that relate primarily to the nuclear portion of the Station. The nonnuclear portion of the Station is discussed only as it relates to overall plant operation or to unusual problems which result from the use of conventional equipment in radioactive environments. 30 refs., 69 figs., 27 tabs.

Budd, W.A. (ed.)

1986-03-01T23:59:59.000Z

169

Materials Science and Technology Division light-water-reactor safety research program: quarterly progress report, January-March 1983  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during January, February and March 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Not Available

1984-04-01T23:59:59.000Z

170

Materials Science Division light-water-reactor safety-research program. Quarterly progress report, April-June 1982. Volume 2  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1982 on water-reactor-safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, and Clad Properties for Code Verification.

Shack, W.J.; Rest, J.; Kassner, T.F.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.; Ruther, W.E.; Yaggee, F.L.

1983-05-01T23:59:59.000Z

171

Materials Science Division light-water-reactor safety research program. Quarterly progress report, July-September 1982  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1982 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, Posttest Fuel Examination of the ORNL Fission Product Release Tests, and Examination of TMI-2 Fuel Specimens.

Shack, W.J.; Rest, J.; Kassner, T.F.; Neimark, L.A.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.

1983-08-01T23:59:59.000Z

172

Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) during the six months from October 1993 to March 1994. EAC and fatigue of piping, pressure vessels, and core components in LWRs are important concerns in operating plants and as extended reactor lifetimes are envisaged. Topics that have been investigated include (a) fatigue of low-alloy steel used in piping, steam generators, and reactor pressure vessels, (b) EAC of wrought and cast austenitic stainless steels (SSs), and (c) radiation-induced segregation and irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS after accumulation of relatively high fluence. Fatigue tests have been conducted on A302-Gr B low-alloy steel to verify whether the current predictions of modest decreases of fatigue life in simulated pressurized water reactor water are valid for high-sulfur heats that show environmentally enhanced fatigue crack growth rates. Additional crack growth data were obtained on fracture-mechanics specimens of austenitic SSs to investigate threshold stress intensity factors for EAC in high-purity oxygenated water at 289{degrees}C. The data were compared with predictions based on crack growth correlations for wrought austenitic SS in oxygenated water developed at ANL and rates in air from Section XI of the ASME Code. Microchemical and microstructural changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating boiling water reactors were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements, which are not specified in the ASTM specifications, may contribute to IASCC of solution-annealed materials.

Chung, H.M.; Chopra, O.K.; Erck, R.A.; Kassner, T.F.; Michaud, W.F.; Ruther, W.E.; Sanecki, J.E.; Shack, W.J.; Soppet, W.K. [Argonne National Lab., IL (United States)

1995-03-01T23:59:59.000Z

173

Depolarized light scattering and dielectric response of a peptide dissolved in water  

SciTech Connect (OSTI)

The density and orientational relaxation of bulk water can be separately studied by depolarized light scattering (DLS) and dielectric spectroscopy (DS), respectively. Here, we ask the question of what are the leading collective modes responsible for polarization anisotropy relaxation (DLS) and dipole moment relaxation (DS) of solutions involving mostly hydrophobic solute-water interfaces. We study, by atomistic molecular dynamics simulations, the dynamics and structure of hydration water interfacing N-Acetyl-leucine-methylamide dipeptide. The DLS response of the solution is consistent with three relaxation processes: bulk water, rotations of single solutes, and collective dipole-induced-dipole polarizability of the solutes, with the time-scale of 130200 ps. No separate DLS response of the hydration shell has been identified by our simulations. Density fluctuations of the hydration layer, which largely contribute to the response, do not produce a dynamical process distinct from bulk water. We find that the structural perturbation of the orientational distribution of hydration waters by the dipeptide solute is quite significant and propagates ?3?5 hydration layers into the bulk. This perturbation is still below that produced by hydrated globular proteins. Despite this structural perturbation, there is little change in the orientational dynamics of the hydration layers, compared to the bulk, as probed by both single-particle orientational dynamics and collective dynamics of the dipole moment of the shells. There is a clear distinction between the perturbation of the interfacial structure by the solute-solvent interaction potential and the perturbation of the interfacial dynamics by the corresponding forces.

Martin, Daniel R. [Department of Physics, Arizona State University, PO Box 871604, Tempe, Arizona 85287-1604 (United States)] [Department of Physics, Arizona State University, PO Box 871604, Tempe, Arizona 85287-1604 (United States); Fioretto, Daniele [Dipartimento di Fisica, Universita di Perugia, via Pascoli, 06123 Perugia (Italy)] [Dipartimento di Fisica, Universita di Perugia, via Pascoli, 06123 Perugia (Italy); Matyushov, Dmitry V., E-mail: dmitrym@asu.edu [Department of Physics and Department of Chemistry and Biochemistry, Arizona State University, PO Box 871604, Tempe, Arizona 85287-1604 (United States)

2014-01-21T23:59:59.000Z

174

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels  

E-Print Network [OSTI]

1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials. 1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) at the end of license (EOL) exceeds 1 1021 neutrons/m2 (1 1017 n/cm2) at the inside surface of the reactor vessel. 1.3 This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. 1.4 This practice does not provide specific procedures for monitoring the radiation induced cha...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

175

Nondestructive examination (NDE) reliability for inservice inspection of light waters reactors  

SciTech Connect (OSTI)

Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other inspected components. This is a progress report covering the programmatic work from April 1988 through September 1988. 33 refs., 70 figs., 12 tabs.

Doctor, S.R.; Deffenbaugh, J.D.; Good, M.S.; Green, E.R.; Heasler, P.G.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T. (Pacific Northwest Lab., Richland, WA (USA))

1989-11-01T23:59:59.000Z

176

ECOLOGICAL TAX REFORM: Estimated Environmental and Employment Effects in British Columbia  

E-Print Network [OSTI]

of the Requirements for the Degree of Master of Resource Management in the School of Resource Environmental Managementi ECOLOGICAL TAX REFORM: Estimated Environmental and Employment Effects in British Columbia by Amy in British Columbia. To do this, I simulated ecological taxes on water consumption, solid waste and carbon

177

Prof. Michael Mauel Columbia University  

E-Print Network [OSTI]

Prof. Michael Mauel Columbia University Exploring Plasma Dynamics with Laboratory Magnetospheres, and control the high-temperature plasma trapped in three large laboratory magneto- spheres, at Columbia University, MIT, and the Uni- versity of Tokyo. With its high-field superconduct- ing magnets, the Levitated

Mauel, Michael E.

178

Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels  

SciTech Connect (OSTI)

To establish a nuclide composition benchmark data set for the verification of burnup codes, destructive analyses of light water reactor spent-fuel samples, which were cut out from several heights of spent-fuel rods, were carried out at the analytical laboratory at the Japan Atomic Energy Research Institute. The 16 samples from three kinds of pressurized water reactor (PWR) fuel rods and the 18 samples from two boiling water reactor (BWR) fuel rods were examined. Their initial {sup 235}U enrichments and burnups were from 2.6 to 4.1% and from 4 to 50 GWd/t, respectively. One PWR fuel rod and one BWR fuel rod contained gadolinia as a burnable poison. The measurements for more than 40 nuclides of uranium, transuranium, and fission product elements were performed by destructive analysis using mass spectrometry, and alpha-ray and gamma-ray spectrometry. Burnup for each sample was determined by the {sup 148}Nd method. The analytical methods and the results as well as the related irradiation condition data are compiled as a complete benchmark data set.

Nakahara, Yoshinori; Suyama, Kenya; Inagawa, Jun; Nagaishi, Ryuji; Kurosawa, Setsumi; Kohno, Nobuaki; Onuki, Mamoru; Mochizuki, Hiroki [Japan Atomic Energy Research Institute (Japan)

2002-02-15T23:59:59.000Z

179

Environmentally assisted cracking in light water reactors annual report January - December 2005.  

SciTech Connect (OSTI)

This report summarizes work performed from January to December 2005 by Argonne National Laboratory on fatigue and environmentally assisted cracking in light water reactors (LWRs). Existing statistical models for estimating the fatigue life of carbon and low-alloy steels and austenitic stainless steels (SSs) as a function of material, loading, and environmental conditions were updated. Also, the ASME Code fatigue adjustment factors of 2 on stress and 20 on life were critically reviewed to assess the possible conservatism in the current choice of the margins. An approach, based on an environmental fatigue correction factor, for incorporating the effects of LWR environments into ASME Section III fatigue evaluations is discussed. The susceptibility of austenitic stainless steels and their welds to irradiation-assisted stress corrosion cracking (IASCC) is being evaluated as a function of the fluence level, water chemistry, material chemistry, and fabrication history. For this task, crack growth rate (CGR) tests and slow strain rate tensile (SSRT) tests are being conducted on various austenitic SSs irradiated in the Halden boiling water reactor. The SSRT tests are currently focused on investigating the effects of the grain boundary engineering process on the IASCC of the austenitic SSs. The CGR tests were conducted on Type 316 SSs irradiated to 0.45-3.0 dpa, and on sensitized Type 304 SS and SS weld heat-affected-zone material irradiated to 2.16 dpa. The CGR tests on materials irradiated to 2.16 dpa were followed by a fracture toughness test in a water environment. The effects of material composition, irradiation, and water chemistry on growth rates are discussed. The susceptibility of austenitic SS core internals to IASCC and void swelling is also being evaluated for pressurized water reactors. Both SSRT tests and microstructural examinations are being conducted on specimens irradiated in the BOR-60 reactor in Russia to doses up to 20 dpa. Crack growth rate data, obtained in the pressurized water reactor environment, are presented on Ni-alloy welds prepared in the laboratory or obtained from the nozzle-to-pipe weld of the V. C. Summer reactor. The experimental CGRs under cyclic and constant load are compared with the existing CGR data for Ni-alloy welds to determine the relative susceptibility of these materials to environmentally enhanced cracking under a variety of loading conditions.

Alexandreanu, B.; Chen, Y.; Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Shack, W. J.; Soppet, W. K.

2007-08-31T23:59:59.000Z

180

Direct Water Splitting under Visible Light with a Nanostructured Photoanode and GaInP2 Photocathode  

SciTech Connect (OSTI)

Thin films of hematite nanorod and GaInP2 were used for direct water splitting under visible light. In open circuit conditions, the potential of hematite shifted cathodically and that of GaInP2 anodically, which generated an open circuit voltage between the two electrodes. In short circuit condition, the combination of the two photoelectrodes can split water under visible light illumination, though with a very low current of {micro}A/cm2 level even at 1 W/cm2 light. By means of chopped light, we found that hematite nanorod has a low photocurrent, which is responsible for the low short circuit current of the 2-electrode combination. The low photoresponse of hematite nanorods is due to the recombination of photo- generated charges, low holes mobility, and short diffusion length.

Wang, H.; Deutsch, T.; Turner, J.

2008-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Light Water Breeder Reactor fuel rod design and performance characteristics (LWBR Development Program)  

SciTech Connect (OSTI)

Light Water Breeder Reactor (LWBR) fuel rods were designed to provide a reliable fuel system utilizing thorium/uranium-233 mixed-oxide fuel while simultaneously minimizing structural material to enhance fuel breeding. The fuel system was designed to be capable of operating successfully under both load follow and base load conditions. The breeding objective required thin-walled, low hafnium content Zircaloy cladding, tightly spaced fuel rods with a minimum number of support grid levels, and movable fuel rod bundles to supplant control rods. Specific fuel rod design considerations and their effects on performance capability are described. Successful completion of power operations to over 160 percent of design lifetime including over 200 daily load follow cycles has proven the performance capability of the fuel system. 68 refs., 19 figs., 44 tabs.

Campbell, W.R.; Giovengo, J.F.

1987-10-01T23:59:59.000Z

182

Chemical aspects of pellet-cladding interaction in light water reactor fuel elements  

SciTech Connect (OSTI)

In contrast to the extensive literature on the mechanical aspects of pellet-cladding interaction (PCI) in light water reactor fuel elements, the chemical features of this phenomenon are so poorly understood that there is still disagreement concerning the chemical agent responsible. Since the earliest work by Rosenbaum, Davies and Pon, laboratory and in-reactor experiments designed to elucidate the mechanism of PCI fuel rod failures have concentrated almost exclusively on iodine. The assumption that this is the reponsible chemical agent is contained in models of PCI which have been constructed for incorporation into fuel performance codes. The evidence implicating iodine is circumstantial, being based primarily upon the volatility and significant fission yield of this element and on the microstructural similarity of the failed Zircaloy specimens exposed to iodine in laboratory stress corrosion cracking (SCC) tests to cladding failures by PCI.

Olander, D.R.

1982-01-01T23:59:59.000Z

183

Categorization of failed and damaged spent LWR (light-water reactor) fuel currently in storage  

SciTech Connect (OSTI)

The results of a study that was jointly sponsored by the US Department of Energy and the Electric Power Research Institute are described in this report. The purpose of the study was to (1) estimate the number of failed fuel assemblies and damaged fuel assemblies (i.e., ones that have sustained mechanical or chemical damage but with fuel rod cladding that is not breached) in storage, (2) categorize those fuel assemblies, and (3) prepare this report as an authoritative, illustrated source of information on such fuel. Among the more than 45,975 spent light-water reactor fuel assemblies currently in storage in the United States, it appears that there are nearly 5000 failed or damaged fuel assemblies. 78 refs., 23 figs., 19 tabs.

Bailey, W.J.

1987-11-01T23:59:59.000Z

184

REACTOR PRESSURE VESSEL ISSUES FOR THE LIGHT-WATER REACTOR SUSTAINABILITY PROGRAM  

SciTech Connect (OSTI)

The Light Water Reactor Sustainability Program Plan is a collaborative program between the U.S. Department of Energy and the private sector directed at extending the life of the present generation of nuclear power plants to enable operation to at least 80 years. The reactor pressure vessel (RPV) is one of the primary components requiring significant research to enable such long-term operation. There are significant issues that need to be addressed to reduce the uncertainties in regulatory application, such as, 1) high neutron fluence/long irradiation times, and flux effects, 2) material variability, 3) high-nickel materials, 4)specimen size effects and the fracture toughness master curve, etc. The first issue is the highest priority to obtain the data and mechanistic understanding to enable accurate, reliable embrittlement predictions at high fluences. This paper discusses the major issues associated with long-time operation of existing RPVs and the LWRSP plans to address those issues.

Nanstad, Randy K [ORNL; Odette, George Robert [UCSB

2010-01-01T23:59:59.000Z

185

Advanced dry head-end reprocessing of light water reactor spent nuclear fuel  

SciTech Connect (OSTI)

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

Collins, Emory D.; Delcul, Guillermo D.; Hunt, Rodney D.; Johnson, Jared A.; Spencer, Barry B.

2014-06-10T23:59:59.000Z

186

Advanced dry head-end reprocessing of light water reactor spent nuclear fuel  

DOE Patents [OSTI]

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

Collins, Emory D; Delcul, Guillermo D; Hunt, Rodney D; Johnson, Jared A; Spencer, Barry B

2013-11-05T23:59:59.000Z

187

Light water reactor safety research program, quarterly report, July-September 1980. Volume 3  

SciTech Connect (OSTI)

The report covers research performed during July-September 1980 for the NRC Light Water Reactor Safety Research Program comprised of: (1) The Molten Fuel Concrete Interactions (MFCI) study of experimental and analytical investigations of the chemical and physical phenomena associated with interactions between molten core materials and concrete; (2) Steam Explosion Phenomena program to assess the probability and consequences of steam explosions during postulated meltdown accidents in LWRs; (3) Separate Effects Tests for TRAP Code Development investigating vapor pressures of fission-product species at elevated temperatures, chemical compound formation and reaction rates; (4) Containment Emergency Sump Performance (CESP) program to investigate the reliability of ECCS sumps; (5) Hydrogen Program designed to quantify the threat posed by hydrogen released during LWR accidents; and (6) Combustible Gas in Containment Program to study the generation of H2 from the corrosion of zinc and other materials located within LWR containment buildings.

Berman, M.

1981-04-01T23:59:59.000Z

188

Light water reactor safety research program. Quarterly report Jan-Mar 80  

SciTech Connect (OSTI)

The Molten Fuel Concrete Interactions (MFCI) study is comprised of experimental and analytical investigations of the chemical and physical phenomena associated with interactions between molten core materials and concrete. Such interactions are possible during hypothetical fuel-melt accidents in light water reactors (LWRs) when molten fuel and steel from the reactor core penetrate the pressure vessel and cascade onto the concrete substructure. The purpose of the MFCI study is to develop an understanding of these interactions suitable for risk assessment. Emphasis is placed on identifying and investigating the dominant interaction phenomena occurring between prototypic materials. The table of contents is the following: Molten fuel concrete interactions study; Steam explosion phenomena; Separate effects tests for TRAP code development; and Containment emergency sump performance.

Berman, M.

1980-09-01T23:59:59.000Z

189

Light-water-reactor safety research program. Quarterly progress report, July-September 1980  

SciTech Connect (OSTI)

A physically realistic description of fuel swelling and fission-gas release is needed to aid in predicting the behavior of fuel rods and fission gases under certain hypothetical light-water-reactor (LWR) accident conditions. To satisfy this need, a comprehensive computer-base model, the Steady-State and Transient Gas-Release and Swelling Subroutine (GRASS-SST), its faster-running version, FASTGRASS, and correlations based on analyses performed with GRASS-SST, PARAGRASS, are being developed at Argonne National Laboratory (ANL). This model is being incorporated into the Fuel-Rod Analysis Program (FRAP) code being developed by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL). The analytical effort is supported by a data base and correlations developed from characterization of irradiated LWR fuel and from out-of-reactor transient heating tests of irradiated commercial and experimental LWR fuel under a range of thermal conditions. 7 refs., 2 figs.

Massey, W.E.; Till, C.E.

1981-02-01T23:59:59.000Z

190

Sensitivity Analysis of Reprocessing Cooling Times on Light Water Reactor and Sodium Fast Reactor Fuel Cycles  

SciTech Connect (OSTI)

The purpose of this study is to quantify the effects of variations of the Light Water Reactor (LWR) Spent Nuclear Fuel (SNF) and fast reactor reprocessing cooling time on a Sodium Fast Reactor (SFR) assuming a single-tier fuel cycle scenario. The results from this study show the effects of different cooling times on the SFRs transuranic (TRU) conversion ratio (CR) and transuranic fuel enrichment. Also, the decay heat, gamma heat and neutron emission of the SFRs fresh fuel charge were evaluated. A 1000 MWth commercial-scale SFR design was selected as the baseline in this study. Both metal and oxide CR=0.50 SFR designs are investigated.

R. M. Ferrer; S. Bays; M. Pope

2008-04-01T23:59:59.000Z

191

Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels  

E-Print Network [OSTI]

1.1 This guide covers the general procedures to be considered for conducting an in-service thermal anneal of a light-water moderated nuclear reactor vessel and demonstrating the effectiveness of the procedure. The purpose of this in-service annealing (heat treatment) is to improve the mechanical properties, especially fracture toughness, of the reactor vessel materials previously degraded by neutron embrittlement. The improvement in mechanical properties generally is assessed using Charpy V-notch impact test results, or alternatively, fracture toughness test results or inferred toughness property changes from tensile, hardness, indentation, or other miniature specimen testing (1). 1.2 This guide is designed to accommodate the variable response of reactor-vessel materials in post-irradiation annealing at various temperatures and different time periods. Certain inherent limiting factors must be considered in developing an annealing procedure. These factors include system-design limitations; physical constrain...

American Society for Testing and Materials. Philadelphia

2003-01-01T23:59:59.000Z

192

Vibrational spectra of light and heavy water with application to neutron cross section calculations  

SciTech Connect (OSTI)

The design of nuclear reactors and neutron moderators require a good representation of the interaction of low energy (E < 1 eV) neutrons with hydrogen and deuterium containing materials. These models are based on the dynamics of the material, represented by its vibrational spectrum. In this paper, we show calculations of the frequency spectrum for light and heavy water at room temperature using two flexible point charge potentials: SPC-MPG and TIP4P/2005f. The results are compared with experimental measurements, with emphasis on inelastic neutron scattering data. Finally, the resulting spectra are applied to calculation of neutron scattering cross sections for these materials, which were found to be a significant improvement over library data.

Damian, J. I. Marquez; Granada, J. R. [Neutron Physics Department and Instituto Balseiro, Centro Atomico Bariloche, CNEA (Argentina); Malaspina, D. C. [Department of Biomedical Engineering and Chemistry of Life Processes Institute, Northwestern University, 2145 Sheridan Road, Evanston, Illinois 60208 (United States)

2013-07-14T23:59:59.000Z

193

Accuracy Based Generation of Thermodynamic Properties for Light Water in RELAP5-3D  

SciTech Connect (OSTI)

RELAP5-3D interpolates to obtain thermodynamic properties for use in its internal calculations. The accuracy of the interpolation was determined for the original steam tables currently used by the code. This accuracy evaluation showed that the original steam tables are generally detailed enough to allow reasonably accurate interpolations in most areas needed for typical analyses of nuclear reactors cooled by light water. However, there were some regions in which the original steam tables were judged to not provide acceptable accurate results. Revised steam tables were created that used a finer thermodynamic mesh between 4 and 21 MPa and 530 and 640 K. The revised steam tables solved most of the problems observed with the original steam tables. The accuracies of the original and revised steam tables were compared throughout the thermodynamic grid.

Cliff B. Davis

2010-09-01T23:59:59.000Z

194

Columbia University Panhellenic www.columbiagreeks.info  

E-Print Network [OSTI]

Columbia University Panhellenic www.columbiagreeks.info Contact: Samantha Goldfarb President Columbia Panhellenic Council Slgoldfarb2010@gmail.com Elizabeth Carrolo Vice President of Marketing and Public Relations Columbia Panhellenic Council esc2156@columbia.edu January 24, 2013 PANHELLENIC FORMAL

Hone, James

195

Columbia University Network Integration Task Force  

E-Print Network [OSTI]

Columbia University Network Integration Task Force Final Report II 30 January 1992 #12;1 TOWARDS A COMMON ADMINISTRATIVE AND ACADEMIC NETWORK AT COLUMBIA UNIVERSITY Columbia University's Administrative or terminal. 1.2. Executive Summary This report examines Columbia University's current academic

Yang, Junfeng

196

University Archives University of Missouri at Columbia  

E-Print Network [OSTI]

University Archives University of Missouri at Columbia 703 Lewis Hall University of Missouri-Columbia Archives of the University of Missouri at Columbia reserves the right to refuse permission to individuals agree to credit the University Archives of the University of Missouri at Columbia in accordance

Taylor, Jerry

197

Professor Garret van Ryzin1 Columbia University  

E-Print Network [OSTI]

Professor Garret van Ryzin1 Columbia University Columbia Business School Wednesday April 27, Time Garrett is the Paul M. Montrone Professor of Decision, Risk and Operations at the Columbia University Columbia University, and the degrees of S.M. in Electrical Engineering and Computer Science and Ph

Lin, Xiaodong

198

University Archives University of Missouri at Columbia  

E-Print Network [OSTI]

University Archives University of Missouri at Columbia 703 Lewis Hall Columbia, Missouri 65211 of Missouri at Columbia, may be loaned out to University personnel. All items on loan will be listed below on loan from the University Archives, University of Missouri at Columbia. He/She further acknowledges full

Taylor, Jerry

199

Final report for the Light Water Breeder Reactor proof-of-breeding analytical support project  

SciTech Connect (OSTI)

The technology of breeding /sup 233/U from /sup 232/Th in a light water reactor is being developed and evaluated by the Westinghouse Bettis Atomic Power Laboratory (BAPL) through operation and examination of the Shippingport Light Water Breeder Reactor (LWBR). Bettis is determining the end-of-life (EOL) inventory of fissile uranium in the LWBR core by nondestructive assay of a statistical sample comprising approximately 500 EOL fuel rods. This determination is being made with an irradiated-fuel assay gauge based on neutron interrogation and detection of delayed neutrons from each rod. The EOL fissile inventory will be compared with the beginning-of-life fissile loading of the LWBR to determine the extent of breeding. In support of the BAPL proof-of-breeding (POB) effort, Argonne National Laboratory (ANL) carried out destructive physical, chemical, and radiometric analyses on 17 EOL LWBR fuel rods that were previously assayed with the nondestructive gauge. The ANL work included measurements on the intact rods; shearing of the rods into pre-designated contiguous segments; separate dissolution of each of the more than 150 segments; and analysis of the dissolver solutions to determine each segment's uranium content, uranium isotopic composition, and loading of selected fission products. This report describes the facilities in which this work was carried out, details operations involved in processing each rod, and presents a comprehensive discussion of uncertainties associated with each result of the ANL measurements. Most operations were carried out remotely in shielded cells. Automated equipment and procedures, controlled by a computer system, provided error-free data acquisition and processing, as well as full replication of operations with each rod. Despite difficulties that arose during processing of a few rod segments, the ANL destructive-assay results satisfied the demanding needs of the parent LWBR-POB program.

Graczyk, D.G.; Hoh, J.C.; Martino, F.J.; Nelson, R.E.; Osudar, J.; Levitz, N.M.

1987-05-01T23:59:59.000Z

200

Environmentally assisted cracking in light water reactors - annual report, January-December 2001.  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from January to December 2001. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of austenitic stainless steels (SSs), (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic SSs, and (c) EAC of Alloy 600. The effects of key material and loading variables, such as strain amplitude, strain rate, temperature, dissolved oxygen (DO) level in water, and material heat treatment, on the fatigue lives of wrought and cast austenitic SSs in air and LWR environments have been evaluated. The mechanism of fatigue crack initiation in austenitic SSs in LWR environments has also been examined. The results indicate that the presence of a surface oxide film or difference in the characteristics of the oxide film has no effect on fatigue crack initiation in austenitic SSs in LWR environments. Slow-strain-rate tensile tests and post-test fractographic analyses were conducted on several model SS alloys irradiated to {approx}2 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) ({approx}3 dpa) in He at 289 C in the Halden reactor. The results were used to determine the influence of alloying and impurity elements on the susceptibility of these steels to IASCC. Corrosion fatigue tests were conducted on nonirradiated austenitic SSs in high-purity water at 289 C to establish the test procedure and conditions that will be used for the tests on irradiated materials. A comprehensive irradiation experiment was initiated to obtain many tensile and disk specimens irradiated under simulated pressurized water reactor conditions at {approx}325 C to 5, 10, 20, and 40 dpa. Crack growth tests were completed on 30% cold-worked Alloy 600 in high-purity water under various environmental and loading conditions. The results are compared with data obtained earlier on several heats of Alloy 600 tested in high-DO water under several heat treatment conditions.

Chopra, O. K.; Chung, H. M.; Clark, R. W.; Gruber, E. E; Hiller, R. W.; Shack, W. J.; Soppet, W. K.; Strain, R. V.; Energy Technology

2003-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Email Archive Analysis Through Graphical Visualization Columbia University  

E-Print Network [OSTI]

Email Archive Analysis Through Graphical Visualization Wei-Jen Li Columbia University weijen@cs.columbia.edu Shlomo Hershkop Columbia University shlomo@cs.columbia.edu Salvatore J. Stolfo Columbia University sal@cs.columbia (EMT) developed at Columbia University [3] is a data mining system that computes behavior profiles

Yang, Junfeng

202

The Columbia River Estuary the Columbia River Basin  

E-Print Network [OSTI]

" fish and wildlife in the Columbia River as affected by development and operation of the hydroelectric modified in terms of physical and biological processes. The development and operation of the hydroelectric

203

Columbia University http://www.columbia.edu/~mem4/  

E-Print Network [OSTI]

Mike Mauel Columbia University http://www.columbia.edu/~mem4/ and Jefferson Science Fellow EEB slow! #12;100-300 s after the "Big-Bang": The Age of Fusion · At 100 sec, the universe cools to 1,000,000,000° · Protons and neutrons fuse to Deuterium (heavy hydrogen).The whole universe is a "burning plasma"! · D + D

Mauel, Michael E.

204

Removal of pollutant compounds from water supplies using ozone, ultraviolet light, and a counter, current packed column. Master's thesis  

SciTech Connect (OSTI)

Many water pollutants are determined to be carcinogenic and often appear in very low concentrations and still pose a health risk. Conventional water treatment processes cannot remove these contaminants and there is a great demand for the development of alternative removal technologies. The use of ozone and ultraviolet light in a counter current packed column could prove to be an effective treatment process to remove these contaminants.

