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1

Distribution of characteristics of LWR [light water reactor] spent fuel  

SciTech Connect

The purpose of this report is to develop a collective description of the entire spent fuel inventory in terms of various fuel properties relevant to Approved Testing Materials (ATMs) using information available from the Characteristics Data Base (CBD), which is sponsored by the US Department of Energy`s (DOE`s) Office of Civilian Radioactive Waste Management. A number of light-water reactor (LWR) characteristics were analyzed including assembly class representation, fuel burnup, enrichment, fuel fabrication data, defective fuel quantities, and, at PNL`s specific request, linear heat generation rate (LHGR) and the utilization of burnable poisons. A quantitative relationships was developed between burnup and enrichment for BWRs and PWRs. The relationship shows that the existing BWR ATM is near the center of the burnup-enrichment distribution, while the four PWR ATMs bracket the center of the burnup range but are on the low side of the enrichment range. Fuel fabrication data are based on vendor specifications for new fuel. Defective fuel distributions were analyzed in terms of assembly class and vendor design. LHGR values were calculated from utility data on burnup and effective full-power days; these calculations incorporate some unavoidable assumptions which may compromise the value of the results. Only a limited amount of data are available on burnable poisons at this time. Based on this distribution study, suggestions for additional ATMs are made. These are based on the class and design concepts and include BWR/2,3 barrier fuel, and the WE 17 {times} 17 class with integral burnable poison. Both should be at relatively high burnups. 16 refs., 5 figs., 15 tabs.

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

1991-01-01T23:59:59.000Z

2

Recycle of LWR (Light Water Reactor) actinides to an IFR (Integral Fast Reactor)  

SciTech Connect

A large quantity of actinide elements is present in irradiated Light Water Reactor (LWR) fuel that is stored throughout the world. Because of the high fission-to-capture ratio for the transuranium (TRU) elements with the high-energy neutrons in the metal-fueled Integral Fast Reactor (IFR), that reactor can consume these elements effectively. The stored fuel represents a valuable resource for an expanding application of fast power reactors. In addition, removal of the TRU elements from the spent LWR fuel has the potential for increasing the capacity of a high-level waste facility by reducing the heat loads and increasing the margin of safety in meeting licensing requirements. Argonne National Laboratory (ANL) is developing a pyrochemical process, which is compatible with the IFR fuel cycle, for the recovery of TRU elements from LWR fuel. The proposed product is a metallic actinide ingot, which can be introduced into the electrorefining step of the IFR process. The major objective of the LWR fuel recovery process is high TRU element recovery, with decontamination a secondary issue, because fission product removal is accomplished in the IFR process. The extensive pyrochemical processing studies of the 1960s and 1970s provide a basis for the design of possible processes. Two processes were selected for laboratory-scale investigation. One is based on the Salt Transport Process studied at ANL for mixed-oxide fast reactor fuel, and the other is based on the blanket processing studies done for ANL's second Experimental Breeder Reactor (EBR-2). This paper discusses the two processes and is a status report on the experimental studies. 5 refs., 2 figs., 2 tabs.

Pierce, R.D.; Ackerman, J.P.; Johnson, G.K.; Mulcahey, T.P.; Poa, D.S.

1991-01-01T23:59:59.000Z

3

Storage of LWR (light-water-reactor) spent fuel in air  

Science Conference Proceedings (OSTI)

An experimental program is being conducted at Pacific Northwest Laboratory (PNL) to determine the oxidation response of light-water-reactor (LWR) spent fuels under conditions appropriate to fuel storage in air. The program is designed to investigate several independent variables that might affect the oxidation behavior of spent fuel. Included are temperature (135 to 230{degree}C), fuel burnup (to about 34 MWd/kgM), reactor type (pressurized and boiling water reactors), moisture level in the air, and the presence of a high gamma field. In continuing tests with declad spent fuel and nonirradiated UO{sub 2} specimens, oxidation rates were monitored by weight-gain measurements and the microstructures of subsamples taken during the weighing intervals were characterized by several analytical methods. The oxidation behavior indicated by weight gain and time to form powder will be reported in Volume III of this series. The characterization results obtained from x-ray diffractometry, transmission electron microscopy, scanning electron microscopy, and Auger electron spectrometry of oxidized fuel samples are presented in this report. 28 refs., 21 figs., 3 tabs.

Thomas, L.E.; Charlot, L.A.; Coleman, J.E. (Pacific Northwest Lab., Richland, WA (USA)); Knoll, R.W. (Johnson Controls, Inc., Madison, WI (USA))

1989-12-01T23:59:59.000Z

4

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

Science Conference Proceedings (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

5

Experience with non-fuel-bearing components in LWR (light-water reactor) fuel systems  

SciTech Connect

Many non-fuel-bearing components are so closely associated with the spent fuel assemblies that their integrity and behavior must be taken into consideration with the fuel assemblies, when handling spent fuel of planning waste management activities. Presented herein is some of the experience that has been gained over the past two decades from non-fuel-bearing components in light-water reactors (LWRs), both pressurized-water reactors (PWRs) and boiling-water reactors (BWRs). Among the most important of these components are the control rod systems, the absorber and burnable poison rods, and the fuel assembly channels. 15 refs., 5 figs., 2 tabs.

Bailey, W.J.; Berting, F.M.

1990-12-01T23:59:59.000Z

6

Evaluation of conceptual flowsheets for incorporating Light Water Reactor (LWR) fuel materials in an advanced nuclear fuel cycle  

SciTech Connect

A preliminary study by a group of experts at ORNL has generated and evaluated a number of aqueous and non-aqueous flowsheets for recovering transuranium actinides from LWR fuel for use as fuel in an LMR and, at the same time, for transmutation of the wastes to less hazardous materials. The need for proliferation resistance was a consideration in the flowsheets. The current state of development of the flowsheets was evaluated and recommendations for additional study were made. 3 refs., 6 figs.

Bell, J.T.; Burch, W.D.; Collins, E.D.; Forsberg, C.W.; Prince, B.E.; Bond, W.D.; Campbell, D.O.; Delene, J.G.; Mailen, J.C.

1990-08-01T23:59:59.000Z

7

Control of degradation of spent LWR (light-water reactor) fuel during dry storage in an inert atmosphere  

DOE Green Energy (OSTI)

Dry storage of Zircaloy-clad spent fuel in inert gas (referred to as inerted dry storage or IDS) is being developed as an alternative to water pool storage of spent fuel. The objectives of the activities described in this report are to identify potential Zircaloy degradation mechanisms and evaluate their applicability to cladding breach during IDS, develop models of the dominant Zircaloy degradation mechanisms, and recommend cladding temperature limits during IDS to control Zircaloy degradation. The principal potential Zircaloy cladding breach mechanisms during IDS have been identified as creep rupture, stress corrosion cracking (SCC), and delayed hydride cracking (DHC). Creep rupture is concluded to be the primary cladding breach mechanism during IDS. Deformation and fracture maps based on creep rupture were developed for Zircaloy. These maps were then used as the basis for developing spent fuel cladding temperature limits that would prevent cladding breach during a 40-year IDS period. The probability of cladding breach for spent fuel stored at the temperature limit is less than 0.5% per spent fuel rod. 52 refs., 7 figs., 1 tab.

Cunningham, M.E.; Simonen, E.P.; Allemann, R.T.; Levy, I.S.; Hazelton, R.F.

1987-10-01T23:59:59.000Z

8

Evaluation of cover gas impurities and their effects on the dry storage of LWR (light-water reactor) spent fuel  

DOE Green Energy (OSTI)

The purposes of this report are to (1) identify the sources of impurity gases in spent fuel storage casks; (2) identify the expected concentrations and types of reactive impurity gases from these sources over an operating lifetime of 40 years; and (3) determine whether these impurities could significantly degrade cladding or exposed fuel during this period. Four potential sources of impurity gases in the helium cover gas in operating casks were identified and evaluated. Several different bounding cases have been considered, where the reactive gas inventory is either assumed to be completely gettered by the cladding or where all oxygen is assumed to react completely with the exposed fuel. It is concluded that the reactive gas inventory will have no significant effect on the cladding unless all available oxygen reacts with the UO/sub 2/ fuel to produce U/sub 3/O/sub 8/ at one or two cladding breaches. Based on Zircaloy oxidation data, the oxygen inventory in a fully loaded pressurized water reactor cask such as the Castor-V/21 will be gettered by the Zircaloy cladding in about 1 year if the peak cladding temperature within the task is greater than or equal to300/sup 0/C. Only a negligible decrease in the thickness of the cladding would result. 24 refs., 4 tabs.

Knoll, R.W.; Gilbert, E.R.

1987-11-01T23:59:59.000Z

9

DESTRUCTIVE EXAMINATION OF 3-CYCLE LWR (LIGHT WATER REACTOR) FUEL RODS FROM TURKEY POINT UNIT 3 FOR THE CLIMAX - SPENT FUEL TEST  

DOE Green Energy (OSTI)

The destructive examination results of five light water reactor rods from the Turkey Point Unit 3 reactor are presented. The examinations included fission gas collection and analyses, burnup and hydrogen analyses, and a metallographic evaluation of the fuel, cladding, oxide, and hydrides. The rods exhibited a low fission gas release with all other results appearing representative for pressurized water reator fuel rods with similar burnups (28 GWd/MTU) and operating histories.

ATKIN SD

1981-06-01T23:59:59.000Z

10

Light Water Reactor Sustainability Technical Documents | Department of  

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

Initiatives » Nuclear Reactor Technologies » Light Water Reactor Initiatives » Nuclear Reactor Technologies » Light Water Reactor Sustainability Program » Light Water Reactor Sustainability Technical Documents Light Water Reactor Sustainability Technical Documents September 30, 2011 Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR licenses are now being extended from 40y to 60y by the U.S. Nuclear Regulatory Commission (NRC) with intentions to extend licenses to 80y and beyond. The RPV materials exhibit varying degrees of sensitivity to irradiation-induced embrittlement

11

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.

12

Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation: Appendix 2A, Physical descriptions of LWR (Light-Water Reactor) fuel assemblies  

SciTech Connect

This appendix includes a four-page Physical Description report for each assembly type identified from the current data. Where available, a drawing of an assembly follows the appropriate Physical Description report. If no drawing is available for an assembly, a cross-reference to a similar assembly is provided if possible. For Advanced Nuclear Fuels, Babcock and Wilcox, Combustion Engineering, and Westinghouse assemblies, information was obtained via subcontracts with these fuel vendors. Data for some assembly types are not available. For such assemblies, the information shown in this report was obtained from the open literature and by inference from reload fuels made by other vendors. Efforts to obtain additional information are continuing. Individual Physical Description reports can be generated interactively through the menu-driven LWR Assemblies Data Base system. These reports can be viewed on the screen or directed to a printer. Special reports and compilations of specific data items can be produced on request.

Not Available

1987-12-01T23:59:59.000Z

13

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

14

Light Water Reactors Technology Development - Nuclear Reactors  

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

Light Water Reactors Light Water Reactors About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

15

Technologies for Upgrading Light Water Reactor Outlet Temperature  

SciTech Connect

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

16

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

17

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

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

Light Water Reactor Fuel Cladding Research Light Water Reactor Fuel Cladding Research June 01, 2013 Severe Accident Test Station ORNL is the focus point for Light Water Reactor (LWR) fuel cladding research and testing. The purpose of this research is to furnish U.S. industry (EPRI, Areva, Westinghouse), and regulators (NRC) with much-needed data supporting safe and economical nuclear power generation and used fuel management. LWR fuel cladding work is tightly integrated with ORNL accident tolerant fuel development and used fuel disposition programs thereby providing a powerful capability that couples basic materials science research with the nuclear applications research and development. The ORNL LWR fuel cladding program consists of five complementary areas of research: Accident tolerant fuel and cladding material testing under design

18

Advanced Light Water Reactor - Boiling Water Reactor Degradation Matrix (ALWR BWR DM), Revision 0  

Science Conference Proceedings (OSTI)

The advanced light water reactorboiling water reactor degradation matrix (ALWR BWR DM) is an essential piece of the Electric Power Research Institutes (EPRIs) Advanced Nuclear Technology (ANT) materials management matrix initiative for advanced LWR designs. The materials management matrix provides a tool to assist the industry in proactive identification and consideration of materials issues as well as mitigation and management opportunities from the design phase, through component fabrication and pla...

2009-08-25T23:59:59.000Z

19

Assessment of high-burnup LWR fuel response to reactivity-initiated accidents  

E-Print Network (OSTI)

The economic advantages of longer fuel cycle, improved fuel utilization and reduced spent fuel storage have been driving the nuclear industry to pursue higher discharge burnup of Light Water Reactor (LWR) fuel. A design ...

Liu, Wenfeng, Ph.D. Massachusetts Institute of Technology

2007-01-01T23:59:59.000Z

20

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

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

Columbia Water & Light- Solar Rebates  

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

Columbia Water & 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...

22

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

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

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

23

Metal-fueled HWR (heavy water reactors) severe accident issues: Differences and similarities to commercial LWRs (light water reactors)  

DOE Green Energy (OSTI)

Differences and similarities in severe accident progression and phenomena between commercial Light Water Reactors (LWR) and metal-fueled isotopic production Heavy Water Reactors (HWR) are described. It is very important to distinguish between accident progression in the two systems because each reactor type behaves in a unique manner to a fuel melting accident. Some of the lessons learned as a result of the extensive commercial severe accident research are not applicable to metal-fueled heavy water reactors. A direct application of severe accident phenomena developed from oxide-fueled LWRs to metal-fueled HWRs may lead to large errors or substantial uncertainties. In general, the application of severe accident LWR concepts to HWRs should be done with the intent to define the relevant issues, define differences, and determine areas of overlap. This paper describes the relevant differences between LWR and metal-fueled HWR severe accident phenomena. Also included in the paper is a description of the phenomena that govern the source term in HWRs, the areas where research is needed to resolve major uncertainties, and areas in which LWR technology can be directly applied with few modifications.

Ellison, P.G.; Hyder, M.L.; Monson, P.R. (Westinghouse Savannah River Co., Aiken, SC (USA)); Coryell, E.W. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-01-01T23:59:59.000Z

24

Program on Technology Innovation: Prediction and Evaluation of Environmentally Assisted Cracking in LWR Structural Materials  

Science Conference Proceedings (OSTI)

This report describes the final results of Phase III of a three-year joint research program sponsored by EPRI in collaboration with Fracture & Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor (LWR) structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) environments.

2007-11-20T23:59:59.000Z

25

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

SciTech Connect

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

Not Listed

2011-11-01T23:59:59.000Z

26

Baseline descriptions for LWR spent fuel storage, handling, and transportation  

SciTech Connect

Baseline descriptions for the storage, handling, and transportation of reactor spent fuel are provided. The storage modes described include light water reactor (LWR) pools, away-from-reactor basins, dry surface storage, reprocessing-facility interim storage pools, and deep geologic storage. Land and water transportation are also discussed. This work was sponsored by the Department of Energy/Office of Safeguards and Security as part of the Sandia Laboratories Fixed Facility Physical Protection Program. 45 figs, 4 tables.

Moyer, J.W.; Sonnier, C.S.

1978-04-01T23:59:59.000Z

27

Report on Assessment of Environmentally--Assisted Fatigue for LWR Extended  

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

on Assessment of Environmentally--Assisted Fatigue for LWR on Assessment of Environmentally--Assisted Fatigue for LWR Extended Service Conditions Report on Assessment of Environmentally--Assisted Fatigue for LWR Extended Service Conditions This report provides an update on the assessment of environmentally-assisted fatigue for light water reactor (LWR) extended service conditions. The report is a deliverable in FY11 under the work package for LWRS under the Advanced Reactor Concepts. Most of the current fleet of aging LWRs were designed using the 1970s version of the ASME Boiler and Pressure Vessels Code, Section III, and are reaching their design lifetime of 30-40 yrs. For economic reasons, the utilities have great interest in extending the operating life of the plants via the Nuclear Regulatory Commission (NRC) licensing renewal application

28

Report on Assessment of Environmentally--Assisted Fatigue for LWR Extended  

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

on Assessment of Environmentally--Assisted Fatigue for LWR on Assessment of Environmentally--Assisted Fatigue for LWR Extended Service Conditions Report on Assessment of Environmentally--Assisted Fatigue for LWR Extended Service Conditions This report provides an update on the assessment of environmentally-assisted fatigue for light water reactor (LWR) extended service conditions. The report is a deliverable in FY11 under the work package for LWRS under the Advanced Reactor Concepts. Most of the current fleet of aging LWRs were designed using the 1970s version of the ASME Boiler and Pressure Vessels Code, Section III, and are reaching their design lifetime of 30-40 yrs. For economic reasons, the utilities have great interest in extending the operating life of the plants via the Nuclear Regulatory Commission (NRC) licensing renewal application

29

Flow-induced vibration for light-water reactors. Progress report, April 1978-December 1979  

SciTech Connect

Flow-Induced vibration for Light Water Reactors (FIV for LWRs) is a four-year program designed to improve the FIV performance of light water reactors through the development of design criteria, analytical models for predicting behavior of components, general scaling laws to improve the accuracy of reduced-scale tests, and the identification of high FIV risk areas. The program commenced December 1, 1976, but was suspended on September 30, 1978, due to a shift in Department of Energy (DOE) priorities away from LWR productivity/availability. It was reinitiated as of August 1, 1979. This progress report summarizes the accomplishments achieved during the period from April 1978 to December 1979.

Schardt, J. F.

1980-03-01T23:59:59.000Z

30

Cedarburg Light & Water Utility - Residential Energy Efficiency...  

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

Cedarburg Light & Water Utility - Residential Energy Efficiency Rebate Program Cedarburg Light & Water Utility - Residential Energy Efficiency Rebate Program Eligibility Low-Income...

31

Light Water Reactor Sustainability Program: Integrated Program...  

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

Light Water Reactor Sustainability Program: Integrated Program Plan Light Water Reactor Sustainability Program: Integrated Program Plan Nuclear power has safely, reliably, and...

32

Environmentally assisted cracking in light water reactors.  

DOE Green Energy (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 2002. Topics that have been investigated include: (a) environmental effects on fatigue crack initiation in carbon and low-alloy steels and austenitic stainless steels (SSs), (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic SSs in BWRs, (c) evaluation of causes and mechanisms of irradiation-assisted cracking of austenitic SS in PWRs, and (d) cracking in Ni-alloys and welds. A critical review of the ASME Code fatigue design margins and an assessment of the conservation in the current choice of design margins are presented. The existing fatigue {var_epsilon}-N data have been evaluated to define the effects of key material, loading, and environmental parameters on the fatigue lives of carbon and low-alloy steels and austenitic SSs. Experimental data are presented on the effects of surface roughness on fatigue crack initiation in these materials in air and LWR environments. Crack growth tests were performed in BWR environments on SSs irradiated to 0.9 and 2.0 x 10{sup 21} n x cm{sup -2}. The crack growth rates (CGRs) of the irradiated steels are a factor of {approx}5 higher than the disposition curve proposed in NUREG-0313 for thermally sensitized materials. The CGRs decreased by an order of magnitude in low-dissolved oxygen (DO) environments. Slow-strain-rate tensile (SSRT) tests were conducted in high-purity 289 C water on steels irradiated to {approx}3 dpa. The bulk S content correlated well with the susceptibility to intergranular SCC in 289 C water. The IASCC susceptibility of SSs that contain >0.003 wt. % S increased drastically. bend tests in inert environments at 23 C were conducted on broken pieces of SSRT specimens and on unirradiated specimens of the same materials after hydrogen charging. The results of the tests and a review of other data in the literature indicate that IASCC in 289 C water is dominated by a crack-tip grain-boundary process that involves S. An initial IASCC model has been proposed. A crack growth test was completed on mill annealed Alloy 600 in high-purity water at 289 C and 320 C under various environmental and loading conditions. The results from this test are compared with data obtained earlier on several other heats of Alloy 600.

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

2007-11-06T23:59:59.000Z

33

Columbia Water and Light - HVAC and Lighting Efficiency Rebates |  

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

Columbia Water and Light - HVAC and Lighting Efficiency Rebates Columbia Water and Light - HVAC and Lighting Efficiency Rebates Columbia Water and Light - HVAC and Lighting Efficiency Rebates < Back Eligibility Commercial Industrial Savings Category Heating & Cooling Commercial Heating & Cooling Cooling Heat Pumps Appliances & Electronics Commercial Lighting Lighting Maximum Rebate Lighting: 50% of invoiced cost up to $22,500 Program Info State Missouri Program Type Utility Rebate Program Rebate Amount HVAC Replacements: $570 - $3,770 Lighting: $300/kW reduction or half of project cost Provider Columbia Water and Light 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 measures are based upon the

34

Columbia Water & Light- HVAC and Lighting Efficiency Rebates  

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

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

35

A review of irradiation effects on LWR core internal materials - IASCC susceptibility and crack growth rates of austenitic stainless steels.  

SciTech Connect

Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to neutron irradiation for extended periods changes the microstructure (radiation hardening) and microchemistry (radiation-induced segregation) of these steels, and degrades their fracture properties. Irradiation-assisted stress corrosion cracking (IASCC) is another degradation process that affects LWR internal components exposed to neutron radiation. The existing data on irradiated austenitic SSs were reviewed to evaluate the effects of key parameters such as material composition, irradiation dose, and water chemistry on IASCC susceptibility and crack growth rates of these materials in LWR environments. The significance of microstructural and microchemistry changes in the material on IASCC susceptibility is also discussed. The results are used to determine (a) the threshold fluence for IASCC and (b) the disposition curves for cyclic and IASCC growth rates for irradiated SSs in LWR environments.

Chopra, O. K.; Roa, A. S.; Environmental Science Division; U.S. NRC

2010-12-15T23:59:59.000Z

36

Use of Thorium in Light Water Reactors  

Science Conference Proceedings (OSTI)

Technical Paper / Advances in Nuclear Fuel Management - Use of Alternate Fuels in Light Water Reactors

Michael Todosow; A. Galperin; S. Herring; M. Kazimi; T. Downar; A. Morozov

37

Thermal Expansion Coefficient of Steels Used in LWR Vessels  

Science Conference Proceedings (OSTI)

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

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

2008-05-01T23:59:59.000Z

38

High temperature thermal properties for metals used in LWR vessels  

Science Conference Proceedings (OSTI)

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

Joy L. Rempe

2008-01-01T23:59:59.000Z

39

LIGHT WATER MODERATED NEUTRONIC REACTOR  

DOE Patents (OSTI)

A uranium fuel reactor designed to utilize light water as a moderator is described. The reactor core is in a tank at the bottom of a substantially cylindrical cross-section pit, the core being supported by an apertured grid member and comprised of hexagonal tubes each containing a pluralily of fuel rods held in a geometrical arrangement between end caps of the tubes. The end caps are apertured to permit passage of the coolant water through the tubes and the fuel elements are aluminum clad to prevent corrosion. The tubes are hexagonally arranged in the center of the tank providing an amulus between the core and tank wall which is filled with water to serve as a reflector. In use, the entire pit and tank are filled with water in which is circulated during operation by coming in at the bottom of the tank, passing upwardly through the grid member and fuel tubes and carried off near the top of the pit, thereby picking up the heat generated by the fuel elements during the fission thereof. With this particular design the light water coolant can also be used as the moderator when the uranium is enriched by fissionable isotope to an abundance of U/sup 235/ between 0.78% and 2%.

Christy, R.F.; Weinberg, A.M.

1957-09-17T23:59:59.000Z

40

Integrity of neutron-absorbing components of LWR fuel systems  

Science Conference Proceedings (OSTI)

A study of the integrity and behavior of neutron-absorbing components of light-water (LWR) fuel systems was performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE). The components studies include control blades (cruciforms) for boiling-water reactors (BWRs) and rod cluster control assemblies for pressurized-water reactors (PWRs). The results of this study can be useful for understanding the degradation of neutron-absorbing components and for waste management planning and repository design. The report includes examples of the types of degradation, damage, or failures that have been encountered. Conclusions and recommendations are listed. 84 refs.

Bailey, W.J.; Berting, F.M.

1991-03-01T23:59:59.000Z

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

Sustained Recycle in Light Water and Sodium-Cooled Reactors  

Science Conference Proceedings (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

42

Program on Technology Innovation: Prediction and Evaluation of Environmentally Assisted Cracking in LWR Structural Materials  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E, a five-year extension of the joint research program sponsored by EPRI in collaboration with Fracture & Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor (LWR) structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) environments.

2009-12-16T23:59:59.000Z

43

Cedarburg Light & Water Utility - Commercial Energy Efficiency...  

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

Energy Efficiency Rebate Program Cedarburg Light & Water Utility - Commercial Energy Efficiency Rebate Program Eligibility Agricultural Commercial Fed. Government Industrial Local...

44

Program on Technology Innovation: Prediction and Evaluation of Environmentally Assisted Cracking in LWR Structural Materials: 2011 P EACE-E Phase II Report  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E, a joint research program sponsored by the Electric Power Research Institute (EPRI) in collaboration with the Fracture & Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor (LWR) structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) ...

2012-12-23T23:59:59.000Z

45

Low-temperature Swelling in LWR Internal Components: Current Data and  

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

Low-temperature Swelling in LWR Internal Components: Current Data Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment Recent experimental observations have made it clear that cavity formation can occur in light-water reactor internal components fabricated from austenitic stainless during the course of their service life. In order to assess the potential for cavity swelling in these components at end-of-life doses, it is necessary to develop a validated computational model that incorporates the relevant physical mechanisms and accounts for recent experiment data. Such a modeling activity is underway; the model development and some preliminary results are described. For the relatively low temperatures involved, cavity formation is shown to be sensitive to

46

Low-temperature Swelling in LWR Internal Components: Current Data and  

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

Low-temperature Swelling in LWR Internal Components: Current Data Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment Recent experimental observations have made it clear that cavity formation can occur in light-water reactor internal components fabricated from austenitic stainless during the course of their service life. In order to assess the potential for cavity swelling in these components at end-of-life doses, it is necessary to develop a validated computational model that incorporates the relevant physical mechanisms and accounts for recent experiment data. Such a modeling activity is underway; the model development and some preliminary results are described. For the relatively low temperatures involved, cavity formation is shown to be sensitive to

47

Accident Tolerant Fuels for Light Water Reactors  

Science Conference Proceedings (OSTI)

Presentation Title, Accident Tolerant Fuels for Light Water Reactors. Author(s), Steven J. Zinkle, Kurt A. Terrani, Lance L. Snead. On-Site Speaker (Planned)...

48

Columbia Water & Light- Residential HVAC Rebate Program  

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

Columbia Water & 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...

49

Detection and characterization of flaws in segments of light water reactor pressure vessels  

Science Conference Proceedings (OSTI)

Studies have been conducted to determine flaw density in segments cut from light water reactor (LWR) pressure vessels as part of the Oak Ridge National Laboratory's Heavy-Section Steel Technology (HSST) Program. Segments from the Hope Creek Unit 2 vessil and the Pilgrim Unit 2 Vessel were purchased from salvage dealers. Hope Creek was a boiling water reactor (BWR) design and Pilgrim was a pressurized water reactor (PWR) design. Neither were ever placed in service. Objectives were to evaluate these LWR segments for flaws with ultrasonic and liquid penetrant techniques. Both objectives were successfully completed. One significant indication was detected in a Hope Creek seam weld by ultrasonic techniques and characterized by further analyses terminating with destructive correlation. This indication (with a through-wall dimension of approx.6 mm (approx.0.24 in.)) was detected in only 3 m (10 ft) of weldment and offers extremely limited data when compared to the extent of welding even in a single pressure vessel. However, the detection and confirmation of the flaw in the arbitrarily selected sections implies the Marshall report estimates (and others) are nonconservative for such small flaws. No significant indications were detected in the Pilgrim material by ultrasonic techniques. Unfortunately, the Pilgrim segments contained relatively little weldment; thus, we limited our ultrasonic examinations to the cladding and subcladding regions. Fluorescent liquid penetrant inspection of the cladding surfaces for both LWR segments detected no significant indications (i.e., for a total of approximately 6.8 m/sup 2/ (72 ft/sup 2/) of cladding surface).

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

1987-01-01T23:59:59.000Z

50

Program on Technology Innovation: Environmentally Assisted Cracking in LWR Structural Materials--2009-10 PEACE-E Annual Report  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E Phase-1, a three-year joint research program sponsored by EPRI in collaboration with Fracture Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor (LWR) structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) environments. PEACE-E Phase-1 focuses on combining multiple a...

2010-12-15T23:59:59.000Z

51

Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment  

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

LTR-2012/390 LTR-2012/390 Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment R. E. Stoller, A. V. Barashev, and S. I. Golubov Materials Science and Technology Division Oak Ridge National Laboratory Prepared for: Light Water Reactor Sustainability Program Office of Nuclear Energy, Science and Technology U.S. Department of Energy September 2012 ORNL/LTR-2012/390 1 Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment Abstract Recent experimental observations have made it clear that cavity formation can occur in light-water reactor internal components fabricated from austenitic stainless during the course of their service life. In order to assess the potential for cavity swelling

52

Light Water Reactor Sustainability Nondestructive Evaluation...  

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

to the safety of LWR plants include the containment building, spent fuel pool, and cooling towers. This use has made its long-term performance crucial for the safe operation...

53

Advanced LWR Fuel Testing Capabilities in the ORNL High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

A new test capability for the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) is being developed that will allow testing of advanced nuclear fuels and cladding materials under prototypic light-water reactor (LWR) operating conditions in less time than it takes in other research reactors. This paper will describe the HFIR testing capabilities, the new advanced fuel/cladding testing facilities, and the initial cooperative irradiation experiments currently planned to start in late 2008.

Ott, Larry J [ORNL; McDuffee, Joel Lee [ORNL; Spellman, Donald J [ORNL

2008-01-01T23:59:59.000Z

54

Effects of LWR coolant environments on fatigue lives of austenitic stainless steels  

Science Conference Proceedings (OSTI)

The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not explicitly address the effects of reactor coolant environments on fatigue life. Recent test data indicate a significant decrease in fatigue life of pressure vessel and piping materials in light water reactor (LWR) environments. Fatigue tests have been conducted on Types 304 and 316NG stainless steel in air and LWR environments to evaluate the effects of various material and loading variables, e.g., steel type, strain rate, dissolved oxygen (DO) in water, and strain range, on fatigue lives of these steels. The results confirm the significant decrease in fatigue life in water. The environmentally assisted decrease in fatigue life depends both on strain rate and DO content in water. A decrease in strain rate from 0.4 to 0.004%/s decreases fatigue life by a factor of {approx} 8. However, unlike carbon and low-alloy steels, environmental effects are more pronounced in low-DO than in high-DO water. At {approx} 0.004%/s strain rate, reduction in fatigue life in water containing <10 ppb D is greater by a factor of {approx} 2 than in water containing {ge} 200 ppb DO. Experimental results have been compared with estimates of fatigue life based on the statistical model. The formation and growth of fatigue cracks in austenitic stainless steels in air and LWR environments are discussed.

Chopra, O.K.; Gavenda, D.J. [Argonne National Lab., IL (United States). Energy Technology Div.

1997-07-01T23:59:59.000Z

55

Weapons-grade plutonium dispositioning. Volume 4. Plutonium dispositioning in light water reactors  

SciTech Connect

This study is in response to a request by the Reactor Panel Subcommittee of the National Academy of Sciences (NAS) Committee on International Security and Arms Control (CISAC) to evaluate the feasibility of using plutonium fuels (without uranium) for disposal in existing conventional or advanced light water reactor (LWR) designs and in low temperature/pressure LWR designs that might be developed for plutonium disposal. Three plutonium-based fuel forms (oxides, aluminum metallics, and carbides) are evaluated for neutronic performance, fabrication technology, and material and compatibility issues. For the carbides, only the fabrication technologies are addressed. Viable plutonium oxide fuels for conventional or advanced LWRs include plutonium-zirconium-calcium oxide (PuO{sub 2}-ZrO{sub 2}-CaO) with the addition of thorium oxide (ThO{sub 2}) or a burnable poison such as erbium oxide (Er{sub 2}O{sub 3}) or europium oxide (Eu{sub 2}O{sub 3}) to achieve acceptable neutronic performance. Thorium will breed fissile uranium that may be unacceptable from a proliferation standpoint. Fabrication of uranium and mixed uranium-plutonium oxide fuels is well established; however, fabrication of plutonium-based oxide fuels will require further development. Viable aluminum-plutonium metallic fuels for a low temperature/pressure LWR include plutonium aluminide in an aluminum matrix (PuAl{sub 4}-Al) with the addition of a burnable poison such as erbium (Er) or europium (Eu). Fabrication of low-enriched plutonium in aluminum-plutonium metallic fuel rods was initially established 30 years ago and will require development to recapture and adapt the technology to meet current environmental and safety regulations. Fabrication of high-enriched uranium plate fuel by the picture-frame process is a well established process, but the use of plutonium would require the process to be upgraded in the United States to conform with current regulations and minimize the waste streams.

Sterbentz, J.W.; Olsen, C.S.; Sinha, U.P.

1993-06-01T23:59:59.000Z

56

Columbia Water & Light- Commercial Super Saver Loans  

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

Columbia Water & 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...

57

Columbia Water & Light- Residential Super Saver Loans  

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

The Columbia Water & 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...

58

Analytical Transmission Electron Microscopy (ATEM) Characterization of Stress-Corrosion Cracks in LWR-Irradiated Austenitic Stainless Steel Core Components - Revision 2  

Science Conference Proceedings (OSTI)

This work was sponsored by the Cooperative IASCC Research (CIR) Program, which is an international research effort designed to address irradiation-assisted stress corrosion cracking (IASCC) in light water reactor (LWR) components. The program's goal is to develop a mechanistically based predictive methodology for IASCC and to identify potential countermeasures to mitigate IASCC.

2006-10-30T23:59:59.000Z

59

Analytical Transmission Electron Microscopy (ATEM) Characterization of Stress Corrosion Cracks in LWR-Irradiated Austenitic Stainless Steel Core Components: Revision 1  

Science Conference Proceedings (OSTI)

This work was sponsored by the Cooperative IASCC Research (CIR) Program, which is an international research effort designed to address irradiation-assisted stress corrosion cracking (IASCC) in light water reactor (LWR) components. The program's goal is to develop a mechanistically based predictive methodology for IASCC and to identify potential countermeasures to mitigate IASCC.

2003-09-17T23:59:59.000Z

60

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

SciTech Connect

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

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

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

Science Conference Proceedings (OSTI)

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

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

2008-06-01T23:59:59.000Z

62

City Water Light and Power - Commercial Energy Efficiency Rebate...  

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

Water Light and Power - Commercial Energy Efficiency Rebate Programs City Water Light and Power - Commercial Energy Efficiency Rebate Programs Eligibility Commercial Nonprofit...

63

A flammability and combustion model for integrated accident analysis. [Advanced light water reactors  

DOE Green Energy (OSTI)

A model for flammability characteristics and combustion of hydrogen and carbon monoxide mixtures is presented for application to severe accident analysis of Advanced Light Water Reactors (ALWR's). Flammability of general mixtures for thermodynamic conditions anticipated during a severe accident is quantified with a new correlation technique applied to data for several fuel and inertant mixtures and using accepted methods for combining these data. Combustion behavior is quantified by a mechanistic model consisting of a continuity and momentum balance for the burned gases, and considering an uncertainty parameter to match the idealized process to experiment. Benchmarks against experiment demonstrate the validity of this approach for a single recommended value of the flame flux multiplier parameter. The models presented here are equally applicable to analysis of current LWR's. 21 refs., 16 figs., 6 tabs.

Plys, M.G.; Astleford, R.D.; Epstein, M. (Fauske and Associates, Inc., Burr Ridge, IL (USA))

1988-01-01T23:59:59.000Z

64

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

Science Conference Proceedings (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

65

Comparative analysis of LWR and FBR spent fuels for nuclear forensics evaluation  

SciTech Connect

Some interesting issues are attributed to nuclide compositions of spent fuels from thermal reactors as well as fast reactors such as a potential to reuse as recycled fuel, and a possible capability to be manage as a fuel for destructive devices. In addition, analysis on nuclear forensics which is related to spent fuel compositions becomes one of the interesting topics to evaluate the origin and the composition of spent fuels from the spent fuel foot-prints. Spent fuel compositions of different fuel types give some typical spent fuel foot prints and can be estimated the origin of source of those spent fuel compositions. Some technics or methods have been developing based on some science and technological capability including experimental and modeling or theoretical aspects of analyses. Some foot-print of nuclear forensics will identify the typical information of spent fuel compositions such as enrichment information, burnup or irradiation time, reactor types as well as the cooling time which is related to the age of spent fuels. This paper intends to evaluate the typical spent fuel compositions of light water (LWR) and fast breeder reactors (FBR) from the view point of some foot prints of nuclear forensics. An established depletion code of ORIGEN is adopted to analyze LWR spent fuel (SF) for several burnup constants and decay times. For analyzing some spent fuel compositions of FBR, some coupling codes such as SLAROM code, JOINT and CITATION codes including JFS-3-J-3.2R as nuclear data library have been adopted. Enriched U-235 fuel composition of oxide type is used for fresh fuel of LWR and a mixed oxide fuel (MOX) for FBR fresh fuel. Those MOX fuels of FBR come from the spent fuels of LWR. Some typical spent fuels from both LWR and FBR will be compared to distinguish some typical foot-prints of SF based on nuclear forensic analysis.

Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki [Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 Nuclear Physics and Bio (Indonesia); Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 (Japan); Nuclear Physics and Bio Physics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia)

2012-06-06T23:59:59.000Z

66

Developmental Light-Water Reactor Program  

SciTech Connect

This report summarizes the progress of the Developmental Light-Water Reactor (DLWR) Program at Oak Ridge National Laboratory in FY 1989. It also includes (1) a brief description of the program, (2) definition of goals, (3) earlier achievements, and (4) proposed future activities.

Forsberg, C.W.

1989-12-01T23:59:59.000Z

67

Qualification of the Frequency-Scanning Eddy Current Technique for LWR Fuel Assembly Structural Components Under Simulated Poolside Conditions  

Science Conference Proceedings (OSTI)

There is a growing need for nondestructive characterization of hydrogen content in zirconium alloys used in light water reactor (LWR) fuel assembly components. Pending revisions to current regulations and industry emphasis on determining fuel reliability margins have driven the development of poolside-deployable nondestructive characterization techniques to inspect fuel assembly materials. Poolside inspection reduces risk, dose, time and costs related to the transportation of these materials for ...

2013-10-29T23:59:59.000Z

68

Cedarburg Light & Water Utility - Commercial Shared Savings Loan Program  

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

Cedarburg Light & Water Utility - Commercial Shared Savings Loan Cedarburg Light & Water Utility - Commercial Shared Savings Loan Program (Wisconsin) Cedarburg Light & Water Utility - Commercial Shared Savings Loan Program (Wisconsin) < Back Eligibility Agricultural Commercial Industrial Savings Category Other Heating & Cooling Commercial Heating & Cooling Heating Cooling Appliances & Electronics Manufacturing Home Weatherization Sealing Your Home Design & Remodeling Windows, Doors, & Skylights Commercial Weatherization Ventilation Construction Heat Pumps Commercial Lighting Lighting Water Heating Maximum Rebate $50,000 Program Info State Wisconsin Program Type Utility Loan Program Rebate Amount $2,500 - $50,000 Provider Cedarburg Light and Water Utility Cedarburg Light and Water Utility (CLWU) provides loans for commercial,

69

Cedarburg Light & Water Utility- Commercial Energy Efficiency Rebate Program  

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

70

Cedarburg Light & Water Utility - Commercial Shared Savings Loan...  

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

& Skylights Commercial Weatherization Ventilation Construction Heat Pumps Commercial Lighting Lighting Water Heating Maximum Rebate 50,000 Program Information Wisconsin Program...

71

Cedarburg Light and Water Utility - Commercial Energy Efficiency Rebate  

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

Cedarburg Light and Water Utility - Commercial Energy Efficiency Cedarburg Light and Water Utility - Commercial Energy Efficiency Rebate Program Cedarburg Light and Water Utility - Commercial Energy Efficiency Rebate Program < Back Eligibility Agricultural Commercial Fed. Government Industrial Local Government Nonprofit Schools State Government Savings Category Other Heating & Cooling Commercial Heating & Cooling Cooling Home Weatherization Construction Commercial Weatherization Design & Remodeling Manufacturing Appliances & Electronics Commercial Lighting Lighting Maximum Rebate Unspecified ($250,000 per bid cycle) Program Info State Wisconsin Program Type Utility Rebate Program Rebate Amount Varies by measure Provider Cedarburg Light and Water Utility Cedarburg Light and Water Utility provides incentives for commercial,

72

Advanced Light Water Reactor utility requirements document  

SciTech Connect

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

1986-06-01T23:59:59.000Z

73

Characterization of Neutron-Irradiated 300-Series Stainless Steels to Assess Mechanisms of Irradiation-Assisted Stress Corrosion Cra cking: Volume 1: LWR-Irradiated Type 304 and 316SS Heats with Established IASCC Susceptibility  

Science Conference Proceedings (OSTI)

This work was sponsored by the Cooperative IASCC Research (CIR) Program, which is an international research effort designed to address irradiation-assisted stress corrosion cracking (IASCC) in LWR (light water reactor) components. The program's goal is to develop a mechanistically based predictive methodology for IASCC and to identify potential countermeasures to mitigate IASCC.

2001-04-17T23:59:59.000Z

74

Sun Prairie Water & Light Comm | Open Energy Information  

Open Energy Info (EERE)

Sun Prairie Water & Light Comm Sun Prairie Water & Light Comm Jump to: navigation, search Name Sun Prairie Water & Light Comm Place Wisconsin Utility Id 18312 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes ISO MISO Yes Activity Distribution Yes Alt Fuel Vehicle Yes Alt Fuel Vehicle2 Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Area Lighting 1000w Halide existing poles Lighting Area Lighting 1000w Halide provided poles Lighting Area Lighting 100w HPS existing poles Lighting Area Lighting 100w HPS provided poles Lighting Area Lighting 150w HPS existing poles Lighting

75

Towards the reanalysis of void coefficients measurements at proteus for high conversion light water reactor lattices  

Science Conference Proceedings (OSTI)

High Conversion Light Water Reactors (HCLWR) allows a better usage of fuel resources thanks to a higher breeding ratio than standard LWR. Their uses together with the current fleet of LWR constitute a fuel cycle thoroughly studied in Japan and the US today. However, one of the issues related to HCLWR is their void reactivity coefficient (VRC), which can be positive. Accurate predictions of void reactivity coefficient in HCLWR conditions and their comparisons with representative experiments are therefore required. In this paper an inter comparison of modern codes and cross-section libraries is performed for a former Benchmark on Void Reactivity Effect in PWRs conducted by the OECD/NEA. It shows an overview of the k-inf values and their associated VRC obtained for infinite lattice calculations with UO{sub 2} and highly enriched MOX fuel cells. The codes MCNPX2.5, TRIPOLI4.4 and CASMO-5 in conjunction with the libraries ENDF/B-VI.8, -VII.0, JEF-2.2 and JEFF-3.1 are used. A non-negligible spread of results for voided conditions is found for the high content MOX fuel. The spread of eigenvalues for the moderated and voided UO{sub 2} fuel are about 200 pcm and 700 pcm, respectively. The standard deviation for the VRCs for the UO{sub 2} fuel is about 0.7% while the one for the MOX fuel is about 13%. This work shows that an appropriate treatment of the unresolved resonance energy range is an important issue for the accurate determination of the void reactivity effect for HCLWR. A comparison to experimental results is needed to resolve the presented discrepancies. (authors)

Hursin, M.; Koeberl, O.; Perret, G. [Paul Scherrer Institut PSI, 5232 Villigen (Switzerland)

2012-07-01T23:59:59.000Z

76

Abstract: Isochoric Heat Capacity of Light and Heavy Water at ...  

Science Conference Proceedings (OSTI)

Isochoric Heat Capacity of Light and Heavy Water at Subcritical and Supercritical Conditions. IM Abdulagatov, JW Magee ...

77

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

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

Light Water Reactor Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program The Light Water Reactor Sustainability (LWRS) Program is developing the scientific basis to extend existing nuclear power plant operating life beyond the current 60-year licensing period and ensure long-term reliability, productivity, safety, and security. The program is conducted in collaboration with national laboratories, universities, industry, and international partners. Idaho National Laboratory serves as the Technical Integration Office and coordinates the research and development (R&D) projects in the following pathways: Materials Aging and Degradation Assessment, Advanced Instrumentation, Information, and Control Systems

78

Light Water Reactor Sustainability Technical Documents | Department of  

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

Reactor Technologies » Light Water Reactor Reactor Technologies » Light Water Reactor Sustainability Program » Light Water Reactor Sustainability Technical Documents Light Water Reactor Sustainability Technical Documents April 30, 2013 LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs: DOE-NE's Light Water Reactor Sustainability (LWRS) Program and EPRI's Long-Term Operations (LTO) Program. April 30, 2013 Light Water Reactor Sustainability Program - Integrated Program Plan The Light Water Reactor Sustainability (LWRS) Program is a research and

79

Parkland Light & Water Company | Open Energy Information  

Open Energy Info (EERE)

Parkland Light & Water Company Parkland Light & Water Company Jump to: navigation, search Name Parkland Light & Water Company Place Washington Utility Id 14505 Utility Location Yes Ownership C NERC Location WECC NERC WECC Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Large Commercial (Over 50kVA) Commercial Residential Rate Residential Security Lights-100 WATT HP SODIUM Lighting Security Lights-200 WATT HP SODIUM Lighting Security Lights-250 WATT HP SODIUM Lighting Security Lights-400 WATT HP SODIUM Lighting Small Commercial (Under 50kVA) Commercial Average Rates

80

Albany Water Gas & Light Comm | Open Energy Information  

Open Energy Info (EERE)

Water Gas & Light Comm Water Gas & Light Comm Jump to: navigation, search Name Albany Water Gas & Light Comm Place Georgia Utility Id 230 Utility Location Yes Ownership M NERC Location SERC NERC SERC Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Commercial Demand Commercial Commercial Non-Demand Commercial Large Commercial Demand Commercial Residential Residential Security Lights 1000 Watt Metal Halide Metal Pole Lighting Security Lights 1000 Watt Metal Halide Wooden Pole Lighting Security Lights 150 HPSV Fixtures Metal Pole Lighting Security Lights 150 HPSV Fixtures Wooden Pole Lighting

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

Columbia Water and Light - Commercial Super Saver Loans | Department of  

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

Columbia Water and Light - Commercial Super Saver Loans Columbia Water and Light - Commercial Super Saver Loans Columbia Water and Light - Commercial Super Saver Loans < Back Eligibility Commercial Fed. Government Industrial Nonprofit State Government Savings Category Heating & Cooling Commercial Heating & Cooling Cooling Heating Heat Pumps Appliances & Electronics Commercial Lighting Lighting Water Heating Solar Maximum Rebate $30,000 Program Info Start Date 06/01/2010 State Missouri Program Type Utility Loan Program Rebate Amount Up to $30,000 Provider Columbia Water and Light 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 efficiency rating 11 EER or greater for units 6 tons or larger. No prepayment penalties are enforced through the

82

Light water reactor lower head failure analysis  

SciTech Connect

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

83

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

SciTech Connect

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

84

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

SciTech Connect

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

85

An Estimate of the Cost of Electricity from Light Water Reactors and Fossil Plants with Carbon Capture and Sequestration  

SciTech Connect

As envisioned in this report, LIFE technology lends itself to large, centralized, baseload (or 'always on') electrical generation. Should LIFE plants be built, they will have to compete in the electricity market with other generation technologies. We consider the economics of technologies with similar operating characteristics: significant economies of scale, limited capacity for turndown, zero dependence on intermittent resources and ability to meet environmental constraints. The five generation technologies examined here are: (1) Light Water Reactors (LWR); (2) Coal; (3) Coal with Carbon Capture and Sequestration (CCS); (4) Natural Gas; and (5) Natural Gas with Carbon Capture and Sequestration. We use MIT's cost estimation methodology (Du and Parsons, 2009) to determine the cost of electricity at which each of these technologies is viable.

Simon, A J

2009-08-21T23:59:59.000Z

86

City Water Light and Power - Commercial Energy Efficiency Rebate Programs |  

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

Water Light and Power - Commercial Energy Efficiency Rebate Water Light and Power - Commercial Energy Efficiency Rebate Programs City Water Light and Power - Commercial Energy Efficiency Rebate Programs < Back Eligibility Commercial Nonprofit Savings Category Home Weatherization Commercial Weatherization Heating & Cooling Commercial Heating & Cooling Heat Pumps Appliances & Electronics Commercial Lighting Lighting Maximum Rebate Insulation: $3,000 Retro-Commissioning: $50,000 Lighting: $15,000 Program Info State Illinois Program Type Utility Rebate Program Rebate Amount Air-Source Heat Pumps: $300/ton Geothermal Heat Pump: $500/ton Insulation: 30% Retro-Commissioning Study: $0.30 per sq. ft. of conditioned space Retro-Commissioning EMC: varies Lighting: $3 - $35/unit Lighting (Custom): $0.28/Watt reduced Water Loop Heat Pump: Contact CWLP

87

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

Sørensen, Henrik

88

McMinnville Water and Light - Conservation Service Loan Program |  

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

McMinnville Water and Light - Conservation Service Loan Program McMinnville Water and Light - Conservation Service Loan Program McMinnville Water and Light - Conservation Service Loan Program < Back Eligibility Commercial Residential Savings Category Home Weatherization Commercial Weatherization Sealing Your Home Heating & Cooling Construction Commercial Heating & Cooling Design & Remodeling Windows, Doors, & Skylights Manufacturing Heat Pumps Appliances & Electronics Commercial Lighting Lighting Maximum Rebate $10,000 Program Info State Oregon Program Type Utility Loan Program Rebate Amount $500-$10,000 Provider McMinnville Water and Light McMinnville Water and Light offers financing to residential and commercial customers to make energy efficient improvements to eligible facilities and homes. Financing is available for pre-approved conservation measures only.

89

MCNP LWR Core Generator  

Science Conference Proceedings (OSTI)

The reactor core input generator allows for MCNP input files to be tailored to design specifications and generated in seconds. Full reactor models can now easily be created by specifying a small set of parameters and generating an MCNP input for a full reactor core. Axial zoning of the core will allow for density variation in the fuel and moderator, with pin-by-pin fidelity, so that BWR cores can more accurately be modeled. LWR core work in progress: (1) Reflectivity option for specifying 1/4, 1/2, or full core simulation; (2) Axial zoning for moderator densities that vary with height; (3) Generating multiple types of assemblies for different fuel enrichments; and (4) Parameters for specifying BWR box walls. Fuel pin work in progress: (1) Radial and azimuthal zoning for generating further unique materials in fuel rods; (2) Options for specifying different types of fuel for MOX or multiple burn assemblies; (3) Additional options for replacing fuel rods with burnable poison rods; and (4) Control rod/blade modeling.

Fischer, Noah A. [Los Alamos National Laboratory

2012-08-14T23:59:59.000Z

90

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

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

Memphis Light, Gas and Water (Electric) - Commercial Efficiency Memphis Light, Gas and Water (Electric) - Commercial Efficiency Advice and Incentives Program Memphis Light, Gas and Water (Electric) - Commercial Efficiency Advice and Incentives Program < Back Eligibility Commercial Industrial Savings Category Heating & Cooling Commercial Heating & Cooling Heating Cooling Manufacturing Other Appliances & Electronics Heat Pumps Commercial Lighting Lighting Commercial Weatherization Maximum Rebate 70% of project cost Program Info State Tennessee Program Type Utility Rebate Program Rebate Amount Commercial Dishwashers: $400 - $1500 Commercial Refrigerator: $60 - $100 Ice Machines: $100 - $400 Insulated Holding Cabinets: $250 - $600 Electric Steam Cookers: $400 Electric Convection Ovens: $200 Electric Griddles: $200 Electric Combination Ovens: $2,000

91

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

Science Conference Proceedings (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

92

City Water Light and Power - Residential Energy Efficiency Rebate Programs  

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

City Water Light and Power - Residential Energy Efficiency Rebate City Water Light and Power - Residential Energy Efficiency Rebate Programs City Water Light and Power - Residential Energy Efficiency Rebate Programs < Back Eligibility Residential Savings Category Home Weatherization Commercial Weatherization Heating & Cooling Commercial Heating & Cooling Cooling Heat Pumps Appliances & Electronics Maximum Rebate Refrigerator Recycling: 2 units Insulation: $1,000 Program Info State Illinois Program Type Utility Rebate Program Rebate Amount Clothes Washer: $150 Central Air Conditioner: $9 per kBTUh Air-Source Heat Pumps: $300/ton Geothermal Heat Pump: $500 Refrigerator Recycling: $50 per appliance Insulation: 30% Provider Energy Services Office City Water Light and Power (CWLP) offers rebates to Springfield residential

93

Columbia Water & Light - New Home Energy Star Rebate | Department...  

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

New Home Energy Star Rebate Columbia Water & Light - New Home Energy Star Rebate Eligibility Construction Residential Savings For Heating & Cooling Home Weatherization Construction...

94

Columbia Water & Light - Home Performance with Energy Star Rebates...  

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

Home Performance with Energy Star Rebates Columbia Water & Light - Home Performance with Energy Star Rebates Eligibility Residential Savings For Home Weatherization Commercial...

95

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

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

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

96

Columbia Water & Light - Commercial Super Saver Loans | Department...  

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

Commercial Super Saver Loans Columbia Water & Light - Commercial Super Saver Loans Eligibility Commercial Fed. Government Industrial Nonprofit State Government Savings For Heating...

97

Columbia Water & Light - Residential Super Saver Loans | Department...  

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

Super Saver Loans Columbia Water & Light - Residential Super Saver Loans Eligibility Multi-Family Residential Residential Savings For Home Weatherization Commercial Weatherization...

98

Columbia Water and Light - Solar Rebates | Department of Energy  

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

Solar Rebates Columbia Water and Light - Solar Rebates Eligibility Commercial Fed. Government Nonprofit Residential State Government Savings For Solar Buying & Making Electricity...

99

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

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

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

100

City Water Light and Power - Solar Rewards Program | Department...  

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

Solar Rewards Program City Water Light and Power - Solar Rewards Program Eligibility Commercial Residential Savings For Solar Buying & Making Electricity Maximum Rebate 15,000 per...

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

Light Water Reactor Materials for Commercial Nuclear Power ...  

Science Conference Proceedings (OSTI)

Presentation Title, Light Water Reactor Materials for Commercial Nuclear ... First- Principles Theory of Magnetism, Crystal Field and Phonon Spectrum of UO2.

102

McMinnville Water & Light- Conservation Service Loan Program  

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

McMinnville Water & Light offers financing to residential and commercial customers to make energy efficient improvements to eligible facilities and homes. Financing is available for pre...

103

Moose Lake Water & Light Comm | Open Energy Information  

Open Energy Info (EERE)

Lake Water & Light Comm Lake Water & Light Comm Jump to: navigation, search Name Moose Lake Water & Light Comm Place Minnesota Utility Id 12897 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes ISO MISO Yes Operates Generating Plant Yes Activity Generation Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png 2-250HPS-FRO Lighting 250 HPS ELEOLY Lighting 3-250 HPS Lighting 4-250 HPS Lighting 400 HPS Rent Lighting BEST OIL CO Commercial BIKE TRAIL Commercial CIP Commercial Commercial Demand Commercial Commercial Electricity Commercial Demand 1 Phase Industrial

104

Columbia Water & Light - HVAC and Lighting Efficiency Rebates...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

105

Two Rivers Water & Light | Open Energy Information  

Open Energy Info (EERE)

Water & Light Water & Light Jump to: navigation, search Name Two Rivers Water & Light Place Wisconsin Utility Id 19324 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes ISO MISO Yes Activity Distribution Yes Alt Fuel Vehicle Yes Alt Fuel Vehicle2 Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Business District Lighting- 150W HPS Lighting Business District Lighting- 200W HPS Lighting General Service- Single-Phase Commercial General Service- Single-Phase- Time-of-Day- 7am-7pm Commercial General Service- Single-Phase- Time-of-Day- 8am-8pm Commercial

106

Azusa Light and Water - Solar Partnership Program | Department of Energy  

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

Azusa Light and Water - Solar Partnership Program Azusa Light and Water - Solar Partnership Program Azusa Light and Water - Solar Partnership Program < Back Eligibility Commercial Residential Savings Category Solar Buying & Making Electricity Maximum Rebate 50% of system cost Program Info Expiration Date 12/31/2016 State California Program Type Utility Rebate Program Rebate Amount Program is fully subscribed for fiscal year 2013-2014. New applicants will be placed on a wait list. $1.55/W-DC Provider Azusa Light and Water '''''This program is fully subscribed through fiscal year 2013/2014. New applicants will be placed on a wait list in the order they were received. ''''' Azusa Light and Water provides rebates to customers who install photovoltaic (PV) systems through the utility's Solar Partnership Program.

107

Duquesne Light Company - Residential Solar Water Heating Program |  

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

Duquesne Light Company - Residential Solar Water Heating Program Duquesne Light Company - Residential Solar Water Heating Program Duquesne Light Company - Residential Solar Water Heating Program < Back Eligibility Multi-Family Residential Residential Savings Category Heating & Cooling Solar Water Heating Program Info Start Date 11/30/2009 Expiration Date 03/31/2013 State Pennsylvania Program Type Utility Rebate Program Rebate Amount $286/system Provider Duquesne Light Company 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 system. Various equipment, installation, contractor, and warranty requirements apply, as summarized above and described in more detail in program documents. Customers must

108

LIFE vs. LWR: End of the Fuel Cycle  

Science Conference Proceedings (OSTI)

The worldwide energy consumption in 2003 was 421 quadrillion Btu (Quads), and included 162 quads for oil, 99 quads for natural gas, 100 quads for coal, 27 quads for nuclear energy, and 33 quads for renewable sources. The projected worldwide energy consumption for 2030 is 722 quads, corresponding to an increase of 71% over the consumption in 2003. The projected consumption for 2030 includes 239 quads for oil, 190 quads for natural gas, 196 quads for coal, 35 quads for nuclear energy, and 62 quads for renewable sources [International Energy Outlook, DOE/EIA-0484, Table D1 (2006) p. 133]. The current fleet of light water reactors (LRWs) provides about 20% of current U.S. electricity, and about 16% of current world electricity. The demand for electricity is expected to grow steeply in this century, as the developing world increases its standard of living. With the increasing price for oil and gasoline within the United States, as well as fear that our CO2 production may be driving intolerable global warming, there is growing pressure to move away from oil, natural gas, and coal towards nuclear energy. Although there is a clear need for nuclear energy, issues facing waste disposal have not been adequately dealt with, either domestically or internationally. Better technological approaches, with better public acceptance, are needed. Nuclear power has been criticized on both safety and waste disposal bases. The safety issues are based on the potential for plant damage and environmental effects due to either nuclear criticality excursions or loss of cooling. Redundant safety systems are used to reduce the probability and consequences of these risks for LWRs. LIFE engines are inherently subcritical, reducing the need for systems to control the fission reactivity. LIFE engines also have a fuel type that tolerates much higher temperatures than LWR fuel, and has two safety systems to remove decay heat in the event of loss of coolant or loss of coolant flow. These features of LIFE are expected to result in a more straightforward licensing process and are also expected to improve the public perception of risk from nuclear power generation, transportation of nuclear materials, and nuclear waste disposal. Waste disposal is an ongoing issue for LWRs. The conventional (once-through) LWR fuel cycle treats unburned fuel as waste, and results in the current fleet of LWRs producing about twice as much waste in their 60 years of operation as is legally permitted to be disposed of in Yucca Mountain. Advanced LWR fuel cycles would recycle the unused fuel, such that each GWe-yr of electricity generation would produce only a small waste volume compared to the conventional fuel cycle. However, the advanced LWR fuel cycle requires chemical reprocessing plants for the fuel, multiple handling of radioactive materials, and an extensive transportation network for the fuel and waste. In contrast, the LIFE engine requires only one fueling for the plant lifetime, has no chemical reprocessing, and has a single shipment of a small amount of waste per GWe-yr of electricity generation. Public perception of the nuclear option will be improved by the reduction, for LIFE engines, of the number of shipments of radioactive material per GWe-yr and the need to build multiple repositories. In addition, LIFE fuel requires neither enrichment nor reprocessing, eliminating the two most significant pathways to proliferation from commercial nuclear fuel to weapons programs.

Farmer, J C; Blink, J A; Shaw, H F

2008-10-02T23:59:59.000Z

109

Clarksville Light & Water Co | Open Energy Information  

Open Energy Info (EERE)

Clarksville Light & Water Co Clarksville Light & Water Co Jump to: navigation, search Name Clarksville Light & Water Co Place Arkansas Utility Id 3705 Utility Location Yes Ownership M NERC Location SPP NERC SPP Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Large Commercial (Rate schedule p) Commercial Large Industrial (Rate schedule p) Industrial Residential (R1) Residential Residential Rate Schedule R-2 Residential Security Light Service (Rate schedule L)HPS 100 W Commercial Security Light Service 1000 W MH Commercial Security light service 150 W HPS Commercial

110

North Branch Municipal Water and Light - Residential Energy Efficiency  

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

North Branch Municipal Water and Light - Residential Energy North Branch Municipal Water and Light - Residential Energy Efficiency Rebate Program North Branch Municipal Water and Light - Residential Energy Efficiency Rebate Program < Back Eligibility Commercial Residential Savings Category Heating & Cooling Commercial Heating & Cooling Cooling Appliances & Electronics Heat Pumps Commercial Lighting Lighting Program Info State Minnesota Program Type Utility Rebate Program Rebate Amount Lighting: See program website Room A/C: $25, plus $25 for recycling an old, working unit Central A/C: $100 - $200, plus additional rebate for efficiency ratings above 14.5 SEER Air Source Heat Pump:$100 - $200, plus additional rebate for efficiency ratings above 14.5 SEER Geothermal Heat Pump:$200/ton, plus $25/ton for every 1 EER above minimum

111

Columbia Water and Light - Residential Super Saver Loans | Department of  

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

Residential Super Saver Loans Residential Super Saver Loans Columbia Water and Light - Residential Super Saver Loans < Back Eligibility Multi-Family Residential Residential Savings Category Home Weatherization Commercial Weatherization Heating & Cooling Commercial Heating & Cooling Cooling Sealing Your Home Design & Remodeling Windows, Doors, & Skylights Ventilation Heating Heat Pumps Appliances & Electronics Water Heating Solar Maximum Rebate $15,000 Program Info State Missouri Program Type Utility Loan Program Rebate Amount Home Performance Super Saver Loan: up to $15,000 Provider Columbia Water and Light 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 terms. If a Water and Light

112

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

Science Conference Proceedings (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

113

Paragould Light & Water Comm | Open Energy Information  

Open Energy Info (EERE)

Paragould Light & Water Comm Paragould Light & Water Comm Jump to: navigation, search Name Paragould Light & Water Comm Place Arkansas Utility Id 14446 Utility Location Yes Ownership M NERC Location SPP NERC SPP Yes Operates Generating Plant Yes Activity Generation Yes Activity Buying Transmission Yes Activity Distribution Yes Activity Wholesale Marketing Yes Activity Bundled Services Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png General Single Phase Commercial General Three Phase Commercial Industrial Industrial Residential Residential Security Lighting 100 W HPS Lighting

114

Light Water Reactor Sustainability Program - Integrated Program Plan |  

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

Light Water Reactor Sustainability Program - Integrated Program Light Water Reactor Sustainability Program - Integrated Program Plan Light Water Reactor Sustainability Program - Integrated Program Plan The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U. S. Department of Energy (DOE), performed in close collaboration and cooperation with related industry R&D programs. The LWRS Program provides technical foundations for licensing and managing the long-term, safe, and economical operation of current nuclear power plants, utilizing the unique capabilities of the national laboratory system. Sustainability is defined as the ability to maintain safe and economic operation of the existing fleet of nuclear power plants for a longer than-initially-licensed lifetime. It has two facets

115

Columbia Water & Light- Home Performance with Energy Star Rebates  

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

Columbia Water and Light, a municipal utility, offers rebates to its residential customers who make certain energy efficient improvements to the home. Under the Home Performance with Energy Star...