Kelly, E.L.

1991-01-01T23:59:59.000Z

205

Snake and Columbia Rivers Sediment Sampling Project  

SciTech Connect (OSTI)

The disposal of dredged material in water is defined as a discharge under Section 404 of the Clean Water Act and must be evaluated in accordance with US Environmental Protection Agency regulation 40 CFR 230. Because contaminant loads in the dredged sediment or resuspended sediment may affect water quality or contaminant loading, the US Army Corps of Engineers (USACE), Walla Walla District, has requested Battelle/Marine Sciences Laboratory to collect and chemically analyze sediment samples from areas that may be dredged near the Port Authority piers on the Snake and Columbia rivers. Sediment samples were also collected at River Mile (RM) stations along the Snake River that may undergo resuspension of sediment as a result of the drawdown. Chemical analysis included grain size, total organic carbon, total volatile solids, ammonia, phosphorus, sulfides, oil and grease, total petroleum hydrocarbons, metals, polynuclear aromatic hydrocarbons, pesticides, polychlorinated biphenyls, and 21 congeners of polychlorinated dibenzodioxins and dibenzofurans.

Pinza, M.R.; Word, J.Q; Barrows, E.S.; Mayhew, H.L.; Clark, D.R. (Battelle/Marine Sciences Lab., Sequim, WA (United States))

1992-12-01T23:59:59.000Z

206

Stress corrosion cracking and crack tip characterization of Alloy X-750 in light water reactor environments  

E-Print Network [OSTI]

Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water ...

Gibbs, Jonathan Paul

2011-01-01T23:59:59.000Z

207

Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Light Water Reactor Environments  

E-Print Network [OSTI]

Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water ...

Gibbs, Jonathan Paul

208

309NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 A NEW BOOK: "LIGHT-WATER REACTOR MATERIALS"  

E-Print Network [OSTI]

309NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 A NEW BOOK: "LIGHT-WATER REACTOR review; it is a book preview. Thirty years ago, "Fundamental Aspects of Nuclear Reactor Fuel Elements of nuclear fuels among other topics pertinent to the materials in the ensemble of the nuclear reactor

Motta, Arthur T.

209

EIS-0071: Memphis Light, Gas and Water Division Industrial Fuels Gas Demonstration Plant, Memphis, Shelby County, Tennessee  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this EIS to assesses the potential environmental impacts associated with the construction and operation of a 3,155-ton-per-day capacity facility, which will demonstrate the technical operability, economic viability, and environmental acceptability of the Memphis Division of Light, Gas and Water coal gasification plant at Memphis, Tennessee.

210

EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement  

Broader source: Energy.gov [DOE]

This Supplemental EIS updates the environmental analyses in DOEs 1999 EIS for the Production of Tritium in a Commercial Light Water Reactor (CLWR EIS). The CLWR EIS addressed the production of tritium in Tennessee Valley Authority reactors in Tennessee using tritium-producing burnable absorber rods.

211

Ferritic Alloys as Accident Tolerant Fuel Cladding Material for Light Water Reactors  

SciTech Connect (OSTI)

The objective of the GE project is to demonstrate that advanced steels such as iron-chromium-aluminum (FeCrAl) alloys could be used as accident tolerant fuel cladding material in commercial light water reactors. The GE project does not include fuel development. Current findings support the concept that a FeCrAl alloy could be used for the cladding of commercial nuclear fuel. The use of this alloy will benefit the public since it is going to make the power generating light water reactors safer. In the Phase 1A of this cost shared project, GE (GRC + GNF) teamed with the University of Michigan, Los Alamos National Laboratory, Brookhaven National Laboratory, Idaho National Laboratory, and Oak Ridge National Laboratory to study the environmental and mechanical behavior of more than eight candidate cladding material both under normal operation conditions of commercial nuclear reactors and under accident conditions in superheated steam (loss of coolant condition). The main findings are as follows: (1) Under normal operation conditions the candidate alloys (e.g. APMT, Alloy 33) showed excellent resistance to general corrosion, shadow corrosion and to environmentally assisted cracking. APMT also showed resistance to proton irradiation up to 5 dpa. (2) Under accident conditions the selected candidate materials showed several orders of magnitude improvement in the reaction with superheated steam as compared with the current zirconium based alloys. (3) Tube fabrication feasibility studies of FeCrAl alloys are underway. The aim is to obtain a wall thickness that is below 400 m. (4) A strategy is outlined for the regulatory path approval and for the insertion of a lead fuel assembly in a commercial reactor by 2022. (5) The GE team worked closely with INL to have four rodlets tested in the ATR. GE provided the raw stock for the alloys, the fuel for the rodlets and the cost for fabrication/welding of the rodlets. INL fabricated the rodlets and the caps and welded them to provide hermetic seal. The replacement of a zirconium alloy using a ferritic material containing chromium and aluminum appears to be the most near term implementation for accident tolerant nuclear fuels.

Rebak, Raul B. [General Electric] (ORCID:0000000280704475)

2014-12-30T23:59:59.000Z

212

1992 Columbia River Salmon Flow Measures Options Analysis/EIS.  

SciTech Connect (OSTI)

This Options Analysis/Environmental Impact Statement (OA/EIS) identifies, presents effects of, and evaluates the potential options for changing instream flow levels in efforts to increase salmon populations in the lower Columbia and Snake rivers. The potential actions would be implemented during 1992 to benefit juvenile and adult salmon during migration through eight run-of-river reservoirs. The Corps of Engineers (Corps) prepared this document in cooperation with the Bonneville Power Administration and the Bureau of Reclamation. The US Fish and Wildlife Service (FSWS) is a participating agency. The text and appendices of the document describe the characteristics of 10 Federal projects and one private water development project in the Columbia River drainage basin. Present and potential operation of these projects and their effects on the salmon that spawn and rear in the Columbia and Snake River System are presented. The life history, status, and response of Pacific salmon to current environmental conditions are described.

Not Available

1992-01-01T23:59:59.000Z

213

Adaptation of gas tagging for failed fuel identification in light water reactors  

SciTech Connect (OSTI)

This paper discusses experience with noble gas tagging and its adaptation to commercial reactors. It reviews the recent incidence of fuel failures in light water reactors, and methods used to identify failures, and concludes that the on-line technique of gas tagging could significantly augment present flux tilting, sipping and ultrasonic testing of assemblies. The paper describes calculations on tag gas stability in-reactor, and tag injection tests that were carried out collaboratively with Commonwealth Edison Company in the Byron-2 pressurized water reactor (P%a) and with Duke Power Company and Babcock and Wilcox Fuel Company in the Oconee-2 PWM. The tests gave information on: (a) noble gas concentration dynamics as the tag gases were dissolved in and eventually removed from subsystems of the RCS; and (b) the suitability of candidate Ar, Ne, Kr and Xe isotopes for tagging PWR fuel. It was found that the activity of Xe{sup 125} (the activation product of the tag isotope Xe{sup 124}) acted as a ``tag of a tag`` and tracked gas through the reactor; measured activities are being used to model gas movement in the RCS. Several interference molecules (trace contaminants normally present at sub-ppM concentrations in RCS samples) and entrained air in the RCS were found to affect mass spectrometer sensitivity for tag isotopes. In all instances the contaminants could be differentiated from the tag isotopes by operating the mass spectrometer at high resolution (2500). Similarly, it was possible to distinguish all the candidate tag gases against a high background of air. The test results suggested, however, that for routine analysis a high resolution static mass spectrometer will be preferable to the dynamic instrument used for the present analyses.

Lambert, J.D.B.; Gross, K.C.; Depiante, E.V. [Argonne National Lab., IL (United States); Callis, E.L. [Los Alamos National Lab., NM (United States); Egebrecht, P.M. [Commonwealth Edison Company, Downers Grove, IL (United States)

1996-03-01T23:59:59.000Z

214

Radioactive Fission Product Release from Defective Light Water Reactor Fuel Elements  

SciTech Connect (OSTI)

Results are provided of the experimental investigation of radioactive fission product (RFP) release, i.e., krypton, xenon, and iodine radionuclides from fuel elements with initial defects during long-term (3 to 5 yr) irradiation under low linear power (5 to 12 kW/m) and during special experiments in the VK-50 vessel-type boiling water reactor.The calculation model for the RFP release from the fuel-to-cladding gap of the defective fuel element into coolant was developed. It takes into account the convective transport in the fuel-to-cladding gap and RFP sorption on the internal cladding surface and is in good agreement with the available experimental data. An approximate analytical solution of the transport equation is given. The calculation dependencies of the RFP release coefficients on the main parameters such as defect size, fuel-to-cladding gap, temperature of the internal cladding surface, and radioactive decay constant were analyzed.It is shown that the change of the RFP release from the fuel elements with the initial defects during long-term irradiation is, mainly, caused by fuel swelling followed by reduction of the fuel-to-cladding gap and the fuel temperature. The calculation model for the RFP release from defective fuel elements applicable to light water reactors (LWRs) was developed. It takes into account the change of the defective fuel element parameters during long-term irradiation. The calculation error according to the program does not exceed 30% over all the linear power change range of the LWR fuel elements (from 5 to 26 kW/m)

Konyashov, Vadim V.; Krasnov, Alexander M. [State Scientific Centre of Russian Federation-Research Institute of Atomic Reactors (Russian Federation)

2002-04-15T23:59:59.000Z

215

Feasibility Study of Supercritical Light Water Cooled Reactors for Electrical Power Production, 5th Quarterly Report, October - December 2002  

SciTech Connect (OSTI)

The overall objective of this project is to evaluate the feasibility of supercritical light water cooled reactors for electric power production. The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies for the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed. If no additional moderator is added to the fuel rod lattice, it is possible to attain fast neutron energy spectrum conditions in a supercritical water-cooled reactor (SCWR). This type of core can make use of either fertile or fertile-free fuel and retain a hard spectrum to effectively burn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity. One can also add moderation and design a thermal spectrum SCWR that can also burn actinides. The project is organized into three tasks:

Philip MacDonald; Jacopo Buongiorno; Cliff Davis; J. Stephen Herring; Kevan Weaver; Ron Latanision; Bryce Mitton; Gary Was; Luca Oriani; Mario Carelli; Dmitry Paramonov; Lawrence Conway

2003-01-01T23:59:59.000Z

216

Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production, 3rd Quarterly Report  

SciTech Connect (OSTI)

The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed.

Mac Donald, Philip Elsworth

2002-06-01T23:59:59.000Z

217

Accident source terms for Light-Water Nuclear Power Plants. Final report  

SciTech Connect (OSTI)

In 1962 tile US Atomic Energy Commission published TID-14844, ``Calculation of Distance Factors for Power and Test Reactors`` which specified a release of fission products from the core to the reactor containment for a postulated accident involving ``substantial meltdown of the core``. This ``source term``, tile basis for tile NRC`s Regulatory Guides 1.3 and 1.4, has been used to determine compliance with tile NRC`s reactor site criteria, 10 CFR Part 100, and to evaluate other important plant performance requirements. During the past 30 years substantial additional information on fission product releases has been developed based on significant severe accident research. This document utilizes this research by providing more realistic estimates of the ``source term`` release into containment, in terms of timing, nuclide types, quantities and chemical form, given a severe core-melt accident. This revised ``source term`` is to be applied to the design of future light water reactors (LWRs). Current LWR licensees may voluntarily propose applications based upon it.

Soffer, L.; Burson, S.B.; Ferrell, C.M.; Lee, R.Y.; Ridgely, J.N.

1995-02-01T23:59:59.000Z

218

Analysis of assembly serial number usage in domestic light-water reactors  

SciTech Connect (OSTI)

Domestic light-water reactor (LWR) fuel assemblies are identified by a serial number that is placed on each assembly. These serial numbers are used as identifiers throughout the life of the fuel. The uniqueness of assembly serial numbers is important in determining their effectiveness as unambiguous identifiers. The purpose of this study is to determine what serial numbering schemes are used, the effectiveness of these schemes, and to quantify how many duplicate serial numbers occur on domestic LWR fuel assemblies. The serial numbering scheme adopted by the American National Standards Institute (ANSI) ensures uniqueness of assembly serial numbers. The latest numbering scheme adopted by General Electric (GE), was also found to be unique. Analysis of 70,971 fuel assembly serial numbers from permanently discharged fuel identified 11,948 serial number duplicates. Three duplicate serial numbers were found when analysis focused on duplication within the individual fuel inventory at each reactor site, but these were traced back to data entry errors and will be corrected by the Energy Information Administration (EIA). There were also three instances where the serial numbers used to identify assemblies used for hot cell studies differed from the serial numbers reported to the EIA. It is recommended that fuel fabricators and utilities adhere to the ANSI serial numbering scheme to ensure serial number uniqueness. In addition, organizations collecting serial number information, should request that all known serial numbers physically attached or associated with each assembly be reported and identified by the corresponding number scheme. 10 refs., 5 tabs.

Reich, W.J. (Oak Ridge National Lab., TN (USA)); Moore, R.S. (Automated Sciences Group, Inc., Oak Ridge, TN (USA))

1991-05-01T23:59:59.000Z

219

Assessment of the use of extended burnup fuel in light water power reactors  

SciTech Connect (OSTI)

This study has been conducted by Pacific Northwest Laboratory for the US Nuclear Regulatory Commission to review the environmental and economic impacts associated with the use of extended burnup nuclear fuel in light water power reactors. It has been proposed that current batch average burnup levels of 33 GWd/t uranium be increased to above 50 GWd/t. The environmental effects of extending fuel burnup during normal operations and during accident events and the economic effects of cost changes on the fuel cycle are discussed in this report. The physical effects of extended burnup on the fuel and the fuel assembly are also presented as a basis for the environmental and economic assessments. Environmentally, this burnup increase would have no significant impact over that of normal burnup. Economically, the increased burnup would have favorable effects, consisting primarily of a reduction: (1) total fuel requirements; (2) reactor downtime for fuel replacement; (3) the number of fuel shipments to and from reactor sites; and (4) repository storage requirements. 61 refs., 4 figs., 27 tabs.

Baker, D.A.; Bailey, W.J.; Beyer, C.E.; Bold, F.C.; Tawil, J.J.

1988-02-01T23:59:59.000Z

220

Safeguards and security requirements for weapons plutonium disposition in light water reactors  

SciTech Connect (OSTI)

This paper explores the issues surrounding the safeguarding of the plutonium disposition process in support of the United States nuclear weapons dismantlement program. It focuses on the disposition of the plutonium by burning mixed oxide fuel in light water reactors (LWR) and addresses physical protection, material control and accountability, personnel security and international safeguards. The S and S system needs to meet the requirements of the DOE Orders, NRC Regulations and international safeguards agreements. Experience has shown that incorporating S and S measures into early facility designs and integrating them into operations provides S and S that is more effective, more economical, and less intrusive. The plutonium disposition safeguards requirements with which the US has the least experience are the implementation of international safeguards on plutonium metal; the large scale commercialization of the mixed oxide fuel fabrication; and the transportation to and loading in the LWRs of fresh mixed oxide fuel. It is in these areas where the effort needs to be concentrated if the US is to develop safeguards and security systems that are effective and efficient.

Thomas, L.L.; Strait, R.S. [Lawrence Livermore National Lab., CA (United States). Fission Energy and Systems Safety Program

1994-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Insights for aging management of light water reactor components: Metal containments. Volume 5  

SciTech Connect (OSTI)

This report evaluates the available technical information and field experience related to management of aging damage to light water reactor metal containments. A generic aging management approach is suggested for the effective and comprehensive aging management of metal containments to ensure their safe operation. The major concern is corrosion of the embedded portion of the containment vessel and detection of this damage. The electromagnetic acoustic transducer and half-cell potential measurement are potential techniques to detect corrosion damage in the embedded portion of the containment vessel. Other corrosion-related concerns include inspection of corrosion damage on the inaccessible side of BWR Mark I and Mark II containment vessels and corrosion of the BWR Mark I torus and emergency core cooling system piping that penetrates the torus, and transgranular stress corrosion cracking of the penetration bellows. Fatigue-related concerns include reduction in the fatigue life (a) of a vessel caused by roughness of the corroded vessel surface and (b) of bellows because of any physical damage. Maintenance of surface coatings and sealant at the metal-concrete interface is the best protection against corrosion of the vessel.

Shah, V.N.; Sinha, U.P. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Smith, S.K. [Ogden Environmental and Energy Services, Southfield, MI (United States)

1994-03-01T23:59:59.000Z

222

Modeling of the performance of weapons MOX fuel in light water reactors  

SciTech Connect (OSTI)

Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light water reactors (LWRs) for the disposition of excess plutonium from disassembled nuclear warheads. Fuel performance models are used which describe the behavior of MOX fuel during irradiation under typical power reactor conditions. The objective of this project is to perform the analysis of the thermal, mechanical, and chemical behavior of weapons MOX fuel pins under LWR conditions. If fuel performance analysis indicates potential questions, it then becomes imperative to assess the fuel pin design and the proposed operating strategies to reduce the probability of clad failure and the associated release of radioactive fission products into the primary coolant system. Applying the updated code to anticipated fuel and reactor designs, which would be used for weapons MOX fuel in the US, and analyzing the performance of the WWER-100 fuel for Russian weapons plutonium disposition are addressed in this report. The COMETHE code was found to do an excellent job in predicting fuel central temperatures. Also, despite minor predicted differences in thermo-mechanical behavior of MOX and UO{sub 2} fuels, the preliminary estimate indicated that, during normal reactor operations, these deviations remained within limits foreseen by fuel pin design.

Alvis, J.; Bellanger, P.; Medvedev, P.G.; Peddicord, K.L. [Texas A and M Univ., College Station, TX (United States). Nuclear Engineering Dept.; Gellene, G.I. [Texas Tech Univ., Lubbock, TX (United States). Dept. of Chemistry and Biochemistry

1999-05-01T23:59:59.000Z

223

Survey of Worldwide Light Water Reactor Experience with Mixed Uranium-Plutonium Oxide Fuel  

SciTech Connect (OSTI)

The US and the Former Soviet Union (FSU) have recently declared quantities of weapons materials, including weapons-grade (WG) plutonium, excess to strategic requirements. One of the leading candidates for the disposition of excess WG plutonium is irradiation in light water reactors (LWRs) as mixed uranium-plutonium oxide (MOX) fuel. A description of the MOX fuel fabrication techniques in worldwide use is presented. A comprehensive examination of the domestic MOX experience in US reactors obtained during the 1960s, 1970s, and early 1980s is also presented. This experience is described by manufacturer and is also categorized by the reactor facility that irradiated the MOX fuel. A limited summary of the international experience with MOX fuels is also presented. A review of MOX fuel and its performance is conducted in view of the special considerations associated with the disposition of WG plutonium. Based on the available information, it appears that adoption of foreign commercial MOX technology from one of the successful MOX fuel vendors will minimize the technical risks to the overall mission. The conclusion is made that the existing MOX fuel experience base suggests that disposition of excess weapons plutonium through irradiation in LWRs is a technically attractive option.

Cowell, B.S.; Fisher, S.E.

1999-02-01T23:59:59.000Z

224

Qualification Requirements of Guided Ultrasonic Waves for Inspection of Piping in Light Water Reactors  

SciTech Connect (OSTI)

Guided ultrasonic waves (GUW) are being increasingly used for both NDT and monitoring of piping. GUW offers advantages over many conventional NDE technologies due to the ability to inspect large volumes of piping components without significant removal of thermal insulation or protective layers. In addition, regions rendered inaccessible to more conventional NDE technologies may be more accessible using GUW techniques. For these reasons, utilities are increasingly considering the use of GUWs for performing the inspection of piping components in nuclear power plants. GUW is a rapidly evolving technology and its usage for inspection of nuclear power plant components requires refinement and qualification to ensure it is able to achieve consistent and acceptable levels of performance. This paper will discuss potential requirements for qualification of GUW techniques for the inspection of piping components in light water reactors (LWRs). The Nuclear Regulatory Commission has adopted ASME Boiler and Pressure Vessel Code requirements in Sections V, III, and XI for nondestructive examination methods, fabrication inspections, and pre-service and in-service inspections. A Section V working group has been formed to place the methodology of GUW into the ASME Boiler and Pressure Vessel Code but no requirements for technique, equipment, or personnel exist in the Code at this time.

Meyer, Ryan M.; Ramuhalli, Pradeep; Doctor, Steven R.; Bond, Leonard J.

2013-08-01T23:59:59.000Z

225

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

SciTech Connect (OSTI)

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

Shannon Bragg-Sitton

2014-02-01T23:59:59.000Z

226

COLUMBIA UNIVERSITY LIBRARIES "Columbia's Libraries are second to none. The online search  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY LIBRARIES "Columbia's Libraries are second to none. The online search the return on investment from an outstanding library system." --Steven Schinke, Professor Columbia University School of Social Work faculty guide to the columbia university libraries @YOUR SERVICE #12;Librarian

Salzman, Daniel

227

Student Financial Aid 11 Jesse Hall University of Missouri Columbia Columbia, MO 65211-1600  

E-Print Network [OSTI]

Student Financial Aid 11 Jesse Hall University of Missouri ­ Columbia Columbia, MO 65211-1600 PHONE;Student Financial Aid 11 Jesse Hall University of Missouri ­ Columbia Columbia, MO 65211-1600 PHONE (573 ________________________________________________________________________________________________________________________ Name of Host Institution (College or University you will be attending or taking additional classes

Taylor, Jerry

228

COLUMBIA STARTUP LAB, THE IDEAS KEEP  

E-Print Network [OSTI]

alumni include John Stevens 1768KC, who pioneered the steam-engine locomotive; Edwin Armstrong 1913SEAS, Columbia Engineering, SIPA, and the business school cut the ribbon for the Columbia Startup Lab, a 5

Qian, Ning

229

Columbia University X-Ray Measurements  

E-Print Network [OSTI]

Columbia University X-Ray Measurements of the Levitated Dipole Experiment J. L. Ellsworth, J. Kesner MIT Plasma Science and Fusion Center D.T. Garnier, A.K. Hansen, M.E. Mauel Columbia University

230

Environmentally assisted cracking in light water reactors. Semiannual report, July 1998-December 1998.  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from July 1998 to December 1998. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of primary pressure boundary materials, (b) irradiation-assisted stress corrosion cracking of austenitic stainless steels (SSs), and (c) EAC of Alloys 600 and 690. Fatigue tests have been conducted to determine the crack initiation and crack growth characteristics of austenitic SSs in LWR environments. Procedures are presented for incorporating the effects of reactor coolant environments on the fatigue life of pressure vessel and piping steels. Slow-strain-rate tensile tests and posttest fractographic analyses were conducted on several model SS alloys irradiated to {approx}0.3 and 0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) in helium at 289 C in the Halden reactor. The results have been used to determine the influence of alloying and impurity elements on the susceptibility of these steels to irradiation-assisted stress corrosion cracking. Fracture toughness J-R curve tests were also conducted on two heats of Type 304 SS that were irradiated to {approx}0.3 x 10{sup 21} n {center_dot} cm{sup -2} in the Halden reactor. Crack-growth-rate tests have been conducted on compact-tension specimens of Alloys 600 and 690 under constant load to evaluate the resistance of these alloys to stress corrosion cracking in LWR environments.

Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Kassner, T. F.; Ruther, W. E.; Shack, W. J.; Smith, J. L.; Soppet, W. K.; Strain; R. V. (Energy Technology); ( APS-USR)

1999-10-01T23:59:59.000Z

231

Light Water Reactor Sustainability Research and Development Program Plan -- Fiscal Year 20092013  

SciTech Connect (OSTI)

Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60-year operating licenses. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to declineeven with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary this year. U.S. regulators have begun considering extended operations of nuclear power plants and the research needed to support long-term operations. The Light Water Reactor Sustainability (LWRS) Research and Development (R&D) Program, developed and sponsored by the Department of Energy, is performed in close collaboration with industry R&D programs. The purpose of the LWRS R&D Program is to provide technical foundations for licensing and managing long-term, safe and economical operation of the current operating nuclear power plants. The LWRS R&D Program vision is captured in the following statements: Existing operating nuclear power plants will continue to safely provide clean and economic electricity well beyond their first license- extension period, significantly contributing to reduction of United States and global carbon emissions, enhancement of national energy security, and protection of the environment. There is a comprehensive technical basis for licensing and managing the long-term, safe, economical operation of nuclear power plants. Sustaining the existing operating U.S. fleet also will improve its international engagement and leadership on nuclear safety and security issues.

Idaho National Laboratory

2009-12-01T23:59:59.000Z

232

Light Water Reactor Sustainability Program A Reference Plan for Control Room Modernization: Planning and Analysis Phase  

SciTech Connect (OSTI)

The U.S. Department of Energys Light Water Reactor Sustainability (LWRS) program is collaborating with a U.S. nuclear utility to bring about a systematic fleet-wide control room modernization. To facilitate this upgrade, a new distributed control system (DCS) is being introduced into the control rooms of these plants. The DCS will upgrade the legacy plant process computer and emergency response facility information system. In addition, the DCS will replace an existing analog turbine control system with a display-based system. With technology upgrades comes the opportunity to improve the overall human-system interaction between the operators and the control room. To optimize operator performance, the LWRS Control Room Modernization research team followed a human-centered approach published by the U.S. Nuclear Regulatory Commission. NUREG-0711, Rev. 3, Human Factors Engineering Program Review Model (OHara et al., 2012), prescribes four phases for human factors engineering. This report provides examples of the first phase, Planning and Analysis. The three elements of Planning and Analysis in NUREG-0711 that are most crucial to initiating control room upgrades are: Operating Experience Review: Identifies opportunities for improvement in the existing system and provides lessons learned from implemented systems. Function Analysis and Allocation: Identifies which functions at the plant may be optimally handled by the DCS vs. the operators. Task Analysis: Identifies how tasks might be optimized for the operators. Each of these elements is covered in a separate chapter. Examples are drawn from workshops with reactor operators that were conducted at the LWRS Human System Simulation Laboratory HSSL and at the respective plants. The findings in this report represent generalized accounts of more detailed proprietary reports produced for the utility for each plant. The goal of this LWRS report is to disseminate the technique and provide examples sufficient to serve as a template for other utilities projects for control room modernization.

Jacques Hugo; Ronald Boring; Lew Hanes; Kenneth Thomas

2013-09-01T23:59:59.000Z

233

Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems  

SciTech Connect (OSTI)

The Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems, prepared to support the U.S. Advanced Fuel Cycle Initiative (AFCI) systems analysis, provides a technology-oriented baseline system cost comparison between the open fuel cycle and closed fuel cycle systems. The intent is to understand their overall cost trends, cost sensitivities, and trade-offs. This analysis also improves the AFCI Programs understanding of the cost drivers that will determine nuclear powers cost competitiveness vis-a-vis other baseload generation systems. The common reactor-related costs consist of capital, operating, and decontamination and decommissioning costs. Fuel cycle costs include front-end (pre-irradiation) and back-end (post-iradiation) costs, as well as costs specifically associated with fuel recycling. This analysis reveals that there are large cost uncertainties associated with all the fuel cycle strategies, and that overall systems (reactor plus fuel cycle) using a closed fuel cycle are about 10% more expensive in terms of electricity generation cost than open cycle systems. The study concludes that further U.S. and joint international-based design studies are needed to reduce the cost uncertainties with respect to fast reactor, fuel separation and fabrication, and waste disposition. The results of this work can help provide insight to the cost-related factors and conditions needed to keep nuclear energy (including closed fuel cycles) economically competitive in the U.S. and worldwide. These results may be updated over time based on new cost information, revised assumptions, and feedback received from additional reviews.