116

Light Water Reactors [Corrosion and Mechanics of Materials] - Nuclear  

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

Light Water Reactors Light Water Reactors Capabilities Materials Testing Environmentally Assisted Cracking (EAC) of Reactor Materials Corrosion Performance/Metal Dusting Overview Light Water Reactors Fatigue Testing of Carbon Steels and Low-Alloy Steels Environmentally Assisted Cracking of Ni-Base Alloys Irradiation-Induced Stress Corrosion Cracking of Austenitic Stainless Steels Steam Generator Tube Integrity Program Air Oxidation Kinetics for Zr-based Alloys Fossil Energy Fusion Energy Metal Dusting Publications List Irradiated Materials Steam Generator Tube Integrity Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Corrosion and Mechanics of Materials Light Water Reactors Bookmark and Share To continue safe operation of current LWRs, the aging degradation of the

117

Lockwood Water & Light Company | Open Energy Information  

Open Energy Info (EERE)

Lockwood Water & Light Company Lockwood Water & Light Company Jump to: navigation, search Name Lockwood Water & Light Company Place Missouri Utility Id 11121 Utility Location Yes Ownership M NERC Location SPP NERC SPP Yes Activity Retail Marketing Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Commercial Commercial Demand Industrial Industrial Residential Residential Average Rates Residential: $0.1060/kWh Commercial: $0.1110/kWh Industrial: $0.0926/kWh References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=Lockwood_Water_%26_Light_Company&oldid=410998

118

Columbia Water and Light- Residential HVAC Rebate Program  

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

119

McMinnville Water & Light- Commercial Energy Efficiency Rebate Programs  

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

120

Environmentally assisted cracking of light-water reactor materials  

SciTech Connect

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

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

Cedarburg Light & Water Utility - Residential Energy Efficiency...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

122

Cedarburg Light & Water Utility - Commercial Energy Efficiency...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

123

Azusa Light & Water - Solar Partnership Program (California)...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

124

The scale analysis sequence for LWR fuel depletion  

Science Conference Proceedings (OSTI)

The SCALE (Standardized Computer Analyses for Licensing Evaluation) code system is used extensively to perform away-from-reactor safety analysis (particularly criticality safety, shielding, heat transfer analyses) for spent light water reactor (LWR) fuel. Spent fuel characteristics such as radiation sources, heat generation sources, and isotopic concentrations can be computed within SCALE using the SAS2 control module. A significantly enhanced version of the SAS2 control module, which is denoted as SAS2H, has been made available with the release of SCALE-4. For each time-dependent fuel composition, SAS2H performs one-dimensional (1-D) neutron transport analyses (via XSDRNPM-S) of the reactor fuel assembly using a two-part procedure with two separate unit-cell-lattice models. The cross sections derived from a transport analysis at each time step are used in a point-depletion computation (via ORIGEN-S) that produces the burnup-dependent fuel composition to be used in the next spectral calculation. A final ORIGEN-S case is used to perform the complete depletion/decay analysis using the burnup-dependent cross sections. The techniques used by SAS2H and two recent applications of the code are reviewed in this paper. 17 refs., 5 figs., 5 tabs.

Hermann, O.W.; Parks, C.V.

1991-01-01T23:59:59.000Z

125

Dry oxidation and fracture of LWR spent fuels  

SciTech Connect

This report evaluates the characteristics of oxidation and fracture of light-water reactor (LWR) spent fuel in dry air. It also discusses their effects on radionuclide releases in the anticipated high-level waste repository environment. A sphere model may describe diffusion-limited formation of lower oxides, such as U{sub 4}O{sub 9}, in the oxidation of the spent fuel (SF) matrix. Detrimental higher oxides, such as U{sub 3}O{sub 8}, may not form at temperatures below a threshold temperature. The nucleation process suggests that a threshold temperature exists. The calculated results regarding fracture properties of the SF matrix agree with experimental observations. Oxidation and fracture of Zircaloy may not be significant under anticipated conditions. Under saturated or unsaturated aqueous conditions, oxidation of the SF matrix is believed to increase the releases of Pu-(239+240), Am-(241+243), C-14, Tc-99, I-129, and Cs-135. Under dry conditions, I-129 releases are likely to be small, unlike C-14, in lower oxides; Cl-36, Tc-99, I-129, and Cs-135 may be released fast in higher oxides. 79 refs.

Ahn, T.M.

1996-11-01T23:59:59.000Z

126

Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report  

SciTech Connect

The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: Give priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools. Give special technical emphasis and funding priorityto activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors. Report to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020. Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and Commercialization. The activities performed during the feasibility assessment phase include laboratory scale experiments; fuel performance code updates; and analytical assessment of economic, operational, safety, fuel cycle, and environmental impacts of the new concepts. The development and qualification stage will consist of fuel fabrication and large scale irradiation and safety basis testing, leading to qualification and ultimate NRC licensing of the new fuel. The commercialization phase initiates technology transfer to industry for implementation. Attributes for fuels with enhanced accident tolerance include improved reaction kinetics with steam and slower hydrogen generation rate, while maintaining acceptable cladding thermo-mechanical properties; fuel thermo-mechanical properties; fuel-clad interactions; and fission-product behavior. These attributes provide a qualitative guidance for parameters that must be considered in the development of fuels and cladding with enhanced accident tolerance. However, quantitative metrics must be developed for these attributes. To initiate the quantitative metrics development, a Light Water Reactor Enhanced Accident Tolerant Fuels Metrics Development Workshop was held October 10-11, 2012, in Germantown, Maryland. This document summarizes the structure and outcome of the two-day workshop. Questions regarding the content can be directed to Lori Braase, 208-526-7763, lori.braase@inl.gov.

Lori Braase

2013-01-01T23:59:59.000Z

127

ERDA LWR plant technology program: role of government/industry in improving LWR performance  

SciTech Connect

Information is presented under the following chapter headings: executive summary; LWR plant outages; LWR plant construction delays and cancellations; programs addressing plant outages, construction delays, and cancellations; need for additional programs to remedy continuing problems; criteria for government role in LWR commercialization; and the proposed government program.

1975-10-07T23:59:59.000Z

128

Materials Degradation in Light Water Reactors: Life After 60 | Department  

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

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

129

Materials Degradation in Light Water Reactors: Life After 60 | Department  

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

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

130

Tools for LWR spent fuel characterization: Assembly classes and fuel designs  

Science Conference Proceedings (OSTI)

The Characteristics Data Base (CDB) is sponsored by the DOE's Office of Civilian Radioactive Waste Management (OCRWM). The CDB provides a single, comprehensive source of data pertaining to radioactive wastes that will or may require geologic disposal, including detailed data describing the physical, quantitative, and radiological characteristics of light-water reactor (LWR) spent fuel. In developing the CDB, tools for the classification of fuel assembly types have been developed. The assembly class scheme is particularly useful for size- and handling-based describes these tools and presents results of their applications in the areas of fuel assembly type identification, characterization of projected discharges, cask accommodation analyses, and defective fuel analyses. Suggestions for additional applications are also made. 7 refs., 1 fig., 2 tabs.

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

1991-01-01T23:59:59.000Z

131

Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study  

SciTech Connect

The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R&D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental improvements are required in the areas of nuclear fuel composition, cladding integrity, and the fuel/cladding interaction to allow power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an accident tolerant fuel system that would offer improved coping time under accident scenarios. With a development time of about 20 25 years, advanced fuel designs must be started today and proven in current reactors if future reactor designs are to be able to use them with confidence.

Kristine Barrett; Shannon Bragg-Sitton

2012-09-01T23:59:59.000Z

132

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

133

Waterloo Light & Water Comm | Open Energy Information  

Open Energy Info (EERE)

Waterloo Light & Water Comm Waterloo Light & Water Comm Jump to: navigation, search Name Waterloo Light & Water Comm Place Wisconsin Utility Id 20182 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes ISO MISO Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png General Service Three Phase Commercial General Service Single Phase Commercial General Service TOU Single Phase Commercial General Service TOU Three Phase Commercial Industrial TOU Industrial Large Power TOU Industrial Renewable Energy Rider 1 Commercial Renewable Energy Rider 2 Industrial

134

Cedarburg Light & Water Comm | Open Energy Information  

Open Energy Info (EERE)

Cedarburg Light & Water Comm Cedarburg Light & Water Comm Jump to: navigation, search Name Cedarburg Light & Water Comm Place Wisconsin Utility Id 3208 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes ISO MISO Yes Activity Distribution Yes Alt Fuel Vehicle Yes Alt Fuel Vehicle2 Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png General Service - Regular Rate - Single Phase Commercial General Service - Regular rate - Three Phase Commercial General Service Optional Time-of-Day Rate - Single Phase 7am-7pm Commercial General Service Optional Time-of-Day Rate - Single Phase 8am-8pm Commercial

135

Brodhead Water & Lighting Comm | Open Energy Information  

Open Energy Info (EERE)

Brodhead Water & Lighting Comm Brodhead Water & Lighting Comm Jump to: navigation, search Name Brodhead Water & Lighting Comm Place Wisconsin Utility Id 2273 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes ISO MISO Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png General Service - GS-1 - Single Phase Commercial General Service - GS-1 Three Phase Commercial General-OTD 1-Three Phase Commercial General-OTD- Single Phase Commercial Industrial Power Time of day CP-3 above 1,000kW Demand Primary Metering and Transformer Discount Industrial Industrial Power Time of day CP-3 above 1,000kW Demand Industrial

136

Light Water Reactor Sustainability Nondestructive Evaluation for Concrete  

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

Nondestructive Evaluation for Nondestructive Evaluation for Concrete Research and Development Roadmap Light Water Reactor Sustainability Nondestructive Evaluation for Concrete Research and Development Roadmap Materials issues are a key concern for the existing nuclear reactor fleet as material degradation can lead to increased maintenance, increased downtown, and increased risk. Extending reactor life to 60 years and beyond will likely increase susceptibility and severity of known forms of degradation. Additionally, new mechanisms of materials degradation are also possible. The purpose of the US Department of Energy Office of Nuclear Energy's Light Water Reactor Sustainability (LWRS) Program is to develop technologies and other solutions that can improve the reliability, sustain the safety, and extend

137

Plutonium Recycling in Light Water Reactors at Framatome ANP: Status and Trends  

Science Conference Proceedings (OSTI)

Technical Paper / Advances in Nuclear Fuel Management - Use of Alternate Fuels in Light Water Reactors

Dieter Porsch; Walter Stach; Pascal Charmensat; Michel Pasquet

138

Superior Water, Light and Power Co | Open Energy Information  

Open Energy Info (EERE)

Water, Light and Power Co Water, Light and Power Co Jump to: navigation, search Name Superior Water, Light and Power Co Place Wisconsin Utility Id 18336 Utility Location Yes Ownership I NERC Location MRO NERC MRO Yes Activity Bundled Services Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] Energy Information Administration Form 826[2] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png No rate schedules available. Average Rates Residential: $0.1050/kWh Commercial: $0.0835/kWh Industrial: $0.0674/kWh The following table contains monthly sales and revenue data for Superior Water, Light and Power Co (Wisconsin). Month RES REV (THOUSAND $) RES SALES (MWH) RES CONS COM REV (THOUSAND $) COM SALES (MWH) COM CONS IND_REV (THOUSAND $) IND SALES (MWH) IND CONS OTH REV (THOUSAND $) OTH SALES (MWH) OTH CONS TOT REV (THOUSAND $) TOT SALES (MWH) TOT CONS

139

Turbine Technologies for High Performance Light Water Reactors  

SciTech Connect

Available turbine technologies for a High Performance Light Water Reactor (HPLWR) have been analysed. For the envisaged steam pressures and temperatures of 25 MPa and 500 deg. C, no further challenges in turbine technologies have to be expected. The results from a steam cycle analysis indicate a net plant efficiency of 43.9% for the current HPLWR design. (authors)

Bitterman, D. [Framatome ANP GmbH, P.O. Box 3220, 91050 Erlangen (Germany); Starflinger, J.; Schulenberg, T. [Forschungszentrum Karlsruhe, P.O. Box 3640, 76021 Karlsruhe (Germany)

2004-07-01T23:59:59.000Z

140

Lansing Board of Water and Light - Hometown Energy Savers Commercial  

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

Savers Savers Commercial Rebates Lansing Board of Water and Light - Hometown Energy Savers Commercial Rebates < Back Eligibility Commercial Industrial Savings Category Heating & Cooling Commercial Heating & Cooling Cooling Manufacturing Other Construction Heat Pumps Appliances & Electronics Commercial Lighting Lighting Maximum Rebate Incentives for Prescriptive measures may not exceed 100% of the total project cost, or $50,000 per electric meter per year. Incentives for Custom measures may not exceed 40% of the total project cost, or $20,000. Program Info Expiration Date 11/30/2013 State Michigan Program Type Utility Rebate Program Rebate Amount Small Business Direct Install Program: No cost or purchase necessary for participation Custom $0.08/kWh Commercial Cooking Equipment: Varies

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

City Water and Light Plant | Open Energy Information  

Open Energy Info (EERE)

and Light Plant and Light Plant Jump to: navigation, search Name City Water and Light Plant Place Arkansas Utility Id 9879 Utility Location Yes Ownership M NERC Location SPP NERC SPP Yes RTO SPP Yes Operates Generating Plant Yes Activity Generation Yes Activity Buying Transmission Yes Activity Distribution Yes Alt Fuel Vehicle Yes Alt Fuel Vehicle2 Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png General Service- Large Industrial General Service- Large(Primary Metering) Industrial General Service- Small Electric Rate Commercial General service (Residential Electric Rate) Residential

142

North Branch Water & Light Comm | Open Energy Information  

Open Energy Info (EERE)

North Branch Water & Light Comm North Branch Water & Light Comm Place Minnesota Utility Id 13681 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes Operates Generating Plant Yes Activity Generation Yes Activity Distribution Yes Activity Bundled Services Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Commercial Commercial Large General Service Industrial Residential Residential Residential- Seasonal Residential Average Rates Residential: $0.1250/kWh Commercial: $0.1140/kWh Industrial: $0.0750/kWh References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a"

143

An Evaluation of the Proliferation Resistant Characteristics of Light Water  

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

An Evaluation of the Proliferation Resistant Characteristics of An Evaluation of the Proliferation Resistant Characteristics of Light Water Reactor Fuel with the Potential for Recycle in the United States An Evaluation of the Proliferation Resistant Characteristics of Light Water Reactor Fuel with the Potential for Recycle in the United States The Advanced Fuel Cycle Initiative (AFCI) of the Department of Energy has been formulated to perform research leading to advanced fuels and fuel cycles for advanced nuclear power systems. One of the objectives of AFCI is to determine if partitioning and transmutation of spent nuclear fuel will reduce the burden on the geologic repository. The AFCI program is periodically reviewed by the Advanced Nuclear Transmutation Technology (ANTT) subcommittee of the Nuclear Energy Research Advisory Committee

144

Oconto Falls Water & Light Comm | Open Energy Information  

Open Energy Info (EERE)

Oconto Falls Water & Light Comm Oconto Falls Water & Light Comm Place Wisconsin Utility Id 13965 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes ISO MISO Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Cp-1 Small Power Service Industrial Cp-1 Small Power Service Primary Metering Discount with Parallel Generation(20kW or less) Industrial Cp-1 Small Power Service Primary Metering Discount Industrial Cp-1 Small Power Service with Parallel Generation(20kW or less) Industrial Cp-1 TOD Small Power Optional Time-of-Day Service Primary Metering Discount

145

Newberry Water & Light Board | Open Energy Information  

Open Energy Info (EERE)

Board Board Jump to: navigation, search Name Newberry Water & Light Board Place Michigan Utility Id 13525 Utility Location Yes Ownership M NERC Location RFC NERC RFC Yes ISO MISO Yes Operates Generating Plant Yes Activity Generation Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Commercial Electric Commercial Residential Electric Residential Average Rates Residential: $0.1100/kWh Commercial: $0.1030/kWh Industrial: $0.1390/kWh References ↑ "EIA Form EIA-861 Final Data File for 2010 - File1_a" Retrieved from "http://en.openei.org/w/index.php?title=Newberry_Water_%26_Light_Board&oldid=411182

146

McMinnville Water and Light - Commercial Energy Efficiency Rebate Programs  

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

McMinnville Water and Light - Commercial Energy Efficiency Rebate McMinnville Water and Light - Commercial Energy Efficiency Rebate Programs McMinnville Water and Light - Commercial Energy Efficiency Rebate Programs < Back Eligibility Commercial Industrial Savings Category Appliances & Electronics Commercial Lighting Lighting Manufacturing Program Info State Oregon Program Type Utility Rebate Program Rebate Amount McMinnville Water and Light Company Provider McMinnville Water and Light 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 three categories: Lighting retrofits, motor replacements, and process efficiency. Past lighting projects have included fluorescent lighting retrofits, mercury vapor

147

Program on Technology Innovation: Cooling Water Review of the Advanced Light Water Reactor Utility Requirements Document  

Science Conference Proceedings (OSTI)

The EPRI Utility Requirements Document (URD) was developed and last revised in 1999 to provide a list of requirements for the design and construction of new nuclear power plants. The objective of this project was to review URD Vol. III. This volume covers passive advanced light water reactors (ALWRs) for plant design requirements with respect to operations and maintenance (O&M) practices of the plant's cooling water systems (not including the circulating water system used for condenser cooling). The revi...

2007-07-26T23:59:59.000Z

148

3D Simulation of Missing Pellet Surface Defects in Light Water Reactor Fuel Rods  

Science Conference Proceedings (OSTI)

The cladding on light water reactor (LWR) fuel rods provides a stable enclosure for fuel pellets and serves as a first barrier against fission product release. Consequently, it is important to design fuel to prevent cladding failure due to mechanical interactions with fuel pellets. Cladding stresses can be effectively limited by controlling power increase rates. However, it has been shown that local geometric irregularities caused by manufacturing defects known as missing pellet surfaces (MPS) in fuel pellets can lead to elevated cladding stresses that are sufficiently high to cause cladding failure. Accurate modeling of these defects can help prevent these types of failures. Nuclear fuel performance codes commonly use a 1.5D (axisymmetric, axially-stacked, one-dimensional radial) or 2D axisymmetric representation of the fuel rod. To study the effects of MPS defects, results from 1.5D or 2D fuel performance analyses are typically mapped to thermo-mechanical models that consist of a 2D plane-strain slice or a full 3D representation of the geometry of the pellet and clad in the region of the defect. The BISON fuel performance code developed at Idaho National Laboratory employs either a 2D axisymmetric or 3D representation of the full fuel rod. This allows for a computational model of the full fuel rod to include local defects. A 3D thermo-mechanical model is used to simulate the global fuel rod behavior, and includes effects on the thermal and mechanical behavior of the fuel due to accumulation of fission products, fission gas production and release, and the effects of fission gas accumulation on thermal conductivity across the fuel-clad gap. Local defects can be modeled simply by including them in the 3D fuel rod model, without the need for mapping between two separate models. This allows for the complete set of physics used in a fuel performance analysis to be included naturally in the computational representation of the local defect, and for the effects of the local defect to be coupled with the global fuel rod model. This approach for modeling fuel with MPS defects is demonstrated and compared with alternative techniques. The effects of varying parameters of the MPS defect are studied using this technique and presented here.

B.W. Spencer; J.D. Hales; S.R. Novascone; R.L. Williamson

2012-09-01T23:59:59.000Z

149

Lake Mills Light & Water | Open Energy Information  

Open Energy Info (EERE)

Water Water Jump to: navigation, search Name Lake Mills Light & Water Place Wisconsin Utility Id 10605 Utility Location Yes Ownership M NERC Location MRO NERC MRO Yes ISO MISO Yes Activity Distribution Yes Alt Fuel Vehicle Yes Alt Fuel Vehicle2 Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Cp-1 Small Power Service between 50kW and 200kW Demand Primary Metering and Transformer Ownership Discount with Parallel Generation(20kW or less) Industrial Cp-1 Small Power Service between 50kW and 200kW Demand Primary Metering and Transformer Ownership Discount Industrial

150

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

151

Program on Technology Innovation: Review of EPRI Advanced Light Water Reactor Utility Requirement Document to Include Small Modular Light Water Reactors  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) conducted a limited scope assessment to better understand what areas of the current EPRI advanced light water reactor (ALWR) Utility Requirement Document (URD) should be modified to ensure that the document is applicable to light water small modular reactors (LWSMRs). The LWSMRs differ from current light water reactors in that LWSMRs are significantly smaller than existing plants and utilize revolutionary design and construction strategies.

2011-04-25T23:59:59.000Z

152

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

Science Conference Proceedings (OSTI)

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

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

2002-09-01T23:59:59.000Z

153

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

154

Accident Performance of Light Water Reactor Cladding Materials  

DOE Green Energy (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

155

Mechanical design of a light water breeder reactor  

DOE Patents (OSTI)

In a light water reactor system using the thorium-232 -- uranium-233 fuel system in a seed-blanket modular core configuration having the modules arranged in a symmetrical array surrounded by a reflector blanket region, the seed regions are disposed for a longitudinal movement between the fixed or stationary blanket region which surrounds each seed region. Control of the reactor is obtained by moving the inner seed region thus changing the geometry of the reactor, and thereby changing the leakage of neutrons from the relatively small seed region into the blanket region. The mechanical design of the Light Water Breeder Reactor (LWBR) core includes means for axially positioning of movable fuel assemblies to achieve the neutron economy required of a breeder reactor, a structure necessary to adequately support the fuel modules without imposing penalties on the breeding capability, a structure necessary to support fuel rods in a closely packed array and a structure necessary to direct and control the flow of coolant to regions in the core in accordance with the heat transfer requirements.

Fauth, Jr., William L. (Germantown, MD); Jones, Daniel S. (Pittsburgh, PA); Kolsun, George J. (Pittsburgh, PA); Erbes, John G. (San Jose, CA); Brennan, John J. (Bethel Park, PA); Weissburg, James A. (Pittsburgh, PA); Sharbaugh, John E. (Acme, PA)

1976-01-01T23:59:59.000Z

156

Multi-Applications Small Light Water Reactor - NERI Final Report  

Science Conference Proceedings (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

157

Fuel Summary Report: Shippingport Light Water Breeder Reactor  

SciTech Connect

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

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

1999-01-01T23:59:59.000Z

158

The Consortium for Advanced Simulation of Light Water Reactors  

SciTech Connect

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

159

Repair and Replacement Applications Center: Stress Corrosion Cracking in Closed Cooling Water Systems  

Science Conference Proceedings (OSTI)

The results of a recent EPRI project "Stress Corrosion Cracking in PWR and BWR Closed Cooling Water Systems," (EPRI Report 1009721, October 2004) indicated that approximately 10 of 143 light water reactor (LWR) plants surveyed had through-wall leaks in carbon steel piping in their closed cooling water (CCW) systems. The root cause of this leakage was intergranular stress corrosion cracking. Since there has not been extensive non-destructive testing in these systems, it is likely that the incidence rate o...

2006-09-28T23:59:59.000Z

160

Light Water Reactor Sustainability Program: Materials Aging and Degradation  

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

Materials Aging and Materials Aging and Degradation Technical Program Plan Light Water Reactor Sustainability Program: Materials Aging and Degradation Technical Program Plan Components serving in a nuclear reactor plant must withstand a very harsh environment including extended time at temperature, neutron irradiation, stress, and/or corrosive media. The many modes of degradation are complex and vary depending on location and material. However, understanding and managing materials degradation is a key for the continued safe and reliable operation of nuclear power plants. Extending reactor service to beyond 60 years will increase the demands on materials and components. Therefore, an early evaluation of the possible effects of extended lifetime is critical. The recent NUREG/CR-6923 gives a

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161

Light Water Reactor Sustainability Program - Non-Destructive Evaluation  

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

Program - Non-Destructive Program - Non-Destructive Evaluation R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants Light Water Reactor Sustainability Program - Non-Destructive Evaluation R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. A workshop was held to gather subject matter experts to develop the NDE R&D Roadmap for Cables. The focus of the workshop was to identify the technical gaps in detecting aging cables and predicting their remaining life expectancy. The workshop was held in Knoxville, Tennessee, on July 30, 2012, at Analysis and Measurement Services Corporation (AMS) headquarters.

162

Light Water Reactor Sustainability Program: Integrated Program Plan |  

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

Integrated Program Plan Integrated Program Plan Light Water Reactor Sustainability Program: Integrated Program Plan 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 grow by more than 30% 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

163

Light-water breeder reactor (LWBR Development Program)  

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, L.J. Jr.; Raab, H.F.

1972-06-20T23:59:59.000Z

164

SAFETY EVALUATION OF LIGHT-WATER-MODERATED POWER REACTOR  

SciTech Connect

Important problems associated with safety evaluation are reviewed. In contrast to absolute safety,'' the concept of social safety'' is explained and factors to compose social safety'' are evaluated. Some comments are made on the philosophy of safety evaluation. A core spray and enclosure spray systems, which are essential with respect to safety evaluation of the maximum credible accident of light-water-moderated power reactors, are analyzed in detail. In evaluation of a core spray system, detailed analysis is made on loss-of- coolant accident, and effects of core spray system design (spray initiation time, spray flow rate, spray distribution, etc.) on fission release are quantitatively clarified. In evaluation of an enclosure spray system, various product release reduction factors are calculated and relative importance of an enclosure spray system is discussed. A hypothetical accident is analyzed. (auth)

Togo, Y.

1963-03-01T23:59:59.000Z

165

Materials Inventory Database for the Light Water Reactor Sustainability Program  

Science Conference Proceedings (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

166

Effect of welding conditions on transformation and properties of heat-affected zones in LWR (light-water reactor) vessel steels  

DOE Green Energy (OSTI)

The continuous cooling transformation behavior (CCT) and isothermal transformation (IT) behavior were determined for SA-508 and SA-533 materials for conditions pertaining to standard heat treatment and for the coarse-grained region of the heat-affected zone (HAZ). The resulting diagrams help to select welding conditions that produce the most favorable microconstituent for the development of optimum postweld heat treatment (PWHT) toughness levels. In the case of SA-508 and SA-533, martensite responds more favorably to PWHT than does bainite. Bainite is to be avoided for the optimum toughness characteristics of the HAZ. The reheat cracking tendency for both steels was evaluated by metallographic studies of simulated HAZ structures subjected to PWHT cycles and simultaneous restraint. Both SA-533, Grade B, Class 1, and SA-508, Class 2, cracked intergranularly. The stress rupture parameter (the product of the stress for a rupture life of 10 min and the corresponding reduction of area) calculated for both steels showed that SA-508, Class 2, was more susceptible to reheat cracking than SA-533, Grade B, Class 1. Cold cracking tests (Battelle Test and University of Tennessee modified hydrogen susceptibility test) indicated that a higher preheat temperature is required for SA-508, Class 2, to avoid cracking than is required for SA-533, Grade B, Class 1. Further, the Hydrogen Susceptibility Test showed that SA-508, Class 2, is more susceptible to hydrogen embrittlement than is SA-533, Grade B, Class 1.

Lundin, C.D.; Mohammed, S. (Tennessee Univ., Knoxville, TN (USA). Welding Research and Engineering)

1990-11-01T23:59:59.000Z

167

Tritium separation from light and heavy water by bipolar electrolysis  

DOE Green Energy (OSTI)

Use of bipolar electrolysis with countercurrent electrolyte flow to separate hydrogen isotopes was investigated for the removal of tritium from light water effluents or from heavy water moderator. Deuterium-tritium and protium-tritium separation factors occurring on a Pd-25% Ag bipolar electrode were measured to be 2.05 to 2.16 and 11.6 to 12.4 respectively, at current densities between 0.21 and 0.50 A cm/sup -2/, and at 35 to 90/sup 0/C. Current densities up to 0.3 A cm/sup -2/ have been achieved in continuous operation, at 80 to 90/sup 0/C, without significant gas formation on the bipolar electrodes. From the measured overvoltage at the bipolar electrodes and the electrolyte conductivity the power consumption per stage was calculated to be 3.0 kwh/kg H/sub 2/O at 0.2 A cm/sup -2/ and 5.0 kwh/kg H/sub 2/O at 0.5 A cm/sup -2/ current density, compared to 6.4 and 8.0 kwh/kg H/sub 2/O for normal electrolysis. A mathematical model derived for hydrogen isotope separation by bipolar electrolysis, i.e., for a square cascade, accurately describes the results for protium-tritium separation in two laboratory scale, multistage experiments with countercurrent electrolyte flow; the measured tiritum concentration gradient through the cascade agreed with the calculated values.

Ramey, D.W.; Petek, M.; Taylor, R.D.; Kobisk, E.H.; Ramey, J.; Sampson, C.A.

1979-10-01T23:59:59.000Z

168

Light Water Reactor Sustainability Constellation Pilot Project FY12 Summary Report  

SciTech Connect

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

R. Johansen

2012-09-01T23:59:59.000Z

169

ANL/NE-12/43 Light Water Reactor Sustainability (LWRS)  

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

ANLNE-1243 Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping ...

170

Light Water Reactor Sustainability Constellation Pilot Project FY13 Summary Report  

SciTech Connect

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

R. Johansen

2013-09-01T23:59:59.000Z

171

Three-dimensional modeling and simulation of vapor explosions in Light Water Reactors.  

E-Print Network (OSTI)

??Steam explosions can occur during a severe accident in light water nuclear reactors with the core melting as the consequence of interaction of molten core (more)

Schrder, Maxim

2012-01-01T23:59:59.000Z

172

SEIS for the Production of Tritium in a Commercial Light Water...  

National Nuclear Security Administration (NNSA)

SEIS for the Production of Tritium in a Commercial Light Water Reactor | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation...

173

CHEMICAL ASPECTS OF PELLET-CLADDING INTERACTION IN LIGHT WATER REACTOR FUEL ELEMENTS  

E-Print Network (OSTI)

ANS/ENS Topical Meeting on Reactor Safety Aspects of FuelINTERACTION IN LiaiT-WATER-REACTOR FUEL ELEMENTS by D. R.PCI) in light water reactor fuel elements, the chemical

Olander, D.R.

2010-01-01T23:59:59.000Z

174

Chemical and light-stable isotope characteristics of waters from the raft  

Open Energy Info (EERE)

light-stable isotope characteristics of waters from the raft light-stable isotope characteristics of waters from the raft river geothermal area and environs, Cassia County, Idaho, Box Elder county, Utah Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Journal Article: Chemical and light-stable isotope characteristics of waters from the raft river geothermal area and environs, Cassia County, Idaho, Box Elder county, Utah Details Activities (1) Areas (1) Regions (0) Abstract: Chemical and light-stable isotope data are presented for water samples from the Raft River geothermal area and environs. On the basis of chemical character, as defined by a trilinear plot of per cent milliequivalents, and light-stable isotope data, the waters in the geothermal area can be divided into waters that have and have not mixed

175

A Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water  

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

A Review of Stress Corrosion Cracking/Fatigue Modeling for Light A Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water Reactor Cooling System Components A Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water Reactor Cooling System Components In the United States currently there are approximately 104 operating light water reactors. Of these, 69 are pressurized water reactors (PWRs) and 35 are boiling water reactors (BWRs). In 2007, the 104 light-water reactors (LWRs) in the United States generated approximately 100 GWe, equivalent to 20% of total US electricity production. Most of the US reactors were built before 1970 and the initial design lives of most of the reactors are 40 years. It is expected that by 2030, even those reactors that have received 20-year life extension license from the US Nuclear Regulatory Commission

176

Cedarburg Light and Water Utility - Residential Energy Efficiency...  

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

300 Water Heaters: 25 - 100 Tankless Water Heaters: 100 Heat Pump Water Heater: 300 Air SealingAttic Insulation: Up to 300 Energy Star Home Performance: 33.3% of cost up to...