D. E. Shropshire

2009-01-01T23:59:59.000Z

234

Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics  

SciTech Connect (OSTI)

The safe, reliable and economic operation of the nations nuclear power reactor fleet has always been a top priority for the United States nuclear industry. As a result, continual improvement of technology, including advanced materials and nuclear fuels, remains central to industrys success. Decades of research combined with continual operation have produced steady advancements in technology and yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. In 2011, following the Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex, enhancing the accident tolerance of LWRs became a topic of serious discussion. As a result of direction from the U.S. Congress, the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) initiated an Accident Tolerant Fuel (ATF) Development program. The complex multiphysics behavior of LWR nuclear fuel makes defining specific material or design improvements difficult; as such, establishing qualitative attributes is critical to guide the design and development of fuels and cladding with enhanced accident tolerance. This report summarizes a common set of technical evaluation metrics to aid in the optimization and down selection of candidate designs. As used herein, metrics describe a set of technical bases by which multiple concepts can be fairly evaluated against a common baseline and against one another. Furthermore, this report describes a proposed technical evaluation methodology that can be applied to assess the ability of each concept to meet performance and safety goals relative to the current UO2 zirconium alloy system and relative to one another. The resultant ranked evaluation can then inform concept down-selection, such that the most promising accident tolerant fuel design option(s) can continue to be developed for lead test rod or lead test assembly insertion into a commercial reactor within the desired timeframe (by 2022).

Brad Merrill; Melissa Teague; Robert Youngblood; Larry Ott; Kevin Robb; Michael Todosow; Chris Stanek; Mitchell Farmer; Michael Billone; Robert Montgomery; Nicholas Brown; Shannon Bragg-Sitton

2014-02-01T23:59:59.000Z

235

Nuclear Systems Enhanced Performance Program, Maintenance Cycle Extension in Advanced Light Water Reactor Design  

SciTech Connect (OSTI)

A renewed interest in new nuclear power generation in the US has spurred interest in developing advanced reactors with features which will address the public's concerns regarding nuclear generation. However, it is economic performance which will dictate whether any new orders for these plants will materialize. Economic performance is, to a great extent, improved by maximizing the time that the plant is on-line generating electricity relative to the time spent off-line conducting maintenance and refueling. Indeed, the strategy for the advanced light water reactor plant IRIS (International Reactor, Innovative and Secure) is to utilize an eight year operating cycle. This report describes a formalized strategy to address, during the design phase, the maintenance-related barriers to an extended operating cycle. The top-level objective of this investigation was to develop a methodology for injecting component and system maintainability issues into the reactor plant design process to overcome these barriers. A primary goal was to demonstrate the applicability and utility of the methodology in the context of the IRIS design. The first step in meeting the top-level objective was to determine the types of operating cycle length barriers that the IRIS design team is likely to face. Evaluation of previously identified regulatory and investment protection surveillance program barriers preventing a candidate operating PWR from achieving an extended (48 month) cycle was conducted in the context of the IRIS design. From this analysis, 54 known IRIS operating cycle length barriers were identified. The resolution methodology was applied to each of these barriers to generate design solution alternatives for consideration in the IRIS design. The methodology developed has been demonstrated to narrow the design space to feasible design solutions which enable a desired operating cycle length, yet is general enough to have broad applicability. Feedback from the IRIS design team indicates that the proposed solutions to the investigated operating cycle length barriers are both feasible and consistent with sound design practice.

Professor Neill Todreas

2001-10-01T23:59:59.000Z

236

MWCNT/WO{sub 3} nanocomposite photoanode for visible light induced water splitting  

SciTech Connect (OSTI)

The Multi-walled carbon nanotube (MWCNT)/WO{sub 3} nanocomposite thin films with different MWCNTs weight percentages were prepared by solgel method as visible light induced photoanode in water splitting reaction. Weight percentage of MWCNT in the all nanocomposite thin films was confirmed by TGA/DSC analysis. According to XPS analysis, oxygenated groups at the surface of the MWCNT and stoichiometric formation of WO{sub 3} thin films were determined, while the crystalline structure of the nanocomposite samples was studied by XRD indicating (0 0 2) peak of MWCNT in the monoclinic phase of WO{sub 3}. The influence of different weight percentage (wt%) of MWCNT on WO{sub 3} photoactivity showed that the electron conductivity, charge transfer and electron life time had improved as compared with the pure WO{sub 3}. Based on linear sweep voltammetry and chronoamperometry measurements, the (1 wt%) MWCNT/WO{sub 3} nanocomposite thin films photoanode has a maximum photocurrent density of ?4.5 A/m{sup 2} and electron life time of about 57 s. - Graphical abstract: Photocurrent density versus time at constant potential (0.7 V) for the WO{sub 3} films containing different MWCNT weight percentages annealed at 400 C under 1000 Wm{sup ?2} visible photo-illumination. Display Omitted - Highlights: MWCNT/ WO{sub 3} nanocomposite thin films were synthesized using solgel derived method. TGA/DSC confirmed the weight percentage of MWCNT in the all nanocomposite thin films. XPS analysis revealed that WO{sub 3} was attached on the oxygenated group of MWCNT surface. The Highest Photoelectrochemical activity is achieved for (1 wt%)MWCNT/WO{sub 3} thin film.

Yousefzadeh, Samira [Physics Department, Sharif University of Technology, P.O. Box 11155-9161, Tehran (Iran, Islamic Republic of); Reyhani, Ali [Physics Department, Faculty of Science, Imam Khomeini International University, P.O. Box 34149-16818, Qazvin (Iran, Islamic Republic of); Naseri, Naimeh [Physics Department, Sharif University of Technology, P.O. Box 11155-9161, Tehran (Iran, Islamic Republic of); Moshfegh, Alireza Z., E-mail: moshfegh@sharif.edu [Physics Department, Sharif University of Technology, P.O. Box 11155-9161, Tehran (Iran, Islamic Republic of); Institute for Nanoscience and Nanotechnology, Sharif University of Technology, P.O. Box 14588-89694, Tehran (Iran, Islamic Republic of)

2013-08-15T23:59:59.000Z

237

Atlas of the Columbia River Basin  

E-Print Network [OSTI]

#12;Atlas of the Columbia River Basin Oregon State University Computer-Assisted Cartography Course & GEOVISUALIZATION GROUP UNIVERSITY #12;2013 Oregon State University Atlas of the Columbia River Basin FOREWORDAtlas, Montana, Nevada, Wyoming, and Utah. 2013 Oregon State University Atlas of the Columbia River Basin

Jenny, Bernhard

238

Tony Jebara, Columbia University Advanced Machine  

E-Print Network [OSTI]

Tony Jebara, Columbia University Advanced Machine Learning & Perception Instructor: Tony Jebara #12;Tony Jebara, Columbia University Topic 1 ·Introduction, researchy course, latest papers ·Going beyond and shortcomings it entails #12;Tony Jebara, Columbia University About me ·Tony Jebara, Associate Professor

Jebara, Tony

239

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures  

E-Print Network [OSTI]

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures Facilities ­ Parking Services or under the charge or control of the University of Northern British Columbia hereinafter referred.2 Authorization A parking permit conveys the authorization by the University of Northern British Columbia

Bolch, Tobias

240

Tony Jebara, Columbia University Advanced Machine  

E-Print Network [OSTI]

Tony Jebara, Columbia University Advanced Machine Learning & Perception Instructor: Tony Jebara #12;Tony Jebara, Columbia University Topic 2 ·Nonlinear Manifold Learning ·Multidimensional Scaling (MDS) ·Semidefinite Embedding (SDE) ·Minimum Volume Embedding (MVE) #12;Tony Jebara, Columbia University Principal

Jebara, Tony

Note: This page contains sample records for the topic "light columbia water" 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

Tony Jebara, Columbia University Advanced Machine  

E-Print Network [OSTI]

Tony Jebara, Columbia University Advanced Machine Learning & Perception Instructor: Tony Jebara #12;Tony Jebara, Columbia University Topic 9 Semi-Supervised Learning Felix X. Yu · Semi-supervised SVM (S3, Columbia University How ·Transduction: discriminative, find large margin region. ·Hidden Labels: use

Jebara, Tony

242

Columbia University Opportunities to Gain Experience  

E-Print Network [OSTI]

Columbia University Opportunities to Gain Experience There are myriad ways to build experience Sciences at Columbia University offers on-campus research opportunities for the summer term Dec. 13 - March careereducation.columbia.edu Join LionSHARE ­ CCE's internship/job board Double Discovery Center Volunteer

Shepard, Kenneth

243

Columbia University Opportunities to Gain Experience  

E-Print Network [OSTI]

Columbia University Opportunities to Gain Experience There are so many ways to build experience The Columbia University Office of Government and Community Affairs provides assistance to undergraduates.edu/academics/research/science Summer Undergraduate Research Fellowship The Department of Biological Sciences at Columbia University

Hone, James

244

Revised 4/9/13 Columbia University  

E-Print Network [OSTI]

Revised 4/9/13 Columbia University Research Financial Operations Studebaker Building 615 West 131st Giscombe Anita Accountant University-Wide (212) 854-1062 adg9@columbia.edu 499P Hamdan Tamara Director University-Wide (212) 854-1071 jk2740@columbia.edu 457 Lee-Johnson Seran Project Manager I CUMC (212) 851

Hone, James

245

Tony Jebara, Columbia University Advanced Machine  

E-Print Network [OSTI]

Tony Jebara, Columbia University Advanced Machine Learning & Perception Instructor: Tony Jebara #12;Tony Jebara, Columbia University Boosting ·Combining Multiple Classifiers ·Voting ·Boosting ·Adaboost ·Based on material by Y. Freund, P. Long & R. Schapire #12;Tony Jebara, Columbia University Combining

Jebara, Tony

246

Columbia University Panhellenic www.columbiagreeks.info  

E-Print Network [OSTI]

Columbia University Panhellenic www.columbiagreeks.info Contact: Kara B. Mantooth Director AT COLUMBIA UNIVERSITY Brentwood, Tenn.--Alpha Omicron Pi is pleased to formally begin our colonization efforts to join the Greek community at Columbia University. AOII's colonization events conclude a semester

Hone, James

247

Tony Jebara, Columbia University Advanced Machine  

E-Print Network [OSTI]

Tony Jebara, Columbia University Advanced Machine Learning & Perception Instructor: Tony Jebara #12;Tony Jebara, Columbia University Topic 3 ·Maximum Margin ·Empirical Risk Minimization ·VC Dimension, Columbia University Generative vs. Discriminative ·Generative approach to classification: get p(x,y) then p

Jebara, Tony

248

COLUMBIA UNIVERSITY PREGNANCY POLICY FOR RADIATION WORKERS  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY PREGNANCY POLICY FOR RADIATION WORKERS POLICY: Under applicable regulations and Federal statutes (2), it is the policy of the Columbia University to limit the radiation dose (3). Further, it is the policy of the Columbia University to provide counseling and education

Jia, Songtao

249

Columbia University Inter-Greek Jonathan Dean  

E-Print Network [OSTI]

Columbia University Inter-Greek Council Contact: Jonathan Dean Director of IGC Public Relations's recognition at Columbia University due to the chapter's involvement in an incident of hazing. After Dean Terry members and the effectiveness of the Greek experience here at Columbia University

Hone, James

250

Quantum Mechanics and Representation Theory Columbia University  

E-Print Network [OSTI]

Quantum Mechanics and Representation Theory Peter Woit Columbia University Texas Tech, November 21 2013 Peter Woit (Columbia University) Quantum Mechanics and Representation Theory November 2013 1 / 30, 1967 Peter Woit (Columbia University) Quantum Mechanics and Representation Theory November 2013 2 / 30

Woit, Peter

251

Columbia University Opportunities to Gain Experience  

E-Print Network [OSTI]

Columbia University Opportunities to Gain Experience There are so many ways to build experience Program The Columbia University Office of Government and Community Affairs provides assistance.edu/academics/research/science Summer Undergraduate Research Fellowship The Department of Biological Sciences at Columbia University

Hone, James

252

Columbia University Libraries/ Information Services is a  

E-Print Network [OSTI]

, rare books, microforms, maps, and more.Our website is the gateway to our services and resources, 3rd, and 4th floors of Butler Library library.columbia.edu/undergraduate Rare Book & Manuscript.columbia.edu/dssc Global Studies 309 Lehman Library library.columbia.edu/global 12 Mathematics Library 303 Mathematics Hall

Qian, Ning

253

Columbia University http://www.columbia.edu/~mem4/  

E-Print Network [OSTI]

to mine Earth's primary source of energy, Helium-3. It is a lonely job, made harder by a broken satellite is fusion primer · Fusion: "Green" nuclear power · Magnetic fusion energy primer · ITER: Fusion at the scale of a power plant · Columbia University's plasma physics experiments 2Tuesday, March 1, 2011 #12;Energy from

Mauel, Michael E.

254

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Semiannual report, October 1990--March 1991: Volume 13  

SciTech Connect (OSTI)

The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties.

Doctor, S.R.; Good, M.S.; Heasler, P.G.; Hockey, R.L.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

1992-07-01T23:59:59.000Z

255

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

SciTech Connect (OSTI)

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

Hulstrom, L.

2011-02-07T23:59:59.000Z

256

LIGHT WATER REACTOR SUSTAINABILITY PROGRAM ADVANCED INSTRUMENTATION, INFORMATION, AND CONTROL SYSTEMS TECHNOLOGIES TECHNICAL PROGRAM PLAN FOR 2013  

SciTech Connect (OSTI)

Reliable instrumentation, information, and control (II&C) systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration.

Hallbert, Bruce; Thomas, Ken

2014-07-01T23:59:59.000Z

257

Columbia River System Operation Review : Final Environmental Impact Statement, Appendix N: Wildlife.  

SciTech Connect (OSTI)

The Columbia River System is a vast and complex combination of Federal and non-Federal facilities used for many purposes including power production, irrigation, navigation, flood control, recreation, fish and wildlife habitat and municipal and industrial water supply. Each river use competes for the limited water resources in the Columbia River Basin. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. The environmental impact statement (EIS) itself and some of the other appendices present analyses of the alternative approaches to the other three decisions considered as part of the SOR. This document is the product of the Wildlife Work Group, focusing on wildlife impacts but not including fishes. Topics covered include the following: scope and process; existing and affected environment, including specific discussion of 18 projects in the Columbia river basin. Analysis, evaluation, and alternatives are presented for all projects. System wide impacts to wildlife are also included.

Columbia River System Operation Review (U.S.)

1995-11-01T23:59:59.000Z

258

EIS-0163-S: Supplemental EIS/1993 Interim Columbia and Snake Rivers Flow Improvement Measures for Salmon  

Broader source: Energy.gov [DOE]

The U.S. Army Corps of Engineers Walla Walla District has prepared this statement to assess alternatives to improve flows of water in the lower Columbia-Snake rivers in 1993 and future years to assist the migration of juvenile and adult anadromous fish past eight hydropower dams. The U.S. Department of Energys Bonneville Power Administration served as a cooperating agency in developing this supplement due to its key role in direct operation of the integrated and coordinated Columbia-Snake River System, and adopted this statement in March of 1993. This statement supplements the 1992 Columbia River Salmon Flow Measures Options Analysis Environmental Impact Statement, which evaluated ways to alter water management operations in 1992 on the lower Columbia and Snake rivers to enhance the survival of wild Snake River salmon.

259

Tectonic development of Columbia Plateau  

SciTech Connect (OSTI)

The Columbia Plateau can be subdivided into two structural subprovinces: the Palouse, characterized by the Blue Mountain anticlinorium, and the Yakima foldbelt, characterized by generally narrow, asymmetric (faulted) anticlinal ridges separated by broad basins. The tectonic features of the Columbia Plateau result from (1) north-south compression during and following the emplacement of the Columbia River Basalt (CRB); (2) the subsidence of the Yakima foldbelt subprovince relative to a stable Palouse subprovince; (3) the growth of the Yakima folds superimposed on a subsiding basin; (4) the growth of major northwest-trending strike-slip faults on the western side of the plateau; and (5) the influence of regional structures that trend into the Columbia Plateau. Subsidence of the Yakima foldbelt subprovince began prior to the eruption of the CRB and has continued from the Miocene to the present. The rate of subsidence kept pace with CRB emplacement, decreasing as eruption rates waned. Simultaneously, anticlinal fold growth within the Yakima foldbelt occurred under north-south compression, and decreased as the rate of subsidence and CRB eruptions declined. Paleomagnetic data indicate fold growth was accompanied by a component of clockwise rotation that occurred on a local scale and only in anticlines. The development of these tectonic features is consistent with oblique subduction along a converging plate margin.

Reidel, S.B.; Chamness, M.A.; Fecht, K.R.; Hagood, M.C.; Nolan, T.L.

1987-08-01T23:59:59.000Z

260

Environmentally assisted cracking in light water reactors : semiannual report, July 2000 - December 2000.  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from July 2000 to December 2000. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of primary pressure boundary materials, (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels (SSs), and (c) EAC of Alloys 600 and 690. The fatigue strain-vs.-life data are summarized for the effects of various material, loading, and environmental parameters on the fatigue lives of carbon and low-alloy steels and austenitic SSs. Effects of the reactor coolant environment on the mechanism of fatigue crack initiation are discussed. Two methods for incorporating the effects of LWR coolant environments into the ASME Code fatigue evaluations are presented. Slow-strain-rate tensile tests and posttest fractographic analyses were conducted on several model SS alloys irradiated to {approx}0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) in He at 289 C in the Halden reactor. The results were used to determine the influence of alloying and impurity elements on the susceptibility of these steels to IASCC. A fracture toughness J-R curve test was conducted on a commercial heat of Type 304 SS that was irradiated to {approx}2.0 x 10{sup 21} n {center_dot} cm{sup -2} in the Halden reactor. The results were compared with the data obtained earlier on steels irradiated to 0.3 and 0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) (0.45 and 1.35 dpa). Neutron irradiation at 288 C was found to decrease the fracture toughness of austenitic SSs. Tests were conducted on compact-tension specimens of Alloy 600 under cyclic loading to evaluate the enhancement of crack growth rates in LWR environments. Then, the existing fatigue crack growth data on Alloys 600 and 690 were analyzed to establish the effects of temperature, load ratio, frequency, and stress intensity range on crack growth rates in air.

Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Shack, W. J.; Soppet, W. K.; Strain, R. V.; Energy Technology

2002-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Research and Development of High Temperature Light Water Cooled Reactor Operating at Supercritical-Pressure in Japan  

SciTech Connect (OSTI)

This paper summarizes the status and future plans of research and development of the high temperature light water cooled reactor operating at supercritical-pressure in Japan. It includes; the concept development; material for the fuel cladding; water chemistry under supercritical pressure; thermal hydraulics of supercritical fluid; and the conceptual design of core and plant system. Elements of concept development of the once-through coolant cycle reactor are described, which consists of fuel, core, reactor and plant system, stability and safety. Material studies include corrosion tests with supercritical water loops and simulated irradiation tests using a high-energy transmission electron microscope. Possibilities of oxide dispersion strengthening steels for the cladding material are studied. The water chemistry research includes radiolysis and kinetics of supercritical pressure water, influence of radiolysis and radiation damage on corrosion and behavior on the interface between water and material. The thermal hydraulic research includes heat transfer tests of single tube, single rod and three-rod bundles with a supercritical Freon loop and numerical simulations. The conceptual designs include core design with a three-dimensional core simulator and sub-channel analysis, and balance of plant. (authors)

Yoshiaki Oka [Nuclear Engineering Research Laboratory, The University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, Tokyo, 112-0006 (Japan); Katsumi Yamada [Isogo Nuclear Engineering Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan)

2004-07-01T23:59:59.000Z

262

DIRECTORY OF UNIVERSITY WATER EXPERTISE  

E-Print Network [OSTI]

DIRECTORY OF UNIVERSITY WATER EXPERTISE IN THE DISTRICT OF COLUMBIA 1982 Preparation of the directory was supported in part by Federal funds from the Office of Water Research and Technology, U. The directory of faculty expertise in the District of Columbia is prepared as part of the information

District of Columbia, University of the

263

E-Print Network 3.0 - abb-ce light water Sample Search Results  

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

Supplier Beginning in 1999... , community water supply systems must provide an annual report describ- ing the quality of their drinking Source: Fernndez-Juricic, Esteban -...

264

Materials Science and Technology Division Light-Water-Reactor Safety Research Program. Volume 4. Quarterly progress report, October-December 1983  

SciTech Connect (OSTI)

The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Not Available

1984-08-01T23:59:59.000Z

265

Light Water Reactor Sustainability Program Grizzly Year-End Progress Report  

SciTech Connect (OSTI)

The Grizzly software application is being developed under the Light Water Reactor Sustainability (LWRS) program to address aging and material degradation issues that could potentially become an obstacle to life extension of nuclear power plants beyond 60 years of operation. Grizzly is based on INLs MOOSE multiphysics simulation environment, and can simultaneously solve a variety of tightly coupled physics equations, and is thus a very powerful and flexible tool with a wide range of potential applications. Grizzly, the development of which was begun during fiscal year (FY) 2012, is intended to address degradation in a variety of critical structures. The reactor pressure vessel (RPV) was chosen for an initial application of this software. Because it fulfills the critical roles of housing the reactor core and providing a barrier to the release of coolant, the RPV is clearly one of the most safety-critical components of a nuclear power plant. In addition, because of its cost, size and location in the plant, replacement of this component would be prohibitively expensive, so failure of the RPV to meet acceptance criteria would likely result in the shutting down of a nuclear power plant. The current practice used to perform engineering evaluations of the susceptibility of RPVs to fracture is to use the ASME Master Fracture Toughness Curve (ASME Code Case N-631 Section III). This is used in conjunction with empirically based models that describe the evolution of this curve due to embrittlement in terms of a transition temperature shift. These models are based on an extensive database of surveillance coupons that have been irradiated in operating nuclear power plants, but this data is limited to the lifetime of the current reactor fleet. This is an important limitation when considering life extension beyond 60 years. The currently available data cannot be extrapolated with confidence further out in time because there is a potential for additional damage mechanisms (i.e. late blooming phases) to become active later in life beyond the current operational experience. To develop a tool that can eventually serve a role in decision-making, it is clear that research and development must be perfomed at multiple scales. At the engineering scale, a multiphysics analysis code that can capture the thermomechanical response of the RPV under accident conditions, including detailed fracture mechanics evaluations of flaws with arbitrary geometry and orientation, is needed to assess whether the fracture toughness, as defined by the master curve, including the effects of embrittlement, is exceeded. At the atomistic scale, the fundamental mechanisms of degradation need to be understood, including the effects of that degradation on the relevant material properties. In addition, there is a need to better understand the mechanisms leading to the transition from ductile to brittle fracture through improved continuum mechanics modeling at the fracture coupon scale. Work is currently being conducted at all of these levels with the goal of creating a usable engineering tool informed by lower length-scale modeling. This report summarizes progress made in these efforts during FY 2013.

Benjamin Spencer; Yongfeng Zhang; Pritam Chakraborty; S. Bulent Biner; Marie Backman; Brian Wirth; Stephen Novascone; Jason Hales

2013-09-01T23:59:59.000Z

266

COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK Institutional Review Board Standard Operating to the Columbia Human Research Protection Program Columbia University (CU or Columbia or the University) has). CU has two Federalwide Assurances (FWAs): one for Columbia University Medical Center (CUMC) and one

Hone, James

267

COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK COLUMBIA COLLEGE THE FU FOUNDATION SCHOOL on your student's acceptance into and decision to enroll at Columbia University in the City of New York and your family to Columbia University and we look forward to having you join the Columbia community

Hone, James

268

Visible Light-Driven Water Oxidation by Ir oxide Clusters Coupledto Single Cr Centers in Mesoporous Silica  

SciTech Connect (OSTI)

Visible light-induced water oxidation has been demonstrated at an Ir oxide nanocluster coupled to a single Cr{sup VI} site on the pore surface of MCM-41 mesoporous silica. The photocatalytic unit was assembled by the reaction of surface Cr=O groups with Ir(acac){sub 3} precursor followed by calcination at 300 C and bond formation monitored by FT-Raman and FT-IR spectroscopy. High-resolution Z-contrast electron micrographs of the calcined material combined with energy-dispersive X-ray spot analysis confirmed the occlusion of Ir oxide nanoparticles inside the mesopores. Oxygen evolution of an aqueous suspension of the Ir{sub x}O{sub y}-CrMCM-41 upon visible light irradiation of the Cr{sup VI}-O ligand-to-metal charge-transfer absorption was monitored mass-spectrometrically. Comparison of the product yields for samples with low Cr content (Cr/Si {le} 0.02) and high Cr content (Cr/Si = 0.05) indicates that only isolated Cr centers are capable of extracting electrons from Ir oxide clusters, while di- or polychromate species are not. Water oxidation at a multielectron-transfer catalyst coupled to a single metal center has not been demonstrated before. The ability to drive water oxidation with a single metal center as electron pump offers opportunities for coupling the oxygen-evolving photocatalytic unit to reducing sites in the nanoporous scaffold.

Nakamura, Ryuhei; Frei, Heinz

2006-07-10T23:59:59.000Z

269

Environmentally assisted cracking in light-water reactors: Semi-annual report, January--June 1997. Volume 24  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from January 1997 to June 1997. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Types 304 and 304L SS, and (c) EAC of Alloys 600 and 690. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during various portions of a tensile-loading cycle is equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated boiling water reactor (BWR) water at 288 C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from several heats of Alloys 600 and 690 in low-DO, simulated pressurized water reactor environments.

Chopra, O.K.; Chung, H.M.; Gruber, E.E. [Argonne National Lab., IL (United States)] [and others

1998-04-01T23:59:59.000Z

270

Columbia River Component Data Evaluation Summary Report  

SciTech Connect (OSTI)

The purpose of the Columbia River Component Data Compilation and Evaluation task was to compile, review, and evaluate existing information for constituents that may have been released to the Columbia River due to Hanford Site operations. Through this effort an extensive compilation of information pertaining to Hanford Site-related contaminants released to the Columbia River has been completed for almost 965 km of the river.

C.S. Cearlock

2006-08-02T23:59:59.000Z

271

Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors  

E-Print Network [OSTI]

There has been an ongoing interest in replacing the fuel cladding zirconium-based alloys by other materials to reduce if not eliminate the autocatalytic and exothermic chemical reaction with water and steam at above 1,200 ...

Sukjai, Yanin

2014-01-01T23:59:59.000Z

272

Light-water-reactor safety research program. Quarterly progress report, January-March 1980  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during January, February, and March 1980 on water-reactor-safety problems. The research and development area covered is Transient Fuel Response and Fission-Product Release.

Massey, W.E.; Kyger, J.A.

1980-08-01T23:59:59.000Z

273

Light-water-reactor safety research program: quarterly progress report, July-September, 1980  

SciTech Connect (OSTI)

The progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1980 on water-reactor-safety problems. The research and development area covered is Transient Fuel Response and Fission-product Release.

Massey, W.E.; Till, C.E.

1981-04-01T23:59:59.000Z

274

Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production  

SciTech Connect (OSTI)

The supercritical water reactor (SCWR) has been the object of interest throughout the nuclear Generation IV community because of its high potential: a simple, direct cycle, compact configuration; elimination of many traditional LWR components, operation at coolant temperatures much higher than traditional LWRs and thus high thermal efficiency. It could be said that the SWR was viewed as the water counterpart to the high temperature gas reactor.

Philip MacDonald; Jacopo Buongiorno; James Sterbentz; Cliff Davis; Robert Witt; Gary Was; J. McKinley; S. Teysseyre; Luca Oriani; Vefa Kucukboyaci; Lawrence Conway; N. Jonsson: Bin Liu

2005-02-13T23:59:59.000Z

275

Washington Nuclear Profile - Columbia Generating Station  

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

Columbia Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

276

Business Energy Rebate Program (District of Columbia)  

Broader source: Energy.gov [DOE]

The District of Columbia's Sustainable Energy Utility (SEU) administers the Business Energy Rebate Program. Rebates are available to businesses and institutions for the installation of energy...

277

New Columbia River Estuary purchases benefit salmon  

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

the mouth of the Columbia River to permanently protect riverside habitat for Northwest fish and wildlife, including threatened and endangered salmon and steelhead. The...

278

Materials Science and Technology Division Light-Water-Reactor Safety Research Program. Quarterly progress report, April-June 1983. Volume 2  

SciTech Connect (OSTI)

The progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Shack, W.J.

1984-06-01T23:59:59.000Z

279

Materials Science and Technology Division light-water-reactor safety research program. Quarterly progress report, July-September 1983. Volume 3  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors (reported elsewhere), Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems (reported elsewhere).

Not Available

1984-07-01T23:59:59.000Z

280

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 14, Semiannual report, April 1991--September 1991  

SciTech Connect (OSTI)

The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWR`s); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section XI of the ASME Code. This is a progress report covering the programmatic work from April 1991 through September 1991.

Doctor, S.R.; Diaz, A.A.; Friley, J.R.; Good, M.S.; Greenwood, M.S.; Heasler, P.G.; Hockey, R.L.; Kurtz, R.J.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

1992-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 15, Semiannual report: October 1991--March 1992  

SciTech Connect (OSTI)

The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section XI of the ASME Code. This is a progress report covering the programmatic work from October 1991 through March 1992.

Doctor, S.R.; Diaz, A.A.; Friley, J.R. [Pacific Northwest Lab., Richland, WA (United States)

1993-09-01T23:59:59.000Z

282

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Semiannual report, April 1992--September 1992: Volume 16  

SciTech Connect (OSTI)

The Evaluation and Improvement of NDE Reliability for Inservice inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs);using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel and other components inspected in accordance with Section XI of the ASME Code. This is a programs report covering the programmatic work from April 1992 through September 1992.

Doctor, S.R.; Diaz, A.A.; Friley, J.R.; Greenwood, M.S.; Heasler, P.G.; Kurtz, R.J.; Simonen, F.A.; Spanner, J.C.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

1993-11-01T23:59:59.000Z

283

COLUMBIA UNIVERSITY CLUB OF NEW YORK Now is a great time to join the Columbia University Club of New York!  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY CLUB OF NEW YORK Now is a great time to join the Columbia University Club-719-0380 fax: 212-944-6944 info@columbiaclub.org www.columbiaclub.org Columbia's Social

Hone, James

284

Adaptive Management of Water Resources in Light of Future Climate Uncertainty  

SciTech Connect (OSTI)

Water resources managers have always had to make operational decisions in spite of a relatively high degree of uncertainty caused by changing climate, hydrologic, population, land use, socioeconomic, and other conditions. However, based on current climate change predictions and observations of current impacts of climate change or natural variability, the degree of uncertainty appears to be increasing drastically. By better understanding these uncertainties and their policy implications and by managing those uncertainties adaptively, water resources managers and policy makers can reduce the risk of not meeting their management goals and reduce the potential physical, biological and socioeconomic impacts associated with climate change/variation.

Gerald Sehlke; Mark Colosimo

2007-11-01T23:59:59.000Z

285

Major habitat purchase in Columbia estuary benefits salmon ...  

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

COLUMBIA LAND TRUST - BONNEVILLE POWER ADMINISTRATION -- U.S. ARMY CORPS OF ENGINEERS PR 04 12 FOR IMMEDIATE RELEASE Tuesday, Jan. 24, 2012 CONTACT: Glenn Lamb, Columbia Land...

286

Importance of Delayed Neutrons on the Coupled Neutronic-Thermohydraulic Stability of a Natural Circulation Heavy Water-Moderated Boiling Light Water-Cooled Reactor  

SciTech Connect (OSTI)

The coupled neutronic-thermohydraulic stability characteristics of a natural circulation heavy water-moderated boiling light water-cooled reactor was investigated analytically considering the effects of prompt and delayed neutrons. For this purpose, the reactor considered is the Indian Advanced Heavy Water Reactor. The analytical model considers a point kinetics model for the neutron dynamics, a homogeneous two-phase flow model for the coolant thermal hydraulics, and a lumped heat transfer model for the fuel thermal dynamics. A higher mode of oscillation having a frequency much greater than the density-wave oscillation frequency was observed if prompt neutrons alone were considered. The occurrence of a higher mode of oscillation was found to be dependent on the concentration of delayed neutrons, the void reactivity coefficient, and the fuel time constant. The core inlet subcooling is found to have different effects on the decay ratio of the fundamental and higher modes of oscillations. The influences of void reactivity coefficient and fuel time constant on the fundamental and higher modes of oscillations were also found to be opposite in nature.

Nayak, A.K. [Bhaha Atomic Research Centre (India); Aritomi, M. [Tokyo Institute of Technology (Japan); Raj, V. Venkat [Bhaha Atomic Research Centre (India)

2001-07-15T23:59:59.000Z

287

Study of Pu consumption in Advanced Light Water Reactors. Evaluation of GE Advanced Boiling Water Reactor plants  

SciTech Connect (OSTI)

Timely disposal of the weapons plutonium is of paramount importance to permanently safeguarding this material. GE`s 1300 MWe Advanced Boiling Water Reactor (ABWR) has been designed to utilize fill] core loading of mixed uranium-plutonium oxide fuel. Because of its large core size, a single ABWR reactor is capable of disposing 100 metric tons of plutonium within 15 years of project inception in the spiking mode. The same amount of material could be disposed of in 25 years after the start of the project as spent fuel, again using a single reactor, while operating at 75 percent capacity factor. In either case, the design permits reuse of the stored spent fuel assemblies for electrical energy generation for the remaining life of the plant for another 40 years. Up to 40 percent of the initial plutonium can also be completely destroyed using ABWRS, without reprocessing, either by utilizing six ABWRs over 25 years or by expanding the disposition time to 60 years, the design life of the plants and using two ABWRS. More complete destruction would require the development and testing of a plutonium-base fuel with a non-fertile matrix for an ABWR or use of an Advanced Liquid Metal Reactor (ALMR). The ABWR, in addition, is fully capable of meeting the tritium target production goals with already developed target technology.

Not Available

1993-05-13T23:59:59.000Z

288

Electrical, optical, and material characterizations of blue InGaN light emitting diodes submitted to reverse-bias stress in water vapor condition  

SciTech Connect (OSTI)

In this paper, we investigate degradation of InGaN/GaN light emitting diodes (LEDs) under reverse-bias operations in water vapor and dry air. To examine failure origins, electrical characterizations including current-voltage, breakdown current profiles, optical measurement, and multiple material analyses were performed. Our findings indicate that the diffusion of indium atoms in water vapor can expedite degradation. Investigation of reverse-bias stress can help provide insight into the effects of water vapor on LEDs.

Chen, Hsiang, E-mail: hchen@ncnu.edu.tw; Chu, Yu-Cheng; Chen, Yun-Ti; Chen, Chian-You [Department of Applied Materials and Optoelectronic Engineering, National Chi Nan University, No. 1, University Road, Puli, Nantou County 54561, Taiwan (China); Shei, Shih-Chang [Department of Electrical Engineering, National University of Tainan, No.33, Sec. 2, Shulin St., West Central Dist., Tainan City 70005, Taiwan (China)

2014-09-07T23:59:59.000Z

289

Measurements and simulations of polarization states of underwater light in clear oceanic waters  

E-Print Network [OSTI]

Remote Sensing Laboratory, The City College of the City University of New York, New York, New York 10031 under various atmospheric, surface, and water conditions, as well as solar and viewing geometries solar elevation. This implies that animals can use the DoLP signal for orientation. © 2011 Optical

Cummings, Molly E.

290

Photoassisted Overall Water Splitting in a Visible Light-Absorbing Dye-Sensitized Photoelectrochemical Cell  

E-Print Network [OSTI]

splitting system based on oxyni- tride semiconductor particles.4 In comparison, progress on overall water the heteroleptic ruthenium dye 1 to serve as both a sensitizer component and a molecular bridge to connect IrO2 nH2O particles to a metal oxide semiconductor. Phosphonates are chemically selective for TiO2

291

Light-Water-Reactor Safety Research Program. Quarterly progress report, October-December 1979  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during October, November, and December 1979 on water-reactor-safety problems. The research and development areas covered are: (1) Heat Transfer Coordination for LOCA Research Programs and (2) Transient Fuel Response and Fission-Product Release. 29 refs., 39 figs., 1 tab.

Massey, W.E.; Kyger, J.A.

1980-05-01T23:59:59.000Z

292

Light Water Reactor Fuel Cladding Research and Testing | ornl.gov  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces and Interfaces Sample6, 2011 LawrenceEfeedstocks and the climateLife a9Light

293

SEIS for the Production of Tritium in a Commercial Light Water Reactor |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGE Awards ,# , onLightThePrices andSEE HOW

294

Michael Hahn Daniel Wolf Savin (Columbia)  

E-Print Network [OSTI]

Michael Hahn Columbia University #12;Daniel Wolf Savin (Columbia) Enrico Landi (Michigan) NSF Solar. (2007) #12;#12; Only 0.01% of Sun's energy output required. Energy source is fluid motion in outer convection zone. #12;G-band 4305.6+/- 10.8 ? #12; Only 0.01% of Sun's energy output required. Energy source

Columbia University

295

Favourability Map of British Columbia Geothermal Resources  

E-Print Network [OSTI]

Favourability Map of British Columbia Geothermal Resources by Sarah Kimball A THESIS SUBMITTED carbon economy stipulates that power supply must be from renewable and low emission sources. Geothermal energy offers significant benefits to British Columbia which hosts Canadas best geothermal resources

Pedersen, Tom

296

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures  

E-Print Network [OSTI]

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies & Procedures Services President's Council Page 1, including vending, will be administered by the University of Northern British Columbia. Food and beverage will be contracted out to one or more qualified contractors. All university catering under the current Food

Bolch, Tobias

297

FEASIBILITY OF RECYCLING PLUTONIUM AND MINOR ACTINIDES IN LIGHT WATER REACTORS USING HYDRIDE FUEL  

SciTech Connect (OSTI)

The objective of this DOE NERI program sponsored project was to assess the feasibility of improving the plutonium (Pu) and minor actinide (MA) recycling capabilities of pressurized water reactors (PWRs) by using hydride instead of oxide fuels. There are four general parts to this assessment: 1) Identifying promising hydride fuel assembly designs for recycling Pu and MAs in PWRs 2) Performing a comprehensive systems analysis that compares the fuel cycle characteristics of Pu and MA recycling in PWRs using the promising hydride fuel assembly designs identified in Part 1 versus using oxide fuel assembly designs 3) Conducting a safety analysis to assess the likelihood of licensing hydride fuel assembly designs 4) Assessing the compatibility of hydride fuel with cladding materials and water under typical PWR operating conditions Hydride fuel was found to offer promising transmutation characteristics and is recommended for further examination as a possible preferred option for recycling plutonium in PWRs.

Greenspan, Ehud; Todreas, Neil; Taiwo, Temitope

2009-03-10T23:59:59.000Z

298

Water stress, temperature, and light effects on isoprene emission and photosynthesis of Kudzu leaves  

SciTech Connect (OSTI)

Kudzu (Pueraia lobata (Willd) Ohwi.) emits isoprene, a hydrocarbon which can significantly affect atmospheric chemistry. Isoprene emission under standard conditions of 1000 [mu]mol photons[center dot]M[sup [minus]2][center dot]S[sup [minus]1] and 30[degrees]C developed only after the leaf bad reached full expansion and was not maximal until up to two weeks past the point of full expansion of the leaf. Isoprene emission from kudzu was stimulated by increases in temperature and photon flux density (up to 3000 [mu]mol photons[center dot]m[sup [minus]2][center dot]s[sup [minus]1]). For unstressed plants, 20 % of the carbon fixed in photosynthesis was reemitted as isoprene at 1000 [mu]mol photons[center dot]m[sup [minus]2][center dot]S[sup [minus]1]. Following the relief of water stress, photosynthesis recovered to the prestress rate but isoprene emission increased up to five times the prestress rate. At 1000 [mu]mol photons[center dot]M[sup [minus]2][center dot]S[sup [minus]1] and 35[degrees]C, 67% of the carbon fixed in photosynthesis was reemitted as isoprene eight days after water stress. For some leaves the rate of isoprene emission exceeded 500 nmol[center dot]M[sup [minus]2][center dot]S[sup [minus]1], substantially higher than ever reported before. Leaves of plants grown at less than 20[degrees]C did not make isoprene until an inductive treatment was given. Withholding water from plants or keeping leaves at 30[degrees]C induced isoprene emission. The observation of rapid and dramatic changes in the rate of isoprene emission from leaves in response to water stress and temperature may indicate that isoprene emission improves the ability of plants to cope with these conditions. With the new information on temperature and water stress effects on isoprene emission we speculate on possible reasons for isoprene emission from plants.

Sharkey, T.D.; Loreto, F. (Univ. of Wisconsin, Madison (United States))

1993-05-01T23:59:59.000Z

299

Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors  

SciTech Connect (OSTI)

Background: The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of Generation IV reactor systems such as supercritical water reactors (SCWR) for higher efficiency, improved performance and operation, design simplification, enhanced safety and reduced waste and cost. The objective of this Korean / US / laboratory / university collaboration of coupled fundamental computational and experimental studies is to develop the supporting knowledge needed for improved predictive techniques for use in the technology development of Generation IV reactor concepts and their passive safety systems. The present study emphasizes SCWR concepts in the Generation IV program.

D.M. McEligot; K. G. Condie; G. E. McCreery; H. M. McIlroy; R. J. Pink; L.E. Hochreiter; J.D. Jackson; R.H. Pletcher; B.L. Smith; P. Vukoslavcevic; J.M. Wallace; J.Y. Yoo; J.S. Lee; S.T. Ro; S.O. Park

2005-10-01T23:59:59.000Z

300

Light Water Reactor Sustainability Program Risk-Informed Safety Margins Characterization (RISMC) PathwayTechnical Program Plan  

SciTech Connect (OSTI)

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly over-design portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as safety margin. Historically, specific safety margin provisions have been formulated, primarily based on engineering judgment.

Curtis Smith; Cristian Rabiti; Richard Martineau

2012-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" 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

Acoustic Emission and Guided Ultrasonic Waves for Detection and Continuous Monitoring of Cracks in Light Water Reactor Components  

SciTech Connect (OSTI)

Acoustic emission (AE) and guided ultrasonic waves (GUW) are considered for continuous monitoring and detection of cracks in Light Water Reactor (LWR) components. In this effort, both techniques are applied to the detection and monitoring of fatigue crack growth in a full scale pipe component. AE results indicated crack initiation and rapid growth in the pipe, and significant GUW responses were observed in response to the growth of the fatigue crack. After initiation, the crack growth was detectable with AE for approximately 20,000 cycles. Signals associated with initiation and rapid growth where distinguished based on total rate of activity and differences observed in the centroid frequency of hits. An intermediate stage between initiation and rapid growth was associated with significant energy emissions, though few hits. GUW exhibit a nearly monotonic trend with crack length with an exception of measurements obtained at 41 mm and 46 mm.

Meyer, Ryan M.; Coble, Jamie B.; Ramuhalli, Pradeep; Watson, Bruce E.; Cumblidge, Stephen E.; Doctor, Steven R.; Bond, Leonard J.

2012-06-28T23:59:59.000Z

302

The Application of Structural Materials Data From the BN-350 Fast Reactor to Life Extension of Light Water Reactors  

SciTech Connect (OSTI)

This paper describes the results of investigations of 08Cr16Ni11Mo3 (AISI 316 steel analogue) austenitic stainless steel irradiated in BN-350 breeder reactor at irradiation conditions close to that for Light Water Reactor (LWR) Internals. The pores were found in 08Cr16Ni11Mo3 steel irradiated at temperature 280 deg. C up to rather low damage 1.3 dpa and with dose rate 3.9 x 10{sup -9} dpa/s. There were obtained dose rate dependencies of yield strength, ultimate strength and ductility for 08Cr16Ni11Mo3 steel irradiated up to 7-13 dpa at 302-311 deg. C. These dependencies show a decrease in both yield strength and ultimate strength when dose rate decreases. There was observed an apparent decrease in total elongation when dose rate decreases, which was presumably connected with the pores formation in the steel at low dose rates. (authors)

Romanenko, O.G. [Nuclear Technology Safety Center, Liza Chaikina 4, Almaty 050020 (Kazakhstan); Kislitsin, S.B.; Maksimkin, O.P. [Institute of Nuclear Physics, 1 Ibragimova St., Almaty, 050032 (Kazakhstan); Shiganakov, Sh.B.; Chumakov, Ye.V. [Kazakhstan Atomic Energy Committee, Liza Chaikina 4, Almaty (Kazakhstan); Dumchev, I.V. [MAEC Kazatomprom, Aktau, 130000 (Kazakhstan)

2006-07-01T23:59:59.000Z

303

Computerized operating procedures for shearing and dissolution of segments from LWBR (Light Water Breeder Reactor) fuel rods  

SciTech Connect (OSTI)

This report presents two detailed computerized operating procedures developed to assist and control the shearing and dissolution of irradiated fuel rods. The procedures were employed in the destructive analysis of end-of-life fuel rods from the Light Water Breeder Reactor (LWBR) that was designed by the Westinghouse Electric Corporation Bettis Atomic Power Laboratory. Seventeen entire fuel rods from the end-of-life core of the LWBR were sheared into 169 precisely characterized segments, and more than 150 of these segments were dissolved during execution of the LWBR Proof-of-Breeding (LWBR-POB) Analytical Support Project at Argonne National Laboratory. The procedures illustrate our approaches to process monitoring, data reduction, and quality assurance during the LWBR-POB work.

Osudar, J.; Deeken, P.G.; Graczyk, D.G.; Fagan, J.E.; Martino, F.J.; Parks, J.E.; Levitz, N.M.; Kessie, R.W.; Leddin, J.M.

1987-05-01T23:59:59.000Z

304

Columbia River System Operation Review : Final Environmental Impact Statement, Appendix O: Economic and Social Impact.  

SciTech Connect (OSTI)

This Appendix O of the Final Environmental Impact Statement for the Columbia River System measures the economic and social effects of the alternative system operation strategies and includes both geographic and methodology components. Areas discussed in detail include the following: purpose, scope and process; an economic history of the Columbia River Basin and its use today including the Columbia River and Socio-economic development in the Northwest and Major uses of the River System; Analysis procedures and methodologies including national economic evaluation, the concepts, analysis of assumptions, analysis for specific river uses, water quality, Regional evaluation, analysis, and social impacts; alternatives and impacts including implementation costs, andromous fish, resident fish and wildlife, flood control, irrigation and municipal and industrial water supply, navigation impacts, power, recreation, annual costs, regional economic analysis. Extensive comparison of alternatives is included.

Columbia River System Operation Review (U.S.)

1995-11-01T23:59:59.000Z

305

Fundamental Understanding of Crack Growth in Structural Components of Generation IV Supercritical Light Water Reactors  

SciTech Connect (OSTI)

This work contributes to the design of safe and economical Generation-IV Super-Critical Water Reactors (SCWRs) by providing a basis for selecting structural materials to ensure the functionality of in-vessel components during the entire service life. During the second year of the project, we completed electrochemical characterization of the oxide film properties and investigation of crack initiation and propagation for candidate structural materials steels under supercritical conditions. We ranked candidate alloys against their susceptibility to environmentally assisted degradation based on the in situ data measure with an SRI-designed controlled distance electrochemistry (CDE) arrangement. A correlation between measurable oxide film properties and susceptibility of austenitic steels to environmentally assisted degradation was observed experimentally. One of the major practical results of the present work is the experimentally proven ability of the economical CDE technique to supply in situ data for ranking candidate structural materials for Generation-IV SCRs. A potential use of the CDE arrangement developed ar SRI for building in situ sensors monitoring water chemistry in the heat transport circuit of Generation-IV SCWRs was evaluated and proved to be feasible.

Iouri I. Balachov; Takao Kobayashi; Francis Tanzella; Indira Jayaweera; Palitha Jayaweera; Petri Kinnunen; Martin Bojinov; Timo Saario

2004-11-17T23:59:59.000Z

306

THE UNIVERSITY OF BRITISH COLUMBIA Curriculum Vitae for Faculty Members  

E-Print Network [OSTI]

THE UNIVERSITY OF BRITISH COLUMBIA Curriculum Vitae for Faculty Members Date: May 5. 2009 Initials-1980 University of British Columbia M Sc Physics 1980-1982 University of British Columbia Ph D Physics 1982 The University of British Columbia Study Leave 07/2007-06/2008 8. TEACHING (a) Areas of special interest

Karczmarek, Joanna

307

GUIDE TO THE LIBRARIES COLUMBIA UNIVERSITY LIBR ARIES 201011  

E-Print Network [OSTI]

GUIDE TO THE LIBRARIES COLUMBIA UNIVERSITY LIBR ARIES 2010­11 #12;WELCOME James G. Neal VICE PRESIDENT FOR INFORMATION SERVICES AND UNIVERSITY LIBRARIAN LIBRARY INFORMATION OFFICE (LIO) www.columbia OF DISABILITY SERVICES (ODS) www.health.columbia.edu/docs/services/ods Columbia University is committed

Lazar, Aurel A.

308

Columbia University 1754 Royal Charter establishes King's College  

E-Print Network [OSTI]

Columbia University FACTS 2013 1 Timeline 1754 Royal Charter establishes King's College under King an affiliate of Columbia. 1896 Trustees formally designate Columbia as a university. 1897 The University moves of Social Work, est. 1898, Dean Jeanette C. Takamura #12;Columbia University FACTS 2013 2 Affiliated

Yang, Junfeng

309

Columbia University The Italian Academy for Advanced Studies  

E-Print Network [OSTI]

Columbia University The Italian Academy for Advanced Studies ITALY AT COLUMBIA A SERIES OF FREE PUBLIC LECTURES BY COLUMBIA UNIVERSITY PROFESSORS MONDAY, October 1 at 1:10 PM HOLGER A. KLEIN The Art in the Western Middle Ages (Columbia University Press, 2011). Neslihan enocak received her PhD at Bilkent

Lazar, Aurel A.

310

Columbia University Statistics Tian Zheng and Zhiliang Ying  

E-Print Network [OSTI]

Columbia University Statistics Tian Zheng and Zhiliang Ying Statistical Activities at Columbia Leung Lai for their comments and suggestions on earlier versions of this chapter. Columbia University at Columbia University to support the emerging statistical needs of the war effort (Rees 1980). Over the 39

Columbia University

311

Direct Water Splitting under Visible Light with Nanostructured Hematite and WO3 Photoanodes and a GaInP2 Photocathode  

SciTech Connect (OSTI)

A p-GaInP{sub 2} photocathode was paired with nanostructured hematite and tungsten trioxide photoanodes to investigate the utility of these systems for direct water splitting under visible light illumination. For the hematite system, under illumination at open-circuit conditions, the potential of hematite shifts cathodically and that of the GaInP{sub 2} shifts anodically. Under short-circuit condition and visible light illumination, the combination of the two photoelectrodes can split water, though with a very low rate of a few {micro}A/cm{sup 2} even at an intensity of 1 W/cm{sup 2}. It was determined that the very low photocurrent from the hematite nanorod photoelectrode limits the short-circuit current of the two-photoelectrode combination. Similar potential shifts were observed with the nanostructured WO{sub 3}/GaInP{sub 2} combination. However, at light intensities below 0.2 W/cm{sup 2}, the short-circuited combination would not split water due to an insufficient potential difference. Above 0.2 W/cm{sup 2}, the combination can split water under visible light, with {approx}20 {micro}A/cm{sup 2} obtained at 1 W/cm{sup 2}. A linear photocurrent-light intensity relationship was observed and was attributed to efficient charge transfer and a low recombination of the charge carriers. The bandgap and the associated absorption limit of WO{sub 3} remain a challenge for a higher efficiency system.

Wang, H.; Deutsch, T.; Turner, J. A.

2008-01-01T23:59:59.000Z

312

Columbia Earth Engineering Center http://www.seas.columbia.edu/earth/Chan.html[8/19/2009 3:16:12 PM  

E-Print Network [OSTI]

Columbia Earth Engineering Center http://www.seas.columbia.edu/earth/Chan.html[8/19/2009 3:16:12 PM Woman Scientist Award 1997 #12;Columbia Earth Engineering Center http://www.seas.columbia.edu/earth

313

An economic analysis of a light and heavy water moderated reactor synergy: burning americium using recycled uranium  

SciTech Connect (OSTI)

An economic analysis is presented for a proposed synergistic system between 2 nuclear utilities, one operating light water reactors (LWR) and another running a fleet of heavy water moderated reactors (HWR). Americium is partitioned from LWR spent nuclear fuel (SNF) to be transmuted in HWRs, with a consequent averted disposal cost to the LWR operator. In return, reprocessed uranium (RU) is supplied to the HWRs in sufficient quantities to support their operation both as power generators and americium burners. Two simplifying assumptions have been made. First, the economic value of RU is a linear function of the cost of fresh natural uranium (NU), and secondly, plutonium recycling for a third utility running a mixed oxide (MOX) fuelled reactor fleet has been already taking place, so that the extra cost of americium recycling is manageable. We conclude that, in order for this scenario to be economically attractive to the LWR operator, the averted disposal cost due to partitioning americium from LWR spent fuel must exceed 214 dollars per kg, comparable to estimates of the permanent disposal cost of the high level waste (HLW) from reprocessing spent LWR fuel. (authors)

Wojtaszek, D.; Edwards, G. [Atomic Energy of Canada Ltd., Chalk River Laboratories, Chalk River, Ontario (Canada)

2013-07-01T23:59:59.000Z

314

Columbia University Medical Center CUMC Home | Columbia University | Jobs at CUMC | Contact CUMC | Find People Search CUMC  

E-Print Network [OSTI]

Columbia University Medical Center CUMC Home | Columbia University | Jobs at CUMC | Contact CUMC and Molecular Biophysics and Pathology at Columbia University Medical Center and recipient of the 2004 Nobel University | Affiliated with New York-Presbyterian Hospital | Comments | Text-Only Version http://www.cumc.columbia

315

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Charges Relating to Nuclear Reactor Safety," 1976, availablestudies of light-water nuclear reactor safety, emphasizingstudies of overall nuclear reactor safety have been

Nero, A.V.

2010-01-01T23:59:59.000Z

316

Mechanism of Irradiation Assisted Cracking of Core Components in Light Water Reactors  

SciTech Connect (OSTI)

The overall goal of the project is to determine the mechanism of irradiation assisted stress corrosion cracking (IASCC). IASCC has been linked to hardening, microstructural and microchemical changes during irradiation. Unfortunately, all of these changes occur simultaneously and at similar rates during irradiation, making attribution of IASCC to any one of these features nearly impossible to determine. The strategy set forth in this project is to develop means to separate microstructural from microchemical changes to evaluate each separately for their effect on IASCC. In the first part, post irradiation annealing (PIA) treatments are used to anneal the irradiated microstructure, leaving only radiation induced segregation (RIS) for evaluation for its contribution to IASCC. The second part of the strategy is to use low temperature irradiation to produce a radiation damage dislocation loop microstructure without radiation induced segregation in order to evaluate the effect of the dislocation microstructure alone. A radiation annealing model was developed based on the elimination of dislocation loops by vacancy absorption. Results showed that there were indeed, time-temperature annealing combinations that leave the radiation induced segregation profile largely unaltered while the dislocation microstructure is significantly reduced. Proton irradiation of 304 stainless steel irradiated with 3.2 MeV protons to 1.0 or 2.5 dpa resulted in grain boundary depletion of chromium and enrichment of nickel and a radiation damaged microstructure. Post irradiation annealing at temperatures of 500 ? 600C for times of up to 45 min. removed the dislocation microstructure to a greater degree with increasing temperatures, or times at temperature, while leaving the radiation induced segregation profile relatively unaltered. Constant extension rate tensile (CERT) experiments in 288C water containing 2 ppm O2 and with a conductivity of 0.2 mS/cm and at a strain rate of 3 x 10-7 s-1 showed that the IASCC susceptibility, as measured by the crack length per unit strain, decreased with very short anneals and was almost completely removed by an anneal at 500C for 45 min. This annealing treatment removed about 15% of the dislocation microstructure and the irradiation hardening, but did not affect the grain boundary chromium depletion or nickel segregation, nor did it affect the grain boundary content of other minor impurities. These results indicate that RIS is not the sole controlling feature of IASCC in irradiated stainless steels in normal water chemistry. The isolation of the irradiated microstructure was approached using low temperature irradiation or combinations of low and high temperature irradiations to achieve a stable, irradiated microstructure without RIS. Experiments were successful in achieving a high degree of irradiation hardening without any evidence of RIS of either major or minor elements. The low temperature irradiations to doses up to 0.3 dpa at T<75C were also very successful in producing hardening to levels considerably above that for irradiations conducted under nominal conditions of 1 dpa at 360C. However, the microstructure consisted of an extremely fine dispersion of defect clusters of sizes that are not resolvable by either transmission electron microscopy (TEM) or small angle x-ray scattering (SAXS). The microstructure was not stable at the 288C IASCC test temperature and resulted in rapid reduction of hardening and presumably, annealing of the defect clusters at this temperature as well. Nevertheless, the annealing studies showed that treatments that resulted in significant decreases in the hardening produced small changes in the dislocation microstructure that were confined to the elimination of the finest of loops (~1 nm). These results substantiate the importance of the very fine defect microstructure in the IASCC process. The results of this program provide the first definitive evidence that RIS is not the sole controlling factor in the irradiation assisted stress corrosion cracking of austenitic stain

Gary S. Was; Michael Atzmon; Lumin Wang

2003-04-28T23:59:59.000Z

317

Protocols for Monitoring Habitat Restoration Projects in the Lower Columbia River and Estuary  

SciTech Connect (OSTI)

Protocols for monitoring salmon habitat restoration projects are essential for the U.S. Army Corps of Engineers' environmental efforts in the Columbia River estuary. This manual provides state-of-the science data collection and analysis methods for landscape features, water quality, and fish species composition, among others.