177

Liquid Water Content of Fogs and Hazes from Visible Light Scattering  

Science Conference Proceedings (OSTI)

A new method is proposed for measuring the liquid water content of fogs and hazes. It consists of a planar circular light sensor placed perpendicular to and coaxial with a narrow collimated light beam of a visible wavelength. The direct light ...

H. Gerber

1984-08-01T23:59:59.000Z

178

Columbia Water and Light - New Home Energy Star Rebate | Department of  

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

Columbia Water and Light - New Home Energy Star Rebate Columbia Water and Light - New Home Energy Star Rebate Columbia Water and Light - New Home Energy Star Rebate < Back Eligibility Construction Residential Savings Category Heating & Cooling Home Weatherization Construction Commercial Weatherization Commercial Heating & Cooling Design & Remodeling Other Program Info State Missouri Program Type Utility Rebate Program Rebate Amount 1,000 Provider Columbia Water and Light Columbia Water and Light offers a $1,000 rebate to customers for the construction of new homes that achieve certification as Energy Star homes. The Energy Star designation is given to homes that receive an 85 or less on the Home Energy Rating System (HERS) index, meaning that they can be expected to use 15% less energy on average than a standard home (i.e., the

179

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect

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

180

MIXED-OXIDE FUEL USE IN COMMERCIAL LIGHT WATER REACTORS  

E-Print Network (OSTI)

In a Commission briefing on high-bumup fuel on March 25, 1997, the staff said that they would prepare a white paper on mixed-oxide (MOX) fuel in anticipation of a DOE program to bum excess weapons plutonium in commercial reactors. This memorandum and its attachment comprise that paper and are provided to inform the Commissioners of technical issues associated with such a program. More recently, on February 5, 1999, I was contacted by the Nuclear Control Institute regarding a paper they have written on this subject. They presented that paper to the staff in a public meeting on April 7, 1999. The Nuclear Control Institute's written paper had been provided to the staff earlier, and we have taken the paper into consideration in preparing this memorandum. Back-ground In January 1997, the U.S. Department of Energy released a record of decision for the storage and disposition of weapons-usable fissile materials. In this record, DOE recommended that excess weapons-grade plutonium be disposed of by two methods: (1) reconstituting the plutonium into mixed-oxide (MOX) fuel rods and burning it in current light water reactors, and (2) immobilizing the plutonium in glass logs with appropriate radioactive isotopes to deter theft prior to geologic disposal. Based on current information, it now appears that, if the MOX fuel method is utilized, fuel fabrication will take place at the Savannah River site in South Carolina with burning in nearby Westinghouse-type PWRs. Although DOE will probably not receive funding in FY 2000 for developing a license application, Congress has already given its approval for NRC licensing authority over a MOX fuel fabrication facility operated under

United States; William D. Travers

1999-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "lwr light 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 Reactor Sustainability Program Integrated Program Plan  

Science Conference Proceedings (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

182

The burnup dependence of light water reactor spent fuel oxidation  

SciTech Connect

Over the temperature range of interest for dry storage or for placement of spent fuel in a permanent repository under the conditions now being considered, UO{sub 2} is thermodynamically unstable with respect to oxidation to higher oxides. The multiple valence states of uranium allow for the accommodation of interstitial oxygen atoms in the fuel matrix. A variety of stoichiometric and nonstoichiometric phases is therefore possible as the fuel oxidizers from UO{sub 2} to higher oxides. The oxidation of UO{sub 2} has been studied extensively for over 40 years. It has been shown that spent fuel and unirradiated UO{sub 2} oxidize via different mechanisms and at different rates. The oxidation of LWR spent fuel from UO{sub 2} to UO{sub 2.4} was studied previously and is reasonably well understood. The study presented here was initiated to determine the mechanism and rate of oxidation from UO{sub 2.4} to higher oxides. During the early stages of this work, a large variability in the oxidation behavior of samples oxidized under nearly identical conditions was found. Based on previous work on the effect of dopants on UO{sub 2} oxidation and this initial variability, it was hypothesized that the substitution of fission product and actinide impurities for uranium atoms in the spent fuel matrix was the cause of the variable oxidation behavior. Since the impurity concentration is roughly proportional to the burnup of a specimen, the oxidation behavior of spent fuel was expected to be a function of both temperature and burnup. This report (1) summarizes the previous oxidation work for both unirradiated UO{sub 2} and spent fuel (Section 2.2) and presents the theoretical basis for the burnup (i.e., impurity concentration) dependence of the rate of oxidation (Sections 2.3, 2.4, and 2.5), (2) describes the experimental approach (Section 3) and results (Section 4) for the current oxidation tests on spent fuel, and (3) establishes a simple model to determine the activation energies associated with spent fuel oxidation (Section 5).

Hanson, B.D.

1998-07-01T23:59:59.000Z

183

McMinnville Water and Light - Residential Energy Efficiency Rebate Program  

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

McMinnville Water and Light - Residential Energy Efficiency Rebate McMinnville Water and Light - Residential Energy Efficiency Rebate Program McMinnville Water and Light - Residential Energy Efficiency Rebate Program < Back Eligibility Residential Savings Category Appliances & Electronics Heating & Cooling Home Weatherization Construction Commercial Weatherization Commercial Heating & Cooling Design & Remodeling Water Heating Program Info State Oregon Program Type Utility Rebate Program Rebate Amount Energy Star Homes: up to $1,180 Energy Star Manufactured Homes: $850 Clothes Washer: $20 - $70 Refrigerator: $15 Freezer: $15 Refrigerator/Freezer Decommissioning: $100 Electric Water Heater: $25 - $50, varies by warranty Heat Pump PTCS Tune-up: contact utility Weatherization Measures: contact utility Provider McMinnville Water and Light

184

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

E-Print Network (OSTI)

energy in bulk water, producing a major impact on energy conservation.6 Heavy water was added to light, if it is produced, will be observed only as the water cools through 4°C. Fig. 2S. Here we show a graph (a) of the temperature gradient produced in the center of the bottle when it is filled with regular water with no added D

Suzuki, Masatsugu

185

Multi-Application Small Light Water Reactor Final Report  

Science Conference Proceedings (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

186

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

187

Lighting.  

SciTech Connect

Since lighting accounts for about one-third of the energy used in commercial buildings, there is opportunity to conserve. There are two ways to reduce lighting energy use: modify lighting systems so that they used less electricity and/or reduce the number of hours the lights are used. This booklet presents a number of ways to do both. Topics covered include: reassessing lighting levels, reducing lighting levels, increasing bulb & fixture efficiency, using controls to regulate lighting, and taking advantage of daylight.

United States. Bonneville Power Administration.

1992-09-01T23:59:59.000Z

188

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

Open Energy Info (EERE)

of waters from the raft river geothermal area and environs, Cassia County, Idaho, Box Elder county, Utah Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home...

189

Analysis of the Reuse of Uranium Recovered from the Reprocessing of Commercial LWR Spent Fuel  

Science Conference Proceedings (OSTI)

This report provides an analysis of the factors involved in the reuse of uranium recovered from commercial light-water-reactor (LWR) spent fuels (1) by reenrichment and recycling as fuel to LWRs and/or (2) by recycling directly as fuel to heavy-water-reactors (HWRs), such as the CANDU (registered trade name for the Canadian Deuterium Uranium Reactor). Reuse is an attractive alternative to the current Advanced Fuel Cycle Initiative (AFCI) Global Nuclear Energy Partnership (GNEP) baseline plan, which stores the reprocessed uranium (RU) for an uncertain future or attempts to dispose of it as 'greater-than-Class C' waste. Considering that the open fuel cycle currently deployed in the United States already creates a huge excess quantity of depleted uranium, the closed fuel cycle should enable the recycle of the major components of spent fuel, such as the uranium and the hazardous, long-lived transuranic (TRU) actinides, as well as the managed disposal of fission product wastes. Compared with the GNEP baseline scenario, the reuse of RU in the uranium fuel cycle has a number of potential advantages: (1) avoidance of purchase costs of 11-20% of the natural uranium feed; (2) avoidance of disposal costs for a large majority of the volume of spent fuel that is reprocessed; (3) avoidance of disposal costs for a portion of the depleted uranium from the enrichment step; (4) depending on the {sup 235}U assay of the RU, possible avoidance of separative work costs; and (5) a significant increase in the production of {sup 238}Pu due to the presence of {sup 236}U, which benefits somewhat the transmutation value of the plutonium and also provides some proliferation resistance.

DelCul, Guillermo D [ORNL; Trowbridge, Lee D [ORNL; Renier, John-Paul [ORNL; Ellis, Ronald James [ORNL; Williams, Kent Alan [ORNL; Spencer, Barry B [ORNL; Collins, Emory D [ORNL

2009-02-01T23:59:59.000Z

190

City Water Light and Power - Solar Rewards Program | Department of Energy  

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

You are here You are here Home » City Water Light and Power - Solar Rewards Program City Water Light and Power - Solar Rewards Program < Back Eligibility Commercial Residential Savings Category Solar Buying & Making Electricity Maximum Rebate $15,000 per account Program Info Start Date 01/23/2012 State Illinois Program Type Utility Rebate Program Rebate Amount $1,500/kW Provider City Water Light and Power '''''Note: Funding for the Solar Rewards program has been exhausted. Check the program web site for more information regarding additional funding, expected March 2013.''''' City Water, Light and Power (CWLP) is now offering residential and commercial customers a $1,500 per kilowatt (kW) rebate for installing solar photovoltaic (PV) systems. Rebates are limited to $15,000 per customer

191

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

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

288: Production of Tritium in a Commercial Light Water Reactor 288: Production of Tritium in a Commercial Light Water Reactor EIS-0288: Production of Tritium in a Commercial Light Water Reactor SUMMARY 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 of the following five CLWRs: (1) Watts Bar Nuclear Plant Unit 1 (Spring City, Tennessee); (2) Sequoyah Nuclear Plant Unit 1 (Soddy Daisy, Tennessee); (3) Sequoyah Nuclear Plant Unit 2 (Soddy Daisy, Tennessee); (4) Bellefonte Nuclear Plant Unit 1 (Hollywood, Alabama); and (5) Bellefonte Nuclear Plant Unit 2 (Hollywood, Alabama). Specifically, this EIS analyzes the potential environmental impacts associated with fabricating tritium-producing

192

EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor  

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

8-S1: Production of Tritium in a Commercial Light Water 8-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement Summary This Supplemental EIS updates the environmental analyses in DOE's 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. Public Comment Opportunities No public comment opportunities at this time. Documents Available for Download September 28, 2011 EIS-0288-S1: Notice of Intent to Prepare a Supplemental Environmental

193

Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for  

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

Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light water reactor sustainability (LWRS) nondestructive evaluation (NDE) Workshops were held at Oak Ridge National Laboratory (ORNL) during July 30th to August 2nd, 2012. This activity was conducted to help develop the content of the NDE R&D roadmap for the materials aging and degradation (MAaD) pathway of the LWRS program. The workshops focused on identifying NDE R&D needs in four areas: cables, concrete, reactor pressure vessel, and piping. A selected group of subject matter experts (SMEs) from DOE national

194

Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor  

E-Print Network (OSTI)

A design for a large, passive, light water reactor has been developed. The proposed concept is a pressure tube reactor of similar design to CANDU reactors, but differing in three key aspects. First, a solid SiC-coated ...

Hejzlar, P.

195

Visible-Light Water-Splitting Performance of TiO - Programmaster.org  

Science Conference Proceedings (OSTI)

Presentation Title, Visible-Light Water-Splitting Performance of TiO2 ... Ammonia Borane for Chemical Hydrogen Storage: Effect of Nano-Confinement ... Thermodynamic Characterization on Hydrogen Absorption and Desorption Reactions of...

196

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

197

Memphis Light, Gas and Water Division Smart Grid Project | Open Energy  

Open Energy Info (EERE)

Light, Gas and Water Division Smart Grid Project Light, Gas and Water Division Smart Grid Project Jump to: navigation, search Project Lead Memphis Light, Gas and Water Division Country United States Headquarters Location Memphis, Tennessee Recovery Act Funding $5,063,469.00 Total Project Value $13112363 Coverage Area Coverage Map: Memphis Light, Gas and Water Division Smart Grid Project Coordinates 35.1495343°, -90.0489801° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[]}

198

RADIATION RESEARCH 153, 220238 (2000) 0033-7587/00 $5.00  

E-Print Network (OSTI)

): the light water reactor [(LWR) in both pressurized and boil- ing versions]; heavy water (CANDU) reactor

199

Lighting  

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

There are many different types of artificial lights, all of which have different applications and uses.Types of lighting include:

200

Lansing Board of Water & Light - Hometown Energy Savers Residential...  

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

30-50 HID Replacement Fixtures: 25-120 HID Replacement Lamps: 0.30watt saved HVAC and Process Air Conditioners and Heat Pumps: 6-30ton Air and Water Cooled Chillers:...

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

Lansing Board of Water & Light - Hometown Energy Savers Commercial...  

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

30-50 HID Replacement Fixtures: 25-120 HID Replacement Lamps: 0.30watt saved HVAC and Process Air Conditioners and Heat Pumps: 6-30ton Air and Water Cooled Chillers:...

202

Corrosion-Product Release in Light Water Reactors  

Science Conference Proceedings (OSTI)

Colbalt released through corrosion is the primary source of radiation fields on out-of-core surfaces in pressurized water reactors. Lowering colbalt impurity levels in Inconel 600, a generator tubing material, could reduce radiation fields.

1984-03-01T23:59:59.000Z

203

Jonesboro City Water & Light - Energy Conservation Rebate Program...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

204

City Water Light and Power - Residential Energy Efficiency Rebate...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

205

City Water Light and Power - Solar Rewards Program | Open Energy...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

206

Columbia Water & Light - Residential HVAC Rebate Program (Missouri...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

207

Columbia Water & Light - Commercial Super Saver Loans (Missouri...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

208

Columbia Water & Light - New Home Energy Star Rebate (Missouri...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

209

Columbia Water & Light - Residential Super Saver Loans (Missouri...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

210

Columbia Water & Light - Home Performance with Energy Star Rebates...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

211

Cedarburg Light & Water Utility - Commercial Shared Savings Loan...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

212

City Water Light and Power - Commercial Energy Efficiency Rebate...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

213

Columbia Water & Light - Solar Rebates (Missouri) | Open Energy...  

Open Energy Info (EERE)

Low Emission Development Strategies Oil & Gas Smart Grid Solar U.S. OpenLabs Utilities Water Wind Page Actions View form View source History View New Pages Recent Changes All...

214

X-Ray Shines Light on Water Mystery  

DOE Green Energy (OSTI)

Water is the key compound for our existence on this planet and it is involved in many important physical, chemical, biological and geological processes. Although water is the most common molecular substance it is also most unusual with many anomalies in its thermodynamic properties such as compressibility, density variation and heat capacity. The question of the structure of the hydrogen bonding network in water has been discussed intensively for over 100 years and has not yet been resolved. This talk will describe recent x-ray spectroscopy and scattering measurements showing that the liquid can be described as fluctuations between two types of local hydrogen bonded structures driven by in commensurate requirements for minimizing enthalpy and maximizing entropy.

Nilsson, Anders (SLAC)

2010-11-17T23:59:59.000Z

215

Evaluation of measured LWR spent fuel composition data for use in code validation  

Science Conference Proceedings (OSTI)

Burnup credit (BUC) is a concept applied in the criticality safety analysis of spent nuclear fuel in which credit or partial credit is taken for the reduced reactivity worth of the fuel due to both fissile depletion and the buildup of actinides and fission products that act as net neutron absorbers. Typically, a two-step process is applied in BUC analysis: first, depletion calculations are performed to estimate the isotopic content of spent fuel based on its burnup history; second, three-dimensional (3-D) criticality calculations are performed based on specific spent fuel packaging configurations. In seeking licensing approval of any BUC approach (e.g., disposal, transportation, or storage) both of these two computational procedures must be validated. This report was prepared in support of the validation process for depletion methods applied in the analysis of spent fuel from commercial light-water-reactor (LWR) designs. Such validation requires the comparison of computed isotopic compositions with those measured via radiochemical assay to assess the ability of a computer code to predict the contents of spent fuel samples. The purpose of this report is to address the availability and appropriateness of measured data for use in the validation of isotopic depletion methods. Although validation efforts to date at ORNL have been based on calculations using the SAS2H depletion sequence of the SCALE code system, this report has been prepared as an overview of potential sources of validation data independent of the code system used. However, data that are identified as in use in this report refer to earlier validation work performed using SAS2H in support of BUC. This report is the result of a study of available assay data, using the experience gained in spent fuel isotopic validation and with a consideration of the validation issues described earlier. This report recommends the suitability of each set of data for validation work similar in scope to the earlier work.

Hermann, O.W.; DeHart, M.D.; Murphy, B.D.

1998-02-01T23:59:59.000Z

216

Evaluation of Strobe Lights for Reducing Fish Impingement at Cooling Water Intakes  

Science Conference Proceedings (OSTI)

This report presents results of a two-year effort that examined the effectiveness for reducing impingement of freshwater fish at cooling water intake structures at two of the Tennessee Valley Authority's (TVA) power plants. This research project also was supported by a Water Quality Cooperative Grant from the U.S. Environmental Protection Agency (EPA). Research results advance our understanding on the utility of strobe lights as a fish protection technology for meeting Clean Water Act 316(b) requirements.

2008-09-30T23:59:59.000Z

217

EPRI Materials Management Matrix Project: Advanced Light-Water Reactor - Pressurized Water Reactor Degradation Matrix - Revision 1  

Science Conference Proceedings (OSTI)

The Advanced Light Water Reactor - Pressurized Water Reactor Degradation Matrix (ALWR PWR DM) is an integral piece of the Electric Power Research Institutes (EPRIs) Materials Management Matrix (MMM) initiative for ALWR designs. The MMM provides a tool to assist the industry in proactive identification and consideration of materials issues and mitigation/management opportunities from the design phase through component fabrication and plant construction to operations and maintenance.

2010-09-22T23:59:59.000Z

218

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

SciTech Connect

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

219

Criticality safety criteria for the handling, storage, and transportation of LWR fuel outside reactors: ANS-8.17-1984  

SciTech Connect

The potential for criticality accidents during the handling, storage, and transportation of fuel for nuclear reactors represents a health and safety risk to personnel involved in these activities, as well as to the general public. Appropriate design of equipment and facilities, handling procedures, and personnel training can minimize this risk. Even though the focus of the American National Standard, `Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors,` ANSI/ANS-8.1-1983, is general criteria for the ensurance of criticality safety, ANS-8.17-1984, provides additional guidance applicable to handling, storage, and transportation of light-water- reactor (LWR) nuclear fuel units in any phase of the fuel cycle outside the reactor core. ANS-8.17 had its origin in the late 1970s when a work group consisting of representatives from private industry, personnel from government contractor facilities, and scientists and engineers from the national laboratories was established. The work of this group resulted in the issuance of ANSI/ANS-8.17 in January 1984. This document provides a discussion of this standard.

Whitesides, G.E.

1996-09-01T23:59:59.000Z

220

Lansing Board of Water and Light - Hometown Energy Savers® Residential  

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

Savers® Savers® Residential Rebates Lansing Board of Water and Light - Hometown Energy Savers® Residential Rebates < Back Eligibility Low-Income Residential Multi-Family Residential Residential Savings Category Heating & Cooling Commercial Heating & Cooling Cooling Manufacturing Appliances & Electronics Construction Heating Heat Pumps Commercial Lighting Lighting Water Heating Other Program Info State Michigan Program Type Utility Rebate Program Rebate Amount Small Business Direct Install Program: No cost or purchase necessary for participation Custom $0.08/kWh Commercial Cooking Equipment: Varies Commercial Refrigeration Equipment: Varies Lighting Compact Fluorescent Lamps: $1.50-$8 Compact Fluorescent Lamp Fixtures: $20 LED Lamps: $5-$15 LED Fixtures: $20 LED Exit Signs: $12.50

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

ORGANIC SPECIES IN GEOTHERMAL WATERS IN LIGHT OF FLUID INCLUSION GAS  

Open Energy Info (EERE)

ORGANIC SPECIES IN GEOTHERMAL WATERS IN LIGHT OF FLUID INCLUSION GAS ORGANIC SPECIES IN GEOTHERMAL WATERS IN LIGHT OF FLUID INCLUSION GAS ANALYSES Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Conference Proceedings: ORGANIC SPECIES IN GEOTHERMAL WATERS IN LIGHT OF FLUID INCLUSION GAS ANALYSES Details Activities (1) Areas (1) Regions (0) Abstract: Measurement of organic compounds in Karaha- Telaga Bodas and Coso fluid inclusions shows there are strong relationships between H2 concentrations and alkane/alkene ratios and benzene concentrations. Inclusion analyses that indicate H2 concentrations > 0.001 mol % typically have ethane > ethylene, propane > propylene, and butane > butylene. There are three end member fluid compositions: type 1 fluids in which alkane compounds predominate, type 2 fluids that have ethane and propylene and no

222

DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term  

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

DOE-NE Light Water Reactor Sustainability Program and EPRI DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program - Joint Research and Development Plan DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program - Joint Research and Development Plan Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's

223

DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term  

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

DOE-NE Light Water Reactor Sustainability Program and EPRI DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program - Joint Research and Development Plan DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program - Joint Research and Development Plan Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's

224

An Assessment of PWR Water Chemistry Control in Advanced Light Water Reactors: U.S. EPR  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) developed the Water Chemistry Guidelines to support improved industry water chemistry operations. This report reviews the AREVA US EPR design to assess the applicability of the EPRI Pressurized Water Reactor (PWR) Primary and Secondary Water Chemistry Guidelines to that design. It is anticipated that the timely identification of any inconsistencies will allow EPRI and its member utilities to resolve them before the first US EPR plant begins operation.

2011-12-15T23:59:59.000Z

225

An Assessment of PWR Water Chemistry in Advanced Light Water Reactors: US-APWR  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) developed the Water Chemistry Guidelines to support improved industry water chemistry operations. This report reviews the Mitsubishi US-APWR design to assess the applicability of the EPRI Pressurized Water Reactor (PWR) Primary and Secondary Water Chemistry Guidelines to that design. It is anticipated that the timely identification of any inconsistencies will allow EPRI and its member utilities to resolve them before the first Mitsubishi Nuclear Energy Systems...

2012-01-31T23:59:59.000Z

226

An Assessment of PWR Water Chemistry Control in Advanced Light Water Reactors: APR1400  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) developed the Water Chemistry Guidelines to support improved industry water chemistry operations. This report reviews the Korea Hydro & Nuclear Power (KHNP) APR1400 design to assess the applicability of the EPRI Pressurized Water Reactor (PWR) Primary (Volume 1) and Secondary (Volume 2) Water Chemistry Guidelines to that design. The timely identification of any inconsistencies and technical gaps will allow EPRI and its member utilities to resolve them ...

2012-12-13T23:59:59.000Z

227

Lighting  

SciTech Connect

The lighting section of ASHRAE standard 90.1 is discussed. It applies to all new buildings except low-rise residential, while excluding specialty lighting applications such as signage, art exhibits, theatrical productions, medical and dental tasks, and others. In addition, lighting for indoor plant growth is excluded if designed to operate only between 10 p.m. and 6 a.m. Lighting allowances for the interior of a building are determined by the use of the system performance path unless the space functions are not fully known, such as during the initial stages of design or for speculative buildings. In such cases, the prescriptive path is available. Lighting allowances for the exterior of all buildings are determined by a table of unit power allowances. A new addition the exterior lighting procedure is the inclusion of facade lighting. However, it is no longer possible to trade-off power allotted for the exterior with the interior of a building or vice versa. A significant change is the new emphasis on lighting controls.

McKay, H.N. (Hayden McKay Lighting Design, New York, NY (US))

1990-02-01T23:59:59.000Z

228

PWR Primary-Side Gas Management in Advanced Light Water Reactors  

Science Conference Proceedings (OSTI)

The designs for advanced light water reactors (ALWRs) have incorporated new water chemistry controls that have been developed over the past few decades to improve material and equipment reliability and fuel performance and to minimize radionuclide production and transport. It is important to ensure that the new designs operate within ranges that are considered safe based on current knowledge and that industry guidance for normal operation, startup, and shutdown are updated to account for expanding ...

2013-07-17T23:59:59.000Z

229

Radiation Effects in Oxide Ceramics and Novel LWR Fuels  

Science Conference Proceedings (OSTI)

Nuclear fuels, such as uranium dioxide (UO2) and Mixed Oxide (MOX) fuels, have been used in current light water reactors (LWRs) to produce about 15% of the ... of oxide ceramics for nuclear applications through experiment, theory and...

230

Rethinking the Offer: The Impact on Nuclear Non-Proliferation of Providing North Korea or Iran with Light Water Reactors.  

E-Print Network (OSTI)

??This paper examines the impact on nuclear non-proliferation efforts of providing the DPRK and Iran with light water reactors (LWRs). I argue that LWRs in (more)

Lee, Eun Joo

2009-01-01T23:59:59.000Z

231

Light Water Reactor Sustainability Constellation Pilot Project FY11 Summary Report  

Science Conference Proceedings (OSTI)

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

R. Johansen

2011-09-01T23:59:59.000Z

232

A classification scheme for LWR fuel assemblies  

Science Conference Proceedings (OSTI)

With over 100 light water nuclear reactors operating nationwide, representing designs by four primary vendors, and with reload fuel manufactured by these vendors and additional suppliers, a wide variety of fuel assembly types are in existence. At Oak Ridge National Laboratory, both the Systems Integration Program and the Characteristics Data Base project required a classification scheme for these fuels. This scheme can be applied to other areas and is expected to be of value to many Office of Civilian Radioactive Waste Management programs. To develop the classification scheme, extensive information on the fuel assemblies that have been and are being manufactured by the various nuclear fuel vendors was compiled, reviewed, and evaluated. It was determined that it is possible to characterize assemblies in a systematic manner, using a combination of physical factors. A two-stage scheme was developed consisting of 79 assembly types, which are grouped into 22 assembly classes. The assembly classes are determined by the general design of the reactor cores in which the assemblies are, or were, used. The general BWR and PWR classes are divided differently but both are based on reactor core configuration. 2 refs., 15 tabs.

Moore, R.S.; Williamson, D.A.; Notz, K.J.

1988-11-01T23:59:59.000Z

233

Californias Energy Future: The View to 2050 - Summary Report  

E-Print Network (OSTI)

National Ignition Facility (NIF) and its associated researchdiode LWR Light water reactor NIF National Ignition Facility

Yang, Christopher

2011-01-01T23:59:59.000Z

234

California's Energy Future - The View to 2050  

E-Print Network (OSTI)

National Ignition Facility (NIF) and its associated researchdiode LWR Light water reactor NIF National Ignition Facility

2011-01-01T23:59:59.000Z

235

Fully Ceramic Microencapsulated Fuel Development for LWR Applications  

SciTech Connect

The concept, fabrication, and key feasibility issues of a new fuel form based on the microencapsulated (TRISO-type) fuel which has been specifically engineered for LWR application and compacted within a SiC matrix will be presented. This fuel, the so-called fully ceramic microencapsulated fuel is currently undergoing development as an accident tolerant fuel for potential UO2 replacement in commercial LWRs. While the ability of this fuel to facilitate normal LWR cycle performance is an ongoing effort within the program, this will not be a focus of this paper. Rather, key feasibility and performance aspects of the fuel will be presented including the ability to fabricate a LWR-specific TRISO, the need for and route to a high thermal conductivity and fully dense matrix that contains neutron poisons, and the performance of that matrix under irradiation and the interaction of the fuel with commercial zircaloy clad.

Snead, Lance Lewis [ORNL; Besmann, Theodore M [ORNL; Terrani, Kurt A [ORNL; Voit, Stewart L [ORNL

2012-01-01T23:59:59.000Z

236

Postirradiation examination of light water reactor fuel: a United States perspective  

Science Conference Proceedings (OSTI)

Poolside and hot-cell postirradiation examination (PIE) have played and will continue to play a significant role in the US LWR program. The principal uses of PIE are in fuel surveillance, fuel improvement, and failure analysis programs and in the postmortem analysis of safety-related tests. Institutional problems associated with fuel shipping, waste disposal, and fuel disposal can be expected to pose obstacles to hot-cell examinations and likely result in more sophisticated poolside examinations.

Neimark, L.A.; Ocken, H.

1980-01-01T23:59:59.000Z

237

Transmission of light in deep sea water at the site of the Antares neutrino telescope  

E-Print Network (OSTI)

The ANTARES neutrino telescope is a large photomultiplier array designed to detect neutrino-induced upward-going muons by their Cherenkov radiation. Understanding the absorption and scattering of light in the deep Mediterranean is fundamental to optimising the design and performance of the detector. This paper presents measurements of blue and UV light transmission at the ANTARES site taken between 1997 and 2000. The derived values for the scattering length and the angular distribution of particulate scattering were found to be highly correlated, and results are therefore presented in terms of an absorption length lambda_abs and an effective scattering length lambda_sct^eff. The values for blue (UV) light are found to be lambda_abs ~ 60(26) m, lambda_sct^eff ~ 265(122) m, with significant (15%) time variability. Finally, the results of ANTARES simulations showing the effect of these water properties on the anticipated performance of the detector are presented.

ANTARES collaboration

2004-12-06T23:59:59.000Z

238

Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for  

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

(LWRS) Program - R&D Roadmap (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light water reactor sustainability (LWRS) nondestructive evaluation (NDE) Workshops were held at Oak Ridge National Laboratory (ORNL) during July 30th to August 2nd, 2012. This activity was conducted to help develop the content of the NDE R&D roadmap for the materials aging and degradation (MAaD) pathway of the LWRS program. The workshops focused on identifying NDE R&D needs in four areas: cables, concrete, reactor pressure vessel, and piping. A selected group of subject matter experts (SMEs) from DOE national laboratories, academia, vendors, EPRI, and NRC were invited to each

239

Effects of light water reactor coolant environment on the fatigue lives of  

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

Effects of light water reactor coolant environment on the fatigue lives of Effects of light water reactor coolant environment on the fatigue lives of reactor materials July 8, 2013 A metal component can become progressively degraded, and its structural integrity can be adversely impacted when it is subjected to repeated fluctuating loads, or fatigue loading. Fatigue loadings on nuclear reactor pressure vessel components can occur because of changes in pressure and temperature caused by transients during operation, such as reactor startup or shutdown and turbine trip events. The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code recognizes fatigue as a possible cause of failure of reactor materials and provides rules for designing nuclear power plant components to avoid fatigue failures. For various materials, the ASME Code defines the

240

Technical specification: Mixed-oxide pellets for the light-water reactor irradiation demonstration test  

Science Conference Proceedings (OSTI)

This technical specification is a Level 2 Document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-oxide Fuel Irradiation Test Project Plan. It is patterned after the pellet specification that was prepared by Atomic Energy of Canada, Limited, for use by Los Alamos National Laboratory in fabrication of the test fuel for the Parallex Project, adjusted as necessary to reflect the differences between the Canadian uranium-deuterium reactor and light-water reactor fuels. This specification and the associated engineering drawing are to be utilized only for preparation of test fuel as outlined in the accompanying Request for Quotation and for additional testing as directed by Oak Ridge National Laboratory or the Department of Energy.

Cowell, B.S.

1997-06-01T23:59:59.000Z

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

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

SciTech Connect

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

1986-06-01T23:59:59.000Z

242

Flow-induced vibration for light water reactors. Progress report, October 1980-December 1980  

Science Conference Proceedings (OSTI)

Flow-Induced Vibration for Light Water Reactors (FIV for LWRs) is a four-year program designed to improve the FIV performance of light water reactors through the development of design criteria, analytical models for predicting behavior of components, general scaling laws to improve the accuracy of reduced-scale tests, and the identification of high FIV risk areas. The program is managed by the General Electric Nuclear Power Systems Engineering Department and has three major contributors: General Electric Nuclear Power Systems Engineering Department (NPSED), General Electric Corporate Research and Development (CR and D) and Argonne National Laboratory (ANL). The program commenced December 1, 1976. This progress report summarizes the accomplishments achieved during the period from October 1980 to December 1980.