Roegner, G. Curtis; Diefenderfer, Heida L.; Borde, Amy B.; Thom, Ronald M.; Dawley, Earl M.; Whiting, Allan H.; Zimmerman, Shon A.; Johnson, Gary E.

2008-04-25T23:59:59.000Z

318

SECTION 29 Table of Contents 29 Upper Columbia Subbasin Overview ...........................................................2  

E-Print Network [OSTI]

Description 29.2.1 Drainage Area The Upper Columbia Subbasin incorporates five water resource inventory areas,000 acres of land was inundated (Merker 1993). The watershed area that comprises the Subbasin resident fish. #12;29-4 0 1000 2000 3000 4000 5000 6000 7000 8000 January February M arch April M ay June

319

E-Print Network 3.0 - assessment columbia river Sample Search...  

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

for: assessment columbia river Page: << < 1 2 3 4 5 > >> 1 352000 Columbia river Basin Fish and Wildlife Program "...the Council is adopting Summary: 352000 Columbia river Basin...

320

COLUMBIA RIVER TREATY ENTITY AGREEMENT ON THE  

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

AGREEMENT (10NTSSA) The Bonneville Power Administration (BPA) and the British Columbia Hydro and Power Authority (B.C. Hydro) have signed an agreement relating to the use of...

Note: This page contains sample records for the topic "light columbia water" 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.
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to obtain the most current and comprehensive results.


321

COLUMBIA RIVER TREATY ENTITY AGREEMENT ON THE  

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

AGREEMENT (09NTSSA) The Bonneville Power Administration @PA) and the British Columbia Hydro and Power Authority (B.C. Hydro) have signed an agreement relating to the use of...

322

COLUMBIA RIVER TREATY ENTITY AGREEMENT ON THE  

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

AGREEMENT (1 1NTSSA) The Bonneville Power Administration (BPA) and the British Columbia Hydro and Power Authority (B.C. Hydro) have signed an agreement relating to the use of...

323

COLUMBIA RIVER TREATY ENTITY AGREEMENT ON THE  

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

AGREEMENT (12NTSSA) The Bonneville Power Administration (BP A) and the British Columbia Hydro and Power Authority (B.C. Hydro) have signed an agreement relating to the use of...

324

Lower Columbia River Estuary Partnership. The  

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

of land on the north side of the Columbia River in Cowlitz County, Wash., to protect fish habitat. An additional 75 acres of land will be donated by the Port of Longview. BPA...

325

Review of experiments to evaluate the ability of electrical heater rods to simulate nuclear fuel rod behavior during postulated loss-of-coolant accidents in light water reactors  

SciTech Connect (OSTI)

Issues related to using electrical fuel rod simulators to simulate nuclear fuel rod behavior during postulated loss-of-coolant accident (LOCA) conditions in light water reactors are summarized. Experimental programs which will provide a data base for comparing electrical heater rod and nuclear fuel rod LOCA responses are reviewed.

McPherson, G D; Tolman, E L

1980-01-01T23:59:59.000Z

326

Evaluation of weapons-grade mixed oxide fuel performance in U.S. Light Water Reactors using COMETHE 4D release 23 computer code  

E-Print Network [OSTI]

The COMETHE 4D Release 23 computer code was used to evaluate the thermal, chemical and mechanical performance of weapons-grade MOX fuel irradiated under U.S. light water reactor typical conditions. Comparisons were made to and UO? fuels exhibited...

Bellanger, Philippe

2012-06-07T23:59:59.000Z

327

Shielding analysis for the 300 area light water reactor spent nuclear fuel within a modified multi-canister overpack canister in a modified multi-canister overpack cask  

SciTech Connect (OSTI)

Spent light water reactor fuel is to be moved out of the 324 Building. It is anticipated that intact fuel assemblies will be loaded in a modified Multi-Canister Overpack Canister, which in turn will be placed in an Overpack Transportation Cask. An estimate of gamma ray dose rates from a transportation cask is desired.

Gedeon, S.R.

1997-04-11T23:59:59.000Z

328

EIS-0163: 1992 Columbia River Salmon Flow Measures Options Analysis/EIS  

Broader source: Energy.gov [DOE]

The U.S. Army Corps of Engineers Walla Walla District prepared this statement to analyze four general alternatives to modify the flow of water in the lower Columbia-Snake River in order to help anadromous fish migrate past eight multipurpose Federal dams. The U.S. Department of Energys Bonneville Power Administration served as a cooperating agency due to its key role in direct operation of the integrated and coordinated Columbia-Snake River System, and adopted this statement on February 10, 1992.

329

DC WRRC Report No. 92 Directory of University Water  

E-Print Network [OSTI]

DC WRRC Report No. 92 Directory of University Water Expertise in the District of Columbia DC Water Avenue, NW Washington, DC 20008 #12;DC WRRC Report No. 92 Directory of University Water Expertise of Columbia 4200 Connecticut Avenue, NW Washington, DC 20008 #12;DC-WRRC Report No. 92 DIRECTORY OF UNIVERSITY

District of Columbia, University of the

330

Transmutation Performance Analysis for Inert Matrix Fuels in Light Water Reactors and Computational Neutronics Methods Capabilities at INL  

SciTech Connect (OSTI)

The urgency for addressing repository impacts has grown in the past few years as a result of Spent Nuclear Fuel (SNF) accumulation from commercial nuclear power plants. One path that has been explored by many is to eliminate the transuranic (TRU) inventory from the SNF, thus reducing the need for additional long term repository storage sites. One strategy for achieving this is to burn the separated TRU elements in the currently operating U.S. Light Water Reactor (LWR) fleet. Many studies have explored the viability of this strategy by loading a percentage of LWR cores with TRU in the form of either Mixed Oxide (MOX) fuels or Inert Matrix Fuels (IMF). A task was undertaken at INL to establish specific technical capabilities to perform neutronics analyses in order to further assess several key issues related to the viability of thermal recycling. The initial computational study reported here is focused on direct thermal recycling of IMF fuels in a heterogeneous Pressurized Water Reactor (PWR) bundle design containing Plutonium, Neptunium, Americium, and Curium (IMF-PuNpAmCm) in a multi-pass strategy using legacy 5 year cooled LWR SNF. In addition to this initial high-priority analysis, three other alternate analyses with different TRU vectors in IMF pins were performed. These analyses provide comparison of direct thermal recycling of PuNpAmCmCf, PuNpAm, PuNp, and Pu. The results of this infinite lattice assembly-wise study using SCALE 5.1 indicate that it may be feasible to recycle TRU in this manner using an otherwise typical PWR assembly without violating peaking factor limits.

Michael A. Pope; Samuel E. Bays; S. Piet; R. Ferrer; Mehdi Asgari; Benoit Forget

2009-05-01T23:59:59.000Z

331

Advanced Light Water Reactor Plants System 80+{trademark} Design Certification Program. Annual progress report, October 1, 1992--September 30, 1993  

SciTech Connect (OSTI)

The purpose of this report is to provide a status of the progress that was made towards Design Certification of System 80+{trademark} during the US government`s 1993 fiscal year. The System 80+ Advanced Light Water Reactor (ALWR) is a 3931 MW{sub t} (1350 MWe) Pressurized Water Reactor (PWR). The design consists of an essentially complete plant. It is based on evolutionary improvements to the Standardized System 80 nuclear steam supply system in operation at Palo Verde Units 1, 2, and 3, and the Duke Power Company P-81 balance-of-plant (BOP) that was designed and partially constructed at the Cherokee plant site. The System 80/P-81 original design has been substantially enhanced to increase conformance with the EPRI ALWR Utility Requirements Document (URD). Some design enhancements incorporated in the System 80+ design are included in the four units currently under construction in the Republic of Korea. These units form the basis of the Korean standardization program. The full System 80+ standard design has been offered to the Republic of China, in response to their recent bid specification. The ABB-CE Standard Safety Analysis Report (CESSAR-DC) was submitted to the NRC and a Draft Safety Evaluation Report was issued by the NRC in October 1992. CESSAR-DC contains the technical basis for compliance with the EPRI URD for simplified emergency planning. The Nuclear Steam Supply System (NSSS) is the standard ABB-Combustion Engineering two-loop arrangement with two steam generators, two hot legs and four cold legs each with a reactor coolant pump. The System 80+ standard plant includes a sperical steel containment vessel which is enclosed in a concrete shield building, thus providing the safety advantages of a dual containment.

Not Available

1993-12-31T23:59:59.000Z

332

Isotopic Tracking of Hanford 300 Area Derived Uranium in the Columbia River  

SciTech Connect (OSTI)

Our objectives in this study are to quantify the discharge rate of uranium (U) to the Columbia River from the Hanford Site's 300 Area, and to follow that U down river to constrain its fate. Uranium from the Hanford Site has variable isotopic composition due to nuclear industrial processes carried out at the site. This characteristic makes it possible to use high-precision isotopic measurements of U in environmental samples to identify even trace levels of contaminant U, determine its sources, and estimate discharge rates. Our data on river water samples indicate that as much as 3.2 kg/day can enter the Columbia River from the 300 Area, which is only a small fraction of the total load of dissolved natural background U carried by the Columbia River. This very low-level of Hanford derived U can be discerned, despite dilution to < 1 percent of natural background U, 350 km downstream from the Hanford Site. These results indicate that isotopic methods can allow the amounts of U from the 300 Area of the Hanford Site entering the Columbia River to be measured accurately to ascertain whether they are an environmental concern, or are insignificant relative to natural uranium background in the Columbia River.

Christensen, John N.; Dresel, P. Evan; Conrad, Mark E.; Patton, Gregory W.; DePaolo, Donald J.

2010-10-31T23:59:59.000Z

333

Prospects for and problems of using light-water supercritical-pressure coolant in nuclear reactors in order to increase the efficiency of the nuclear fuel cycle  

SciTech Connect (OSTI)

Trends in the development of the power sector of the Russian and world power industries both at present time and in the near future are analyzed. Trends in the rise of prices for reserves of fossil and nuclear fuels used for electricity production are compared. An analysis of the competitiveness of electricity production at nuclear power plants as compared to the competitiveness of electricity produced at coal-fired and natural-gas-fired thermal power plants is performed. The efficiency of the open nuclear fuel cycle and various versions of the closed nuclear fuel cycle is discussed. The requirements on light-water reactors under the scenario of dynamic development of the nuclear power industry in Russia are determined. Results of analyzing the efficiency of fuel utilization for various versions of vessel-type light-water reactors with supercritical coolant are given. Advantages and problems of reactors with supercritical-pressure water are listed.

Alekseev, P. N.; Semchenkov, Yu. M.; Sedov, A. A., E-mail: sedov@dhtp.kial.ru; Subbotin, S. A.; Chibinyaev, A. V. [Russian Research Centre Kurchatov Institute (Russian Federation)

2011-12-15T23:59:59.000Z

334

Human-In-The-Loop Simulation in Support of Long-Term Sustainability of Light Water Reactors  

SciTech Connect (OSTI)

Reliable instrumentation, information, and control systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration. The NPP owners and operators realize that this analog technology represents a significant challenge to sustaining the operation of the current fleet of NPPs. Beyond control systems, new technologies are needed to monitor and characterize the effects of aging and degradation in critical areas of key structures, systems, and components. The objective of the efforts sponsored by the U.S. Department of Energy is to develop, demonstrate, and deploy new digital technologies for II&C architectures and provide monitoring capabilities to ensure the continued safe, reliable, and economic operation of the nations NPPs.

Bruce P Hallbert

2015-01-01T23:59:59.000Z

335

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

SciTech Connect (OSTI)

The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin next year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.

Smith, Cyrus M [ORNL; Nanstad, Randy K [ORNL; Clayton, Dwight A [ORNL; Matlack, Katie [Georgia Institute of Technology; Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL); Light, Glenn [Southwest Research Institute, San Antonio

2012-09-01T23:59:59.000Z

336

A global approach of the representativity concept: Application on a high-conversion light water reactor MOX lattice case  

SciTech Connect (OSTI)

The development of new types of reactor and the increase in the safety specifications and requirements induce an enhancement in both nuclear data knowledge and a better understanding of the neutronic properties of the new systems. This enhancement is made possible using ad hoc critical mock-up experiments. The main difficulty is to design these experiments in order to obtain the most valuable information. Its quantification is usually made by using representativity and transposition concepts. These theories enable to extract some information about a quantity of interest (an integral parameter) on a configuration, but generally a posteriori. This paper presents a more global approach of this theory, with the idea of optimizing the representativity of a new experiment, and its transposition a priori, based on a multiparametric approach. Using a quadratic sum, we show the possibility to define a global representativity which permits to take into account several quantities of interest at the same time. The maximization of this factor gives information about all quantities of interest. An optimization method of this value in relation to technological parameters (over-clad diameter, atom concentration) is illustrated on a high-conversion light water reactor MOX lattice case. This example tackles the problematic of plutonium experiment for the plutonium aging and a solution through the optimization of both the over-clad and the plutonium content. (authors)

Santos, N. D.; Blaise, P.; Santamarina, A. [CEA, DEN/DER/SPRC Cadarache, F-13108 Saint Paul-lez-Durance (France)

2013-07-01T23:59:59.000Z

337

Extended-burnup LWR (light-water reactor) fuel: The amount, characteristics, and potential effects on interim storage  

SciTech Connect (OSTI)

The results of a study on extended-burnup, light-water reactor (LWR) spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory for the US Department of Energy (DOE). The purpose of the study was to collect and evaluate information on the status of in-reactor performance and integrity of extended-burnup LWR fuel and initiate the investigation of the effects of extending fuel burnup on the subsequent handling, interim storage, and other operations (e.g., rod consolidation and shipping) associated with the back end of the fuel cycle. The results of this study will aid DOE and the nuclear industry in assessing the effects on waste management of extending the useful in-reactor life of nuclear fuel. The experience base with extended-burnup fuel is now substantial and projections for future use of extended-burnup fuel in domestic LWRs are positive. The basic performance and integrity of the fuel in the reactor has not been compromised by extending the burnup, and the potential limitations for further extending the burnup are not severe. 104 refs., 15 tabs.

Bailey, W.J.

1989-03-01T23:59:59.000Z

338

Separation and Recovery of Uranium Metal from Spent Light Water Reactor Fuel via Electrolytic Reduction and Electrorefining  

SciTech Connect (OSTI)

A series of bench-scale experiments was performed in a hot cell at Idaho National Laboratory to demonstrate the separation and recovery of uranium metal from spent light water reactor (LWR) oxide fuel. The experiments involved crushing spent LWR fuel to particulate and separating it from its cladding. Oxide fuel particulate was then converted to metal in a series of six electrolytic reduction runs that were performed in succession with a single salt loading of molten LiCl 1 wt% Li2O at 650 C. Analysis of salt samples following the series of electrolytic reduction runs identified the diffusion of select fission products from the spent fuel to the molten salt electrolyte. The extents of metal oxide conversion in the post-test fuel were also quantified, including a nominal 99.7% conversion of uranium oxide to metal. Uranium metal was then separated from the reduced LWR fuel in a series of six electrorefining runs that were performed in succession with a single salt loading of molten LiCl-KCl-UCl3 at 500 C. Analysis of salt samples following the series of electrorefining runs identified additional partitioning of fission products into the molten salt electrolyte. Analyses of the separated uranium metal were performed, and its decontamination factors were determined.

S. D. Herrmann; S. X. Li

2010-09-01T23:59:59.000Z

339

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

SciTech Connect (OSTI)

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

L.C. Hulstrom

2010-08-11T23:59:59.000Z

340

Columbia River System Operation Review : Final Environmental Impact Statement, Appendix D: Exhibits.  

SciTech Connect (OSTI)

The Columbia River and its tributaries are the primary water system in the Pacific Northwest, draining some 219,000 square miles in seven states and another 39,500 square miles in British Columbia. Beginning in the 1930`s, the Columbia River has been significantly modified by construction of 30 major dams on the river and its tributaries, along with dozens of non-Federal projects. Construction and subsequent operation of these water development projects have contributed to eight primary uses of the river system, including navigation, flood control, irrigation, electric power generation, fish migration, fish and wildlife habitat, recreation, and water supply and quality considerations. Increasing stress on the water development of the Columbia River and its tributaries has led primary Federal agencies to undertake intensive analysis and evaluation of the operation of these projects. These agencies are the U.S. Army Corps of Engineers and the Bureau of Reclamation, who operate the large Federal dams on the river, and the Bonneville Power Administration who sells the power generated at the dams. This review, termed the System Operation Review (SOR), has as its ultimate goal to define a strategy for future operation of the major Columbia River projects which effectively considers the needs of all river uses. This volume, Appendix D: Cultural resources appendix, Technical imput includes the following: Development of geomorphology based framework for cultural resources management, Dworshak Reservoir, Idaho; Impact profiles for SOR reservoirs; comments from the following Native American tribes: Burns Paiute Tribe; Coville Confederated Tribes; Confederated Tribes of the Warm Springs Indian Reservation; Confederated Tribes and bands of the Yakama Indian Nation (comments); Nez Perce Tribe; Coeur D`Alene Tribe; Spokane Tribe of Indians; The confederated Tribes of the Umatilla Indian Reservation.

Columbia River System Operation Review (U.S.)

1995-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" from the National Library of EnergyBeta (NLEBeta).
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341

Assessment of Possible Cycle Lengths for Fully-Ceramic Micro-Encapsulated Fuel-Based Light Water Reactor Concepts  

SciTech Connect (OSTI)

The tri-isotropic (TRISO) fuel developed for High Temperature reactors is known for its extraordinary fission product retention capabilities [1]. Recently, the possibility of extending the use of TRISO particle fuel to Light Water Reactor (LWR) technology, and perhaps other reactor concepts, has received significant attention [2]. The Deep Burn project [3] currently focuses on once-through burning of transuranic fissile and fissionable isotopes (TRU) in LWRs. The fuel form for this purpose is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the TRISO fuel particle design from high temperature reactor technology, but uses SiC as a matrix material rather than graphite. In addition, FCM fuel may also use a cladding made of a variety of possible material, again including SiC as an admissible choice. The FCM fuel used in the Deep Burn (DB) project showed promising results in terms of fission product retention at high burnup values and during high-temperature transients. In the case of DB applications, the fuel loading within a TRISO particle is constituted entirely of fissile or fissionable isotopes. Consequently, the fuel was shown to be capable of achieving reasonable burnup levels and cycle lengths, especially in the case of mixed cores (with coexisting DB and regular LWR UO2 fuels). In contrast, as shown below, the use of UO2-only FCM fuel in a LWR results in considerably shorter cycle length when compared to current-generation ordinary LWR designs. Indeed, the constraint of limited space availability for heavy metal loading within the TRISO particles of FCM fuel and the constraint of low (i.e., below 20 w/0) 235U enrichment combine to result in shorter cycle lengths compared to ordinary LWRs if typical LWR power densities are also assumed and if typical TRISO particle dimensions and UO2 kernels are specified. The primary focus of this summary is on using TRISO particles with up to 20 w/0 enriched uranium kernels loaded in Pressurized Water Reactor (PWR) assemblies. In addition to consideration of this 'naive' use of TRISO fuel in LWRs, several refined options are briefly examined and others are identified for further consideration including the use of advanced, high density fuel forms and larger kernel diameters and TRISO packing fractions. The combination of 800 {micro}m diameter kernels of 20% enriched UN and 50% TRISO packing fraction yielded reactivity sufficient to achieve comparable burnup to present-day PWR fuel.

R. Sonat Sen; Michael A. Pope; Abderrafi M. Ougouag; Kemal O. Pasamehmetoglu

2012-04-01T23:59:59.000Z

342

Three Pacific Coast States Join British Columbia to Combat Climate...  

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

Three Pacific Coast States Join British Columbia to Combat Climate Change Three Pacific Coast States Join British Columbia to Combat Climate Change November 6, 2013 - 12:00am...

343

Columbia River Food Webs: Developing a Broader Scientific Foundation for  

E-Print Network [OSTI]

Columbia River Food Webs: Developing a Broader Scientific Foundation for Fish and Wildlife and Conservation Council #12;i Columbia River Food Webs: Developing a Broader Scientific Foundation for Fish

344

Redeveloping or preserving public housing : the future of Columbia Point  

E-Print Network [OSTI]

Columbia Point, Boston's largest and most stigmatized public housing project, has been a focal point for public and private. investment strategies to create a new mixed-income residential community. Columbia Point provided ...

Lee, Sharon Hsueh-Jen

1981-01-01T23:59:59.000Z

345

BRITISH COLUMBIA LAND USE PLANNING: BACKCOUNTRY TOURISM PERSPECTIVES  

E-Print Network [OSTI]

BRITISH COLUMBIA LAND USE PLANNING: BACKCOUNTRY TOURISM PERSPECTIVES by Rebekah Edwards-Craig B of Research Project: British Columbia Land Use Planning: Backcountry Tourism Perspectives Supervisory, including the backcountry tourism and outdoor recreation sectors, at a disadvantage in such planning

346

University of British Columbia Physics & Astronomy Outreach Program  

E-Print Network [OSTI]

University of British Columbia Physics & Astronomy Outreach Program Faraday Show is the Outreach Department of Physics & Astronomy, University of British Columbia Email: outreach@phas.ubc.ca; Phone: 604

Karczmarek, Joanna

347

UNIVERSITY OF MISSOURI COLUMBIA College of Arts and Science  

E-Print Network [OSTI]

UNIVERSITY OF MISSOURI ­ COLUMBIA College of Arts and Science Department of German and Russian Studies · 450 Strickland Hall · Columbia, Missouri 65211 ERWERBUNG EINES MASTERS-ABSCHLUSS IN GERMAN

Greifswald, Ernst-Moritz-Arndt-Universität

348

Heavy-Section Steel Irradiation Program on irradiation effects in light-water reactor pressure vessel materials  

SciTech Connect (OSTI)

The safety of commercial light-water nuclear plants is highly dependent on the structural integrity of the reactor pressure vessel (RPV). In the absence of radiation damage to the RPV, fracture of the vessel is difficult to postulate. Exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The Heavy-Section Steel Irradiation (HSSI) Program at Oak Ridge National Laboratory, sponsored by the US Nuclear Regulatory Commission (USNRC), is assessing the effects of neutron irradiation on RPV material behavior, especially fracture toughness. The results of these and other studies are used by the USNRC in the evaluation of RPV integrity and regulation of overall nuclear plant safety. In assessing the effects of irradiation, prototypic RPV materials are characterized in the unirradiated condition and exposed to radiation under varying conditions. Mechanical property tests are conducted to provide data which can be used in the development of guidelines for structural integrity evaluations, while metallurgical examinations and mechanistic modeling are performed to improve understanding of the mechanisms responsible for embrittlement. The results of these investigations, in conjunction with results from commercial reactor surveillance programs, are used to develop a methodology for the prediction of radiation effects on RPV materials. This irradiation-induced degradation of the materials can be mitigated by thermal annealing, i.e., heating the RPV to a temperature above that of normal operation. Thus, thermal annealing and evaluation of reirradiation behavior are major tasks of the HSSI Program. This paper describes the HSSI Program activities by summarizing some past and recent results, as well as current and planned studies. 30 refs., 8 figs., 1 tab.

Nanstad, R.K.; Corwin, W.R.; Alexander, D.J.; Haggag, F.M.; Iskander, S.K.; McCabe, D.E.; Sokolov, M.A.; Stoller, R.E. [Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.

1995-07-01T23:59:59.000Z

349

Hydraulic Geometry and Microtopography of Tidal Freshwater Forested Wetlands and Implications for Restoration, Columbia River, U.S.A.  

SciTech Connect (OSTI)

The hydrologic reconnection of tidal channels, riverine floodplains, and main stem channels are among responses by ecological restoration practitioners to the increasing fragmentation and land conversion occurring in coastal and riparian zones. Design standards and monitoring of such ecological restoration depend upon the characterization of reference sites that vary within and among regions. Few locales, such as the 235 km tidal portion of the Columbia River on the West Coast U.S.A., remain in which the reference conditions and restoration responses of tidal freshwater forested wetlands on temperate zone large river floodplains can be compared. This study developed hydraulic geometry relationships for Picea sitchensis (Sitka spruce) dominated tidal forests (swamps) in the vicinity of Grays Bay on the Columbia River some 37 km from the Pacific Coast using field surveys and Light Detection and Ranging (LiDAR) data. Scaling relationships between catchment area and the parameters of channel cross-sectional area at outlet and total channel length were comparable to tidally influenced systems of San Francisco Bay and the United Kingdom. Dike breaching, culvert replacement, and tide gate replacement all affected channel cross-sectional geometry through changes in the frequency of over-marsh flows. Radiocarbon dating of buried wood provided evidence of changes in sedimentation rates associated with diking, and restoration trajectories may be confounded by historical subsidence behind dikes rendering topographical relationships with water level incomparable to reference conditions. At the same time, buried wood is influencing the development of channel morphology toward characteristics resembling reference conditions. Ecological restoration goals and practices in tidal forested wetland regions of large river floodplains should reflect the interactions of these controlling factors.

Diefenderfer, Heida L.; Coleman, Andre M.; Borde, Amy B.; Sinks, Ian A.

2008-01-01T23:59:59.000Z

350

Creciendo Juntos Plan de la Universidad de Columbia para  

E-Print Network [OSTI]

para la Escuela de Negocios de Columbia, la Escuela de Asuntos Internacionales y Públicos y la Escuela

Hone, James

351

Creciendo Juntos Plan de la Universidad de Columbia para  

E-Print Network [OSTI]

neurológicos; una nuevo local para la Escuela de Negocios de Columbia, la Escuela de Asuntos Internacionales y

Hone, James

352

THE UNIVERSITY OF BRITISH COLUMBIA The Economic Impact of The  

E-Print Network [OSTI]

THE UNIVERSITY OF BRITISH COLUMBIA The Economic Impact of The University of British Columbia on the BC Economy An update for 2013 Sudmant, Walter 9/1/2013 An update on the 2009 study of UBC's economic impact. #12;The Economic Impact of The University of British Columbia on the B.C. Economy, an update

Michelson, David G.