Torres, M.R.

1981-09-01T23:59:59.000Z

243

RELAP5-3D Code for Supercritical-Pressure Light-Water-Cooled Reactors  

SciTech Connect

The RELAP5-3D computer program has been improved for analysis of supercritical-pressure, light-water-cooled reactors. Several code modifications were implemented to correct code execution failures. Changes were made to the steam table generation, steam table interpolation, metastable states, interfacial heat transfer coefficients, and transport properties (viscosity and thermal conductivity). The code modifications now allow the code to run slow transients above the critical pressure as well as blowdown transients (modified Edwards pipe and modified existing pressurized water reactor model) that pass near the critical point.

Riemke, Richard Allan; Davis, Cliff Bybee; Schultz, Richard Raphael

2003-04-01T23:59:59.000Z

244

DOE/NNSA perspective safeguard by design: GEN III/III+ light water reactors and beyond  

SciTech Connect

An overview of key issues relevant to safeguards by design (SBD) for GEN III/IV nuclear reactors is provided. Lessons learned from construction of typical GEN III+ water reactors with respect to SBD are highlighted. Details of SBD for safeguards guidance development for GEN III/III+ light water reactors are developed and reported. This paper also identifies technical challenges to extend SBD including proliferation resistance methodologies to other GEN III/III+ reactors (except HWRs) and GEN IV reactors because of their immaturity in designs.

Pan, Paul Y [Los Alamos National Laboratory

2010-12-10T23:59:59.000Z

245

Preliminary concepts for detecting national diversion of LWR spent fuel  

SciTech Connect

Preliminary concepts for detecting national diversion of LWR spent fuel during storage, handling and transportation are presented. Principal emphasis is placed on means to achieve timely detection by an international authority. This work was sponsored by the Department of Energy/Office of Safeguards and Security (DOE/OSS) as part of the overall Sandia Fixed Facility Physical Protection Program.

Sonnier, C.S.; Cravens, M.N.

1978-04-01T23:59:59.000Z

246

Light tracking through ice and water -- Scattering and absorption in heterogeneous media with Photonics  

E-Print Network (OSTI)

In the field of neutrino astronomy, large volumes of optically transparent matter like glacial ice, lake water, or deep ocean water are used as detector media. Elementary particle interactions are studied using in situ detectors recording time distributions and fluxes of the faint photon fields of Cherenkov radiation generated by ultra-relativistic charged particles, typically muons or electrons. The Photonics software package was developed to determine photon flux and time distributions throughout a volume containing a light source through Monte Carlo simulation. Photons are propagated and time distributions are recorded throughout a cellular grid constituting the simulation volume, and Mie scattering and absorption are realised using wavelength and position dependent parameterisations. The photon tracking results are stored in binary tables for transparent access through ANSI-C and C++ interfaces. For higher-level physics applications, like simulation or reconstruction of particle events, it is then possible to quickly acquire the light yield and time distributions for a pre-specified set of light source and detector properties and geometries without real-time photon propagation. In this paper the Photonics light propagation routines and methodology are presented and applied to the IceCube and Antares neutrino telescopes. The way in which inhomogeneities of the Antarctic glacial ice distort the signatures of elementary particle interactions, and how Photonics can be used to account for these effects, is described.

J. Lundberg; P. Miocinovic; K. Woschnagg; T. Burgess; J. Adams; S. Hundertmark; P. Desiati; P. Niessen

2007-02-05T23:59:59.000Z

247

Advanced Nuclear Technology Advanced Light Water Reactor Utility Requirements Document, Revision 12  

Science Conference Proceedings (OSTI)

The utility requirement document (URD) is an industry-developed technical foundation for the design of advanced light water reactors (ALWRs). It was created with the objective of providing a comprehensive set of plant functional requirements that are considered important to utilities considering the construction of a nuclear plant and in ensuring successful deployment and operation of the plant. The scope of the URD is broad, addressing the entire plant (including the nuclear steam supply system, ...

2013-12-16T23:59:59.000Z

248

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

249

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

250

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

Science Conference Proceedings (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

251

Advanced Light Water Reactor Utility Requirements Document, Volume 2, Revision 8: ALWR Evolutionary Plant  

Science Conference Proceedings (OSTI)

EPRI's ALWR Program has been an industry-wide effort to establish the technical foundation for design of the advanced light water reactor (ALWR). This program included participation and sponsorship of several international utility companies and close cooperation with the U.S. Department of Energy. The cornerstone of the ALWR Program is a set of utility design requirements, which are contained in the ALWR Utility Requirements Document. The purpose of this document is to present a clear, complete statement...

1999-03-30T23:59:59.000Z

252

Advanced Light Water Reactor Utility Requirements Document, Volume 3, Revision 8: ALWR Passive Plant  

Science Conference Proceedings (OSTI)

EPRI's ALWR Program has been an industry-wide effort to establish the technical foundation for design of the advanced light water reactor (ALWR). This program included participation and sponsorship of several international utility companies and close cooperation with the U.S. Department of Energy. The cornerstone of the ALWR Program is a set of utility design requirements, which are contained in the ALWR Utility Requirements Document. The purpose of this document is to present a clear, complete statement...

1999-03-30T23:59:59.000Z

253

Distribution System Reliability Practices: Noteworthy Practices at Memphis Light, Gas and Water  

Science Conference Proceedings (OSTI)

In 2010, EPRI initiated a multiyear effort to identify and illustrate noteworthy practices that utilities are using to meet the service reliability expectations of their customers. EPRI research focused on four host utilities: Ameren Corporation, Central Hudson Gas & Electric Corporation, Alabama Power Company, and We Energies. In 2011, EPRI completed research at American Electric Power Company (AEP) and initiated research with Memphis Light, Gas and Water (MLGW) and Duke Energy. In 2012, EPRI ...

2012-11-14T23:59:59.000Z

254

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

Science Conference Proceedings (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

255

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

SciTech Connect

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

256

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

SciTech Connect

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

257

Light-water-reactor coupled neutronic and thermal-hydraulic codes  

Science Conference Proceedings (OSTI)

An overview is presented of computer codes that model light water reactor cores with coupled neutronics and thermal-hydraulics. This includes codes for transient analysis and codes for steady state analysis which include fuel depletion and fission product buildup. Applications in nuclear design, reactor operations and safety analysis are given and the major codes in use in the USA are identified. The neutronic and thermal-hydraulic methodologies and other code features are outlined for three steady state codes (PDQ7, NODE-P/B and SIMULATE) and four dynamic codes (BNL-TWIGL, MEKIN, RAMONA-3B, RETRAN-02). Speculation as to future trends with such codes is also presented.

Diamond, D.J.

1982-01-01T23:59:59.000Z

258

Core Designs and Economic Analyses of Homogeneous Thoria-Urania Fuel in Light Water Reactors  

SciTech Connect

The objective is to develop equilibrium fuel cycle designs for a typical pressurized water reactor (PWR) loaded with homogeneously mixed uranium-thorium dioxide (ThO{sub 2}-UO{sub 2}) fuel and compare those designs with more conventional UO{sub 2} designs.The fuel cycle analyses indicate that ThO{sub 2}-UO{sub 2} fuel cycles are technically feasible in modern PWRs. Both power peaking and soluble boron concentrations tend to be lower than in conventional UO{sub 2} fuel cycles, and the burnable poison requirements are less.However, the additional costs associated with the use of homogeneous ThO{sub 2}-UO{sub 2} fuel in a PWR are significant, and extrapolation of the results gives no indication that further increases in burnup will make thoria-urania fuel economically competitive with the current UO{sub 2} fuel used in light water reactors.

Saglam, Mehmet; Sapyta, Joe J.; Spetz, Stewart W.; Hassler, Lawrence A. [Framatome ANP, Inc. (France)

2004-07-15T23:59:59.000Z

259

Irradiation behavior of High-Burnup LWR-MOX (mixed-oxide) Fuels  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, 2014 TMS Annual Meeting & Exhibition. Symposium , Radiation Effects in Oxide Ceramics and Novel LWR Fuels. Presentation Title...

260

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

Science Conference Proceedings (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 11 of the ASME Code. This is a progress report covering the programmatic work from October 1989 through September 1990.

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))

1992-05-01T23:59:59.000Z

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

Commercial Light Water Reactor -Tritium Extraction Facility Process Waste Assessment (Project S-6091)  

Science Conference Proceedings (OSTI)

The Savannah River Site (SRS) has been tasked by the Department of Energy (DOE) to design and construct a Tritium Extraction Facility (TEF) to process irradiated tritium producing burnable absorber rods (TPBARs) from a Commercial Light Water Reactor (CLWR). The plan is for the CLWR-TEF to provide tritium to the SRS Replacement Tritium Facility (RTF) in Building 233-H in support of DOE requirements. The CLWR-TEF is being designed to provide 3 kg of new tritium per year, from TPBARS and other sources of tritium (Ref. 1-4).The CLWR TPBAR concept is being developed by Pacific Northwest National Laboratory (PNNL). The TPBAR assemblies will be irradiated in a Commercial Utility light water nuclear reactor and transported to the SRS for tritium extraction and processing at the CLWR-TEF. A Conceptual Design Report for the CLWR-TEF Project was issued in July 1997 (Ref. 4).The scope of this Process Waste Assessment (PWA) will be limited to CLWR-TEF processing of CLWR irradiated TPBARs. Although the CLWR- TEF will also be designed to extract APT tritium-containing materials, they will be excluded at this time to facilitate timely development of this PWA. As with any process, CLWR-TEF waste stream characteristics will depend on process feedstock and contaminant sources. If irradiated APT tritium-containing materials are to be processed in the CLWR-TEF, this PWA should be revised to reflect the introduction of this contaminant source term.

Hsu, R.H.; Delley, A.O.; Alexander, G.J.; Clark, E.A.; Holder, J.S.; Lutz, R.N.; Malstrom, R.A.; Nobles, B.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Carson, S.D. [Sandia National Laboratories, New Mexico, NM (United States); Peterson, P.K. [Sandia National Laboratories, New Mexico, NM (United States)

1997-11-30T23:59:59.000Z

262

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

Science Conference Proceedings (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

263

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

SciTech Connect

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

264

Ice Thermal Storage Systems for LWR Supplemental Cooling and Peak Power Shifting  

SciTech Connect

Availability of enough cooling water has been one of the major issues for the nuclear power plant site selection. Cooling water issues have frequently disrupted the normal operation at some nuclear power plants during heat waves and long draught. The issues become more severe due to the new round of nuclear power expansion and global warming. During hot summer days, cooling water leaving a power plant may become too hot to threaten aquatic life so that environmental regulations may force the plant to reduce power output or even temporarily to be shutdown. For new nuclear power plants to be built at areas without enough cooling water, dry cooling can be used to remove waste heat directly into the atmosphere. However, dry cooling will result in much lower thermal efficiency when the weather is hot. One potential solution for the above mentioned issues is to use ice thermal storage systems (ITS) that reduce cooling water requirements and boost the plants thermal efficiency in hot hours. ITS uses cheap off-peak electricity to make ice and uses those ice for supplemental cooling during peak demand time. ITS is suitable for supplemental cooling storage due to its very high energy storage density. ITS also provides a way to shift large amount of electricity from off peak time to peak time. Some gas turbine plants already use ITS to increase thermal efficiency during peak hours in summer. ITSs have also been widely used for building cooling to save energy cost. Among three cooling methods for LWR applications: once-through, wet cooling tower, and dry cooling tower, once-through cooling plants near a large water body like an ocean or a large lake and wet cooling plants can maintain the designed turbine backpressure (or condensation temperature) during 99% of the time; therefore, adding ITS to those plants will not generate large benefits. For once-through cooling plants near a limited water body like a river or a small lake, adding ITS can bring significant economic benefits and avoid forced derating and shutdown during extremely hot weather. For the new plants using dry cooling towers, adding the ice thermal storage systems can effectively reduce the efficiency loss and water consumption during hot weather so that new LWRs could be considered in regions without enough cooling water. \\ This paper presents the feasibility study of using ice thermal storage systems for LWR supplemental cooling and peak power shifting. LWR cooling issues and ITS application status will be reviewed. Two ITS application case studies will be presented and compared with alternative options: one for once-through cooling without enough cooling for short time, and the other with dry cooling. Because capital cost, especially the ice storage structure/building cost, is the major cost for ITS, two different cost estimation models are developed: one based on scaling method, and the other based on a preliminary design using Building Information Modeling (BIM), an emerging technology in Architecture/Engineering/Construction, which enables design options, performance analysis and cost estimating in the early design stage.

Haihua Zhao; Hongbin Zhang; Phil Sharpe; Blaise Hamanaka; Wei Yan; WoonSeong Jeong

2010-06-01T23:59:59.000Z

265

Thermal-Hydraulic Modeling of the Primary Coolant System of Light Water Reactors During Severely Degraded Core Accidents  

Science Conference Proceedings (OSTI)

The transport of fission-product vapors and aerosols that would be released from an LWR primary system in postulated severe accidents depends on the prevalent thermal-hydraulic conditions. The analytic models developed in this study are incorporated in the PSAAC modular computer program, which can help predict more realistic estimates of accident consequences.

1984-07-01T23:59:59.000Z

266

Passive and inherent safety technologies for light-water nuclear reactors  

SciTech Connect

Passive/inherent safety implies a technical revolution in our approach to nuclear power safety. This direction is discussed herein for light-water reactors (LWRs) -- the predominant type of power reactor used in the world today. At Oak Ridge National Laboratory (ORNL) the approach to the development of passive/inherent safety for LWRs consists of four steps: identify and quantify safety requirements and goals; identify and quantify the technical functional requirements needed for safety; identify, invent, develop, and quantify technical options that meet both of the above requirements; and integrate safety systems into designs of economic and reliable nuclear power plants. Significant progress has been achieved in the first three steps of this program. The last step involves primarily the reactor vendors. These activities, as well as related activities worldwide, are described here. 27 refs., 7 tabs.

Forsberg, C.W.

1990-07-01T23:59:59.000Z

267

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

SciTech Connect

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

268

Advanced reactor design study. Assessing nonbackfittable concepts for improving uranium utilization in light water reactors  

Science Conference Proceedings (OSTI)

The objective of the Advanced Reactor Design Study (ARDS) is to identify and evaluate nonbackfittable concepts for improving uranium utilization in light water reactors (LWRs). The results of this study provide a basis for selecting and demonstrating specific nonbackfittable concepts that have good potential for implementation. Lead responsibility for managing the study was assigned to the Pacific Northwest Laboratory (PNL). Nonbackfittable concepts for improving uranium utilization in LWRs on the once-through fuel cycle were selected separately for PWRs and BWRs due to basic differences in the way specific concepts apply to those plants. Nonbackfittable concepts are those that are too costly to incorporate in existing plants, and thus, could only be economically incorporated in new reactor designs or plants in very early stages of construction. Essential results of the Advanced Reactor Design Study are summarized.

Fleischman, R.M.; Goldsmith, S.; Newman, D.F.; Trapp, T.J.; Spinrad, B.I.

1981-09-01T23:59:59.000Z

269

Development of dual phase magnesia-zirconia ceramics for light water reactor inert matrix fuel  

E-Print Network (OSTI)

Dual phase magnesia-zirconia ceramics were developed, characterized, and evaluated as a potential matrix material for use in light water reactor inert matrix fuel intended for the disposition of plutonium and minor actinides. Ceramics were fabricated from the oxide mixture using conventional pressing and sintering techniques. Characterization of the final product was performed using optical microscopy, scanning electron microscopy, x-ray diffraction analysis, and energy-dispersive x-ray analysis. The final product was found to consist of two phases: cubic zirconia-based solid solution and cubic magnesia. Evaluation of key feasibility issues was limited to investigation of long-term stability in hydrothermal conditions and assessment of the thermal conductivity. With respect to hydrothermal stability, it was determined that limited degradation of these ceramics at 300^oC occurred due to the hydration of the magnesia phase. Normalized mass loss rate, used as a quantitative indicator of degradation, was found to decrease exponentially with the zirconia content in the ceramics. The normalized mass loss rates measured in static 300^oC de-ionized water for the magnesia-zirconia ceramics containing 40, 50, 60, and 70 weight percent of zirconia are 0.00688, 0.00256, 0.000595, 0.000131 g/cm2/hr respectively. Presence of boron in the water had a dramatic positive effect on the hydration resistance. At 300^oC the normalized mass loss rates for the composition containing 50 weight percent of zirconia was 0.00005667 g/cm2/hr in the 13000 ppm aqueous solution of the boric acid. With respect to thermal conductivity, the final product exhibits values of 5.5-9.5 W/(m deg) at 500^oC, and 4-6 W/(m deg) at 1200^oC depending on the composition. This claim is based on the assessment of thermal conductivity derived from thermal diffusivity measured by laser flash method in the temperature range from 200 to 1200^oC, measured density, and heat capacity calculated using rule of mixtures. Analytical estimates of the anticipated maximum temperature during normal reactor operation in a hypothetical inert matrix fuel rod based on the magnesia-zirconia ceramics yielded the values well below the melting temperature and well below current maximum temperatures authorized in light water reactors.

Medvedev, Pavel

2004-12-01T23:59:59.000Z

270

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

Science Conference Proceedings (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

271

Advanced LWR Nuclear Fuel Cladding System Development Trade-off Study |  

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

LWR Nuclear Fuel Cladding System Development Trade-off LWR Nuclear Fuel Cladding System Development Trade-off Study Advanced LWR Nuclear Fuel Cladding System Development Trade-off Study The LWR Sustainability (LWRS) Program activities must support the timeline dictated by utility life extension decisions to demonstrate a lead test rod in a commercial reactor within 10 years. In order to maintain the demanding development schedule that must accompany this aggressive timeline, the LWRS Program focuses on advanced fuel cladding systems that retain standard UO2 fuel pellets for deployment in currently operating LWR power plants. The LWRS work scope focuses on fuel system components outside of the fuel pellet, allowing for alteration of the existing zirconium-based clad system through coatings, addition of ceramic sleeves, or complete replacement

272

Evolution of isotopic composition of reprocessed uranium during the multiple recycling in light water reactors with natural uranium feed  

Science Conference Proceedings (OSTI)

A complex approach based on the consistent modeling of neutron-physics processes and processes of cascade separation of isotopes is applied for analyzing physical problems of the multiple usage of reprocessed uranium in the fuel cycle of light water reactors. A number of scenarios of multiple recycling of reprocessed uranium in light water reactors are considered. In the process, an excess absorption of neutrons by the {sup 236}U isotope is compensated by re-enrichment in the {sup 235}U isotope. Specific consumptions of natural uranium for re-enrichment of the reprocessed uranium depending on the content of the {sup 232}U isotope are obtained.

Smirnov, A. Yu., E-mail: a.y.smirnoff@rambler.ru; Sulaberidze, G. A. [National Research Nuclear University MEPhI (Russian Federation); Alekseev, P. N.; Dudnikov, A. A.; Nevinitsa, V. A., E-mail: neva@dhtp.kiae.ru; Proselkov, V. N.; Chibinyaev, A. V. [Russian Research Centre Kurchatov Institute (Russian Federation)

2012-12-15T23:59:59.000Z

273

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

SciTech Connect

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

NONE

1996-09-01T23:59:59.000Z

274

Determination of Light Water Reactor Fuel Burnup with the Isotope Ratio Method  

Science Conference Proceedings (OSTI)

For the current project to demonstrate that isotope ratio measurements can be extended to zirconium alloys used in LWR fuel assemblies we report new analyses on irradiated samples obtained from a reactor. Zirconium alloys are used for structural elements of fuel assemblies and for the fuel element cladding. This report covers new measurements done on irradiated and unirradiated zirconium alloys, Unirradiated zircaloy samples serve as reference samples and indicate starting values or natural values for the Ti isotope ratio measured. New measurements of irradiated samples include results for 3 samples provided by AREVA. New results indicate: 1. Titanium isotope ratios were measured again in unirradiated samples to obtain reference or starting values at the same time irradiated samples were analyzed. In particular, 49Ti/48Ti ratios were indistinguishably close to values determined several months earlier and to expected natural values. 2. 49Ti/48Ti ratios were measured in 3 irradiated samples thus far, and demonstrate marked departures from natural or initial ratios, well beyond analytical uncertainty, and the ratios vary with reported fluence values. The irradiated samples appear to have significant surface contamination or radiation damage which required more time for SIMS analyses. 3. Other activated impurity elements still limit the sample size for SIMS analysis of irradiated samples. The sub-samples chosen for SIMS analysis, although smaller than optimal, were still analyzed successfully without violating the conditions of the applicable Radiological Work Permit

Gerlach, David C.; Mitchell, Mark R.; Reid, Bruce D.; Gesh, Christopher J.; Hurley, David E.

2007-11-01T23:59:59.000Z

275

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

276

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

277

Compendium of information on hydrogen behavior during LWR accidents  

DOE Green Energy (OSTI)

A manual has been written which attempts to present, in a simple and understandable way, information concerning the generation, transport, detection and combustion of hydrogen which might occur during serious accidents in light water reactors. More than a thousand documents were surveyed over a three month period. Of these, several hundred documents were extensively reviewed. The manual summarizes the results of this review. The manual is divided into four major sections covering hydrogen generation, detection, combustion, and existing schemes for mitigating the effects of combustion.

Berman, M.

1980-01-01T23:59:59.000Z

278

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

SciTech Connect

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

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

1996-10-07T23:59:59.000Z

279

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

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

280

Plutonium Recycling in Light Water Reactors at Framatome ANP: Status and Trends  

SciTech Connect

The civil and military utilization of nuclear power results in continuously increasing stockpiles of spent fuel and separated plutonium. Since fast breeder reactors are at present not available, the majority of spent fuel discharged from commercial nuclear reactors is intended for direct final disposal or designated for interim storage. An effective form of intermediate plutonium storage is recycling in thermal reactors. Recycling of the recovered plutonium in commercial light water reactors (LWRs) is currently practiced in Belgium, France, Germany, and Switzerland. The number of mixed-oxide (MOX) assemblies reloaded each year in a large variety of reactors demonstrates that plutonium recycling in LWRs has reached industrial maturity. The status of experience gained today at Framatome ANP confirms the reliability of the design codes and the suitability of fuel assembly and core designs. The validation database for increasing exposures of MOX fuel is being continuously expanded. This provides the basis for further extending the discharge exposures of MOX assemblies and for licensing the use of higher plutonium concentrations. Options to support the weapons plutonium reduction programs and for the development of advanced MOX assembly designs are investigated.

Porsch, Dieter [Framatome ANP GmbH (France); Stach, Walter [Framatome ANP GmbH (France); Charmensat, Pascal [Framatome ANP S.A.S. (France); Pasquet, Michel [Framatome ANP S.A.S. (France)

2005-08-15T23:59:59.000Z

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

Pyrochemical recovery of actinide elements from spent light water reactor fuel  

Science Conference Proceedings (OSTI)

Argonne National Laboratory is investigating salt transport and lithium pyrochemical processes for recovery of transuranic (TRU) elements from spent light water reactor fuel. The two processes are designed to recover the TRU elements in a form compatible with the Integral Fast Reactor (IFR) fuel cycle. The IFR is uniquely effective in consuming these long-lived TRU elements. The salt transport process uses calcium dissolved in Cu-35 wt % Mg in the presence of a CaCl{sub 2} salt to reduce the oxide fuel. The reduced TRU elements are separated from uranium and most of the fission products by using a MgCl{sub 2} transport salt. The lithium process, which does not employ a solvent metal, uses lithium in the presence of a LiCl salt as the reductant. After separation from the salt, the reduced metal is introduced into an electrorefiner, which separates the TRU elements from the uranium and fission products. In both processes, reductant and reduction salt are recovered by electrochemical decomposition of the oxide reaction product.

Johnson, G.K.; Pierce, R.D.; Poa, D.S.; McPheeters, C.C.

1994-01-01T23:59:59.000Z

282

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

Science Conference Proceedings (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

283

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

SciTech Connect

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

284

Characteristics Data Base: Programmer's guide to the LWR Quantities Data Base  

SciTech Connect

The LWR Quantities Data Base is a menu-driven PC data base developed as part of OCRWM's waste, technical data base on the characteristics of potential repository wastes, which also includes non-LWR spent fuel, high-level and other materials. This programmer's guide completes the documentation for the LWR Quantities Data Base, the user's guide having been published previously. The PC data base itself may be requested from the Oak Ridge National Laboratory, using the order form provided in Volume 1 of publication DOE/RW-0184.

Jones, K.E. (DataPhile, Inc., Knoxville, TN (USA)); Moore, R.S. (Automated Sciences Group, Inc., Oak Ridge, TN (USA))

1990-08-01T23:59:59.000Z

285

Nuclear Fuel Cycle Cost Comparison Between Once-Through and Plutonium Single-Recycling in Pressurized Water Reactors  

Science Conference Proceedings (OSTI)

Within the context of long-term waste management and sustainable nuclear fuel supply, there continue to be discussions regarding whether the United States should consider recycling of light-water reactor (LWR) spent nuclear fuel (SNF) for the current fleet of U.S. LWRs. This report presents a parametric study of equilibrium fuel cycle costs for an open fuel cycle without plutonium recycling (once-through) and with plutonium recycling (single-recycling using mixed-oxide, or MOX, fuel), assuming an all-pre...

2009-02-25T23:59:59.000Z

286

Grating light reflection spectroelectrochemistry for detection of trace amounts of aromatic hydrocarbons in water  

SciTech Connect

Grating light reflection spectroscopy (GLRS) is an emerging technique for spectroscopic analysis and sensing. A transmission diffraction grating is placed in contact with the sample to be analyzed, and an incident light beam is directed onto the grating. At certain angles of incidence, some of the diffracted orders are transformed from traveling waves to evanescent waves. This occurs at a specific wavelength that is a function of the grating period and the complex index of refraction of the sample. The intensities of diffracted orders are also dependent on the sample's complex index of refraction. The authors describe the use of GLRS, in combination with electrochemical modulation of the grating, for the detection of trace amounts of aromatic hydrocarbons. The diffraction grating consisted of chromium lines on a fused silica substrate. The depth of the grating lines was 1 {micro}m, the grating period was 1 {micro}m, and the duty cycle was 50%. Since chromium was not suitable for electrochemical modulation of the analyte concentration, a 200 nm gold layer was deposited over the entire grating. This gold layer slightly degraded the transmission of the grating, but provided satisfactory optical transparency for the spectroelectrochemical experiments. The grating was configured as the working electrode in an electrochemical cell containing water plus trace amounts of the aromatic hydrocarbon analytes. The grating was then electrochemically modulated via cyclic voltammetry waveforms, and the normalized intensity of the zero order reflection was simultaneously measured. The authors discuss the lower limits of detection (LLD) for two analytes, 7-dimethylamino-1,2-benzophenoxazine (Meldola's Blue dye) and 2,4,6-trinitrotoluene (TNT), probed with an incident HeNe laser beam ({lambda} = 543.5 nm) at an incident angle of 52.5{degree}. The LLD for 7-dimethylamino-1,2-benzophenoxazine is approximately 50 parts per billion (ppb), while the LLD for TNT is approximately 50 parts per million (ppm). The possible factors contributing to the differences in LLD for these analytes are discussed. This is the final report for a Sandia National Laboratories Laboratory Directed Research and Development (LDRD) project conducted during fiscal years 1998 and 1999 (case number 3518.190).

KELLY,MICHAEL J.; SWEATT,WILLIAM C.; KEMME,SHANALYN A.; KASUNIC,K.J.; BLAIR,DIANNA S.; ZAIDI,S.H.; MCNEIL,J.R.; BURGESS,L.W.; BRODSKY,A.M.; SMITH,S.A.

2000-04-01T23:59:59.000Z

287

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

SciTech Connect

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

288

Light Water Reactor Sustainability Research and Development Program Plan -- Fiscal Year 2009201/span>3  

Science Conference Proceedings (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

289

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

Science Conference Proceedings (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

290

Final Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor  

DOE Green Energy (OSTI)

The U.S. Department of Energy (DOE) is responsible for providing the nation with nuclear weapons and ensuring that these weapons remain safe and reliable. Tritium, a radioactive isotope of hydrogen, is an essential component of every weapon in the current and projected U.S. nuclear weapons stockpile. Unlike other materials utilized in nuclear weapons, tritium decays at a rate of 5.5 percent per year. Accordingly, as long as the nation relies on a nuclear deterrent, the tritium in each nuclear weapon must be replenished periodically. Currently the U.S. nuclear weapons complex does not have the capability to produce the amounts of tritium that will be required to continue supporting the nation's stockpile. The ''Final Programmatic Environmental Impact Statement for Tritium Supply and Recycling'' (Final Programmatic EIS), DOE/EIS-0161, issued in October 1995, evaluated the alternatives for the siting, construction, and operation of tritium supply and recycling facilities at five DOE sites for four different production technologies. This Programmatic EIS also evaluated the impacts of using a commercial light water reactor (CLWR) without specifying a reactor location. In the Record of Decision for the Final Programmatic EIS (60 FR 63878), issued December 12, 1995, DOE decided to pursue a dual-track approach on the two most promising tritium supply alternatives: (1) to initiate purchase of an existing commercial reactor (operating or partially complete) or reactor irradiation services; and (2) to design, build, and test critical components of an accelerator system for tritium production. At that time, DOE announced that the final decision would be made by the Secretary of Energy at the end of 1998.

N /A

1999-03-12T23:59:59.000Z

291

Advanced methods development for LWR trsansient analysis, final report : 1981-1982  

E-Print Network (OSTI)

The initial development of TITAN, a three-dimensional coupled neutronics/thermal-hydraulics code for LWR safety analysis, has been completed. The transient neutronics code QUANDRY has been joined to the two-fluid ...

Griggs, D. P.

1982-01-01T23:59:59.000Z

292

Radionuclide characterization at US commercial light-water reactors for decommissioning assessment: Distributions, inventories, and waste disposal considerations  

SciTech Connect

A continuing research program, conducted by Pacific Northwest Laboratory for the US Nuclear Regulatory Commission, characterizing radionuclide concentrations associated with US light-water reactors has been conducted for more than a decade. The research initially focused upon sampling and analytical measurements for the purpose of establishing radionuclide distributions and inventories for decommissioning assessment, since very little empirical data existed. The initial phase of the research program examined radionuclide concentrations and distributions external to the reactor vessel at seven US light water reactors. Later stages of the research program have examined the radionuclide distributions in the highly radioactive reactor internals and fuel assembly. Most recently, the research program is determining radionuclide concentrations in these highly radioactive components and comparing empirical results with those derived from the several nonempirical methodologies employed to estimate radionuclide inventories for disposal classification. The results of the research program to date are summarized, and their implications and significance for the decommissioning process are noted.

Abel, K.H.; Robertson, D.E.; Thomas, C.W.

1992-09-01T23:59:59.000Z

293

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

SciTech Connect

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

294

Program on Technology Innovation: Weld Metals and Welding Processes for Fabrication of Advanced Light Water Reactor Pressure Vessels  

Science Conference Proceedings (OSTI)

Light water reactors have traditionally been constructed using roll-formed plates for the reactor pressure vessel (RPV) shells, which were assembled via horizontal and vertical seam welds. Weld filler metals often contained significant quantities of copper, other residual elements such as vanadium, and nonmetallic elements such as phosphorous and sulfur. Low-alloy steel weld filler metals of this chemical composition contributed to the degree of neutron radiation-induced embrittlement of vessel ...

2013-06-26T23:59:59.000Z

295

Light Water Reactor Sustainability Program Grizzly Year-End Progress Report  

SciTech Connect

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

296

Light-induced water oxidation at silicon electrodes functionalized with a cobalt oxygen-evolving catalyst  

E-Print Network (OSTI)

Integrating a silicon solar cell with a recently developed cobalt-based water-splitting catalyst (Co-Pi) yields a robust, monolithic, photo-assisted anode for the solar fuels process of water splitting to O2 at neutral pH. ...

Pijpers, Joep J. H.