353

For immediate release Columbia University School of the Arts  

E-Print Network [OSTI]

For immediate release Columbia University School of the Arts Presents the Inaugural Sound Arts MFA First-Year Show New York, NY, April 28, 2014--Columbia University School of the Arts presents its sound innovation at Columbia University. The interdepartmental program was developed by Faculty from

Qian, Ning

354

University of Missouri-Columbia College of Human Environmental Sciences  

E-Print Network [OSTI]

University of Missouri-Columbia College of Human Environmental Sciences Department of Textile at the University of Missouri-Columbia as a Visiting Scholar. We have enjoyed interacting with those who have come for Scholars at the University of Missouri-Columbia. To fully comply with University procedures before formal

Taylor, Jerry

355

COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK MECHANICAL ENGINEERING 220 S. W. Mudd Mail Code 4703 with other programs at Columbia University. (1) Medical robotics: Possible research areas may include the department. COLUMBIA UNIVERSITY IS AN EQUAL OPPORTUNITY/AFFIRMATIVE ACTION EMPLOYER. #12;

Kim, Philip

356

Proposed laser ion source for the Columbia University microbeam  

E-Print Network [OSTI]

Proposed laser ion source for the Columbia University microbeam Alan W. Bigelow *, G. Randers-Pehrson, D.J. Brenner Center for Radiological Research, Columbia University, New York, NY 10032, USA Abstract analyzer 1. Introduction At Columbia University?s Radiological Re- search Accelerator Facility (RARAF

357

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies and Procedures  

E-Print Network [OSTI]

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies and Procedures Finance President's Council Page to sign cheques on behalf of the University of Northern British Columbia are hereby authorized to make use and charge to the account of the University of Northern British Columbia all instruments purporting

Bolch, Tobias

358

COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK Bulletin 20052006  

E-Print Network [OSTI]

COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK Bulletin 2005­2006 THE FU FOUNDATION SCHOOL of the people who know in the Columbia University Resource List, starting on page 232 of this bulletin. Or look Orling, René Perez, and Ken Tannenbaum. #12;COLUMBIA UNIVERSITY IN THE CITY OF NEW YORK Bulletin 2005

Hone, James

359

Columbia University College of Physicians & Surgeons Anatomical Donor Program  

E-Print Network [OSTI]

Columbia University College of Physicians & Surgeons Anatomical Donor Program Required Affidavits of Columbia University to be used for the purposes of education, research and advancement of medical science for the above named purposes. Columbia University will arrange for transportation and embalming if your body

Grishok, Alla

360

University of Northern British Columbia Posting # 12-048DR  

E-Print Network [OSTI]

University of Northern British Columbia Posting # 12-048DR University Librarian (Full Time, Term - One year) The University of Northern British Columbia (UNBC) aspires to be Canada's premier small quoting competition #12- 048DR to: Human Resources, University of Northern British Columbia, 3333

Northern British Columbia, University of

Note: This page contains sample records for the topic "light columbia water" 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

Summary of the University of Northern British Columbia Pension Plan  

E-Print Network [OSTI]

Summary of the University of Northern British Columbia Pension Plan July 2006 62354-G my plan #12;Summary of the University of Northern British Columbia Pension Plan Page 2 Summary Of The University Of Northern British Columbia Pension Plan TABLE OF CONTENTS INTRODUCTION

Northern British Columbia, University of

362

Columbia University In The City of New York  

E-Print Network [OSTI]

Columbia University In The City of New York Columbia Video Network Application for Certificate Background- List all Higher Education institutions attended: College/University Location Major/Field of Study. __________________________________ _____________________________ Signature Date Columbia Video Network CVN Official Use Only: Decision: Accept/Reject (circle) Decision Date

Yang, Junfeng

363

THE UNIVERSITY OF BRITISH COLUMBIA The report of  

E-Print Network [OSTI]

THE UNIVERSITY OF BRITISH COLUMBIA #12;The report of President Walter H. Gage to the Senate and Board of Governors of The University of British Columbia for the academic year c uber 1, 1969, to August, The University of British Columbia. Mr. Chancellor, ladies and Gentlemen My report to you for the academic year

Pulfrey, David L.

364

University of Northern British Columbia The University Plan  

E-Print Network [OSTI]

1 University of Northern British Columbia The University Plan 2010 #12;1 2 Our Values We excel and responsive to student and community needs. #12;3 4 T he University of Northern British Columbia was born of northern British Columbia motivated 16,000 citizens to pay $5 each and petition government for a university

Northern British Columbia, University of

365

Columbia University 1754 Royal Charter establishes King's College under  

E-Print Network [OSTI]

Columbia University FACTS 2011 TIMELINE 1754 Royal Charter establishes King's College under King Trustees formally designate Columbia as a university. 1897 The University moves from 49th and Madison Seminary LIBRARIES The Columbia University Libraries/Information Service, comprised of 22 libraries, is one

Lazar, Aurel A.

366

The University of British Columbia Board of Governors  

E-Print Network [OSTI]

1 The University of British Columbia Board of Governors Policy No.: 2 Approval Date: November 1990 at The University of British Columbia is individual achievement and merit. Consistent with this principle equitably all faculty and staff. 1.2. The University of British Columbia has established a program

Michelson, David G.

367

University of Missouri-Columbia Transfer Recommendation Form  

E-Print Network [OSTI]

University of Missouri-Columbia Transfer Recommendation Form Complete this form if you to the International Center at the University of Missouri-Columbia. For instructions on SEVIS transfer, please go to permission for the information below to be released to the University of Missouri-Columbia. Do you plan

Taylor, Jerry

368

UNIVERSITY OF MISSOURI -COLUMBIA OFFICE OF RESEARCH AND  

E-Print Network [OSTI]

UNIVERSITY OF MISSOURI - COLUMBIA OFFICE OF RESEARCH AND OFFICE OF SPONSORED PROGRAMS of Missouri The University of Missouri Office of Sponsored Programs Administration 310 Jesse Hall Columbia, MO Programs Administration University of Missouri 310 Jesse Hall Columbia, MO 65211-1230 (573) 882

Taylor, Jerry

369

UNIVERSITY-INDUSTRY LIAISON OFFICE THE UNIVERSITY OF BRITISH COLUMBIA  

E-Print Network [OSTI]

UNIVERSITY-INDUSTRY LIAISON OFFICE THE UNIVERSITY OF BRITISH COLUMBIA BREAKTHROUGHRESEARCHBUSINESSRESULTS 2005|06 ANNUAL REPORT UILO #12;The University of British Columbia, aspiring to be one of the world, Canada, and the world. TREK 2010: UBC'S VISION FOR THE 21ST CENTURY The University of British Columbia

Ollivier-Gooch, Carl

370

Graduate HCI Programs at The University of British Columbia  

E-Print Network [OSTI]

1 Graduate HCI Programs at The University of British Columbia K. S. Booth, S.S. Fels, and B.D. Fisher Media and Graphics Interdisciplinary Centre University of British Columbia ksbooth) at The University of British Columbia (UBC) recently introduced a masters level Specialization in the field of Human

British Columbia, University of

371

From: Emps [mailto:emps-bounces@lists.columbia.edu] On Behalf Of Columbia University Human Sent: Thursday, January 23, 2014 9:30 AM  

E-Print Network [OSTI]

From: Emps [mailto:emps-bounces@lists.columbia.edu] On Behalf Of Columbia University Human at Columbia University Dear Fellow Members of the Columbia Community: Although most of our students are 18 years old and older, Columbia University welcomes minors to our campus and to our programs every day

Grishok, Alla

372

Remedial Investigation of Hanford Site Releases to the Columbia River - 13603  

SciTech Connect (OSTI)

In south-central Washington State, the Columbia River flows through the U.S. Department of Energy Hanford Site. A primary objective of the Hanford Site cleanup mission is protection of the Columbia River, through remediation of contaminated soil and groundwater that resulted from its weapons production mission. Within the Columbia River system, surface water, sediment, and biota samples related to potential Hanford Site hazardous substance releases have been collected since the start of Hanford operations. The impacts from release of Hanford Site radioactive substances to the Columbia River in areas upstream, within, and downstream of the Hanford Site boundary have been previously investigated as mandated by the U.S. Department of Energy requirements under the Atomic Energy Act. The Remedial Investigation Work Plan for Hanford Site Releases to the Columbia River [1] was issued in 2008 to initiate assessment of the impacts under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 [2]. The work plan established a phased approach to characterize contaminants, assess current risks, and determine whether or not there is a need for any cleanup actions. Field investigation activities over a 120-mile stretch of the Columbia River began in October 2008 and were completed in 2010. Sampled media included surface water, pore water, surface and core sediment, island soil, and fish (carp, walleye, whitefish, sucker, small-mouth bass, and sturgeon). Information and sample results from the field investigation were used to characterize current conditions within the Columbia River and assess whether current conditions posed a risk to ecological or human receptors that would merit additional study or response actions under CERCLA. The human health and ecological risk assessments are documented in reports that were published in 2012 [3, 4]. Conclusions from the risk assessment reports are being summarized and integrated with remedial investigation/feasibility study (RI/FS) reports developed for upland areas, riparian areas, and groundwater in the Hanford Site River Corridor. The RI/FS reports will evaluate the impacts to soil, groundwater, and river sediments and lead to proposed cleanup actions and records of decision to address releases from the Hanford Site reactor operations. (authors)

Lerch, J.A.; Hulstrom, L.C. [Washington Closure Hanford, LLC, Richland, Washington 99354 (United States)] [Washington Closure Hanford, LLC, Richland, Washington 99354 (United States); Sands, J.P. [U.S Department of Energy, Richland Operations Office, Richland, Washington 99352 (United States)] [U.S Department of Energy, Richland Operations Office, Richland, Washington 99352 (United States)

2013-07-01T23:59:59.000Z

373

Faculty Positions in Computer Science Columbia Engineering's Department of Computer Science at Columbia University in New York  

E-Print Network [OSTI]

at Columbia University in New York City invites applications for tenure-track faculty positions. Appointments across Columbia University. The Department is especially interested in qualified candidates who canFaculty Positions in Computer Science Columbia Engineering's Department of Computer Science

Yang, Junfeng

374

Columbia University http://www.columbia.edu/~mem4/  

E-Print Network [OSTI]

land- use costs and low nuclear materials risks. With a sustained and strong international research present in every ton of water yields an energy-equivalent of more than 400 tons of oil. The challenge attractive. The most successful approach to date uses strong magnetic fields to create a toroidal magnetic

Mauel, Michael E.

375

The State of the Columbia River Basin  

E-Print Network [OSTI]

, and Washington. The Act authorized the Council to serve as a comprehensive planning agency for energy policy and fish and wildlife policy in the Columbia River Basin and to inform the public about energy and fish Overview 11 Sixth Northwest Power Plan boosts energy efficiency, renewable energy, Energy efficiency

376

Fast Facts About the Columbia River Basin  

E-Print Network [OSTI]

Administration, the federal agency that markets the electricity generated at federal dams in the Columbia River Energy Regulatory Commission; electric utilities; and state energy regulatory agencies. State, tribal directs more than $220 million annually in federal electricity revenues to implement more than 400

377

Applied Econometrics University of British Columbia  

E-Print Network [OSTI]

FRE 528 Applied Econometrics University of British Columbia Fall, 2014 Instructor: Michael Johnson constraints and econometric challenges) along with potential solutions to these problems. Students. Textbook/References: R. Carter Hill, William E. Griffiths and Guay C. Lim, Principles of Econometrics

Farrell, Anthony P.

378

Council's Columbia River Fish and Wildlife Program  

E-Print Network [OSTI]

Walleye Smallmouth bass Northern pike Others 5 Native and Non-native Fish Predators #12; At dams#12;#12;#12;#12;#12;#12;#12;Council's Columbia River Fish and Wildlife Program Summary of Predation Event Center #12;Council's 2009 Fish and Wildlife Program Piscivorous Predator Control Implement

379

D.C. WRRC Report No.41 DIRECTORY OF WATER-RELATED  

E-Print Network [OSTI]

D.C. WRRC Report No.41 #12;#12;DIRECTORY OF WATER-RELATED ORGANIZATIONS IN THE DISTRICT OF COLUMBIA 1982 Preparations of the directory was supported in part by Federal funds from the Office of Water. The directory of water-related organizations in the District of Columbia has been prepared as part

District of Columbia, University of the

380

Mid-Columbia Coho Salmon Reintroduction Feasibility Project : Environmental Assessment.  

SciTech Connect (OSTI)

Before the Bonneville Power Administration (BPA) decides whether to fund a program to reintroduce coho salmon to mid-Columbia River basin tributaries, research is needed to determine the ecological risks and biological feasibility of such an effort. Since the early 1900s, the native stock of coho has been decimated in the tributaries of the middle reach of the Columbia River. The four Columbia River Treaty Tribes identified coho reintroduction in the mid-Columbia as a priority in the Tribal Restoration Plan. It is a comprehensive plan put forward by the Tribes to restore the Columbia River fisheries. In 1996, the Northwest Power Planning Council (NPPC) recommended the tribal mid-Columbia reintroduction project for funding by BPA. It was identified as one of fifteen high-priority supplementation projects for the Columbia River basin, and was incorporated into the NPPC`s Fish and Wildlife Program. The release of coho from lower Columbia hatcheries into mid-Columbia tributaries is also recognized in the Columbia River Fish Management Plan.

United States. Bonneville Power Administration; Washington (State) Department of Fish and Wildlife; Confederated Tribes and Bands of the Yakama Nation

1999-01-01T23:59:59.000Z

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We encourage you to perform a real-time search of NLEBeta
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381

Columbia University Press 2009.06.15 e-e-e-e-ISBN URL  

E-Print Network [OSTI]

Columbia University Press 2009.06.15 e-e-e-e-ISBN URL Art & Humanities 9780231512732 Changing Clothes in China: Fashion, History, Nation 1 Finnane, Antonia Columbia Press University 2008 http://www.igpublish.com/columbia Rotem Columbia Press University 2008 http://www.igpublish.com/columbia- ebooks

Wu, Yih-Min

382

Columbia, Missouri: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectricEnergyCTBarreisVolcanicPowerRaftColumbia Rural Elec Assn, Inc

383

Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production, Progress Report for Work Through September 2003, 2nd Annual/8th Quarterly Report  

SciTech Connect (OSTI)

The supercritical water-cooled reactor (SCWR) is one of the six reactor technologies selected for research and development under the Generation-IV program. SCWRs are promising advanced nuclear systems because of their high thermal efficiency (i.e., about 45% vs. about 33% efficiency for current Light Water Reactors, LWRs) and considerable plant simplification. SCWRs are basically LWRs operating at higher pressure and temperatures with a direct once-through cycle. Operation above the critical pressure eliminates coolant boiling, so the coolant remains single-phase throughout the system. Thus the need for recirculation and jet pumps, a pressurizer, steam generators, steam separators and dryers is eliminated. The main mission of the SCWR is generation of low-cost electricity. It is built upon two proven technologies, LWRs, which are the most commonly deployed power generating reactors in the world, and supercritical fossil-fired boilers, a large number of which is also in use around the world.

Philip E. MacDonald

2003-09-01T23:59:59.000Z

384

Investigation of the use of nanofluids to enhance the In-Vessel Retention capabilities of Advanced Light Water Reactors  

E-Print Network [OSTI]

Nanofluids at very low concentrations experimentally exhibit a substantial increase in Critical Heat Flux (CHF) compared to water. The use of a nanofluid in the In-Vessel Retention (IVR) severe accident management strategy, ...

Hannink, Ryan Christopher

2007-01-01T23:59:59.000Z

385

The CHPRC Columbia River Protection Project Quality Assurance Project Plan  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory researchers are working on the CHPRC Columbia River Protection Project (hereafter referred to as the Columbia River Project). This is a follow-on project, funded by CH2M Hill Plateau Remediation Company, LLC (CHPRC), to the Fluor Hanford, Inc. Columbia River Protection Project. The work scope consists of a number of CHPRC funded, related projects that are managed under a master project (project number 55109). All contract releases associated with the Fluor Hanford Columbia River Project (Fluor Hanford, Inc. Contract 27647) and the CHPRC Columbia River Project (Contract 36402) will be collected under this master project. Each project within the master project is authorized by a CHPRC contract release that contains the project-specific statement of work. This Quality Assurance Project Plan provides the quality assurance requirements and processes that will be followed by the Columbia River Project staff.

Fix, N. J.

2008-11-30T23:59:59.000Z

386

Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production, Progress Report for Work Through September 2002, 4th Quarterly Report  

SciTech Connect (OSTI)

The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed. If no additional moderator is added to the fuel rod lattice, it is possible to attain fast neutron energy spectrum conditions in a supercritical water-cooled reactor (SCWR). This type of core can make use of either fertile or fertile-free fuel and retain a hard spectrum to effectively burn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity. One can also add moderation and design a thermal spectrum SCWR. The Generation IV Roadmap effort has identified the thermal spectrum SCWR (followed by the fast spectrum SCWR) as one of the advanced concepts that should be developed for future use. Therefore, the work in this NERI project is addressing both types of SCWRs.

Mac Donald, Philip Elsworth

2002-09-01T23:59:59.000Z

387

Study of Pu consumption in advanced light water reactors: Evaluation of GE advanced boiling water reactor plants - compilation of Phase 1B task reports  

SciTech Connect (OSTI)

This report contains an extensive evaluation of GE advanced boiling water reactor plants prepared for United State Department of Energy. The general areas covered in this report are: core and system performance; fuel cycle; infrastructure and deployment; and safety and environmental approval.

NONE

1993-09-15T23:59:59.000Z

388

Local Content Requirements in British Columbia's Wind Power Industry  

E-Print Network [OSTI]

Local Content Requirements in British Columbia's Wind Power Industry May Hao, Matt Mackenzie, Alex..................................................................................8 4.1 Current Wind Power Projects

Pedersen, Tom

389

Pepco and PJM Interconnection Comments on District of Columbia...  

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

Pepco and PJM Interconnection Comments on District of Columbia Public Service Commission, Docket No. EO-05-01 Comments and Answer to Requests for Rehearing Pepco and PJM...

390

Columbia Gas of Massachusetts- Residential Energy Efficiency Programs  

Broader source: Energy.gov [DOE]

Columbia Gas of Massachusetts participates in energy efficiency programs that reward eligible residential natural gas customers for utilizing energy efficient equipment or measures. The program...

391

Columbia Gas of Massachusetts- Commercial Energy Efficiency Program  

Broader source: Energy.gov [DOE]

Columbia Gas of Massachusetts offers its multi-family, commercial and industrial customers rebates and assistance for energy efficiency improvements to eligible facilities. The program will perform...

392

Columbia River Treaty Review #2 - April 2009.indd  

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

the Columbia River Treaty has provided signifi cant benefi ts to the United States and Canada through coordinated river management by the two countries. It remains the standard...

393

Columbia River PUD- Residential Energy Efficiency Rebate Programs  

Broader source: Energy.gov [DOE]

Columbia River PUD offers a variety of rebates to residential customers for making energy efficient improvements to electrically heated homes. Rebates are available for Energy Star manufactured...

394

Microsoft Word - CX-ColumbiaREADaytonSubstationTap_WEB.doc  

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

7, 2011 REPLY TO ATTN OF: KEPR-4 SUBJECT: Environmental Clearance Memorandum Mike Normandeau Customer Account Executive - PSE-SPOKANE Proposed Action: Columbia Rural Electric...

395

Columbia Rural Electric Association- Residential Energy Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

Columbia Rural Electric Association offers its residential customers a variety of rebates for the purchase of energy efficient equipment and measures. Eligible equipment includes efficient clothes...

396

Columbia Rural Electric Association- Irrigation Energy Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

Columbia REA, through the Bonneville Power Administration, offers an irrigation energy efficiency program for its agricultural customers. Stationary systems are not eligible for this program due to...

397

Columbia Generating Station debt options for rate relief - November...  

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

extending about 350 million of existing Columbia Generating Station debt to 2024 to the Energy Northwest Audit, Legal and Finance Committee (www.bpa.govcorporateFinanceDebt...

398

Sustainable Energy Utility- Residential Energy Efficiency Program (District of Columbia)  

Broader source: Energy.gov [DOE]

The District of Columbia Sustainable Energy Utility currently offers the Residential Energy Efficiency Program. The program provides financial incentives to District residents who install energy-...

399

MHK Technologies/Oregon State University Columbia Power Technologies...  

Open Energy Info (EERE)

Jump to: navigation, search << Return to the MHK database homepage Oregon State University Columbia Power Technologies Direct Drive Point Absorber.jpg Technology Profile...

400

Panagiota Daskalopoulos - Columbia University, U.S.A. Worn ...  

E-Print Network [OSTI]

Panagiota Daskalopoulos - Columbia University, U.S.A.. Worn Stones with Flat Sides - All Time Regularity of the Interface. We study the all time regularity of the

Note: This page contains sample records for the topic "light columbia water" 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

Light Induced Water Oxidation on Cobalt-Phosphate (Co-Pi) Catalyst Modified Semi-Transparent, Porous SiO2-BiVO4 Electrodes  

SciTech Connect (OSTI)

A facile and simple procedure for the synthesis of semi-transparent and porous SiO{sub 2}-BiVO{sub 4} electrodes is reported. The method involves a surfactant assisted metal-organic decomposition at 500 C. An earth abundant oxygen evolution catalyst (OEC), cobalt phosphate (Co-Pi), has been used to modify the SiO{sub 2}-BiVO{sub 4} electrode by electrodeposition (ED) and photoassisted electrodeposition (PED) methods. Modified electrodes by these two methods have been examined for light induced water oxidation and compared to the unmodified SiO{sub 2}-BiVO{sub 4} electrodes by various photoelectrochemical techniques. The PED method was a more effective method of OEC preparation than the ED method as evidenced by an increased photocurrent magnitude during photocurrent-potential (I-V) characterizations. Electrode surfaces catalyzed by PED exhibited a very large cathodic shift (420 mV) in the onset potential for water oxidation. The chopped-light I-V measurements performed at different intervals over 24-hour extended testing under illumination and applied bias conditions show a fair photostability for PED Co-Pi modified SiO{sub 2}-BiVO{sub 4}.

Pilli, S. K.; Deutsch, T. G.; Furtak, T. E.; Turner, J. A.; Brown, L. D.; Herring, A. M.

2012-04-21T23:59:59.000Z

402

James E. Hansen Columbia University Earth Institute, Climate Science, Awareness and Solutions  

E-Print Network [OSTI]

James E. Hansen Columbia University Earth Institute, Climate Science, Awareness and Solutions Studies, is Adjunct Professor at Columbia University's Earth Institute, where he directs a program Goddard Institute for Space Studies, is Adjunct Professor and at Columbia University's Earth Institute

Hansen, James E.

403

Reintroduction of Lower Columbia River Chum Salmon into Duncan Creek, 2007 Annual Report.  

SciTech Connect (OSTI)

The National Marine Fisheries Service (NMFS) listed Lower Columbia River (LCR) chum salmon as threatened under the Endangered Species Act (ESA) in March, 1999 (64 FR 14508, March 25, 1999). The listing was in response to the reduction in abundance from historical levels of more than one-half million returning adults to fewer than 10,000 present-day spawners. Harvest, habitat degradation, changes in flow regimes, riverbed movement and heavy siltation have been largely responsible for this decline. The timing of seasonal changes in river flow and water temperatures is perhaps the most critical factor in structuring the freshwater life history of this species. This is especially true of the population located directly below Bonneville Dam, where hydropower operations can block access to spawning sites, dewater redds, strand fry, cause scour or fill of redds and increase sedimentation of spawning gravels. Prior to 1997, only two chum salmon populations were recognized as genetically distinct in the Columbia River, although spawning had been documented in many Lower Columbia River tributaries. The first population was in the Grays River (RKm 34), a tributary of the Columbia River, and the second was a group of spawners utilizing the mainstem Columbia River just below Bonneville Dam (RKm 235) adjacent to Ives Island and in Hardy and Hamilton creeks. Using additional DNA samples, Small et al. (2006) grouped chum salmon spawning in the mainstem Columbia River and the Washington State tributaries into three groups: the Coastal, the Cascade and the Gorge. The Coastal group comprises those spawning in the Grays River, Skamokawa Creek and the broodstock used at the Sea Resources facility on the Chinook River. The Cascade group comprises those spawning in the Cowlitz (both summer and fall stocks), Kalama, Lewis, and East Fork Lewis rivers, with most supporting unique populations. The Gorge group comprises those spawning in the mainstem Columbia River from the I-205 Bridge up to Bonneville Dam and those spawning in Hamilton and Hardy creeks. Response to the federal ESA listing has been primarily through direct-recovery actions: reducing harvest, hatchery supplementation using local broodstock for populations at catastrophic risk, habitat restoration (including construction of spawning channels) and flow agreements to protect spawning and rearing areas. Both state and federal agencies have built controlled spawning areas. In 1998, the Washington Department of Fish and Wildlife (WDFW) began a chum salmon supplementation program using native stock on the Grays River. This program was expanded during 1999 - 2001 to include reintroduction into the Chinook River using eggs from the Grays River Supplementation Program. These eggs are incubated at the Grays River Hatchery, reared to release size at the Sea Resources Hatchery on the Chinook River, and the fry are released at the mouth of the Chinook River. Native steelhead, chum, and coho salmon are present in Duncan Creek, and are recognized as subpopulations of the Lower Gorge population, and are focal species in the Lower Columbia Fish Recovery Board (LCFRB) plan. Steelhead, chum and coho salmon that spawn in Duncan Creek are listed as Threatened under the ESA. Duncan Creek is classified by the LCFRB plan as a watershed for intensive monitoring (LCFRB 2004). This project was identified in the 2004 Federal Columbia River Power System (FCRPS) revised Biological Opinion (revised BiOp) to increase survival of chum salmon, 'BPA will continue to fund the program to re-introduce Columbia River chum salmon into Duncan Creek as long as NOAA Fisheries determines it to be an essential and effective contribution to reducing the risk of extinction for this ESU'. (USACE et al. 2004, page 85-86). The Governors Forum on Monitoring and Salmon Recovery and Watershed Health recommends one major population from each ESU have adult and juvenile monitoring. Duncan Creek chum salmon are identified in this plan to be intensively monitored. Planners recommended that a combination of natural and hatchery production

Hillson, Todd D. [Washington Department of Fish and Wildlife

2009-06-12T23:59:59.000Z

404

A Comparative Study of Ozone and Ultraviolet Light/Hydrogen Peroxide for Decolorizing Textile Dyeing Waste Water  

E-Print Network [OSTI]

UVjperoxide batch reactor Description of Dyes Ten dyes representing a broad range of types of structure found in dye molecules were included in the study. Azo and anthraquinone structures were included as were water soluble and water insoluble dyes... Diazo o~-io--03~-o-, ~ '101' Yellow 44 29000 Diazo O~-o.-o?~ Table 2: Description of Acid Dyes CI Acid CINo. Classification Structure Red 1 Blue 25 18050 62055 Monazo Anthraquinone OH HMCOCHJ O-:(O,sor o HoO~ . c05'" o HH-Q Yellow 151...

Namboodri, C. G.; Perkins, W. S.; Walsh, W. K.

405

Interim Columbia and Snake rivers flow improvement measures for salmon: Final Supplemental Environmental Impact Statement (SEIS)  

SciTech Connect (OSTI)

Public comments are sought on this final SEIS, which supplements the 1992 Columbia River Salmon Flow Measures Options Analysis (OA)/Environmental Impact Statement (EIS). The Corps of Engineers, in cooperation with the Bonneville Power Administration and the Bureau of Reclamation proposes five alternatives to improve flows of water in the lower Columbia-Snake rivers in 1993 and future years to assist the migration of juvenile and adult anadromous fish past eight hydropower dams. These are: (1) Without Project (no action) Alternative, (2) the 1992 Operation, (3) the 1992 Operation with Libby/Hungry Horse Sensitivity, (4) a Modified 1992 Operation with Improvements to Salmon Flows from Dworshak, and (5) a Modified 1992 Operation with Upper Snake Sensitivity. Alternative 4, Modified 1992 Operations, has been identified as the preferred alternative.

Not Available

1993-03-01T23:59:59.000Z

406

CdSe-MoS2: A Quantum Size-Confined Photocatalyst for Hydrogen Evolution from Water under Visible Light  

E-Print Network [OSTI]

and for the conversion of carbon dioxides into methanol and hydrocarbons. Metal chalcogenides1­9 are promisingCdSe-MoS2: A Quantum Size-Confined Photocatalyst for Hydrogen Evolution from Water under Visible driven pathway to hydrogen. Hydrogen is not only an environmentally benign fuel for the generation

Osterloh, Frank

407

Light-water-reactor safety fuel systems research programs. Quarterly progress report, January-March 1985. Volume 1  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1985 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 15 refs.

Not Available

1986-01-01T23:59:59.000Z

408

Light-water-reactor safety fuel systems research programs. Quarterly progress report, January-March 1984. [Fuel and cladding problems  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification.