297

Assessment of Dancoff adjusted Wigner-Seitz cells for self-shielding LWR lattices  

E-Print Network (OSTI)

The objective of this thesis was to assess the effectiveness of using a Wigner-Seitz (WS) cell with an adjusted moderator thickness to produce more accurate resonance self-shielded cross sections for light water reactor ...

Roomy, Thomas Hayward

2012-01-01T23:59:59.000Z

298

Compatibility of the ultraviolet light-ozone system for laundry waste water treatment in nuclear power plants  

SciTech Connect

As an alternative treatment system for laundry waste water in nuclear power plants, a system was chosen in which such organic compounds as surfactant would be oxidized by ultraviolet (UV) light and ozone. The system compatibility, UV light source, and dissolved ozone concentration were examined through experiments. First, ozone gas was absorbed in the waste water. After the dissolved ozone concentration equilibrated at the desired value, the waste water was irradiated by a mercury lamp. Then, the time dependence of the concentrations of the organic compounds, the dissolved ozone, and the hydrogen peroxide were measured to estimate the treatment rate of the system. The mercury lamp with a 10{sup 5}-Pa vapor pressure achieved large UV radiation and a treatment rate increase, leading to a compatible system without secondary waste generation. The effect of the dissolved ozone concentration on the treatment rate was saturated when concentration was >3.3 {times} 10{sup {minus}4} mol/10{sup {minus}3} m{sup 3} at the time UV radiation was started. Numerical results indicated the saturation was due to hydrogen peroxide generation, which prevents hydroxyl radical generation.

Matsuo, Toshiaki; Nishi, Takashi; Matsuda, Masami; Izumida, Tatsuo [Hitachi, Ltd. (Japan)

1997-08-01T23:59:59.000Z

299

CORRELATION OF CRITICAL MASS DATA ON LIGHT WATER MODERATED, FULLY ENRICHED URANIUM, STAINLESS STEEL REACTORS. PART I  

SciTech Connect

Experimental data were collected on over 70 light water moderated, fully enriched uranium, stainless steel, critical cores. An equation for the critical mass of cores with a buckling of 0.007 cm/sup -2/ that is lineally dependent on stainless steel volume fraction and grams of B/sup 10/ was compared with available critical experiments and found to yield reasonable results. A correlation method, relating buckling to ( xi SIGMA /sub s// SIGMA /sub a/) was found to fit the available experiments. (auth)

Lee, D.H.

1962-07-17T23:59:59.000Z

300

Solar energy as an alternate energy source to mixed oxide fuels in light-water cooled reactors  

DOE Green Energy (OSTI)

Supplemental information pertaining to the generic environmental impact statement on the Pu recycling process for mixed oxide light-water cooled reactors (GESMO) was requested from several sources. In particular, the role of alternate sources of energy was to be explored and the implications of these alternate sources to the question of Pu recycle in LWRs were to be investigated. In this vein, solar energy as an alternate source is the main subject of this report, along with other information related to solar energy. The general conclusion is that solar energy should have little effect on the decisions concerning GESMO.

Bertini, H.W.

1977-06-30T23:59:59.000Z

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

Light Reflection from Water Waves: Suitable Setup for a Polarimetric Investigation under Controlled Laboratory Conditions  

Science Conference Proceedings (OSTI)

The reflection of sunlight from a wavy water surface, often referred to as sun glint, is a well-known phenomenon that presents challenges but also hitherto untapped opportunities in remote sensing based on satellite imagery. Despite being ...

Matteo Ottaviani; Knut Stamnes; Jeff Koskulics; Hans Eide; Steven R. Long; Wenying Su; Warren Wiscombe

2008-05-01T23:59:59.000Z

302

Simulation of Laser-Induced Light Emissions from Water and Extraction of Raman Signal  

Science Conference Proceedings (OSTI)

A simulation of the laser-induced Raman and fluorescence spectra produced by laser irradiation of the water column is described as well as a method of extracting the Raman signal from the fluorescence spectra using multiple laser excitation ...

Jeffrey E. James; Chung San Lin; William P. Hooper

1999-03-01T23:59:59.000Z

303

Water-Mass Transformations in a Neutral Density Framework and the Key Role of Light Penetration  

Science Conference Proceedings (OSTI)

A new formulation is proposed for the evaluation of the dianeutral transport in the ocean. The method represents an extension of the classical diagnostic approach for estimating the water-mass formation from the buoyancy balance. The inclusion of ...

Daniele Iudicone; Gurvan Madec; Trevor J. McDougall

2008-07-01T23:59:59.000Z

304

Survey of LWR environmental control technology performance and cost  

Science Conference Proceedings (OSTI)

This study attempts to establish a ranking for species that are routinely released to the environment for a projected nuclear power growth scenario. Unlike comparisons made to existing standards, which are subject to frequent revision, the ranking of releases can be used to form a more logical basis for identifying the areas where further development of control technology could be required. This report describes projections of releases for several fuel cycle scenarios, identifies areas where alternative control technologies may be implemented, and discusses the available alternative control technologies. The release factors were used in a computer code system called ENFORM, which calculates the annual release of any species from any part of the LWR nuclear fuel cycle given a projection of installed nuclear generation capacity. This survey of fuel cycle releases was performed for three reprocessing scenarios (stowaway, reprocessing without recycle of Pu and reprocessing with full recycle of U and Pu) for a 100-year period beginning in 1977. The radioactivity releases were ranked on the basis of a relative ranking factor. The relative ranking factor is based on the 100-year summation of the 50-year population dose commitment from an annual release of radioactive effluents. The nonradioactive releases were ranked on the basis of dilution factor. The twenty highest ranking radioactive releases were identified and each of these was analyzed in terms of the basis for calculating the release and a description of the currently employed control method. Alternative control technology is then discussed, along with the available capital and operating cost figures for alternative control methods.

Heeb, C.M.; Aaberg, R.L.; Cole, B.M.; Engel, R.L.; Kennedy, W.E. Jr.; Lewallen, M.A.

1980-03-01T23:59:59.000Z

305

Energy Basics: Lighting and Daylighting  

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

Lighting Daylighting Passive Solar Design Space Heating & Cooling Water Heating Lighting and Daylighting Buildings can be lit in two ways: by using artificial lighting, or by...

306

Nondestructive examination (NDE) reliability for inservice inspection of light water reactors. Annual report, October 1989--September 1990: Volume 12  

Science Conference Proceedings (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 11 of the ASME Code. This is a progress report covering the programmatic work from October 1989 through September 1990.

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)

1992-05-01T23:59:59.000Z

307

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)

LOGA LOFT LWR MWe MWt NRC PWR RSR (systems) - EnvironmentalABC been difficult (now NRC) licensing procedure havethe "Acceptance The criteria go (NRC) licensing procedure.

Nero, A.V.

2010-01-01T23:59:59.000Z

308

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

SciTech Connect

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

309

ASSESSMENT OF POSSIBLE CYCLE LENGTHS FOR FULLY-CERAMIC MICRO-ENCAPSULATED FUEL-BASED LIGHT WATER REACTOR CONCEPTS  

Science Conference Proceedings (OSTI)

The use of TRISO-particle-based dispersion fuel within SiC matrix and cladding materials has the potential to allow the design of extremely safe LWRs with failure-proof fuel. This paper examines the feasibility of LWR-like cycle length for such a low enriched uranium fuel with the imposed constraint of strictly retaining the original geometry of the fuel pins and assemblies. The motivation for retaining the original geometry is to provide the ability to incorporate the fuel 'as-is' into existing LWRs while retaining their thermal-hydraulic characteristics. The feasibility of using this fuel is assessed by looking at cycle lengths and fuel failure rates. Other considerations (e.g., safety parameters, etc.) were not considered at this stage of the study. The study includes the examination of different TRISO kernel diameters without changing the coating layer thicknesses. The study shows that a naive use of UO{sub 2} results in cycle lengths too short to be practical for existing LWR designs and operational demands. Increasing fissile inventory within the fuel compacts shows that acceptable cycle lengths can be achieved. In this study, starting with the recognized highest packing fraction practically achievable (44%), higher enrichment, larger fuel kernel sizes, and the use of higher density fuels have been evaluated. The models demonstrate cycle lengths comparable to those of ordinary LWRs. As expected, TRISO particles with extremely large kernels are shown to fail under all considered scenarios. In contrast, the designs that do not depart too drastically from those of the nominal NGNP HTR fuel TRISO particles are shown to perform satisfactorily and display a high rates of survival under all considered scenarios. Finally, it is recognized that relaxing the geometry constraint will result in satisfactory cycle lengths even using UO{sub 2}-loaded TRISO particles-based fuel with enrichment at or below 20 w/o.

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

2012-04-01T23:59:59.000Z

310

Assessment of possible cycle lengths for fully-ceramic micro-encapsulated fuel-based light water reactor concepts  

Science Conference Proceedings (OSTI)

The use of TRISO-particle-based dispersion fuel within SiC matrix and cladding materials has the potential to allow the design of extremely safe LWRs with accident-tolerant fuel. This paper examines the feasibility of LWR-like cycle length for such a low enriched uranium fuel with the imposed constraint of strictly retaining the original geometry of the fuel pins and assemblies. The motivation for retaining the original geometry is to provide the ability to incorporate the fuel 'as-is' into existing LWRs while retaining their thermal-hydraulic characteristics. The feasibility of using this fuel is assessed by looking at cycle lengths and fuel failure rates. Other considerations (e.g., safety parameters, etc.) were not considered at this stage of the study. The study includes the examination of different TRISO kernel diameters without changing the coating layer thicknesses. The study shows that a naive use of UO{sub 2} results in cycle lengths too short to be practical for existing LWR designs and operational demands. Increasing fissile inventory within the fuel compacts shows that acceptable cycle lengths can be achieved. In this study, starting with the recognized highest packing fraction practically achievable (44%), higher enrichment, larger fuel kernel sizes, and the use of higher density fuels have been evaluated. The models demonstrate cycle lengths comparable to those of ordinary LWRs. As expected, TRISO particles with extremely large kernels are shown to fail under all considered scenarios. In contrast, the designs that do not depart too drastically from those of the nominal NGNP HTR fuel TRISO particles are shown to perform satisfactorily and display a high rate of survival under all considered scenarios. Finally, it is recognized that relaxing the geometry constraint will result in satisfactory cycle lengths even using UO{sub 2}-loaded TRISO particles-based fuel with enrichment at or below 20 w/o. (authors)

Sen, R. S.; Pope, M. A.; Ougouag, A. M.; Pasamehmetoglu, K. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3840 (United States); Venneri, F. [UltraSafe Nuclear (United States)

2012-07-01T23:59:59.000Z

311

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

Science Conference Proceedings (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

312

Effect of Light Water Reactor Environments on Fracture Resistance in Irradiated Stainless Steel  

Science Conference Proceedings (OSTI)

Austenitic stainless steels are used extensively for the fabrication of reactor internal components due to their high strength and fracture toughness. However, the fracture properties of these materials degrade with exposure to neutron irradiation. The effects on the reduction of fracture properties may depend on neutron fluence, cold work, corrosion potential, water purity, temperature, and loading. The exact role of these environmental parameters remains unclear.Fracture toughness ...

2012-09-20T23:59:59.000Z

313

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

SciTech Connect

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

314

Program on Technology Innovation: Prediction and Evaluation of Environmentally Assisted Cracking in LWR Structural Materials  

Science Conference Proceedings (OSTI)

This report describes the interim results of Phase III of a joint research program sponsored by EPRI in collaboration with the Fracture Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations to address environmentally assisted cracking (EAC) of LWR structural materials.

2005-11-30T23:59:59.000Z

315

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

SciTech Connect

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

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

1996-09-01T23:59:59.000Z

316

Air quality impacts due to construction of LWR waste management facilities  

SciTech Connect

Air quality impacts of construction activities and induced housing growth as a result of construction activities were evaluated for four possible facilities in the LWR fuel cycle: a fuel reprocessing facility, fuel storage facility, fuel fabrication plant, and a nuclear power plant. Since the fuel reprocessing facility would require the largest labor force, the impacts of construction of that facility were evaluated in detail.

1977-06-01T23:59:59.000Z

317

EIS-0288; Final Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor  

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

iii iii COVER SHEET Responsible Agency: United States Department of Energy Cooperating Agency: Tennessee Valley Authority Title: Final Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor Contact: For additional information on this Final Environmental Impact Statement, write or call: Jay Rose Office of Defense Programs U.S. Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 Attention: CLWR EIS Telephone: (202) 586-5484 For copies of the CLWR Final EIS call: 1-800-332-0801 | For general information on the DOE National Environmental Policy Act (NEPA) process, write or call: Carol M. Borgstrom, Director Office of NEPA Policy and Assistance (EH-42) U.S. Department of Energy 1000 Independence Avenue, SW Washington, DC 20585

318

Progress in understanding of direct containment heating phenomena in pressurized light water reactors  

DOE Green Energy (OSTI)

Progress is described in development of a mechanistic understanding of direct containment heating phemonena arising during high-pressure melt ejection accidents in pressurized water reactor systems. The experimental data base is discussed which forms the basis for current assessments of containment pressure response using current lumped-parameter containment analysis methods. The deficiencies in available methods and supporting data base required to describe major phenomena occurring in the reactor cavity, intermediate subcompartments and containment dome are highlighted. Code calculation results presented in the literature are cited which demonstrate that the progress in understanding of DCH phenomena has also resulted in current predictions of containment pressure loadings which are significantly lower than are predicted by idealized, thermodynamic equilibrium calculations. Current methods are, nonetheless, still predicting containment-threatening loadings for large participating melt masses under high-pressure ejection conditions. Recommendations for future research are discussed. 36 refs., 5 figs., 1 tab.

Ginsberg, T.; Tutu, N.K.

1988-01-01T23:59:59.000Z

319

Investigation of corrosion and stress corrosion cracking in bolting materials on light water reactors  

Science Conference Proceedings (OSTI)

Laboratory experiments performed at BNL have shown that the concentration of boric acid to a moist paste at approximately the boiling point of water can produce corrosion rates of the order of several tenths of an inch per year on bolting and piping materials, which values are consistent with service experience. Other failure evaluation experience has shown that primary coolant/lubricant interaction may lead to stress corrosion cracking (SCC) of steam generator manway studs. An investigation was also performed on eleven lubricants and their effects on A193 B7 and A540 B24 bolting materials. H/sub 2/S generation by the lubricants, coefficient of friction results and transgranular SCC of the bolting materials in steam are discussed. 13 refs.

Czajkowski, C.J.

1985-01-01T23:59:59.000Z

320

Advanced light water reactor plants system 80+{trademark} design certification program. Annual progress report, October 1, 1993--September 30, 1994  

SciTech Connect

The purpose of this report is to provide a status of the progress that was made towards Design Certification of System 80{sup +}{trademark} during the U.S. government`s 1994 fiscal year. The System 80+ Advanced Light Water Reactor (ALWR) is a 3931 MW (1350 MWe) Pressurized Water Reactor (PWR). The design covers an essentially complete plant. It is based on EPRI ALWR Utility Requirements Document (URD) improvements to the Standardized System 80 Nuclear Steam Supply System (NSSS) in operation at Palo Verde Units 1, 2 and 3. The NSSS is a traditional two-loop arrangement with two steam generators, two hot legs and four cold legs, each with a reactor coolant pump. The System 80+ standard design houses the NSSS in a spherical steel containment vessel which is enclosed in a concrete shield building, thus providing the safety advantages of a dual barrier to radioactivity release. Other major features include an all-digital, human-factors-engineered control room, an alternate electrical AC power source, an In-Containment Refueling Water Storage Tank (IRWST), and plant arrangements providing complete separation of redundant trains in safety systems. 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 and the System 80+ design form the basis of the Korean standardization program. The Nuclear Island portion of the System 80+ standard design has also been offered to the Republic of China, in response to their bid specification for an ALWR. The ABB-CE Standard Safety Analysis Report (CESSAR-DC) was docketed by the Nuclear Regulatory Commission (NRC) in May 1991 and a Draft Safety Evaluation Report (DSER) was issued in October 1992.

Not Available

1995-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "lwr light 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.


321

Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study  

SciTech Connect

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced RISMC toolkit that enables more accurate representation of NPP safety margin. This report describes the RISMC methodology demonstration where the Advanced Test Reactor (ATR) was used as a test-bed for purposes of determining safety margins. As part of the demonstration, we describe how both the thermal-hydraulics and probabilistic safety calculations are integrated and used to quantify margin management strategies.

Curtis Smith; David Schwieder; Cherie Phelan; Anh Bui; Paul Bayless

2012-08-01T23:59:59.000Z

322

Development of a three-dimensional two-fluid code with transient neutronic feedback for LWR applications  

E-Print Network (OSTI)

The development of a three-dimensional coupled neutronics/thermalhydraulics code for LWR safety analysis has been initiated. The transient neutronics code QUANDRY has been joined to the two-fluid thermal-hydraulics code ...

Griggs, D. P.

1981-01-01T23:59:59.000Z

323

Program on Technology Innovation: Prediction and Evaluation of Environmentally Assisted Cracking in LWR Structural Materials  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E, a Five-year extension of the joint research program sponsored by EPRI in collaboration with the Fracture Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor structural materials in PWR and BWR environments.

2008-11-24T23:59:59.000Z

324

Th/U-233 multi-recycle in pressurized water reactors : feasibility study of multiple homogeneous and heterogeneous assembly designs.  

Science Conference Proceedings (OSTI)

The use of thorium in current or advanced light water reactors (LWRs) has been of interest in recent years. These interests have been associated with the need to increase nuclear fuel resources and the perceived non-proliferation advantages of the utilization of thorium in the fuel cycle. Various options have been considered for the use of thorium in the LWR fuel cycle. The possibility for thorium utilization in a multi-recycle system has also been considered in past literature, primarily because of the potential for near breeders with Th/U-233 in the thermal energy range. The objective of this study is to evaluate the potential of Th/U-233 fuel multi-recycle in current LWRs, focusing on pressurized water reactors (PWRs). Approaches for sustainable multi-recycle without the need for external fissile material makeup have been investigated. The intent is to obtain a design that allows existing PWRs to be used with minimal modifications.

Yun, D.; Taiwo, T. A.; Kim, T. K.; Mohamed, A.; Nuclear Engineering Division

2010-10-01T23:59:59.000Z

325

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

SciTech Connect

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

326

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)

A Review of Light-Water Reactor Safety Studies," by A.V.due to a break in the reactor cooling cooling water the therecirculation - Failure of the reactor protection system.

Nero, A.V.

2010-01-01T23:59:59.000Z

327

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

SciTech Connect

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

328

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  

Science Conference Proceedings (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

329

Program on Technology Innovation: Environmentally Assisted Cracking in LWR Structural Materials, 2011 PEACE-E Annual Report  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E, a joint research program sponsored by the Electric Power Research Institute (EPRI) in collaboration with the Fracture & Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking of light water reactor structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) environments.

2011-12-23T23:59:59.000Z

330

Economic Analyiss of "Symbiotic" Light Water Reactor/Fast Burner Reactor Fuel Cycles Proposed as Part of the U.S. Advanced Fuel Cycle Initiative (AFCI)  

Science Conference Proceedings (OSTI)

A spreadsheet-based 'static equilibrium' economic analysis was performed for three nuclear fuel cycle scenarios, each designed for 100 GWe-years of electrical generation annually: (1) a 'once-through' fuel cycle based on 100% LWRs fueled by standard UO2 fuel assemblies with all used fuel destined for geologic repository emplacement, (2) a 'single-tier recycle' scenario involving multiple fast burner reactors (37% of generation) accepting actinides (Pu,Np,Am,Cm) from the reprocessing of used fuel from the uranium-fueled LWR fleet (63% of generation), and (3) a 'two-tier' 'thermal+fast' recycle scenario where co-extracted U,Pu from the reprocessing of used fuel from the uranium-fueled part of the LWR fleet (66% of generation) is recycled once as full-core LWR MOX fuel (8% of generation), with the LWR MOX used fuel being reprocessed and all actinide products from both UO2 and MOX used fuel reprocessing being introduced into the closed fast burner reactor (26% of generation) fuel cycle. The latter two 'closed' fuel cycles, which involve symbiotic use of both thermal and fast reactors, have the advantages of lower natural uranium requirements per kilowatt-hour generated and less geologic repository space per kilowatt-hour as compared to the 'once-through' cycle. The overall fuel cycle cost in terms of $ per megawatt-hr of generation, however, for the closed cycles is 15% (single tier) to 29% (two-tier) higher than for the once-through cycle, based on 'expected values' from an uncertainty analysis using triangular distributions for the unit costs for each required step of the fuel cycle. (The fuel cycle cost does not include the levelized reactor life cycle costs.) Since fuel cycle costs are a relatively small percentage (10 to 20%) of the overall busbar cost (LUEC or 'levelized unit electricity cost') of nuclear power generation, this fuel cycle cost increase should not have a highly deleterious effect on the competitiveness of nuclear power. If the reactor life cycle costs are included in the analysis, with the fast reactors having a higher $/kw(e) capital cost than the LWRs, the overall busbar generation cost ($/MWh) for the closed cycles is approximately 12% higher than for the all-LWR once-through fuel cycle case, again based on the expected values from an uncertainty analysis. It should be noted that such a percentage increase in the cost of nuclear power is much smaller than that expected for fossil fuel electricity generation if CO2 is costed via a carbon tax, cap and trade regimes, or carbon capture and sequestration (CCS).

Williams, Kent Alan [ORNL; Shropshire, David E. [Idaho National Laboratory (INL)

2009-01-01T23:59:59.000Z

331

Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures  

E-Print Network (OSTI)

Next generation nuclear technology calls for more advanced fuels to maximize the effectiveness of new designs. A fuel currently being studied for use in advanced light water reactors (LWRs) is uranium zirconium hydride ...

Ensor, Brendan M. (Brendan Melvin)

2012-01-01T23:59:59.000Z

332

Water  

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

Laws Envirosearch Institutional Controls NEPA Activities RCRA RQ*Calculator Water HSS Logo Water Laws Overview of water-related legislation affecting DOE sites Clean...

333

Energy Basics: Fluorescent Lighting  

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

& Cooling Water Heating Fluorescent Lighting Fluorescent lamps use 25%-35% of the energy used by incandescent lamps to provide the same amount of illumination (efficacy of...

334

Field Evaluation of the Effectiveness of Strobe Lights for Preventing Impingement of Fish at Cooling Water Intakes  

Science Conference Proceedings (OSTI)

Section 316(b) of the Clean Water Act requires that the location, design, construction, and capacity of a cooling water intake structure reflect the "best technology available" for minimizing adverse environmental impacts, such as impingement of fish on intake screens. In the Southeast U.S., over 90% of fish impinged on cooling-water intake screens of thermal power stations are threadfin shad (Dorosoma petenense) or gizzard shad (D. cepedianum). Much of this impingement occurs in winter coincident with c...

2006-12-20T23:59:59.000Z

335

LWR NUCLEAR FUEL BUNDLE DATA FOR USE IN FUEL BUNDLE HANDLING  

Office of Scientific and Technical Information (OSTI)

LWR NUCLEAR FUEL BUNDLE DATA FOR LWR NUCLEAR FUEL BUNDLE DATA FOR USE IN FUEL BUNDLE HANDLING TOPICAL REPORT W. 8. Weihermilfer C. S. Allison Septem bet 1979 Work Performed, Under Contract EY-76-C- M - 1 8 3 0 Form 189 Number 210.1 BAlTELLE PACIFIC NORTHWEST LABORATORY RICHLAND, WA 99352 BASE TECHNOLOGY N O T I C E T h i s report was prepard n an account of work sponrored by the UAed States Govcmmenr. Neither tht Unltcd S t a t e nor !he k p n m c n t of Energy, not any of their ernploylecs, nw any of theb ccmtnctotr, hontncton. or their employper. maka any warranty. expms or Implied, or m u m any legal liability or rcrponrlbllity for the accuracy, c o m p l c r e ~ s or ulefulnm of m y information. -ratus, prodm or p r e di~1Oltd. or represents that Its u w ? would not infringe privateiy o w d rights. The views, opinions and ccnclusionr contained in this report a

336

Compatibility/Stability Issues in the Use of Nitride Kernels in LWR TRISO Fuel  

SciTech Connect

The stability of the SiC layer in the presence of free nitrogen will be dependent upon the operating temperatures and resulting nitrogen pressures whether it is at High Temperature Gas-Cooled Reactor (HTGR) temperatures of 1000-1400 C (coolant design dependent) or LWR temperatures that range from 500-700 C. Although nitrogen released in fissioning will form fission product nitrides, there will remain an overpressure of nitrogen of some magnitude. The nitrogen can be speculated to transport through the inner pyrolytic carbon layer and contact the SiC layer. The SiC layer may be envisioned to fail due to resulting nitridation at the elevated temperatures. However, it is believed that these issues are particularly avoided in the LWR application. Lower temperatures will result in significantly lower nitrogen pressures. Lower temperatures will also substantially reduce nitrogen diffusion rates through the layers and nitriding kinetics. Kinetics calculations were performed using an expression for nitriding silicon. In order to further address these concerns, experiments were run with surrogate fuel particles under simulated operating conditions to determine the resulting phase formation at 700 and 1400 C.

Armstrong, Beth L [ORNL; Besmann, Theodore M [ORNL

2012-02-01T23:59:59.000Z

337

Hydrogen-control systems for severe LWR accident conditions - a state-of-technology report  

Science Conference Proceedings (OSTI)

This report reviews the current state of technology regarding hydrogen safety issues in light water reactor plants. Topics considered in this report relate to control systems and include combustion prevention, controlled combustion, minimization of combustion effects, combination of control concepts, and post-accident disposal. A companion report addresses hydrogen generation, distribution, and combustion. The objectives of the study were to identify the key safety issues related to hydrogen produced under severe accident conditions, to describe the state of technology for each issue, and to point out ongoing programs aimed at resolving the open issues.

Hilliard, R.K.; Postma, A.K.; Jeppson, D.W.

1983-03-01T23:59:59.000Z

338

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 similar conventional UO? fuel. Weapons-grade MOX behavior. However, MOX fuel rods feature higher fuel centerline temperatures due to a lower thermal conductivity. Moreover, higher diffusion in MOX fuel results in a slightly higher fission gas release. Finally, MOX fuel shows better mechanical behavior than UO? fuel due to lower pellet-cladding mechanical interaction and rod deformation. These results indicate that the MOX fuel meets all potential licensing requirements.

Bellanger, Philippe

1999-01-01T23:59:59.000Z

339

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

340

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

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

Note: This page contains sample records for the topic "lwr light 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.


341

Environmentally Assisted Cracking Laboratory - Nuclear Engineering...  

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

internal components are studied in simulated light water reactor (LWR) environments. Two hot-cell test facilities are used to develop experimental data on the irradiation assisted...

342

Microsoft PowerPoint - FY 2011 Budget Slides for NEAC (Revised...  

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

multiyear, 452M program to support the accelerated commercial deployment of LWR Small Modular Reactors * Supports new Light Water Reactor Sustainability R&D activities arising...

343

Software: MSET - Nuclear Engineering Division (Argonne)  

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

light water reactor (LWR) signal validation applications at the Florida Power Corporation Crystal River 3 nuclear power station. During the testing of MSET at the Crystal River 3...

344

Light-Light Scattering  

E-Print Network (OSTI)

For a long time, it is believed that the light by light scattering is described properly by the Lagrangian density obtained by Heisenberg and Euler. Here, we present a new calculation which is based on the modern field theory technique. It is found that the light-light scattering is completely different from the old expression. The reason is basically due to the unphysical condition (gauge condition) which was employed by the QED calcualtion of Karplus and Neumann. The correct cross section of light-light scattering at low energy of $(\\frac{\\omega}{m} \\ll 1)$ can be written as $ \\displaystyle{\\frac{d\\sigma}{d\\Omega}=\\frac{1}{(6\\pi)^2}\\frac{\\alpha^4} {(2\\omega)^2}(3+2\\cos^2\\theta +\\cos^4\\theta)}$.

Kanda, Naohiro

2011-01-01T23:59:59.000Z

345

Light-Light Scattering  

E-Print Network (OSTI)

For a long time, it is believed that the light by light scattering is described properly by the Lagrangian density obtained by Heisenberg and Euler. Here, we present a new calculation which is based on the modern field theory technique. It is found that the light-light scattering is completely different from the old expression. The reason is basically due to the unphysical condition (gauge condition) which was employed by the QED calcualtion of Karplus and Neumann. The correct cross section of light-light scattering at low energy of $(\\frac{\\omega}{m} \\ll 1)$ can be written as $ \\displaystyle{\\frac{d\\sigma}{d\\Omega}=\\frac{1}{(6\\pi)^2}\\frac{\\alpha^4} {(2\\omega)^2}(3+2\\cos^2\\theta +\\cos^4\\theta)}$.

Naohiro Kanda

2011-06-03T23:59:59.000Z

346

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

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

347

Cape Light Compact - Commercial, Industrial and Municipal Buildings...  

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

Manufacturing Other Construction Heat Pumps Appliances & Electronics Commercial Lighting Lighting Commercial Weatherization Water Heating Maximum Rebate Retrofit: 50% of cost...

348

An integrated approach for the verification of fresh mixed oxide fuel (MOX) assemblies at light water reactor MOX recycle reactors  

Science Conference Proceedings (OSTI)

This paper presents an integrated approach for the verification of mixed oxide (MOX) fuel assemblies prior to their being loaded into the reactor. There is a coupling of the verification approach that starts at the fuel fabrication plant and stops with the transfer of the assemblies into the thermal reactor. The key measurement points are at the output of the fuel fabrication plant, the receipt at the reactor site, and the storage in the water pool as fresh fuel. The IAEA currently has the capability to measure the MOX fuel assemblies at the output of the fuel fabrication plants using a passive neutron coincidence counting systems of the passive neutron collar (PNCL) type. Also. at the MOX reactor pool, the underwater coincidence counter (UWCC) has been developed to measure the MOX assemblies in the water. The UWCC measurement requires that the fuel assembly be lifted about two meters up in the storage rack to avoid interference from the fuel that is stored in the rack. This paper presents a new method to verify the MOX fuel assemblies that are in the storage rack without the necessity of moving the fuel. The detector system is called the Underwater MOX Verification System (UMVS). The integration and relationship of the three measurements systems is described.

Menlove, Howard O [Los Alamos National Laboratory; Lee, Sang - Yoon [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

349

LED Lighting  

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

Light-emitting diodes (LEDs) are light sources that differ from more traditional sources of light in that they are semiconductor devices that produce light when an electrical current is applied....

350

Proposed and existing passive and inherent safety-related structures, systems, and components (building blocks) for advanced light-water reactors  

Science Conference Proceedings (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

351

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  

Science Conference Proceedings (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

352

NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669  

Science Conference Proceedings (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

353

NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669  

Science Conference Proceedings (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

354

Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Part II. Final report  

SciTech Connect

Information is presented concerning overview of literature relating to radiation exposure and operating experience; details of LWR-MTC3 classification system; histograms for individual BWR facilities depicting frequency of M and T mode and frequency of systems and components involved with M and T problems; histograms for individual PWR facilities depicting frequency of M and T mode and frequency of systems and components involved with M and T problems; and Fortran program for M and T data clustering.

Husseiny, A. A.; Sabri, Z. A.; Turnage, J. J.

1980-04-01T23:59:59.000Z

355

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

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

356

Uranium Nitride as LWR TRISO Fuel: Thermodynamic Modeling of U-C-N  

SciTech Connect

TRISO coated particle fuel is envisioned as a next generation replacement for current urania pellet fuel in LWR applications. To obtain adequate fissile loading the kernel of the TRISO particle will need to be UN. In support of the fuel development effort, an assessment of phase regions of interest in the U-C-N system was undertaken as the fuel will be prepared by the carbothermic reduction of the oxide and it will be in equilibrium with carbon within the TRISO particle. The phase equilibria and thermochemistry of the U-C-N system is reviewed, including nitrogen pressure measurements above various phase fields. Selected measurements were used to fit a first order model of the UC1-xNx phase, represented by the inter-solution of UN and UC. Fit to the data was significantly improved by also adjusting the heat of formation for UN by ~12 kJ/mol and the phase equilbria was best reproduced by also adjusting the heat for U2N3 by +XXX. The determined interaction parameters yielded a slightly positive deviation from ideality, which agrees with lattice parameter measurements which show positive deviation from Vegard s law. The resultant model together with reported values for other phases in the system were used to generate isothermal sections of the U-C-N phase diagram. Nitrogen partial pressures were also computed for regions of interest.

Besmann, Theodore M [ORNL; Shin, Dongwon [ORNL

2012-01-01T23:59:59.000Z

357

Proceedings of the IAEA specialists` meeting on cracking in LWR RPV head penetrations  

SciTech Connect

This report contains 17 papers that were presented in four sessions at the IAEA Specialists` meeting on Cracking in LWR RPV Head Penetrations held at ASTM Headquarters in Philadelphia on May 2-3, 1995. The papers are compiled here in the order that presentations were made in the sessions, and they relate to operational observations, inspection techniques, analytical modeling, and regulatory control. The goal of the meeting was to allow international experts to review experience in the field of ensuring adequate performance of reactor pressure vessel (RPV) heads and penetrations. The emphasis was to allow a better understanding of RPV material behavior, to provide guidance supporting reliability and adequate performance, and to assist in defining directions for further investigations. The international nature of the meeting is illustrated by the fact that papers were presented by researchers from 10 countries. There were technical experts present form other countries who participated in discussions of the results presented. This present document incorporates the final version of the papers as received from the authors. The final chapter includes conclusions and recommendations. Individual papers have been cataloged separately.

Pugh, C.E.; Raney, S.J. [comps.] [Oak Ridge National Lab., TN (United States)] [comps.; Oak Ridge National Lab., TN (United States)

1996-07-01T23:59:59.000Z

358

Analysis of fission gas release in LWR fuel using the BISON code  

SciTech Connect

Recent advances in the development of the finite-element based, multidimensional fuel performance code BISON of Idaho National Laboratory are presented. Specifically, the development, implementation and testing of a new model for the analysis of fission gas behavior in LWR-UO2 fuel during irradiation are summarized. While retaining a physics-based description of the relevant mechanisms, the model is characterized by a level of complexity suitable for application to engineering-scale nuclear fuel analysis and consistent with the uncertainties pertaining to some parameters. The treatment includes the fundamental features of fission gas behavior, among which are gas diffusion and precipitation in fuel grains, growth and coalescence of gas bubbles at grain faces, grain growth and grain boundary sweeping effects, thermal, athermal, and transient gas release. The BISON code incorporating the new model is applied to the simulation of irradiation experiments from the OECD/NEA International Fuel Performance Experiments database, also included in the IAEA coordinated research projects FUMEX-II and FUMEX-III. The comparison of the results with the available experimental data at moderate burn-up is presented, pointing out an encouraging predictive accuracy, without any fitting applied to the model parameters.

G. Pastore; J.D. Hales; S.R. Novascone; D.M. Perez; B.W. Spencer; R.L. Williamson

2013-09-01T23:59:59.000Z

359

Lighting Techniques  

Science Conference Proceedings (OSTI)

...Lighting is very critical in photography. The specimen should be placed on a background which will not detract from the resolution of the fracture surface. For basic lighting, one spotlight is suggested. The light is then raised or lowered, and

360

Report from the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies  

SciTech Connect

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

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

A SCOPING STUDY: Development of Probabilistic Risk Assessment Models for Reactivity Insertion Accidents During Shutdown In U.S. Commercial Light Water Reactors  

SciTech Connect

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

362

SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis. Volume 4  

Science Conference Proceedings (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

363

Lighting Research Center Lighting Products  

Science Conference Proceedings (OSTI)

... 12) Solid State Lighting Luminaires - Color Characteristic Measurements. [22/S04] IES LM-16:1993 Practical Guide to Colorimetry of Light Sources. ...

2013-07-26T23:59:59.000Z

364

Lighting Group: Light Distribution Systems  

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

Retrofit Alternatives to Incandescent Downlights Hotel and Institutional Bathroom Lighting Portable Office Lighting Systems Low Glare Outdoor Retrofit Luminaire LED Luminaires...

365

Outlaw lighting  

SciTech Connect

Demand-side management programs by utilities and the federal government`s Green Lights program have made significant inroads in promoting energy-efficient lighting. But the Energy Policy Act now prohibits certain types of lighting. This article provides analysis to help architects determine new lamp performance compared with older lighting products.

Bryan, H.

1994-12-01T23:59:59.000Z

366

Flow instabilities in the core and the coolant circuit of advances low-boiling light water reacto: classification of causes and development of simulator for the future analysis  

E-Print Network (OSTI)

The coolant flow instability, apparent in the coolant mass flow fluctuations in the separate parallel heating channels and also in a closed loop of the primary circuit under some operating conditions, is observed in the core fuel assemblies of light water reactors. In some ways this phenomenon is identical with the fluctuations in the once-through steam generators pipes, and changes of the coolant mass flows and length of flow patterns are initiating this phenomenon. The parameters at the core output and the secondary circuit parameters have influence on each other. These parameter changes have significant influences on the operating processes, operating and control algorithms, operating and control system design, and reliability of the operating power plant's machines and equipment. Changes of heating surface temperatures, displacement borders of the flow patterns, and critical heat flux entail changes of the coolant flow parameters, finally causing changes of the initial primary system parameters due to closed loop system feedback. In turn, these cause over-circuit instability in the reactor. Core power generation changes are carried out by means of influencing the nuclear fission process through changing the multiplication factor. Additionally, these local side-to-side power irregularities in sub-zones may appear due to the influence of various hydrodynamic instabilities. The local side-to-side power in these sub-zones may differ significantly from each other. The aforesaid arguments are correct for the both light water reactor types. But, as is shown by our investigations and operational practice of low-boiling reactors, behavior of the core-circuit hydrodynamic system is significantly different from its behavior in the boiling or pressurized reactors with pumping circulation. The coolant flow regimes in typical reactors are defined through pump operating regimes and are not adjustable inside a certain power range. The objective of this thesis is to understand more precisely the influence and the nature of these phenomena. After analyzing the problem from different points of view and showing the necessity of its comprehensive understanding, we present recommendations for engineering solutions and plans for further investigations. We will try to determine limits of their reliable practical application with modern low-to-medium power reactor design and investigate this dynamic system behavior. Finally, it is necessary to take into consideration not separate phenomena, but their complex influence on the whole primary system (i.e. a kind of macro-system is examined without being separated into its individual elements). But, the analysis of every phenomenon is fulfilled separately and a process of formation of a block-scheme, consisting of several sub-systems, is given in this thesis. The final block-scheme is presented as a simulator model, taking into consideration design components chosen for the analysis of system dynamics as the first step of model development.

Rezvyi, Aleksey

2002-01-01T23:59:59.000Z

367

Lighting Controls  

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

corridors. The overall range of savings was six to 80 percent. The Advanced Lighting Guidelines On-Line Edition New Buildings Institute 2011 presents a table of lighting energy...

368

Shape the light, light the shape - lighting installation in performance.  

E-Print Network (OSTI)

??This thesis investigates the lighting design theory Light Inside Out, which is the technique of shaping light toward a creation of lighting installation in performance (more)

Yu, Lih-Hwa, 1972-

2010-01-01T23:59:59.000Z

369

Lighting Systems  

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

Purple LED lamp Purple LED lamp Lighting Systems Lighting research is aimed at improving the energy efficiency of lighting systems in buildings and homes across the nation. The goal is to reduce lighting energy consumption by 50% over twenty years by improving the efficiency of light sources, and controlling and delivering illumination so that it is available, where and when needed, and at the required intensity. Research falls into four main areas: Sources and Ballasts, Light Distribution Systems, Controls and Communications, and Human Factors. Contacts Francis Rubinstein FMRubinstein@lbl.gov (510) 486-4096 Links Lighting Research Group Batteries and Fuel Cells Buildings Energy Efficiency Applications Commercial Buildings Cool Roofs and Heat Islands Demand Response Energy Efficiency Program and Market Trends

370

Alliant Energy Interstate Power and Light (Electric) - Business...  

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

Design & Remodeling Other Windows, Doors, & Skylights Heat Pumps Commercial Lighting Lighting Manufacturing Water Heating Maximum Rebate See program web site Program...

371

Commercial Lighting and LED Lighting Incentives  

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

Incentives for energy efficient commercial lighting equipment as well as commercial LED lighting equipment are available to businesses under the Efficiency Vermont Lighting and LED Lighting...

372

Economic incentives and recommended development for commercial use of high burnup fuels in the once-through LWR fuel cycle  

Science Conference Proceedings (OSTI)

This study calculates the reduced uranium requirements and the economic incentives for increasing the burnup of current design LWR fuels from the current range of 25 to 35 MWD/Kg to a range of 45 to 55 MWD/Kg. The changes in fuel management strategies which may be required to accommodate these high burnup fuels and longer fuel cycles are discussed. The material behavior problems which may present obstacles to achieving high burnup or to license fuel are identified and discussed. These problems are presented in terms of integral fuel response and the informational needs for commercial and licensing acceptance. Research and development programs are outlined which are aimed at achieving a licensing position and commercial acceptance of high burnup fuels.

Stout, R.B.; Merckx, K.R.; Holm, J.S.

1981-01-01T23:59:59.000Z

373

Northern Lights  

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

Northern Lights Northern Lights Nature Bulletin No. 178-A February 6, 1965 Forest Preserve District of Cook County Seymour Simon, President Roland F. Eisenbeis, Supt. of Conservation NORTHERN LIGHTS To a person seeing the Aurora Borealis or "northern lights" for the first time, it is an uncanny awe-inspiring spectacle. Sometimes it begins as a glow of red on the northern horizon, ominously suggesting a great fire, gradually changing to a curtain of violet-white, or greenish-yellow light extending from east to west. Some times this may be transformed to appear as fold upon fold of luminous draperies that march majestically across the sky; sometimes as a vast multitude of gigantic flaming swords furiously slashing at the heavens; sometimes as a flowing crown with long undulating colored streamers fanning downward and outward.

374

NREL: Wind Research - Shedding Light on Offshore Wind Resources  

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

Shedding Light on Offshore Wind Resources March 22, 2013 View of the Chesapeake Bay light tower in the water. The Chesapeake Bay light tower is located approximately 13 miles from...

375

Burbank Water & Power - Business Bucks Energy Efficiency Grant...  

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

& Cooling Cooling Other Design & Remodeling Windows, Doors, & Skylights Ventilation Appliances & Electronics Commercial Lighting Lighting Manufacturing Insulation Water...

376

Light Organizing/Organizing Light [Light in Place  

E-Print Network (OSTI)

a street through alter nating areas of dark and light, welandscapes, streets and squares. Light summons our spiritfor changing light, both outside rooms (such as streets and

Schwartz, Martin

1992-01-01T23:59:59.000Z

377

Alliant Energy Interstate Power and Light (Gas and Electric)...  

Open Energy Info (EERE)

Water Heaters, Windows, Whole House Fans, Room Air Conditioners, Geothermal Heat Pumps, LED Lighting, Heat Pump Water Heaters Active Incentive Yes Implementing Sector Utility...

378

Alliant Energy Interstate Power and Light (Electric) - Residential...  

Open Energy Info (EERE)

Programmable Thermostats, Refrigerators, Water Heaters, Windows, Geothermal Heat Pumps, LED Lighting, Heat Pump Water Heaters Active Incentive Yes Implementing Sector Utility...

379

Alliant Energy Interstate Power and Light (Electric) - Business...  

Open Energy Info (EERE)

Commercial Refrigeration Equipment, Food Service Equipment, Room Air Conditioners, LED Lighting, Tankless Water Heaters, Heat Pump Water Heaters Active Incentive Yes...

380

Alliant Energy Interstate Power and Light (Electric) - Residential...  

Open Energy Info (EERE)

Heat pumps, Lighting, Programmable Thermostats, Refrigerators, Water Heaters, Windows, Room Air Conditioners, Geothermal Heat Pumps, Appliance Recycling, Home Energy...

Note: This page contains sample records for the topic "lwr light 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.


381

LMBFR and LWR in-core thermal-hydraulic codes: the state-of-the-art and research and development needs  

Science Conference Proceedings (OSTI)

A review of analytical design methods used for predicting reactor core flow and temperature distributions is presented with emphasis on LMFBR's. The paper also briefly describes and contrasts the methods used for LWR's. These methods are global analysis, subchannel analysis, distributed parameter, and hybrid analysis. The evolution of the local and subchannel analysis methods is presented. Data used for code validation are also presented. Current research and development needs are identified and discussed. Areas identified for future research and development include methods and expermental data for analysis of distorted bundles and natural convection. Methods that have been developed for predicting the safety performance of LMFBR's and LWR's are not within the scope of this paper.

Khan, E.U.; Coomes, E.P.; Rowe, D.S.; Trent, D.S.

1981-04-01T23:59:59.000Z

382

Solid-State Lighting: LED Lighting Facts  

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

Market-Based Programs Printable Version Share this resource Send a link to Solid-State Lighting: LED Lighting Facts to someone by E-mail Share Solid-State Lighting: LED Lighting Facts on Facebook Tweet about Solid-State Lighting: LED Lighting Facts on Twitter Bookmark Solid-State Lighting: LED Lighting Facts on Google Bookmark Solid-State Lighting: LED Lighting Facts on Delicious Rank Solid-State Lighting: LED Lighting Facts on Digg Find More places to share Solid-State Lighting: LED Lighting Facts on AddThis.com... LED Lighting Facts CALiPER Program Standards Development Technical Information Network Gateway Demonstrations Municipal Consortium Design Competitions LED Lighting Facts LED lighting facts - A Program of the U.S. DOE DOE's LED Lighting Facts® program showcases LED products for general

383

Dynamic light scattering study on phase separation of a protein-water mixture: Application on cold cataract development in the ocular lens  

E-Print Network (OSTI)

We present a detailed dynamic light scattering study on the phase separation in the ocular lens emerging during cold cataract development. Cold cataract is a phase separation effect that proceeds via spinodal decomposition of the lens cytoplasm with cooling. Intensity auto-correlation functions of the lens protein content are analyzed with the aid of two methods providing information on the populations and dynamics of the scattering elements associated with cold cataract. It is found that the temperature dependence of many measurable parameters changes appreciably at the characteristic temperature ~16+1 oC which is associated with the onset of cold cataract. Extending the temperature range of this work to previously inaccessible regimes, i.e. well below the phase separation or coexistence curve at Tcc, we have been able to accurately determine the temperature dependence of the collective and self-diffusion coefficient of proteins near the spinodal. The analysis showed that the dynamics of proteins bears some resemblance to the dynamics of structural glasses where the apparent activation energy for particle diffusion increases below Tcc indicating a highly cooperative motion. Application of ideas developed for studying the critical dynamics of binary protein/solvent mixtures, as well as the use of a modified Arrhenius equation, enabled us to estimate the spinodal temperature Tsp of the lens nucleus. The applicability of dynamic light scattering as a non-invasive, early-diagnostic tool for ocular diseases is also demonstrated in the light of the findings of the present paper.

V. Petta; N. Pharmakakis; G. N. Papatheodorou; S. N. Yannopoulos

2008-06-11T23:59:59.000Z

384

4240 Carson Street, Suite 102 Denver, CO 80239 www.sre3.com SOLAR ELECTRIC SOLAR WATER HEATING ENERGY AUDITS A/C & HEATING INSULATION LIGHTING  

E-Print Network (OSTI)

4240 Carson Street, Suite 102 Denver, CO 80239 www.sre3.com SOLAR ELECTRIC SOLAR WATER HEATING for homeowners, businesses, and government entities that assist them in lowering utility bills, reducing a unique solutions approach based on the RE3 concept, which includes: · Review ­ current energy usage

Colorado at Boulder, University of

385

Supercritical Water Reactor (SCWR) - Survey of Materials Research and Development Needs to Assess Viability  

SciTech Connect

Supercritical water-cooled reactors (SCWRs) are among the most promising advanced nuclear systems because of their high thermal efficiency [i.e., about 45% vs. 33% of current light water reactors (LWRs)] and considerable plant simplification. SCWRs achieve this with superior thermodynamic conditions (i.e., high operating pressure and temperature), and by reducing the containment volume and eliminating the need for recirculation and jet pumps, pressurizer, steam generators, steam separators and dryers. The reference SCWR design in the U.S. is a direct cycle, thermal spectrum, light-water-cooled and moderated reactor with an operating pressure of 25 MPa and inlet/outlet coolant temperature of 280/500 C. The inlet flow splits, partly to a down-comer and partly to a plenum at the top of the reactor pressure vessel to flow downward through the core in special water rods to the inlet plenum. This strategy is employed to provide good moderation at the top of the core, where the coolant density is only about 15-20% that of liquid water. The SCWR uses a power conversion cycle similar to that used in supercritical fossil-fired plants: high- intermediate- and low-pressure turbines are employed with one moisture-separator re-heater and up to eight feedwater heaters. The reference power is 3575 MWt, the net electric power is 1600 MWe and the thermal efficiency is 44.8%. The fuel is low-enriched uranium oxide fuel and the plant is designed primarily for base load operation. The purpose of this report is to survey existing materials for fossil, fission and fusion applications and identify the materials research and development needed to establish the SCWR viabilitya with regard to possible materials of construction. The two most significant materials related factors in going from the current LWR designs to the SCWR are the increase in outlet coolant temperature from 300 to 500 C and the possible compatibility issues associated with the supercritical water environment. Reactor pressure vessel Pumps and piping

Philip E. MacDonald

2003-09-01T23:59:59.000Z

386

Light Computing  

E-Print Network (OSTI)

A configuration of light pulses is generated, together with emitters and receptors, that allows computing. The computing is extraordinarily high in number of flops per second, exceeding the capability of a quantum computer for a given size and coherence region. The emitters and receptors are based on the quantum diode, which can emit and detect individual photons with high accuracy.

Gordon Chalmers

2006-10-13T23:59:59.000Z

387

BNL program in support of LWR degraded-core accident analysis  

SciTech Connect

Two major sources of loading on dry watr reactor containments are steam generatin from core debris water thermal interactions and molten core-concrete interactions. Experiments are in progress at BNL in support of analytical model development related to aspects of the above containment loading mechanisms. The work supports development and evaluation of the CORCON (Muir, 1981) and MARCH (Wooton, 1980) computer codes. Progress in the two programs is described in this paper. 8 figures.

Ginsberg, T.; Greene, G.A.

1982-01-01T23:59:59.000Z

388

EK101 Engineering Light Smart Lighting  

E-Print Network (OSTI)

extensively in concert lighting and are finding increased usage in dance lighting because refers to the upstage back curtain (is white or a light color), which can be us for lighting or special Mixer #12;Monitor House speaker Lighting System Control Board: Similar to the sound board, the light

Bifano, Thomas

389

Pressure vessel and piping codes. Technical basis for revised reference crack growth rate curves for pressure boundary steels in LWR environment  

SciTech Connect

Since the inception of the pressure vessel and piping codes the reference fatigue crack growth rate curves have been contained in Appendix A of Sect. XI. The curves have been designed to be applicable to carbon and low alloy pressure vessel steels exposed to either air or light water reactor coolant environments. Data obtained over the past several years have shown a different behavior of these steels in the light water reactor environment than that predicted by the present reference curve. A revised set of reference curves has been formulated, incorporating a new curve shape as well as a dependency of growth rate on R ratio (minimum load/maximum load). This work provides the background and justification for such a revision, details the methodology used to develop the revised curves, and includes an evalution of the adequacy and impact of the revised curves as compared with the single curve which they replace. 24 references.

Bamford, W.H.

1980-11-01T23:59:59.000Z

390

Texas Electric Lighting Report  

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

electric lighting electric lighting The SNAP House's lighting design aims for elegant simplicity in concept, use, and maintenance. Throughout the house, soft, ambient light is juxtaposed with bright, direct task lighting. All ambient and most task lighting is integrated directly into the architectural design of the house. An accent light wall between the bedroom and bathroom provides a glowing light for nighttime navigation.

391

DESCRIPTION OF THE TRITIUM-PRODUCING BURNABLE ABSORBER ROD FOR THE COMMERCIAL LIGHT WATER REACTOR TTQP-1-015 Rev 19  

Science Conference Proceedings (OSTI)

Tritium-producing burnable absorber rods (TPBARs) used in the U.S. Department of Energys Tritium Readiness Program are designed to produce tritium when placed in a Westinghouse or Framatome 17x17 fuel assembly and irradiated in a pressurized water reactor (PWR). This document provides an unclassified description of the current design baseline for the TPBARs. This design baseline is currently valid only for Watts Bar reactor production cores. A description of the Lead Use TPBARs will not be covered in the text of the document, but the applicable drawings, specifications and test plan will be included in the appropriate appendices.

Burns, Kimberly A.; Love, Edward F.; Thornhill, Cheryl K.

2012-02-01T23:59:59.000Z

392

Light Emitting Diode (LED) Lighting and Systems  

Science Conference Proceedings (OSTI)

This EPRI Technical Update addresses the most promising and unique energy efficient light source light emitting diode (LED) lighting. Business and technical market factors (Chapter 2) explain the upcoming growth of the LED and LED lighting market. Future technical improvements to LEDs and systems are also emphasized. Discussion of the importance of utility involvement in helping their customers make the switch from traditional lighting to LED lighting is provided. LED lighting technologies are covered in...

2007-12-21T23:59:59.000Z

393

Energy resource alternatives competition. Progress report for the period February 1, 1975--December 31, 1975. [Space heating and cooling, hot water, and electricity for homes, farms, and light industry  

DOE Green Energy (OSTI)

This progress report describes the objectives and results of the intercollegiate Energy Resource Alternatives competition. The one-year program concluded in August 1975, with a final testing program of forty student-built alternative energy projects at the Sandia Laboratories in Albuquerque, New Mexico. The goal of the competition was to design and build prototype hardware which could provide space heating and cooling, hot water, and electricity at a level appropriate to the needs of homes, farms, and light industry. The hardware projects were powered by such nonconventional energy sources as solar energy, wind, biologically produced gas, coal, and ocean waves. The competition rules emphasized design innovation, economic feasibility, practicality, and marketability. (auth)

Matzke, D.J.; Osowski, D.M.; Radtke, M.L.

1976-01-01T23:59:59.000Z

394

Photocatalytic splitting of water under visible-light irradiation over the NiOx-loaded Sm{sub 2}InTaO{sub 7} with 4f-d{sup 10}-d{sup 0} configuration  

SciTech Connect

A new visible-light-response photocatalyst Sm{sub 2}InTaO{sub 7} with 4f-d{sup 10}-d{sup 0} configuration crystallized in a cubic system with the space group Fd3m was synthesized by a solid-state reaction method. NiOx-loaded Sm{sub 2}InTaO{sub 7} showed high photocatalytic activities for H{sub 2} evolution from pure water under visible light irradiation (lambda>400 nm). Changes in the photocatalytic activity with the calcination temperature of Sm{sub 2}InTaO{sub 7} and the amount of NiOx loaded indicated that the combination of highly crystallized Sm{sub 2}InTaO{sub 7} and a high dispersion of NiOx particles led to high photocatalytic activity. The high photocatalytic performance of NiOx-loaded Sm{sub 2}InTaO{sub 7} supported the existing view that the photocatalytic activity correlated with the lattice distortion. Density functional theory calculation indicated that strong dispersion from the hybridized In 5s 5p orbitals at the bottom of the conduction band was responsible for the high activity of photocatalyst Sm{sub 2}InTaO{sub 7}. - Graphical abstract: A new visible-light-response photocatalyst Sm{sub 2}InTaO{sub 7} with 4f-d{sup 10}-d{sup 0} configuration was developed. DFT calculation indicated that strong dispersion from the hybridized In 5s 5p orbitals was responsible for the high photocatalytic activity.

Tang Xinde, E-mail: txd738011@yahoo.c [College of Chemistry and Chemical Engineering, Central South University, Changsha 410083 (China); Ye Hongqi [College of Chemistry and Chemical Engineering, Central South University, Changsha 410083 (China); Liu Hui [College of Chemistry and Chemical Engineering, Central South University, Changsha 410083 (China); State Key Laboratory for Powder Metallurgy, Central South University, Changsha 410083 (China); Ma Chenxia; Zhao Zhi [College of Chemistry and Chemical Engineering, Central South University, Changsha 410083 (China)

2010-01-15T23:59:59.000Z

395

Thermal hydraulic analysis of hydride fuels in BWR's  

E-Print Network (OSTI)

This thesis contributes to the hydride nuclear fuel project being completed by UC Berkeley and MIT to assess the possible benefits of using hydride fuel in light water nuclear reactors (LWR's). More specifically, this ...

Creighton, John Everett

2005-01-01T23:59:59.000Z

396

Public comments and Task Force responses regarding the environmental survey of the reprocessing and waste management portions of the LWR fuel cycle  

SciTech Connect

This document contains responses by the NRC Task Force to comments received on the report ''Environmental Survey of the Reprocessing and Waste Management Portions of the LWR Fuel Cycle'' (NUREG-0116). These responses are directed at all comments, inclding those received after the close of the comment period. Additional information on the environmental impacts of reprocessing and waste management which has either become available since the publication of NUREG-0116 or which adds requested clarification to the information in that document.

1977-03-01T23:59:59.000Z

397

Energy and lighting design  

SciTech Connect

A detailed examination of the current energy conservation practices for lighting systems is presented. This first part of a two-part presentation covers the following: energy and lighting design; lighting and energy standards; lighting efficiency factors; light control and photometrics; lighting and the architectural interior; luminaire impact on the environment; basic design techniques; the lighting power budget; and conservation through control.

Helms, R.N.

1979-11-01T23:59:59.000Z

398

Irradiation Planning for Fully-Ceramic Micro-encsapsulated fuel in ATR at LWR-relevant conditions: year-end report on FY-2011  

SciTech Connect

This report presents the estimation of required ATR irradiation levels for the DB-FCM fuel design (fueled with Pu and MAs). The fuel and assembly designs are those considered in a companion report [R. S. Sen et al., FCR&D-2011- 00037 or INL/EXT-11-23269]. These results, pertaining to the DB-FCM fuel, are definitive in as much as the design of said fuel is definitive. In addition to the work performed, as required, for DB-FCM fuel, work has started in a preliminary fashion on single-cell UO2 and UN fuels. These latter activities go beyond the original charter of this project and although the corresponding work is incomplete, significant progress has been achieved. However, in this context, all that has been achieved is only preliminary because the corresponding fuel designs are neither finalized nor optimized. In particular, the UO2 case is unlikely to result in a viable fuel design if limited to enrichment at or under 20 weight % in U-235. The UN fuel allows reasonable length cycles and is likely to make an optimal design possible. Despite being limited to preliminary designs and offering only preliminary conclusions, the irradiation planning tasks for UO2 and UN fuels that are summarized in this report are useful to the overall goal of devising and deploying FCM-LWR fuel since the methods acquired and tested in this project and the overall procedure for planning will be available for planning tests for the finalized fuel design. Indeed, once the fuel design is finalized and the expected burnup level is determined, the methodology that has been assembled will allow the prompt finalization of the neutronic planning of the irradiation experiment and would provide guidance on the expected experimental performance of the fuel. Deviations from the expected behavior will then have to be analyzed and the outcome of the analysis may be corrections or modifications for the assessment models as well as, possibly, fuel design modifications, and perhaps even variation of experimental control for future experimental phases. Besides the prediction of irradiation times, preliminary work was carried out on other aspects of irradiation planning. In particular, a method for evaluating the interplay of depletion, material performance modeling and irradiation is identified by reference to a companion report. Another area that was addressed in a preliminary fashion is the identification and selection of a strategy for the physical and mechanical design of the irradiation experiments. The principal conclusion is that the similarity between the FCM fuel and the fuel compacts of the Next Generation Nuclear Plant prismatic design are strong enough to warrant using irradiation hardware designs and instrumentation adapted from the AGR irradiation tests. Modifications, if found necessary, will probably be few and small, except as pertains to the water environment and its implications on the use of SiC cladding or SiC matrix with no additional cladding.

Abderrafi M. Ougouag; R. Sonat Sen; Michael A. Pope; Brian Boer

2011-09-01T23:59:59.000Z

399

Light Emitting Diodes and General Lighting  

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

Light Emitting Diodes and General Lighting Speaker(s): Martin Moeck Date: August 6, 2009 - 12:00pm Location: 90-3122 We give a short overview on high-power light emitting diodes,...

400

Steam turbine: Alternative emergency drive for the secure removal of residual heat from the core of light water reactors in ultimate emergency situation  

Science Conference Proceedings (OSTI)

In 2011 the nuclear power generation has suffered an extreme probation. That could be the meaning of what happened in Fukushima Nuclear Power Plants. In those plants, an earthquake of 8.9 on the Richter scale was recorded. The quake intensity was above the trip point of shutting down the plants. Since heat still continued to be generated, the procedure to cooling the reactor was started. One hour after the earthquake, a tsunami rocked the Fukushima shore, degrading all cooling system of plants. Since the earthquake time, the plant had lost external electricity, impacting the pumping working, drive by electric engine. When operable, the BWR plants responded the management of steam. However, the lack of electricity had degraded the plant maneuvers. In this paper we have presented a scheme to use the steam as an alternative drive to maintain operable the cooling system of nuclear power plant. This scheme adds more reliability and robustness to the cooling systems. Additionally, we purposed a solution to the cooling in case of lacking water for the condenser system. In our approach, steam driven turbines substitute electric engines in the ultimate emergency cooling system. (authors)

Souza Dos Santos, R. [Instituto de Engenharia Nuclear CNEN/IEN, Cidade Universitaria, Rua Helio de Almeida, 75 - Ilha do Fundiao, 21945-970 Rio de Janeiro (Brazil); Instituto Nacional de Ciencia e Tecnologia de Reatores Nucleares Inovadores / CNPq (Brazil)

2012-07-01T23:59:59.000Z

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

Evaluation of Lighting and Lighting Control Technologies  

Science Conference Proceedings (OSTI)

Energy efficient lighting and lighting controls have been a means to significant energy savings for many facilities around the world. Advances in lighting sources often allow for the conservation of quality of light while providing more flexibility in the control of light. Additionally, advances in core technologies within the lighting marketplace regularly lead to the introduction of new lamps, fixtures and controls. With the rapid introduction of new products and designs, it is important to ...

2013-11-15T23:59:59.000Z

402

Lighting Group: Controls: PIER Lighting Projects  

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

PIER Lighting Projects CEC Public Interest Energy Research (PIER) Projects Objective Lighting controls are often expensive, complex, hard to commission properly and difficult to...

403

Architectural Lighting Analysis in Virtual Lighting Laboratory  

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

Architectural Lighting Analysis in Virtual Lighting Laboratory NOTICE Due to the current lapse of federal funding, Berkeley Lab websites are accessible, but may not be updated...

404

Alliant Energy Interstate Power and Light (Electric)- Residential Energy Efficiency Rebate Program (Minnesota)  

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

Interstate Power and Light (Alliant Energy) offers a number of energy efficiency rebates for Minnesota residential customers which implement HVAC, lighting, appliance, window, insulation and water...