Not Available

1984-09-01T23:59:59.000Z

409

Light-water-reactor safety fuel systems research programs. Quarterly progress report, July-September 1984. Volume 3  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during July, August, and September 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 17 refs., 23 figs., 5 tabs.

Not Available

1985-04-01T23:59:59.000Z

410

Light-water-reactor safety fuel systems research programs. Quarterly progress report, April-June 1984. Volume 2  

SciTech Connect (OSTI)

This progress report report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during April, May, and June 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification.

Not Available

1985-02-01T23:59:59.000Z

411

Light-water-reactor safety fuel systems research programs. Quarterly progress report, October-December 1984. Volume 4  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during October, November, and December 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 30 refs., 23 figs., 2 tabs.

Not Available

1985-08-01T23:59:59.000Z

412

E-Print Network 3.0 - annual british columbia Sample Search Results  

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

Sciences and Ecology 2 University of Northern British Columbia Senior Human Resources Advisor Summary: University of Northern British Columbia Senior Human Resources Advisor...

413

Status Review of Wildlife Mitigation, Columbia Basin Hydroelectric Projects, Columbia River Mainstem Facilities, 1984 Final Report.  

SciTech Connect (OSTI)

This report reviews the status of past, present, and proposed future wildlife planning and mitigation programs at existing hydroelectric projects in the Columbia River Basin. The project evaluations will form the basis for determining any needed remedial measures or additional project analysis. Each hydropower facility report is abstracted separately for inclusion in the Energy Data Base.

Howerton, Jack; Hwang, Diana

1984-11-01T23:59:59.000Z

414

EA-2006: Columbia Estuary Ecosystem Restoration Program  

Broader source: Energy.gov [DOE]

The U.S. Army Corps of Engineers, with DOEs Bonneville Power Administration as a cooperating agency, is preparing a programmatic EA for actions recommended by the Northwest Power and Conservation Council to help restore ecological structure, function, and biodiversity within the Columbia River estuary. Activities under this program could include full reconnection of tidal influence through breaching dikes and levees; partial reconnection of tidal influence through culverts, bridges, and tidegates; enhancement of the quantity and quality of tidal channels; removal of invasive species; and restoration of riparian habitat conditions, such as planting native vegetation.

415

COLUMBIA RIVER TREATY ENTITY AGREEMENT ON THE  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route BTRIC CNMSMethanoliVP-^"^^? COLUMBIA09

416

COLUMBIA RIVER TREATY ENTITY AGREEMENT ON THE  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route BTRIC CNMSMethanoliVP-^"^^? COLUMBIA0910

417

COLUMBIA RIVER TREATY ENTITY AGREEMENT ON THE  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route BTRIC CNMSMethanoliVP-^"^^? COLUMBIA0910 ON

418

COLUMBIA RIVER TREATY ENTITY AGREEMENT ON THE  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route BTRIC CNMSMethanoliVP-^"^^? COLUMBIA0910

419

Columbia University Energy Options & Paths to Climate Stabilization  

E-Print Network [OSTI]

-lived radioactive components. Safe: no catastrophic accidents; Low-risk for nuclear materials proliferation WhyMike Mauel Columbia University Energy Options & Paths to Climate Stabilization Aspen, 9 July 2003 Fusion Energy: "Pipe Dream or Panacea" #12;Mike Mauel Columbia University Energy Options & Paths

Mauel, Michael E.

420

services for grad students http://cdrs.columbia.edu/  

E-Print Network [OSTI]

@cdrs.columbia.edu Academic Commons Academic Commons, Columbia's online repository, increases the visibility and accessibility to dissertations and theses, we accept articles, working papers, datasets, conference proceedings, and more. partnering with researchers and scholars to share new knowledge Links: Academic Commons: http

Salzman, Daniel

Note: This page contains sample records for the topic "light columbia water" 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

Columbia Photographic Images and Photorealistic Computer Graphics Dataset  

E-Print Network [OSTI]

Columbia Photographic Images and Photorealistic Computer Graphics Dataset Tian-Tsong Ng, Shih Abstract Passive-blind image authentication is a new area of research. A suitable dataset. In response to the need for a new dataset, the Columbia Photographic Images and Photorealistic Computer

Chang, Shih-Fu

422

SURVEY OF THE COLUMBIA RIVER AND ITS TRIBUTARIES -Part VII  

E-Print Network [OSTI]

SURVEY OF THE COLUMBIA RIVER AND ITS TRIBUTARIES - Part VII I ^^^^'fie^BkJioJS SPECIAL SCIENTIFIC, Director Special Scientific Report - Fisheries No. UO SURVEY OF THE COLUMBIA RIVER AND ITS TRIBUTARIES PART these have been divided for con- venience into four sub-areas. On the Idaho side of the Snake River

423

Columbia College Portland State University Updated 1/31/2014  

E-Print Network [OSTI]

Columbia College Portland State University Updated 1/31/2014 Transfer Worksheet If you are taking classes that are part of the Intersegmental General Education Transfer Curriculum (IGETC) at Columbia College, you can rest assured that those credits will also transfer to Portland State University (PSU

Caughman, John

424

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies and Procedures  

E-Print Network [OSTI]

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies and Procedures Green University Centre President Idle Free 1. Purpose The University of Northern British Columbia is committed to the principles of sustainability, as reflected in its goal of living Canada's Green UniversityTM. One key goal of the Green

Bolch, Tobias

425

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies and Procedures  

E-Print Network [OSTI]

UNIVERSITY OF NORTHERN BRITISH COLUMBIA Policies and Procedures Facilities PC April 30, 2009 Page 1 traditional, ceremonial, and pedagogical events while adhering to the British Columbia Tobacco Control Act. The University must comply with the law. Smudging and other Ceremonial Use of Smoke: 1.2 Smudging

Bolch, Tobias

426

WATER QUALITY STUDY OF WENATCHEE AND MIDDLE COLUMBIA RIVERS  

E-Print Network [OSTI]

. Sylvester Project Supervisor University of Washington Seattle, Washington U. S. Fish and Wildlife Service Contract No. 14-19-008-2506 United States Fish and Wildlife Service Special Scientific Report --Fisheries

427

The Power of Water Renegotiating the Columbia River Treaty  

E-Print Network [OSTI]

, and release: - Agriculture and food security (THE BIGGEST ISSUE) - Hydroelectric power - Other nonagricultural

428

A domain-specific analysis system for examining nuclear reactor simulation data for light-water and sodium-cooled fast reactors  

E-Print Network [OSTI]

Building a new generation of fission reactors in the United States presents many technical and regulatory challenges. One important challenge is the need to share and present results from new high-fidelity, high-performance simulations in an easily usable way. Since modern multiscale, multi-physics simulations can generate petabytes of data, they will require the development of new techniques and methods to reduce the data to familiar quantities of interest (e.g., pin powers, temperatures) with a more reasonable resolution and size. Furthermore, some of the results from these simulations may be new quantities for which visualization and analysis techniques are not immediately available in the community and need to be developed. This paper describes a new system for managing high-performance simulation results in a domain-specific way that naturally exposes quantities of interest for light water and sodium-cooled fast reactors. It describes requirements to build such a system and the technical challenges faced...

Billings, Jay Jay; Hull, S Forest; Lingerfelt, Eric J; Wojtowicz, Anna

2014-01-01T23:59:59.000Z

429

Possible effects of UO/sub 2/ oxidation on light water reactor spent fuel performance in long-term geologic disposal  

SciTech Connect (OSTI)

Disposal of spent nuclear fuel in a conventionally mined geologic formation is the nearest-term option for permanently isolating radionuclides from the biosphere. Because irradiated uranium dioxide (UO/sub 2/) fuel pellets retain 95 to 99% of the radionuclides generated during normal light water reactor operation, they may represent a significant barrier to radionuclide release. This document presents a technical assessment of published literature representing the current level of understanding of spent fuel characteristics and conditions that may degrade pellet integrity during a geologic disposal sequence. A significant deterioration mechanism is spent UO/sub 2/ oxidation with possible consequences identified as fission gas release, rod diameter increases, cladding breach extension, and release of solid fuel particles containing radionuclides. Areas requiring further study to support development of a comprehensive spent fuel performance prediction model are highlighted. A program and preliminary schedule to obtain the information needed to develop model correlations are also presented.

Almassy, M.Y.; Woodley, R.E.

1982-08-01T23:59:59.000Z

430

Is there a particle-size dependence for the mediation by colloidal redox catalysts of the light-induced hydrogen evolution from water  

SciTech Connect (OSTI)

Particle-size effects for the catalysis by platinum of the light-induced hydrogen evolution from water, using the (Ru(bpy)/sub 3//sup 2 +//methyl viologen/EDTA) model system, were investigated with widely polydispersed colloidal platinum hydrosols and samples with narrower size distributions obtained from the former hydrosols by centrifugation. The optimum values for the hydrogen-formation rates and yields were found to be very similar for all catalysts studied; this was true for those containing polydispersed or selected small (<100 A) as well as large particles (>1000 A). In fact, no platinum particle-size effects on the methyl viologen mediated hydrogen evolutions were observed in the investigated size range. These results are discussed in relation to studies on catalyst-dispersion effects in the field of heterogeous catalysis.

Keller, P.; Moradpour, A.

1980-11-19T23:59:59.000Z

431

Proposed and existing passive and inherent safety-related structures, systems, and components (building blocks) for advanced light-water reactors  

SciTech Connect (OSTI)

A nuclear power plant is composed of many structures, systems, and components (SSCs). Examples include emergency core cooling systems, feedwater systems, and electrical systems. The design of a reactor consists of combining various SSCs (building blocks) into an integrated plant design. A new reactor design is the result of combining old SSCs in new ways or use of new SSCs. This report identifies, describes, and characterizes SSCs with passive and inherent features that can be used to assure safety in light-water reactors. Existing, proposed, and speculative technologies are described. The following approaches were used to identify the technologies: world technical literature searches, world patent searches, and discussions with universities, national laboratories and industrial vendors. 214 refs., 105 figs., 26 tabs.

Forsberg, C.W.; Moses, D.L.; Lewis, E.B.; Gibson, R.; Pearson, R.; Reich, W.J.; Murphy, G.A.; Staunton, R.H.; Kohn, W.E.

1989-10-01T23:59:59.000Z

432

Progress in evaluation and improvement in nondestructive examination reliability for inservice inspection of Light Water Reactors (LWRs) and characterize fabrication flaws in reactor pressure vessels  

SciTech Connect (OSTI)

This paper is a review of the work conducted under two programs. One (NDE Reliability Program) is a multi-year program addressing the reliability of nondestructive evaluation (NDE) for the inservice inspection (ISI) of light water reactor components. This program examines the reliability of current NDE, the effectiveness of evolving technologies, and provides assessments and recommendations to ensure that the NDE is applied at the right time, in the right place with sufficient effectiveness that defects of importance to structural integrity will be reliably detected and accurately characterized. The second program (Characterizing Fabrication Flaws in Reactor Pressure Vessels) is assembling a data base to quantify the distribution of fabrication flaws that exist in US nuclear reactor pressure vessels with respect to density, size, type, and location. These programs will be discussed as two separate sections in this report. 4 refs., 7 figs.

Doctor, S.R.; Bowey, R.E.; Good, M.S.; Friley, J.R.; Kurtz, R.J.; Simonen, F.A.; Taylor, T.T.; Heasler, P.G.; Andersen, E.S.; Diaz, A.A.; Greenwood, M.S.; Hockey, R.L.; Schuster, G.J.; Spanner, J.C.; Vo, T.V.

1991-10-01T23:59:59.000Z

433

REAL ESTATE FOUNDATION OF BRITISH COLUMBIA PARTNERING FUND The intent of the Real Estate Foundation of British Columbia Partnering Fund,  

E-Print Network [OSTI]

REAL ESTATE FOUNDATION OF BRITISH COLUMBIA PARTNERING FUND GUIDELINES The intent of the Real Estate Foundation of British Columbia Partnering Fund, generated by an endowment to UNBC by the Real Estate Foundation of BC, is to assist faculty and students in obtaining and leveraging funding for research

Northern British Columbia, University of

434

NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669  

SciTech Connect (OSTI)

The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the {open_quotes}Advanced Light Water Reactor [ALWR] Utility Requirements Document{close_quotes}, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, {open_quotes}ALWR Policy and Summary of Top-Tier Requirements{close_quotes}, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, {open_quotes}NRC Review of Electric Power Research Institute`s Advanced Light Water Reactor Utility Requirements Document - Program Summary{close_quotes}, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff`s review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

Not Available

1994-08-01T23:59:59.000Z

435

NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669  

SciTech Connect (OSTI)

The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the {open_quotes}Advanced Light Water Reactor [ALWR] Utility Requirements Document{close_quotes}, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, {open_quotes}ALWR Policy and Summary of Top-Tier Requirements{close_quotes}, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, {open_quotes}NRC Review of Electric Power Research Institute`s Advanced Light Water Reactor Utility Requirements Document - Program Summary{close_quotes}, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff`s review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

Not Available

1994-08-01T23:59:59.000Z

436

Evaluating Cumulative Ecosystem Response to Restoration Projects in the Columbia River Estuary, Annual Report 2006  

SciTech Connect (OSTI)

This report is the third annual report of a six-year project to evaluate the cumulative effects of habitat restoration action in the Columbia River Estuary (CRE). The project is being conducted for the U.S. Army Corps of Engineers (Corps) by the Marine Sciences Laboratory of the Pacific Northwest National Laboratory, the Pt. Adams Biological Field Station of the National Marine Fisheries Service, and the Columbia River Estuary Study Taskforce. Measurement of the cumulative effects of ecological restoration projects in the Columbia River estuary is a formidable task because of the size and complexity of the estuarine landscape and the meta-populations of salmonids in the Columbia River basin. Despite the challenges presented by this system, developing and implementing appropriate indicators and methods to measure cumulative effects is the best way to enable estuary managers to track the overall effectiveness of investments in estuarine restoration projects. This project is developing methods to quantify the cumulative effects of multiple restoration activities in the CRE. The overall objectives of the 2006 study were to continue to develop techniques to assess cumulative effects, refine the standard monitoring protocols, and initiate development of an adaptive management system for Corps of Engineers habitat restoration monitoring efforts in the CRE. (The adaptive management effort will be reported at a later date.) Field studies during 2006 were conducted in tidal freshwater at Kandoll Farm on the lower Grays River and tidal brackish water at Vera Slough on Youngs Bay. Within each of area, we sampled one natural reference site and one restoration site. We addressed the overall objectives with field work in 2006 that, coupled with previous field data, had specific objectives and resulted in some important findings that are summarized here by chapter in this report. Each chapter of the report contains data on particular monitored variables for pre- and post-restoration conditions at both the Kandoll and Vera study areas.

Johnson, Gary E.; Borde, Amy B.; Dawley, Earl; Diefenderfer, Heida L.; Ebberts, Blaine D.; Putman, Douglas A.; Roegner, G. C.; Thom, Ronald M.; Vavrinec, John; Whiting, Allan H.

2007-12-06T23:59:59.000Z

437

Light Water Reactor Sustainability Program Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN  

SciTech Connect (OSTI)

The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated. In order to evaluate the impact of these two factors on the safety of the plant, the Risk Informed Safety Margin Characterization (RISMC) project aims to provide insight to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This report focuses, in particular, on the impact of power uprate on the safety of a boiled water reactor system. The case study considered is a loss of off-site power followed by the loss of diesel generators, i.e., a station black out (SBO) event. Analysis is performed by using a thermo-hydraulic code, i.e. RELAP-5, and a stochastic analysis tool currently under development at INL, i.e. RAVEN. Starting from the event tree models contained in SAPHIRE, we built the input file for RELAP-5 that models in great detail system dynamics under SBO conditions. We also interfaced RAVEN with RELAP-5 so that it would be possible to run multiple RELAP-5 simulation runs by changing specific keywords of the input file. We both employed classical statistical tools, i.e. Monte-Carlo, and more advanced machine learning based algorithms to perform uncertainty quantification in order to quantify changes in system performance and limitations as a consequence of power uprate. We also employed advanced data analysis and visualization tools that helped us to correlate simulation outcome such as maximum core temperature with a set of input uncertain parameters. Results obtained gave a detailed overview of the issues associated to power uprate for a SBO accident scenario. We were able to quantify how timing of safety related events were impacted by a higher reactor core power. Such insights can provide useful material to the decision makers to perform risk-infomed safety margins management.

Diego Mandelli; Curtis Smith; Thomas Riley; John Schroeder; Cristian Rabiti; Aldrea Alfonsi; Joe Nielsen; Dan Maljovec; Bie Wang; Valerio Pascucci

2013-09-01T23:59:59.000Z

438

Advanced Proliferation Resistant, Lower Cost, Uranium-Thorium Dioxide Fuels for Light Water Reactors (Progress report for work through June 2002, 12th quarterly report)  

SciTech Connect (OSTI)

The overall objective of this NERI project is to evaluate the potential advantages and disadvantages of an optimized thorium-uranium dioxide (ThO2/UO2) fuel design for light water reactors (LWRs). The project is led by the Idaho National Engineering and Environmental Laboratory (INEEL), with the collaboration of three universities, the University of Florida, Massachusetts Institute of Technology (MIT), and Purdue University; Argonne National Laboratory; and all of the Pressurized Water Reactor (PWR) fuel vendors in the United States (Framatome, Siemens, and Westinghouse). In addition, a number of researchers at the Korean Atomic Energy Research Institute and Professor Kwangheon Park at Kyunghee University are active collaborators with Korean Ministry of Science and Technology funding. The project has been organized into five tasks: Task 1 consists of fuel cycle neutronics and economics analysis to determine the economic viability of various ThO2/UO2 fuel designs in PWRs, Task 2 will determine whether or not ThO2/UO2 fuel can be manufactured economically, Task 3 will evaluate the behavior of ThO2/UO2 fuel during normal, off-normal, and accident conditions and compare the results with the results of previous UO2 fuel evaluations and U.S. Nuclear Regulatory Commission (NRC) licensing standards, Task 4 will determine the long-term stability of ThO2/UO2 high-level waste, and Task 5 consists of the Korean work on core design, fuel performance analysis, and xenon diffusivity measurements.

Mac Donald, Philip Elsworth

2002-09-01T23:59:59.000Z

439

the university of missouri-columbia summary of grants and contracts  

E-Print Network [OSTI]

Research the university of missouri-columbia summary of grants and contracts research division q, it is fitting that our annual summary of grant and contract activity at the University of Missouri-Columbia for Research Published by the Office of Research, University of Missouri-Columbia 205 Jesse Hall, Columbia, MO

Noble, James S.

440

National Society of Black EngineersNational Society of Black Engineers Columbia University Chapter  

E-Print Network [OSTI]

National Society of Black EngineersNational Society of Black Engineers Columbia University Chapter #12;Columbia University Greetings NSBE Family and Friends! My name is Ken Yearwood, the 2008-2009 Columbia University NSBE (National Society of Black Engineers) Chapter President. On behalf of the Columbia

Hone, James

Note: This page contains sample records for the topic "light columbia water" 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

A Guide tO WORKING wITH COLUMBIA UNIVERSITY  

E-Print Network [OSTI]

A Guide tO WORKING wITH COLUMBIA UNIVERSITY Information for Minority, Women, and Local Businesses and Individuals #12;A Guide tO WORKING wITH COLUMBIA University INTRODUCTIONORMATION . . . . . . . . . . . . . . . . . . . . . . . . . .12 #12;A Guide to WORKING wITH COLUMBIA University 1 INTRODUCTION Columbia University has a long

Qian, Ning

442

THE UNIVERSITY OF BRITISH COLUMBIA for theAcademic Tear 1965-1966  

E-Print Network [OSTI]

#12;THE UNIVERSITY OF BRITISH COLUMBIA for theAcademic Tear 1965-1966 BY JOHN BARFOOT MACDONALD, BRITISH COLUMBIA #12;FORE WORD The Board of Governors, The University of British Columbia. Mr of lectures at the Uni- versity of British Columbia. The University of today is a far cry from the fledgling

Pulfrey, David L.

443

Quantitative Finance, Vol. 12, No. 1, January 2012, 1114 Financial engineering at Columbia University  

E-Print Network [OSTI]

University MARK BROADIE*, EMANUEL DERMAN, PAUL GLASSERMAN and STEVEN KOU Columbia University, New York, NY 10027, USA (Received 6 September 2011; in final form 7 October 2011) 1. Introduction Columbia University of Science in Operations*Corresponding author. Email: mnb2@columbia.edu Main quad at Columbia University

Hone, James

444

Copyright A. J. Millis 2013 Columbia University Dynamical Mean Field Theory  

E-Print Network [OSTI]

Copyright A. J. Millis 2013 Columbia University Dynamical Mean Field Theory Antoine Georges http://phys.columbia.edu/~millis/MillisTLH.pdf #12;Copyright A. J. Millis 2013 Columbia University on interactions I #12;Copyright A. J. Millis 2013 Columbia University Example Second order term Hubbard model 1 2

Millis, Andrew

445

Columbia University Purchasing Terms and Conditions Rev. 10/2012 Page 1 of 3  

E-Print Network [OSTI]

Columbia University Purchasing Terms and Conditions Rev. 10/2012 Page 1 of 3 1. DELIVERABLES. If Vendor fails to comply, Columbia reserves all rights available under law, and specifically, the right in Columbia, Vendor hereby assigns to Columbia ownership of all Deliverables to be provided hereunder

Grishok, Alla

446

Columbia University TRECVID-2005 Video Search and High-Level Feature Extraction  

E-Print Network [OSTI]

1 Columbia University TRECVID-2005 Video Search and High-Level Feature Extraction Shih-Fu Chang and Multimedia Lab, Columbia University http://www.ee.columbia.edu/dvmm Oct. 28th 2005 Descriptions of Submitted. Search I_C_2_ColumbiaI1_1: Interactive system, using text search (against ASR/MT), content- based image

Chang, Shih-Fu

447

Species for the screening assessment. Columbia River Comprehensive Impact Assessment  

SciTech Connect (OSTI)

Because of past nuclear production operations along the Columbia River, there is intense public and tribal interest in assessing any residual Hanford Site related contamination along the river from the Hanford Reach to the Pacific Ocean. The Columbia River Comprehensive Impact Assessment was proposed to address these concerns. The assessment of the Columbia River is being conducted in phases. The initial phase is a screening assessment of the risk, which addresses current environmental conditions for a range of potential uses. One component of the screening assessment estimates the risk from contaminants in the Columbia River to the environment. The objective of the ecological risk assessment is to determine whether contaminants from the Columbia River pose a significant threat to selected receptor species that exist in the river and riparian communities of the study area. This report (1) identifies the receptor species selected for the screening assessment of ecological risk and (2) describes the selection process. The species selection process consisted of two tiers. In Tier 1, a master species list was developed that included many plant and animal species known to occur in the aquatic and riparian systems of the Columbia River between Priest Rapids Dam and the Columbia River estuary. This master list was reduced to 368 species that occur in the study area (Priest Rapids Dam to McNary Dam). In Tier 2, the 181 Tier 1 species were qualitatively ranked based on a scoring of their potential exposure and sensitivity to contaminants using a conceptual exposure model for the study area.

Becker, J.M.; Brandt, C.A.; Dauble, D.D.; Maughan, A.D.; O`Neil, T.K.

1996-03-01T23:59:59.000Z

448

Description of the Columbia Basin Wind Energy Study (CBWES)  

SciTech Connect (OSTI)

The purpose of this Technical Report is to provide background information about the Columbia Basin Wind Energy Study (CBWES). This study, which was supported by the U.S. Department of Energys Wind and Water Power Program, was conducted from 16 November 2010 through 21 March 2012 at a field site in northeastern Oregon. The primary goal of the study was to provide profiles of wind speed and wind direction over the depth of the boundary layer in an operating wind farm located in an area of complex terrain. Measurements from propeller and vane anemometers mounted on a 62 m tall tower, Doppler Sodar, and Radar Wind Profiler were combined into a single data product to provide the best estimate of the winds above the site during the first part of CBWES. An additional goal of the study was to provide measurements of Turbulence Kinetic Energy (TKE) near the surface. To address this specific goal, sonic anemometers were mounted at two heights on the 62 m tower on 23 April 2011. Prior to the deployment of the sonic anemometers on the tall tower, a single sonic anemometer was deployed on a short tower 3.1 m tall that was located just to the south of the radar wind profiler. Data from the radar wind profiler, as well as the wind profile data product are available from the Atmospheric Radiation Measurements (ARM) Data Archive (http://www.arm.gov/data/campaigns). Data from the sonic anemometers are available from the authors.

Berg, Larry K.; Pekour, Mikhail S.; Nelson, Danny A.

2012-10-01T23:59:59.000Z

449

100 Area Columbia River sediment sampling  

SciTech Connect (OSTI)

Forty-four sediment samples were collected from 28 locations in the Hanford Reach of the Columbia River to assess the presence of metals and man-made radionuclides in the near shore and shoreline settings of the Hanford Site. Three locations were sampled upriver of the Hanford Site plutonium production reactors. Twenty-two locations were sampled near the reactors. Three locations were sampled downstream of the reactors near the Hanford Townsite. Sediment was collected from depths of 0 to 6 in. and between 12 to 24 in. below the surface. Samples containing concentrations of metals exceeding the 95 % upper threshold limit values (DOE-RL 1993b) are considered contaminated. Contamination by arsenic, chromium, copper, lead, and zinc was found. Man-made radionuclides occur in all samples except four collected opposite the Hanford Townsite. Man-made radionuclide concentrations were generally less than 1 pCi/g.

Weiss, S.G. [Westinghouse Hanford Co., Richland, WA (United States)

1993-09-08T23:59:59.000Z

450

Paradigm or Paradox: Can we Attribute Species Changes to Global Climate Change in Light of Decreasing Water Temperatures in Central California?  

E-Print Network [OSTI]

California and Adjacent Waters. University of Californiamarmoratus) in California waters as assessed in 2005. ReportMonitoring MPAs in Deep Water off Central California: 2007

Breaker, Laurence; Cailliet, Gregor; Launer, Andrea; Wadsworth, Tom

2012-01-01T23:59:59.000Z

451

2 | engineering neWs | spring 2010 coluMBia engineering | spring 2010 | 3 his issue of Columbia Engineering magazine focuses on engineering  

E-Print Network [OSTI]

2 | engineering neWs | spring 2010 coluMBia engineering | spring 2010 | 3 T his issue of Columbia as the inventor of the Pupin coil and father of long- distance telephony. His pupil and, later, faculty colleague

Hone, James

452

Report from the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies  

SciTech Connect (OSTI)

The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U.S. Department of Energy (DOE). The program is operated in close collaboration with industry R&D programs to provide the technical foundations for licensing and managing the long-term, safe, and economical operation of Nuclear Power Plants that are currently in operation. The LWRS Program focus is on longer-term and higher-risk/reward research that contributes to the national policy objectives of energy and environmental security. Advanced instruments and control (I&C) technologies are needed to support the safe and reliable production of power from nuclear energy systems during sustained periods of operation up to and beyond their expected licensed lifetime. This requires that new capabilities to achieve process control be developed and eventually implemented in existing nuclear assets. It also requires that approaches be developed and proven to achieve sustainability of I&C systems throughout the period of extended operation. The strategic objective of the LWRS Program Advanced Instrumentation, Information, and Control Systems Technology R&D pathway is to establish a technical basis for new technologies needed to achieve safety and reliability of operating nuclear assets and to implement new technologies in nuclear energy systems. This will be achieved by carrying out a program of R&D to develop scientific knowledge in the areas of: Sensors, diagnostics, and prognostics to support characterization and prediction of the effects of aging and degradation phenomena effects on critical systems, structures, and components (SSCs) Online monitoring of SSCs and active components, generation of information, and methods to analyze and employ online monitoring information New methods for visualization, integration, and information use to enhance state awareness and leverage expertise to achieve safer, more readily available electricity generation. As an initial step in accomplishing this effort, the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies was held March 2021, 2009, in Columbus, Ohio, to enable industry stakeholders and researchers in identification of the nuclear industrys needs in the areas of future I&C technologies and corresponding technology gaps and research capabilities. Approaches for collaboration to bridge or fill the technology gaps were presented and R&D activities and priorities recommended. This report documents the presentations and discussions of the workshop and is intended to serve as a basis for the plan under development to achieve the goals of the I&C research pathway.

Bruce P. Hallbert; J. J. Persensky; Carol Smidts; Tunc Aldemir; Joseph Naser

2009-08-01T23:59:59.000Z

453

The Compost System at the University of British Columbia  

E-Print Network [OSTI]

The Compost System at the University of British Columbia Date of Submission: April 25, 2007 Course .............................................................................................................................3 The Composting machine and Surrounding Facility...................................................................4 UBC Compost Pick-Up Route

454

Columbia Gas of Ohio- Programmable Thermostat Rebate Program  

Broader source: Energy.gov [DOE]

Columbia Gas of Ohio offers professional Facility/Building Energy Audits to determine the potential for natural gas savings encouraging matching funds and requiring submittal of final energy audit...

455

Mid-Columbia Region Clean Energy Feasibility Assessment - Hanford...  

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

Official Documents > Mid-Columbia Region Clean Energy Assessment Official Documents DOE - RL ContractsProcurements DOE-ORP ContractsProcurements AR-PIR CERCLA Five-Year Review...

456

The Export Question: Designing Policy for British Columbia Electricity Trade  

E-Print Network [OSTI]

The Export Question: Designing Policy for British Columbia Electricity Trade Dr. George Hoberg..........................................................................................................................................5 2 BC's Electricity Trade Picture: Context and Trends........................................................................6 2.1 How electricity trading works

Pedersen, Tom

457

Energy and GHG Emissions in British Columbia 1990 -2010  

E-Print Network [OSTI]

supply and use, greenhouse gas emissions and energy efficiency in British Columbia Canadian Industrial Energy End-use Data and Analysis Centre (CIEEDAC) Simon Fraser University June 2012 Environment Canada, Natural Resources Canada, Aluminium Industry Association, Canadian Chemical Producers

Pedersen, Tom

458

Property Assessed Clean Energy Financing (District of Columbia)  

Broader source: Energy.gov [DOE]

The District of Columbia offers a commercial Property Assessed Clean Energy (PACE) program. In order to receive financing through the commercial PACE program, applicants must first have an energy...

459

Creciendo Juntos Boletn Mensual de la Universidad de Columbia  

E-Print Network [OSTI]

incluirá el Centro de Ciencias Jerome L. Greene y un nuevo hogar para la Escuela de Negocios de Columbia, la Escuela de Asuntos Internacionales y Públicos y la Escuela de Artes. Las fases posteriores harán

Biasutti, Michela

460

Cogeneration Personal Property Tax Credit (District of Columbia)  

Broader source: Energy.gov [DOE]

The District of Columbia Council created a personal property tax exemption for solar energy systems and cogeneration systems within the District by enacting B19-0749 in December of 2012.

Note: This page contains sample records for the topic "light columbia water" 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

A SCOPING STUDY: Development of Probabilistic Risk Assessment Models for Reactivity Insertion Accidents During Shutdown In U.S. Commercial Light Water Reactors  

SciTech Connect (OSTI)

This report documents the scoping study of developing generic simplified fuel damage risk models for quantitative analysis from inadvertent reactivity insertion events during shutdown (SD) in light water pressurized and boiling water reactors. In the past, nuclear fuel reactivity accidents have been analyzed both mainly deterministically and probabilistically for at-power and SD operations of nuclear power plants (NPPs). Since then, many NPPs had power up-rates and longer refueling intervals, which resulted in fuel configurations that may potentially respond differently (in an undesirable way) to reactivity accidents. Also, as shown in a recent event, several inadvertent operator actions caused potential nuclear fuel reactivity insertion accident during SD operations. The set inadvertent operator actions are likely to be plant- and operation-state specific and could lead to accident sequences. This study is an outcome of the concern which arose after the inadvertent withdrawal of control rods at Dresden Unit 3 in 2008 due to operator actions in the plant inadvertently three control rods were withdrawn from the reactor without knowledge of the main control room operator. The purpose of this Standardized Plant Analysis Risk (SPAR) Model development project is to develop simplified SPAR Models that can be used by staff analysts to perform risk analyses of operating events and/or conditions occurring during SD operation. These types of accident scenarios are dominated by the operator actions, (e.g., misalignment of valves, failure to follow procedures and errors of commissions). Human error probabilities specific to this model were assessed using the methodology developed for SPAR model human error evaluations. The event trees, fault trees, basic event data and data sources for the model are provided in the report. The end state is defined as the reactor becomes critical. The scoping study includes a brief literature search/review of historical events, developments of a small set of comprehensive event trees and fault trees and recommendation for future work.

S. Khericha

2011-06-01T23:59:59.000Z

462

An Economic Impact Analysis of DC Drinking Water Quality  

E-Print Network [OSTI]

An Economic Impact Analysis of DC Drinking Water Quality Annual Progress Report for FY 2005 In January 2004, District of Columbia residents learned the drinking water supplied by the D.C. Water immediately responded by forming the Interagency Task Force on Lead in Drinking Water (The Task Force

District of Columbia, University of the

463

Columbia University, EE Technical Report #2011-11-11, Nov. 2011 A Note on Building an Internet Laboratory  

E-Print Network [OSTI]

Columbia University, EE Technical Report #2011-11-11, Nov. 2011 A Note on Building an Internet Laboratory Michael S. Kester Dept. of Computer Science Columbia University msk2117@columbia.edu Gil Zussman Dept. of Electrical Engineering Columbia University gil@ee.columbia.edu Abstract--The Networking Lab

Zussman, Gil

464

Real-Time BRDF Editing in Complex Lighting Aner Ben-Artzi  

E-Print Network [OSTI]

geometry and lighting, and we render the BRDFs using their final placement within a scene using complexReal-Time BRDF Editing in Complex Lighting Aner Ben-Artzi Columbia University Ryan Overbeck, complex illumination. All-frequency effects (ranging from near-mirror reflections and hard shadows

O'Brien, James F.

465

Thank you for your interest in the University of South Carolina Columbia campus. We are pleased you are considering USC Columbia in your education plans.  

E-Print Network [OSTI]

Thank you for your interest in the University of South Carolina Columbia campus. We are pleased you are considering USC Columbia in your education plans. Campus Change Application Instructions: 1. Please complete and make sure Columbia has your intended major. 2. If your home campus releases you to be considered

Almor, Amit

466

Evaluating Cumulative Ecosystem Response to Restoration Projects in the Columbia River Estuary, Annual Report 2005  

SciTech Connect (OSTI)

This report is the second annual report of a six-year project to evaluate the cumulative effects of habitat restoration projects in the Columbia River Estuary, conducted by Pacific Northwest National Laboratory's Marine Sciences Laboratory, NOAA's National Marine Fisheries Service Pt. Adams Biological Field Station, and the Columbia River Estuary Study Taskforce for the US Army Corps of Engineers. In 2005, baseline data were collected on two restoration sites and two associated reference sites in the Columbia River estuary. The sites represent two habitat types of the estuary--brackish marsh and freshwater swamp--that have sustained substantial losses in area and that may play important roles for salmonids. Baseline data collected included vegetation and elevation surveys, above and below-ground biomass, water depth and temperature, nutrient flux, fish species composition, and channel geometry. Following baseline data collection, three kinds of restoration actions for hydrological reconnection were implemented in several locations on the sites: tidegate replacements (2) at Vera Slough, near the city of Astoria in Oregon State, and culvert replacements (2) and dike breaches (3) at Kandoll Farm in the Grays River watershed in Washington State. Limited post-restoration data were collected: photo points, nutrient flux, water depth and temperature, and channel cross-sections. In subsequent work, this and additional post-restoration data will be used in conjunction with data from other sites to estimate net effects of hydrological reconnection restoration projects throughout the estuary. This project is establishing methods for evaluating the effectiveness of individual projects and a framework for assessing estuary-wide cumulative effects including a protocol manual for monitoring restoration and reference sites.

Diefenderfer, Heida L.; Thom, Ronald M.; Borde, Amy B.; Roegner, G. C.; Whiting, Allan H.; Johnson, Gary E.; Dawley, Earl; Skalski, John R.; Vavrinec, John; Ebberts, Blaine D.

2006-12-20T23:59:59.000Z

467

SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis. Volume 4  

SciTech Connect (OSTI)

The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light -- water-reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission products released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume, Volume IV, describes the material properties correlations and computer subroutines (MATPRO) used by SCDAP/RELAP5. formulation of the materials properties are generally semi-empirical in nature. The materials property subroutines contained in this document are for uranium, uranium dioxide, mixed uranium-plutonium dioxide fuel, zircaloy cladding, zirconium dioxide, stainless steel, stainless steel oxide, silver-indium-cadmium alloy, cadmium, boron carbide, Inconel 718, zirconium-uranium-oxygen melts, fill gas mixtures, carbon steel, and tungsten. This document also contains descriptions of the reaction and solution rate models needed to analyze a reactor accident.

Hagrman, D.T. [ed.; Allison, C.M.; Berna, G.A. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)] [and others

1995-06-01T23:59:59.000Z

468

Validation Work to Support the Idaho National Engineering and Environmental Laboratory Calculational Burnup Methodology Using Shippingport Light Water Breeder Reactor (LWBR) Spent Fuel Assay Data  

SciTech Connect (OSTI)

Six uranium isotopes and fourteen fission product isotopes were calculated on a mass basis at end-of-life (EOL) conditions for three fuel rods from different Light Water Breeder Reactor (LWBR) measurements. The three fuel rods evaluated here were taken from an LWBR seed module, a standard blanket module, and a reflector (Type IV) module. The calculated results were derived using a depletion methodology previously employed to evaluate many of the radionuclide inventories for spent nuclear fuels at the Idaho National Engineering and Environmental Laboratory. The primary goal of the calculational task was to further support the validation of this particular calculational methodology and its application to diverse reactor types and fuels. Result comparisons between the calculated and measured mass concentrations in the three rods indicate good agreement for the three major uranium isotopes (U-233, U-234, U-235) with differences of less than 20%. For the seed and standard blanket rod, the U-233 and U-234 differences were within 5% of the measured values (these two isotopes alone represent greater than 97% of the EOL total uranium mass). For the major krypton and xenon fission product isotopes, differences of less than 20% and less than 30% were observed, respectively. In general, good agreement was obtained for nearly all the measured isotopes. For these isotopes exhibiting significant differences, possible explanations are discussed in terms of measurement uncertainty, complex transmutations, etc.

J. W. Sterbentz

1999-08-01T23:59:59.000Z

469

Lower Columbia River and Estuary Habitat Monitoring Study, 2011 - Final Report  

SciTech Connect (OSTI)

The Ecosystem Monitoring Program is a collaborative effort between the Lower Columbia River Estuary Partnership (LCREP), University of Washington, Wetland Ecosystem Team (UW), US Geological Survey, Water Science Center (USGS), National Oceanic and Atmospheric Administration, National Marine Fisheries Service (NOAA-Fisheries, hereafter NOAA), and Pacific Northwest National Laboratory, Marine Sciences Laboratory (PNNL). The goal of the program is to conduct emergent wetland monitoring aimed at characterizing salmonid habitats in the lower Columbia River and estuary (LCRE) from the mouth of the estuary to Bonneville Dam (Figure 1). This is an ecosystem based monitoring program focused on evaluating status and trends in habitat and reducing uncertainties regarding these ecosystems to ultimately improve the survival of juvenile salmonids through the LCRE. This project comprehensively assesses habitat, fish, food web, and abiotic conditions in the lower river, focusing on shallow water and vegetated habitats used by juvenile salmonids for feeding, rearing and refugia. The information is intended to be used to guide management actions associated with species recovery, particularly that of threatened and endangered salmonids. PNNLs role in this multi-year study is to monitor the habitat structure (e.g., vegetation, topography, channel morphology, and sediment type) as well as hydrologic patterns.

Borde, Amy B.; Kaufmann, Ronald M.; Cullinan, Valerie I.; Zimmerman, Shon A.; Thom, Ronald M.; Wright, Cynthia L.

2012-03-22T23:59:59.000Z

470

Light Water Reactor Sustainability Newsletter  

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

the operation of commercial nuclear power plants require conservative mar- gins of fracture toughness for the RPV materials, both during normal operation and under accident...

471

Light Water Reactor Sustainability Newsletter  

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

The small volume required for such analysis is beneficial for correlating with the small-scale mechanical testing currently being investigated. Further studies on the...

472

CINEMA: Columbia InterNet Extensible Multimedia Architecture Kundan Singh, Wenyu Jiang, Jonathan Lennox, Sankaran Narayanan and Henning Schulzrinne  

E-Print Network [OSTI]

CINEMA: Columbia InterNet Extensible Multimedia Architecture Kundan Singh, Wenyu Jiang, Jonathan Lennox, Sankaran Narayanan and Henning Schulzrinne Department of Computer Science, Columbia University and implementation of our Internet telephony system CINEMA (Columbia InterNet Extensible Multimedia Architecture

473

Dear Admitted Student and Parent: Welcome to Columbia University's Center for Career Education (CCE) which provides comprehensive career programs  

E-Print Network [OSTI]

#12;Dear Admitted Student and Parent: Welcome to Columbia University's Center for Career Education entrepreneurship and enterprise management skills. Columbia University Internship Network (CU In) Student (CCE) which provides comprehensive career programs and services to students in Columbia College (CC

Hone, James

474

The University of British Columbia | Department of Physical Therapy Strategic Plan 2010 2014 1 DEPARTMENT OF PHYSICAL THERAPY  

E-Print Network [OSTI]

The University of British Columbia | Department of Physical Therapy Strategic Plan 2010 ­ 2014 1 DEPARTMENT OF PHYSICAL THERAPY UNIVERSITY OF BRITISH COLUMBIA STRATEGIC PLAN 20102014 development. 3. Faculty members teaching assignments. #12;The University of British Columbia | Department

Michelson, David G.

475

Faculty Position Atomic, Molecular and Optical Physics The Columbia University Department of Physics seeks to appoint an assistant professor  

E-Print Network [OSTI]

Faculty Position Atomic, Molecular and Optical Physics The Columbia University Department November 1, 2014 and continue until the position is filled. Columbia University is an Equal Opportunity research program, continuing the long Columbia record of outstanding accomplishment in science. Applicants

Qian, Ning

476

Commercial Lighting  

Broader source: Energy.gov [DOE]

Commercial lighting accounts for more than 20 percent of total commercial building energy use. The Energy Department works to reduce lighting energy use through research and deployment.

477

Daily/Hourly Hydrosystem Operation : How the Columbia River System Responds to Short-Term Needs.  

SciTech Connect (OSTI)

The System Operation Review, being conducted by the Bonneville Power Administration, the US Army Corps of Engineers, and the US Bureau of Reclamation, is analyzing current and potential future operations of the Columbia River System. One goal of the System Operations Review is to develop a new System Operation Strategy. The strategy will be designed to balance the many regionally and nationally important uses of the Columbia River system. Short-term operations address the dynamics that affect the Northwest hydro system and its multiple uses. Demands for electrical power and natural streamflows change constantly and thus are not precisely predictable. Other uses of the hydro system have constantly changing needs, too, many of which can interfere with other uses. Project operators must address various river needs, physical limitations, weather, and streamflow conditions while maintaining the stability of the electric system and keeping your lights on. It takes staffing around the clock to manage the hour-to-hour changes that occur and the challenges that face project operators all the time.

Columbia River System Operation Review (U.S.)

1994-02-01T23:59:59.000Z

478

Solar space heating for the visitors' center, Stephens College, Columbia, Missouri. Final report  

SciTech Connect (OSTI)

This document is the final report of the solar energy system located at the Visitors' Center on the Stephens College Campus, Columbia, Missouri. The system is installed in a four-story, 15,000 square foot building designed to include the college's Admission Office, nine guest rooms for overnight lodging for official guests of the college, a two-story art gallery, and a Faculty Lounge. The solar energy system is an integral design of the building and utilizes 176 Honeywell/Lennox hydronic flat-plate collectors which use a 50% water-ethylene glycol solution and water-to-water heat exchanger. Solar heated water is stored in a 5000 gallon water storage tank located in the basement equipment room. A natural gas fired hot water boiler supplies hot water when the solar energy heat supply fails to meet the demand. The designed solar contribution is 71% of the heating load. The demonstration period for this project ends June 30, 1984.

Not Available

1980-06-01T23:59:59.000Z

479

Industrial Discharge Permits (District of Columbia)  

Broader source: Energy.gov [DOE]

All businesses and government agencies discharging process wastewater to the public sewer system must report their activities to DC Water's Pretreatment Center. Wastewater discharge permits are...

480

Reduction of the Radiotoxicity of Spent Nuclear Fuel Using a Two-Tiered System Comprising Light Water Reactors and Accelerator-Driven Systems  

SciTech Connect (OSTI)

Two main issues regarding the disposal of spent nuclear fuel from nuclear reactors in the United States in the geological repository Yucca Mountain are: (1) Yucca Mountain is not designed to hold the amount of fuel that has been and is proposed to be generated in the next few decades, and (2) the radiotoxicity (i.e., biological hazard) of the waste (particularly the actinides) does not decrease below that of natural uranium ore for hundreds of thousands of years. One solution to these problems may be to use transmutation to convert the nuclides in spent nuclear fuel to ones with shorter half-lives. Both reactor and accelerator-based systems have been examined in the past for transmutation; there are advantages and disadvantages associated with each. By using existing Light Water Reactors (LWRs) to burn a majority of the plutonium in spent nuclear fuel and Accelerator-Driven Systems (ADSs) to transmute the remainder of the actinides, the benefits of each type of system can be realized. The transmutation process then becomes more efficient and less expensive. This research searched for the best combination of LWRs with multiple recycling of plutonium and ADSs to transmute spent nuclear fuel from past and projected nuclear activities (assuming little growth of nuclear energy). The neutronic design of each system is examined in detail although thermal hydraulic performance would have to be considered before a final system is designed. The results are obtained using the Monte Carlo burnup code Monteburns, which has been successfully benchmarked for MOX fuel irradiation and compared to other codes for ADS calculations. The best combination of systems found in this research includes 41 LWRs burning mixed oxide fuel with two recycles of plutonium ({approx}40 years operation each) and 53 ADSs to transmute the remainder of the actinides from spent nuclear fuel over the course of 60 years of operation.

H.R. Trellue

2003-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "light columbia water" from the National Library of EnergyBeta (NLEBeta).
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481

A study of a zone approach to IAEA (International Atomic Energy Agency) safeguards: The low-enriched-uranium zone of a light-water-reactor fuel cycle  

SciTech Connect (OSTI)

At present the IAEA designs its safeguards approach with regard to each type of nuclear facility so that the safeguards activities and effort are essentially the same for a given type and size of nuclear facility wherever it may be located. Conclusions regarding a state are derived by combining the conclusions regarding the effectiveness of safeguards for the individual facilities within a state. In this study it was convenient to define three zones in a state with a closed light-water-reactor nuclear fuel cycle. Each zone contains those facilities or parts thereof which use or process nuclear materials of the same safeguards significance: low-enriched uranium, radioactive spent fuel, or recovered plutonium. The possibility that each zone might be treated as an extended material balance area for safeguards purposes is under investigation. The approach includes defining the relevant features of the facilities in the three zones and listing the safeguards activities which are now practiced. This study has focussed on the fresh-fuel zone, the several facilities of which use or process low-enriched uranium. At one extreme, flows and inventories would be verified at each material balance area. At the other extreme, the flows into and out of the zone and the inventory of the whole zone would be verified. There are a number of possible safeguards approaches which fall between the two extremes. The intention is to develop a rational approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the approach involving the zone as a material balance area, and for some reasonable intermediate safeguards approaches.

Fishbone, L.G.; Higinbotham, W.A.

1986-06-01T23:59:59.000Z

482

Revised February 2013 Page 1 of 1 University of Northern British Columbia Conference and Events Services  

E-Print Network [OSTI]

the laws of British Columbia. British Columbia law prohibits the consumption of alcoholic beverages smoke detectors in suites and common areas resulting in building-wide evacuation. 9.0 Pets

Northern British Columbia, University of

483

Participation by Columbia Researchers in Shared Central High Performance Computing (HPC) Resources  

E-Print Network [OSTI]

) to create a shared central high performance computing (HPC) cluster, ColumbiaParticipation by Columbia Researchers in Shared Central High Performance Computing (HPC) Resources Shared Research Computing Policy Advisory Committee (SRCPAC) Chair, Professor

Champagne, Frances A.

484

COLUMBIA ENGINEERING WINTER GLOBAL EDUCATIONAL EXPERIENCE: EXPLORING GLOBAL ENGINEERING WITH CITY UNIVERSITY OF HONG KONG  

E-Print Network [OSTI]

COLUMBIA ENGINEERING WINTER GLOBAL EDUCATIONAL EXPERIENCE: EXPLORING GLOBAL ENGINEERING WITH CITY UNIVERSITY OF HONG KONG JANUARY 7th ­ 15TH , 2012 Program Features The Winter Global Educational Experience is open to Columbia Engineering

Hone, James

485

SHAHNOZA BOBOEVA Columbia University, The Fu Foundation School of Engineering and Applied Science New York, NY  

E-Print Network [OSTI]

SHAHNOZA BOBOEVA EDUCATION Columbia University, The Fu Foundation School of Engineering and Applied, Economic Theory PROJECT EXPERIENCE Columbia University Master's Thesis New York, NY Potential of Air Branch of Technological University of Tajikistan Khujand, Tajikistan Faculty "Agrotechnology" 2004

486

University of British Columbia Faraday Show is UBC Physics & Astronomy Outreach Program's  

E-Print Network [OSTI]

University of British Columbia Faraday Show is UBC Physics & Astronomy Outreach Program's annual Outreach Program University of British Columbia Email: outreach@phas.ubc.ca; Phone: 604-822-3675 #12;

Karczmarek, Joanna

487

1993-1994 Final technical report for establishing the SECME Model in the District of Columbia  

SciTech Connect (OSTI)

This is the final report for a program to establish the SECME Model in the District of Columbia. This program has seen the development of a partnership between the District of Columbia Public Schools, the University of the District of Columbia, the Department of Energy, and SECME. This partnership has demonstrated positive achievement in mathematics and science education and learning in students within the District of Columbia.

Vickers, R.G.

1995-12-31T23:59:59.000Z

488

SUBMITTED TO: THE D.C. WATER RESOURCES RESEARCH CENTER  

E-Print Network [OSTI]

chemicals and heavy metals such as lead'. Several published reports have suggested that D.C. public waterMARCH 1996 SUBMITTED TO: THE D.C. WATER RESOURCES RESEARCH CENTER UNIVERSITY OF THE DISTRICT OF COLUMBIA WASHINGTON, D.C. 20008 SUBMITTED BY: DR. KWAMENA OCRAN LEAD IN RESIDENTIAL DRINKING WATER: RISK

District of Columbia, University of the

489

EIS-0425: Mid-Columbia Coho Restoration, Washington  

Broader source: Energy.gov [DOE]

This EIS evaluates the environmental impacts of DOEs Bonneville Power Administrations proposal to fund the construction, operation, and maintenance of a coho salmon restoration program sponsored by the Confederated Tribes and Bands of the Yakama Nation to help mitigate impacts to fish affected by the Federal Columbia River Power System dams on the Columbia River. The Proposed Action would involve building a new, small, in-basin adult holding/spawning, incubation and rearing facility on the Wenatchee River at one of two potential sites; and constructing and improving several sites in both the Wenatchee and Methow river basins in north central Washington State.

490

Columbia River Basin Accords -Narrative Proposal Form 1 200880000 ISRP FAN1B  

E-Print Network [OSTI]

: The Columbia Basin Fish Accords (Accords) are ten-year agreements between the federal action agencies and states and tribes. The Accords supplement the Columbia Basin Fish and Wildlife Program and are intended substantial biological benefits for Columbia Basin fish. The Accords also acknowledge the tribes' and states

491

Columbia University in the City of New York Department of Biomedical Engineering Graduate Student  

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Columbia University in the City of New York Department of Biomedical Engineering Graduate Student Handbook 2009-2010 Academic Year Welcome to Columbia BME! The evolution of biomedical engineering of Columbia University's Department of Biomedical Engineering. Focusing in the areas of biomechanics, cell

Hone, James

492

SECTION 34 Table of Contents 34 Upper Columbia Management Plan..............................................................2  

E-Print Network [OSTI]

and formation of the Subbasin Work Teams and the process used to develop and adopt the management plan can34-1 SECTION 34 ­ Table of Contents 34 Upper Columbia Management Plan .........................................................................25 #12;34-2 34 Upper Columbia Management Plan The Upper Columbia Subbasin Management Plan

493

Spatial Distribution of Juvenile Salmonids in the Hanford Reach, Columbia River  

E-Print Network [OSTI]

Spatial Distribution of Juvenile Salmonids in the Hanford Reach, Columbia River Dennis D. Dauble salmon, sockeye salmon. and steelhead was determined in the Hanford Reach of the Columbia River from July field studies conducted in the Hanford Reach ofthe mid-Columbia River in 1983 and 1984. The Hanford

494

THE UNIVERSITY OF BRITISH COLUMBIATHE UNIVERSITY OF BRITISH COLUMBIA ANNUAL REPORT 2000 / 2001  

E-Print Network [OSTI]

THE UNIVERSITY OF BRITISH COLUMBIATHE UNIVERSITY OF BRITISH COLUMBIA #12;ANNUAL REPORT 2000 / 2001 & Partnerships 17-18 Financial Summary 19-20 Notes to Financial Summary 20 #12;The University of British Columbia MISSION The University of British Columbia will provide its students, faculty, and staff with the best

Ollivier-Gooch, Carl

495

TITLE: NON-RETALIATION Columbia University Medical Center will refrain from intimidating, threatening, coercing,  

E-Print Network [OSTI]

TITLE: NON-RETALIATION POLICY: Columbia University Medical Center will refrain from intimidating : Columbia University Medical Center is committed to protecting patient privacy as mandated by city, state-retaliation for exercising rights or reporting actual or suspected violations Columbia University Medical Center

Columbia University

496

Columbia University in the City of New York THE UNIVERSITY SEMINARS  

E-Print Network [OSTI]

Columbia University in the City of New York THE UNIVERSITY SEMINARS 2nd Floor, Faculty House, 64 Morningside Dr, MC 2302, New York, NY 10027 Phone: 212.854.2389| Fax: 212.854.8248 Email: univ.seminars@columbia.edu Web: http://universityseminars.columbia.edu Rev. 6/2/2013 CURRICULUM VITAE for Nomination of Associate

Champagne, Frances A.

497

Columbia University in the City of New York THE UNIVERSITY SEMINARS  

E-Print Network [OSTI]

Columbia University in the City of New York THE UNIVERSITY SEMINARS 2nd Floor, Faculty House, 64 Moringside Drive, MC 2302, New York, NY 10027 Phone: 212.854.2389| Fax: 212.854.8248 Email: univ.seminars@columbia on reverse or include an attachment): HAVE YOU HAD A PREVIOUS APPOINTMENT AT COLUMBIA? YES NO IF "YES", STATE

Champagne, Frances A.

498

University of Northern British Columbia & BC Rural & Remote Health Research Network  

E-Print Network [OSTI]

University of Northern British Columbia & BC Rural & Remote Health Research Network Provincial in the province. The University of Northern British Columbia is the secretariat for the BCRRHRN and satellite sites are located at the University of British Columbia and the University of Victoria. Duties

Bolch, Tobias

499

The Potential for Scholarly Online Books: Views from the Columbia University  

E-Print Network [OSTI]

The Potential for Scholarly Online Books: Views from the Columbia University Online Books Evaluation Project* Mary Summerfield, Carol Mandel, and Paul Kantor The Columbia University Online Books Project, Columbia University: Final Report and many other reports and papers, including the re- search

500

Copyright A. J. Millis 2013 Columbia University Electron-electron interactions  

E-Print Network [OSTI]

Copyright A. J. Millis 2013 Columbia University Electron-electron interactions #12;Copyright A. J. Millis 2013 Columbia University Free fermions: reminder H = - i 2 i 2m + 1 2 i=j e2 |ri - rj| Bohr;Copyright A. J. Millis 2013 Columbia University d orbitals are small relative to spacing between transition

Millis, Andrew