405

Use of Solid Hydride Fuel for Improved long-Life LWR Core Designs  

Science Conference Proceedings (OSTI)

The primary objective of this project was to assess the feasibility of improving the performance of PWR and BWR cores by using solid hydride fuels instead of the commonly used oxide fuel. The primary measure of performance considered is the bus-bar cost of electricity (COE). Additional performance measures considered are safety, fuel bundle design simplicity in particular for BWRs, and plutonium incineration capability. It was found that hydride fuel can safely operate in PWRs and BWRs without restricting the linear heat generation rate of these reactors relative to that attainable with oxide fuel. A couple of promising applications of hydride fuel in PWRs and BWRs were identified: (1) Eliminating dedicated water moderator volumes in BWR cores thus enabling to significantly increase the cooled fuel rods surface area as well as the coolant flow cross section area in a given volume fuel bundle while significantly reducing the heterogeneity of BWR fuel bundles thus achieving flatter pin-by-pin power distribution. The net result is a possibility to significantly increase the core power density on the order of 30% and, possibly, more, while greatly simplifying the fuel bundle design. Implementation of the above modifications is, though, not straightforward; it requires a design of completely different control system that could probably be implemented only in newly designed plants. It also requires increasing the coolant pressure drop across the core. (2) Recycling plutonium in PWRs more effectively than is possible with oxide fuel by virtue of a couple of unique features of hydride fuel reduced inventory of U-238 and increased inventory of hydrogen. As a result, the hydride fuelled core achieves nearly double the average discharge burnup and the fraction of the loaded Pu it incinerates in one pass is double that of the MOX fuel. The fissile fraction of the Pu in the discharged hydride fuel is only ~2/3 that of the MOX fuel and the discharged hydride fuel is more proliferation resistant. Preliminary feasibility assessment indicates that by replacing some of the ZrH1.6 by ThH2 it will be possible to further improve the plutonium incineration capability of PWRs. Other possibly promising applications of hydride fuel were identified but not evaluated in this work. A number of promising oxide fueled PWR core designs were also found as spin-offs of this study: (1) The optimal oxide fueled PWR core design features smaller fuel rod diameter of D=6.5 mm and a larger pitch-to-diameter ratio of P/D=1.39 than presently practiced by industry 9.5mm and 1.326. This optimal design can provide a 30% increase in the power density and a 24% reduction in the cost of electricity (COE) provided the PWR could be designed to have the coolant pressure drop across the core increased from the reference 29 psia to 60 psia. (2) Using wire wrapped oxide fuel rods in hexagonal fuel assemblies it is possible to design PWR cores to operate at 54% higher power density than the reference PWR design that uses grid spacers and a square lattice, provided 60 psia coolant pressure drop across the core could be accommodated. Uprating existing PWRs to use such cores could result in 40% reduction in the COE. The optimal lattice geometry is D = 8.08 mm and P/D = 1.41. The most notable advantages of wire wraps over grid spacers are their significant lower pressure drop, higher critical heat flux and improved vibrations characteristics.

Greenspan, E

2006-04-30T23:59:59.000Z

406

Next Generation Light Source  

Next Generation Light Source Super Thin Light Bulb, Energy Efficient, Long Life, Dimmable, and Uniform Illumination High Entry Barrier 71 ...

407

Cheyenne Light, Fuel and Power (Electric) - Residential Energy Efficiency  

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

Cheyenne Light, Fuel and Power (Electric) - Residential Energy Cheyenne Light, Fuel and Power (Electric) - Residential Energy Efficiency Rebate Program Cheyenne Light, Fuel and Power (Electric) - Residential Energy Efficiency Rebate Program < Back Eligibility Multi-Family Residential Residential Savings Category Appliances & Electronics Commercial Lighting Lighting Water Heating Program Info State Wyoming Program Type Utility Rebate Program Rebate Amount Home Energy Audit: Contact Cheyenne Light, Fuel and Power CFL Bulbs: Up to 10 CFL bulbs at reduced cost Water Heater: $75 Refrigerator Recycling: $30 Cheyenne Light, Fuel and Power offers incentives to electric customers who wish to install energy efficient equipment in participating homes. Incentives are available for home energy audits, CFL light bulbs, tank water heaters and refrigerator recycling. Water heater purchases and

408

First Light  

E-Print Network (OSTI)

The first dwarf galaxies, which constitute the building blocks of the collapsed objects we find today in the Universe, had formed hundreds of millions of years after the big bang. This pedagogical review describes the early growth of their small-amplitude seed fluctuations from the epoch of inflation through dark matter decoupling and matter-radiation equality, to the final collapse and fragmentation of the dark matter on all mass scales above \\~10^{-4} solar masses. The condensation of baryons into halos in the mass range of ~10^5-10^{10} solar masses led to the formation of the first stars and the re-ionization of the cold hydrogen gas, left over from the big bang. The production of heavy elements by the first stars started the metal enrichment process that eventually led to the formation of rocky planets and life. A wide variety of instruments currently under design [including large-aperture infrared telescopes on the ground or in space (JWST), and low-frequency arrays for the detection of redshifted 21cm radiation], will establish better understanding of the first sources of light during an epoch in cosmic history that was largely unexplored so far. Numerical simulations of reionization are computationally challenging, as they require radiative transfer across large cosmological volumes as well as sufficently high resolution to identify the sources of the ionizing radiation. The technological challenges for observations and the computational challenges for numerical simulations, will motivate intense work in this field over the coming decade.

Abraham Loeb

2006-03-14T23:59:59.000Z

409

Lighting | Department of Energy  

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

Lighting Lighting Lighting When you're shopping for lightbulbs, compare lumens and use the Lighting Facts label to be sure you're getting the amount of light, or level of brightness, you want. You can save money and energy while lighting your home and still maintaining good light quantity and quality. Consider energy-efficient lighting options to use the same amount of light for less money. Learn strategies for comparing and buying lighting products and using them efficiently. Featured Lighting Choices to Save You Money Light your home for less money while using the same amount of light. How Energy-Efficient Light Bulbs Compare with Traditional Incandescents Energy-efficient light bulbs are available today and could save you about $50 per year in energy costs when you replace 15 traditional incandescent bulbs in your home.

410

How plants grow toward light  

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

How plants grow toward light How plants grow toward light Name: schwobtj Location: N/A Country: N/A Date: N/A Question: When a seed is planted below the surface of the ground, how does it "know" to grow toward the light? Replies: Plants don't know where the light is, they do respond to gravity. Since light is usually up, a plant seed grows up and finds light enough to keep things going. Psych One way that plants below ground can tell which way is up is with the use of STATOLITHS. Statoliths are dense pieces of material that settle to the bottom of a STATOCYST. In plants, pieces of starch or another material denser than water will settle to the bottom of the cell. Somehow the plant cell determines on what side the statolith has fallen, and then somehow relays a message (probably a chemical) that tells the bottom cells to grow faster than the top cells, therefore causing upward growth. There is still quite a lot of mystery in there to be discovered. I got this explanation from BIOLOGY by Neil Campbell. This is similar to the way in which plants use chemical signals to help them grow towards light.

411

Waverly Light & Power - Residential Energy Efficiency Rebates...  

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

Rebate Program Rebate Amount Energy Star New Home: 1,300 Heat Pump Water Heater: 500 LED Lighting: 50% of cost, up to 200 Central AC: 150 Air-Source Heat Pump: 150...

412

Material Performance of Fully-Ceramic Micro-Encapsulated Fuel under Selected LWR Design Basis Scenarios: Final Report  

SciTech Connect

The extension to LWRs of the use of Deep-Burn coated particle fuel envisaged for HTRs has been investigated. TRISO coated fuel particles are used in Fully-Ceramic Microencapsulated (FCM) fuel within a SiC matrix rather than the graphite of HTRs. TRISO particles are well characterized for uranium-fueled HTRs. However, operating conditions of LWRs are different from those of HTRs (temperature, neutron energy spectrum, fast fluence levels, power density). Furthermore, the time scales of transient core behavior during accidents are usually much shorter and thus more severe in LWRs. The PASTA code was updated for analysis of stresses in coated particle FCM fuel. The code extensions enable the automatic use of neutronic data (burnup, fast fluence as a function of irradiation time) obtained using the DRAGON neutronics code. An input option for automatic evaluation of temperature rise during anticipated transients was also added. A new thermal model for FCM was incorporated into the code; so-were updated correlations (for pyrocarbon coating layers) suitable to estimating dimensional changes at the high fluence levels attained in LWR DB fuel. Analyses of the FCM fuel using the updated PASTA code under nominal and accident conditions show: (1) Stress levels in SiC-coatings are low for low fission gas release (FGR) fractions of several percent, as based on data of fission gas diffusion in UO{sub 2} kernels. However, the high burnup level of LWR-DB fuel implies that the FGR fraction is more likely to be in the range of 50-100%, similar to Inert Matrix Fuels (IMFs). For this range the predicted stresses and failure fractions of the SiC coating are high for the reference particle design (500 {micro}mm kernel diameter, 100 {micro}mm buffer, 35 {micro}mm IPyC, 35 {micro}mm SiC, 40 {micro}mm OPyC). A conservative case, assuming 100% FGR, 900K fuel temperature and 705 MWd/kg (77% FIMA) fuel burnup, results in a 8.0 x 10{sup -2} failure probability. For a 'best-estimate' FGR fraction of 50% and a more modest burnup target level of 500 MWd/kg ,the failure probability drops below 2.0 x 10{sup -5}, the typical performance of TRISO fuel made under the German HTR research program. An optimization study on particle design shows improved performance if the buffer size is increased from 100 to 120 {micro}mm while reducing the OPyC layer. The presence of the latter layer does not provide much benefit at high burnup levels (and fast fluence levels). Normally the shrinkage of the OPyC would result in a beneficial compressive force on the SiC coating. However, at high fluence levels the shrinkage is expected to turn into swelling, resulting in the opposite effect. However, this situation is different when the SiC-matrix, in which the particles are embedded, is also considered: the OPyC swelling can result in a beneficial compressive force on the SiC coating since outward displacement of the OPyC outer surface is inhibited by the presence of the also-swelling SiC matrix. Taking some credit for this effect by adopting a 5 {micro}mm SiC-matrix layer, the optimized particle (100 {micro}mm buffer and 10 {micro}mm OPyC), gives a failure probability of 1.9 x 10{sup -4} for conservative conditions. During a LOCA transient, assuming core re-flood in 30 seconds, the temperature of the coated particle can be expected to be about 200K higher than nominal temperature (900K). For this event the particle failure fraction for a conservative case is 1.0 x 10{sup -2}, for the optimized particle design. For a FGR-fraction of 50% this value reduces to 6.4 x 10{sup -4}.

B. Boer; R. S. Sen; M. A. Pope; A. M. Ougouag

2011-09-01T23:59:59.000Z

413

Proceedings of the workshop on the impact of hydrogen on water reactor safety. Volume I of IV  

DOE Green Energy (OSTI)

Separate abstracts are presented for each of the papers concerning hydrogen behavior during LWR accidents.

Berman, M. (ed.)

1981-08-01T23:59:59.000Z

414

Architectural Lighting Analysis in Virtual Lighting Laboratory  

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

Architectural Lighting Analysis in Virtual Lighting Laboratory Architectural Lighting Analysis in Virtual Lighting Laboratory Speaker(s): Mehlika Inanici Date: July 7, 2003 - 12:00pm Location: Bldg. 90 Seminar Host/Point of Contact: Satkartar K. Kinney Virtual Lighting Laboratory is a Radiance-based lighting analysis tool and methodology that proposes transformations in the utilization of computer visualization in lighting analysis and design decision-making. It is a computer environment, where the user has been provided with matrices of illuminance and luminance values extracted from high dynamic range images. The principal idea is to provide the laboratory to the designer and researcher to explore various lighting analysis techniques instead of imposing limited number of predetermined metrics. In addition, it introduces an analysis approach for temporal and spatial lighting

415

New Light Sources for Tomorrow's Lighting Designs  

E-Print Network (OSTI)

The lighting industry is driven to provide light sources and lighting systems that, when properly applied, will produce a suitable luminous environment in which to perform a specified task. Tasks may include everything from office work, manufacturing and inspection to viewing priceless art objects, selecting the right chair for your living room, and deciding which produce item to select for tonight's dinner. While energy efficiency is a major consideration in any new lighting system design, the sacrifice of lighting quality may cost more in terms of lost productivity and user dissatisfaction than can ever be saved on that monthly energy bill. During the past several years, many new light sources have been developed and introduced. These product introductions have not been limited to anyone lamp type, but instead may be found in filament, fluorescent and high intensity discharge lamp families. Manufacturers of light sources have two basic goals for new product development. These goals are high efficiency lighting and improved color rendering properties. High efficiency lighting may take the form of either increasing lamp efficiency (lumens of light delivered per watt of power consumed) or decreasing lamp size, thus making a more easily controlled light source that places light where it is needed. The manufacturer's second goal is to produce lamps that render colors accurately while maintaining high efficiency. This paper will discuss new introductions in light sources and lighting systems and how they may impact the design of luminous environments of the future.

Krailo, D. A.

1986-06-01T23:59:59.000Z

416

Enhancing the use of coals by gas reburning-sorbent injection: Volume 4 -- Gas reburning-sorbent injection at Lakeside Unit 7, City Water, Light and Power, Springfield, Illinois. Final report  

Science Conference Proceedings (OSTI)

A demonstration of Gas Reburning-Sorbent Injection (GR-SI) has been completed at a cyclone-fired utility boiler. The Energy and Environmental Research Corporation (EER) has designed, retrofitted and tested a GR-SI system at City Water Light and Power`s 33 MWe Lakeside Station Unit 7. The program goals of 60% NO{sub x} emissions reduction and 50% SO{sub 2} emissions reduction were exceeded over the long-term testing period; the NO{sub x} reduction averaged 63% and the SO{sub 2} reduction averaged 58%. These were achieved with an average gas heat input of 22% and a calcium (sorbent) to sulfur (coal) molar ratio of 1.8. GR-SI resulted in a reduction in thermal efficiency of approximately 1% at full load due to firing natural gas which forms more moisture in flue gas than coal and also results in a slight increase in air heater exit gas temperature. Minor impacts on other areas of unit performance were measured and are detailed in this report. The project at Lakeside was carried out in three phases, in which EER designed the GR-SI system (Phase 1), completed construction and start-up activities (Phase 2), and evaluated its performance with both short parametric tests and a long-term demonstration (Phase 3). This report contains design and technical performance data; the economics data for all sites are presented in Volume 5.

NONE

1996-03-01T23:59:59.000Z

417

Seattle City Light- Residential Energy Efficiency Rebate Program  

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

Seattle City Light provides rebates to residential customers for purchasing and installing clothes washers, refrigerator, heat pump water heaters, and ductless heat pumps. [http://www...

418

Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production, Nuclear Energy Research Initiative Project 2001-001, Westinghouse Electric Co. Grant Number: DE-FG07-02SF22533, Final Report  

SciTech Connect

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% versus 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 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 are also in use around the world. The reference SCWR design for the U.S. program is a direct cycle system operating at 25.0 MPa, with core inlet and outlet temperatures of 280 and 500 C, respectively. The coolant density decreases from about 760 kg/m3 at the core inlet to about 90 kg/m3 at the core outlet. The inlet flow splits with about 10% of the inlet flow going down the space between the core barrel and the reactor pressure vessel (the downcomer) and about 90% of the inlet flow going to the plenum at the top of the rector pressure vessel, to then flow down through the core in special water rods to the inlet plenum. Here it mixes with the feedwater from the downcomer and flows upward to remove the heat in the fuel channels. This strategy is employed to provide good moderation at the top of the core. The coolant is heated to about 500 C and delivered to the turbine. The purpose of this NERI project was to assess the reference U.S. Generation IV SCWR design and explore alternatives to determine feasibility. The project was organized into three tasks: Task 1. Fuel-cycle Neutronic Analysis and Reactor Core Design Task 2. Fuel Cladding and Structural Material Corrosion and Stress Corrosion Cracking Task 3. Plant Engineering and Reactor Safety Analysis. moderator rods. materials.

Philip E. MacDonald

2005-01-01T23:59:59.000Z

419

Light Water Reactor Materials [Irradiation Performance] - Nuclear...  

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

Zircaloy-2 and -4 fuel and cladding have been characterized by the IPS in the Alpha-Gamma Hot-Cell Facility (AGHCF). The high-burnup BWR rod segments were received at Argonne in...

420

Light Water Reactor Sustainability (LWRS) Program | Department...  

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

the research and development (R&D) projects in the following pathways: Materials Aging and Degradation Assessment, Advanced Instrumentation, Information, and Control Systems...

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

Rethinking the light water reactor fuel cycle  

E-Print Network (OSTI)

The once through nuclear fuel cycle adopted by the majority of countries with operating commercial power reactors imposes a number of concerns. The radioactive waste created in the once through nuclear fuel cycle has to ...

Shwageraus, Evgeni, 1973-

2004-01-01T23:59:59.000Z

422

North Branch Municipal Water & Light - Commercial & Industrial...  

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

150 - 400 Dishwashers: 300 - 1,000 Ventilation Hood Controllers: 165HP Low-Flow Spray Valve: 50% of installed cost Southern Minnesota Municipal Power Agency (http:...

423

Azusa Light & Water- Solar Partnership Program  

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

'''''This program is fully subscribed through fiscal year 2012/2013. New applicants will be placed on wait list. Additional funding will be available on July 1, 2013.'''''

424

Lighting Options for Homes.  

SciTech Connect

This report covers many aspects of various lighting options for homes. Types of light sources described include natural light, artificial light, incandescent lamps, fluorescent lamps, and high intensity discharge lamps. A light source selection guide gives the physical characteristics of these, design considerations, and common applications. Color, strategies for efficient lighting, and types of lighting are discussed. There is one section giving tips for various situations in specific rooms. Rooms and types of fixtures are shown on a matrix with watts saved by using the recommended type lighting for that room and room location. A major emphasis of this report is saving energy by utilizing the most suitable, recommended lighting option. (BN)

Baker, W.S.

1991-04-01T23:59:59.000Z

425

Mobile lighting apparatus  

DOE Patents (OSTI)

A mobile lighting apparatus includes a portable frame such as a moveable trailer or skid having a light tower thereon. The light tower is moveable from a stowed position to a deployed position. A hydrogen-powered fuel cell is located on the portable frame to provide electrical power to an array of the energy efficient lights located on the light tower.

Roe, George Michael; Klebanoff, Leonard Elliott; Rea, Gerald W; Drake, Robert A; Johnson, Terry A; Wingert, Steven John; Damberger, Thomas A; Skradski, Thomas J; Radley, Christopher James; Oros, James M; Schuttinger, Paul G; Grupp, David J; Prey, Stephen Carl

2013-05-14T23:59:59.000Z

426

Intercomparison of the finite difference and nodal discrete ordinates and surface flux transport methods for a LWR pool-reactor benchmark problem in X-Y geometry  

Science Conference Proceedings (OSTI)

The aim of the present work is to compare and discuss the three of the most advanced two dimensional transport methods, the finite difference and nodal discrete ordinates and surface flux method, incorporated into the transport codes TWODANT, TWOTRAN-NODAL, MULTIMEDIUM and SURCU. For intercomparison the eigenvalue and the neutron flux distribution are calculated using these codes in the LWR pool reactor benchmark problem. Additionally the results are compared with some results obtained by French collision probability transport codes MARSYAS and TRIDENT. Because the transport solution of this benchmark problem is close to its diffusion solution some results obtained by the finite element diffusion code FINELM and the finite difference diffusion code DIFF-2D are included.

O'Dell, R.D.; Stepanek, J.; Wagner, M.R.

1983-01-01T23:59:59.000Z

427

Geometry-dependent lighting  

E-Print Network (OSTI)

Abstract In this paper we introduce geometrydependent lighting that allows lighting parameters to be defined independently and possibly discrepantly over an object or scene based on the local geometry. We present and discuss Light Collages, a lighting design system with geometry-dependent lights for effective feature-enhanced visualization. Our algorithm segments the objects into local surface patches and places lights that are locally consistent but globally discrepant to enhance the perception of shape. We use spherical harmonics for efficiently storing and computing light placement and assignment. We also outline a method to find the minimal number of light sources sufficient to illuminate an object well with our globally discrepant lighting approach. Index Terms Lighting design, scientific illustration, discrepant lighting, light placement, silhouette enhancement, proximity shadows, spherical harmonics I.

Chang Ha Lee; Xuejun Hao; Amitabh Varshney

2005-01-01T23:59:59.000Z

428

Lighting Group: What's New  

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

What's New What's New in the Lighting Group For more information on what's new in the Lighting Group, please contact: Francis Rubinstein Lighting Group Leader (510) 486-4096...

429

Light in the city  

E-Print Network (OSTI)

This thesis focuses on enhancing the awareness of light for the pedestrian,and using light as a way of revealing the structure of the city and its relation to the cosmos. It proposes that aesthetic qualities of light inform ...

Srinivasan, Kavita, 1976-

2002-01-01T23:59:59.000Z

430

Specific light in sculpture  

E-Print Network (OSTI)

Specific light is defined as light from artificial or altered natural sources. The use and manipulation of light in three dimensional sculptural work is discussed in an historic and contemporary context. The author's work ...

Powell, John William

1989-01-01T23:59:59.000Z

431

Energy_Savings_Light_Emitting_Diodes_Niche_Lighting_Apps.pdf...  

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

EnergySavingsLightEmittingDiodesNicheLightingApps.pdf EnergySavingsLightEmittingDiodesNicheLightingApps.pdf EnergySavingsLightEmittingDiodesNicheLightingApps.p...

432

Prospects for LED lighting.  

SciTech Connect

Solid-state lighting using light-emitting diodes (LEDs) has the potential to reduce energy consumption for lighting by 50% while revolutionizing the way we illuminate our homes, work places, and public spaces. Nevertheless, substantial technical challenges remain in order for solid-state lighting to significantly displace the well-developed conventional lighting technologies. We review the potential of LED solid-state lighting to meet the long-term cost goals.

Tsao, Jeffrey Yeenien; Gee, James Martin; Simmons, Jerry Alvon

2003-08-01T23:59:59.000Z

433

Lighting Control Systems  

Science Conference Proceedings (OSTI)

The demand for lighting control systems in residential, commercial, and industrial facilities is on the rise with the demand for increased energy savings. With lighting accounting for almost 23% of grid load, there is significant opportunity to reduce lighting load while improving the quality of light for customers. Lighting control systems are becoming more intelligent as the need for them to interface with building control systems and demand response systems also increases. Lighting control systems use...

2009-12-17T23:59:59.000Z

434

Composite Lighting Simulations with Lighting Networks  

E-Print Network (OSTI)

A whole variety of different techniques for simulating global illumination in virtual environments have been developed over recent years. Each technique, including Radiosity, Monte-Carlo ray- or photon tracing, and directional-dependent Radiance computations, is best suited for simulating only some special case environments. None of these techniques is currently able to efficiently simulate all important lighting effects in non-trivial scenes. In this paper, we describe a new approach for efficiently combining different global illumination algorithms to yield a composite lighting simulation: Lighting Networks. Lighting Networks can exploit the advantages of each algorithm and can combine them in such a way as to simulate lighting effects that could only be computed at great costs by any single algorithm. Furthermore, this approach allows a user to configure the Lighting Network to compute only specific lighting effects that are important for a given task, while avoiding a costly simulation of the full global illumination in a scene. We show how the light paths computed by a Lighting Network can be described using regular expressions. This mapping allows us to analyze the composite lighting simulation and ensure completeness and redundant-free computations. Several examples demonstrate the advantages and unique lighting effects that can be obtained using this technique. 1

Philipp Slusallek; Marc Stamminger; Wolfgang Heidrich; Jan-Christian Popp; Hans-peter Seidel

1998-01-01T23:59:59.000Z

435

Lighting Group: Links  

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

Links Links Links Organizations Illuminating Engineering Society of North America (IESNA) International Commission on Illumination (CIE) International Association of Lighting Designers (IALD) International Association of Energy-Efficient Lighting Lightfair International Energy Agency - Task 21: Daylight in Buildings: Design Tools and Performance Analysis International Energy Agency - Task 31: Daylighting Buildings in 21st Century National Association on Qualifications for the Lighting Professions (NCQLP) National Association of Independent Lighting Distributors (NAILD) International Association of Lighting Management Companies (NALMCO) Research Centers California Lighting Technology Center Lighting Research Center Lighting Research at Canada Institute for Research in Construction

436

Advanced Demand Responsive Lighting  

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

Demand Demand Responsive Lighting Host: Francis Rubinstein Demand Response Research Center Technical Advisory Group Meeting August 31, 2007 10:30 AM - Noon Meeting Agenda * Introductions (10 minutes) * Main Presentation (~ 1 hour) * Questions, comments from panel (15 minutes) Project History * Lighting Scoping Study (completed January 2007) - Identified potential for energy and demand savings using demand responsive lighting systems - Importance of dimming - New wireless controls technologies * Advanced Demand Responsive Lighting (commenced March 2007) Objectives * Provide up-to-date information on the reliability, predictability of dimmable lighting as a demand resource under realistic operating load conditions * Identify potential negative impacts of DR lighting on lighting quality Potential of Demand Responsive Lighting Control

437

Light Laboratory, Inc.  

Science Conference Proceedings (OSTI)

... 12) Solid State Lighting Luminaires - Color Characteristic Measurements. [22/S04] IES LM-16:1993 Practical Guide to Colorimetry of Light Sources. ...

2013-07-26T23:59:59.000Z

438

Hubbell Lighting Photometric Laboratory  

Science Conference Proceedings (OSTI)

... 12) Solid State Lighting Luminaires - Color Characteristic Measurements. [22/S04] IES LM-16:1993 Practical Guide to Colorimetry of Light Sources. ...

2013-07-26T23:59:59.000Z

439

Energy Efficient Lighting Products  

Science Conference Proceedings (OSTI)

... Road Vista, San Diego, CA [200823- 0] Light Laboratory, Inc ... GA. CSA Group, Alpharetta, GA [200732- 0] Cooper Lighting Photometric Laboratory ...

2013-07-26T23:59:59.000Z

440

Light Metals 2010  

Science Conference Proceedings (OSTI)

Feb 1, 2010 ... Softcover book: Light Metals 2008 Volume 2: Aluminum Reduction. Hardcover book and CD-ROM: Light Metals 2009...

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

Plant and Lighting  

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

publicationshouseplantligh t.html Sincerely, Anthony R. Brach "Artificial" light comes from many kinds of bulbs that emit different wavelengths of light; Many plants...

442

National Synchrotron Light Source  

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

Angle Limit," Phys. Rev. Lett., 99: 134801 (2007). 33 Researchers Produce Firsts with Bursts of Light BNL researchers have generated extremely short pulses of light that are the...

443

Lighting and Daylighting Basics  

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

Buildings can be lit in two ways: by using artificial lighting, or by using daylighting, or the process of using natural sunlight, windows, and skylights to provide lighting.

444

Lighting | Open Energy Information  

Open Energy Info (EERE)

Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon Lighting Jump to: navigation, search TODO: Add description List of Lighting Incentives...

445

Lighting Systems Test Facilities  

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

Measurement equipment with light beam Lighting Systems Test Facilities NOTICE Due to the current lapse of federal funding, Berkeley Lab websites are accessible, but may not be...

446

Lighting and Daylighting  

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

Buildings can be lit in two ways: by using artificial lighting, or by using daylighting, or the process of using natural sunlight, windows, and skylights to provide lighting.

447

Looking For Light.  

E-Print Network (OSTI)

??In my search for the way light can dictate the overall expression of an image, I have found that light is the means that activates (more)

Lindholm, Kevin R.

2010-01-01T23:59:59.000Z

448

LBNL Lighting Research Group  

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

LED and ballast berkeley lamp workstation light switch Overview | What's New | Publications | Software | Facilities | People | Contact Us | Links Sources and Ballasts | Light...

449

Properties of Light  

Science Conference Proceedings (OSTI)

... Scattering of Light. Exploration: Sunset in a glass. ... How would you design a camera that could see through a sand storm? Invisible Light. ...

2012-03-23T23:59:59.000Z

450

Robustness of RISMC Insights under Alternative Aleatory/Epistemic Uncertainty Classifications: Draft Report under the Risk-Informed Safety Margin Characterization (RISMC) Pathway of the DOE Light Water Reactor Sustainability Program  

SciTech Connect

The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, would be founded on probabilistic characterizations of uncertainty in SSC performance. In the context of probabilistic risk assessment (PRA) technology, there has arisen a general consensus about the distinctive roles of two types of uncertainty: aleatory and epistemic, where the former represents irreducible, random variability inherent in a system, whereas the latter represents a state of knowledge uncertainty on the part of the analyst about the system which is, in principle, reducible through further research. While there is often some ambiguity about how any one contributing uncertainty in an analysis should be classified, there has nevertheless emerged a broad consensus on the meanings of these uncertainty types in the PRA setting. However, while RISMC methodology shares some features with conventional PRA, it will nevertheless be a distinctive methodology set. Therefore, the paradigms for classification of uncertainty in the PRA setting may not fully port to the RISMC environment. Yet the notion of risk-informed margin is based on the characterization of uncertainty, and it is therefore critical to establish a common understanding of uncertainty in the RISMC setting.

Unwin, Stephen D.; Eslinger, Paul W.; Johnson, Kenneth I.

2012-09-20T23:59:59.000Z

451

Cree LED Lighting Solutions Formerly LED Lighting Fixtures LLF...  

Open Energy Info (EERE)

Cree LED Lighting Solutions Formerly LED Lighting Fixtures LLF Jump to: navigation, search Name Cree LED Lighting Solutions (Formerly LED Lighting Fixtures (LLF)) Place...

452

Incandescent Lighting | Department of Energy  

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

Incandescent Lighting Incandescent Lighting August 16, 2013 - 10:00am Addthis Incandescent lighting is the most common type of lighting used in homes. Incandescent lamps operate...

453

Solid-State Lighting: Registration  

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

Lighting: Registration on Twitter Bookmark Solid-State Lighting: Registration on Google Bookmark Solid-State Lighting: Registration on Delicious Rank Solid-State Lighting:...

454

Solid-State Lighting: Postings  

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

Solid-State Lighting: Postings on Twitter Bookmark Solid-State Lighting: Postings on Google Bookmark Solid-State Lighting: Postings on Delicious Rank Solid-State Lighting:...

455

Alliant Energy Interstate Power and Light (Electric) - Residential Energy  

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

Alliant Energy Interstate Power and Light (Electric) - Residential Alliant Energy Interstate Power and Light (Electric) - Residential Energy Efficiency Rebate Program (Iowa) Alliant Energy Interstate Power and Light (Electric) - Residential Energy Efficiency Rebate Program (Iowa) < Back Eligibility Multi-Family Residential Residential Savings Category Home Weatherization Commercial Weatherization Heating & Cooling Cooling Commercial Heating & Cooling Appliances & Electronics Other Heat Pumps Commercial Lighting Lighting Water Heating Windows, Doors, & Skylights Program Info State Iowa Program Type Utility Rebate Program Rebate Amount Central Air Conditioners: $100 - $200 Air Source Heat Pumps: $100 - $400 Geothermal Heat Pumps: $300/ton + $50/EER/ton Fan Motors: $50/unit Programmable Thermostats: $25 Tank Water Heater: $50

456

Northern Lights Inc. - Energy Conservation Rebate Program | Department of  

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

Northern Lights Inc. - Energy Conservation Rebate Program Northern Lights Inc. - Energy Conservation Rebate Program Northern Lights Inc. - Energy Conservation Rebate Program < Back Eligibility Commercial Construction Industrial Installer/Contractor Multi-Family Residential Nonprofit Residential Savings Category Appliances & Electronics Heating & Cooling Home Weatherization Construction Commercial Weatherization Commercial Heating & Cooling Design & Remodeling Heat Pumps Commercial Lighting Lighting Water Heating Windows, Doors, & Skylights Program Info State Idaho Program Type Utility Rebate Program Rebate Amount Refrigerator/Freezer: $15 each Clothes Washer: $30 Energy Star Manufactured Home: $1,000 Water Heater: $25 - $100 Window Replacement: $6/sq ft Insulation: Varies Duct Sealing: Free Ductless Heat Pumps: $1,500

457

Lighting Research Group  

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

Lighting Research Group overview what's new publications software facilities people contact us links...

458

Energy and lighting decisions  

SciTech Connect

This report reviews the fundamental principles of lighting and uses them to evaluate energy-conserving lighting equipment and techniques. The selection of the proper lighting components and systems is complex, requiring a knowledge of the characteristics of light sources and their interactions with the auxiliary equipment and the environment. Furthermore, there are subjective aspects of lighting that are difficult to quantify. We address the simplistic way in which lighting is commonly approached, then present an argument as to the critical nature of the lighting decision. In the final sections we discuss and evaluate lighting equipment in terms of its applications and characteristics. Familiarity with the fundamental characteristics of the elements of lighting equipment will also permit more judicious appraisal and use of lighting concepts that may be introduced in the future. 6 figs., 9 tabs.

Verderber, R.R.