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1

Nuclear power generation and fuel cycle report 1996  

SciTech Connect (OSTI)

This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

NONE

1996-10-01T23:59:59.000Z

2

Next Generation Nuclear Plant GAP Analysis Report  

SciTech Connect (OSTI)

As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

2008-12-01T23:59:59.000Z

3

Nuclear power generation and fuel cycle report 1997  

SciTech Connect (OSTI)

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

NONE

1997-09-01T23:59:59.000Z

4

Next Generation Nuclear Plant Project 2009 Status Report  

SciTech Connect (OSTI)

The mission of the NGNP Project is to broaden the environmental and economic benefits of nuclear energy technology to the United States and other economies by demonstrating its applicability to market sectors not served by light water reactors (LWRs). Those markets typically use fossil fuels to fulfill their energy needs, and high temperature gas-cooled reactors (HTGRs) like the NGNP can reduce this dependence and the resulting carbon footprint.

Larry Demick; Jim Kinsey; Keith Perry; Dave Petti

2010-05-01T23:59:59.000Z

5

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Final Report  

SciTech Connect (OSTI)

Final report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Mockups applied to design review of AP600/1000, Construction planning for AP 600, and AP 1000 maintenance evaluation. Proof of concept study also performed for GenIV PBMR models.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

6

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 1: Main Report  

SciTech Connect (OSTI)

A phenomena identification and ranking table (PIRT) process was conducted for the Next Generation Nuclear Plant (NGNP) design. This design (in the conceptual stage) is a modular high-temperature gas-cooled reactor (HTGR) that generates both electricity and process heat for hydrogen production. Expert panels identified safety-relevant phenomena, ranked their importance, and assessed the knowledge levels in the areas of accidents and thermal fluids, fission-product transport and dose, high-temperature materials, graphite, and process heat for hydrogen production. This main report summarizes and documents the process and scope of the reviews, noting the major activities and conclusions. The identified phenomena, analyses, rationales, and associated ratings of the phenomena, plus a summary of each panel's findings, are presented. Individual panel reports for these areas are provided as attached volumes to this main report and provide considerably more detail about each panel's deliberations as well as a more complete listing of the phenomena that were evaluated.

Ball, Sydney J [ORNL

2008-03-01T23:59:59.000Z

7

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report  

SciTech Connect (OSTI)

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

Saurwein, John

2011-07-15T23:59:59.000Z

8

High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August, 2000 - July 2001  

SciTech Connect (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August 2000 - July 2001. Currently no large scale, cost-effective, environmentally attractive hydrogen production process is available for commercialization nor has such a process been identified. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Carbon dioxide emissions from fossil fuel combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. The benefits of this work will include the generation of a low-polluting transportable energy feedstock in an efficient method that has little or no implication for greenhouse gas emissions from a primary energy source whose availability and sources are domestically controlled. This will help to ensure energy for a future transportation/energy infrastructure that is not influenced/controlled by foreign governments. This report describes work accomplished during the second year (Phase 2) of a three year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first year (Phase 1) was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water, in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most, three) for further detailed consideration. Phase 1 met its goals and did select one process, the sulfur-iodine process, for investigation in Phases 2 and 3. The combined goals of Phases 2 and 3 were to select the advanced nuclear reactor best suited to driving the selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

Brown, L.C.

2002-11-01T23:59:59.000Z

9

Site Selection & Characterization Status Report for Next Generation Nuclear Plant (NGNP)  

SciTech Connect (OSTI)

In the near future, the US Department of Energy (DOE) will need to make important decisions regarding design and construction of the Next Generation Nuclear Plant (NGNP). One part of making these decisions is considering the potential environmental impacts that this facility may have, if constructed here at the Idaho National Laboratory (INL). The National Environmental Policy Act (NEPA) of 1969 provides DOE decision makers with a process to systematically consider potential environmental consequences of agency decisions. In addition, the Energy Policy Act of 2005 (Title VI, Subtitel C, Section 644) states that the 'Nuclear Regulatory Commission (NRC) shall have licensing and regulatory authority for any reactor authorized under this subtitle.' This stipulates that the NRC will license the NGNP for operation. The NRC NEPA Regulations (10 CFR Part 51) require tha thte NRC prepare an Environmental Impact Statement (EIS) for a permit to construct a nuclear power plant. The applicant is required to submit an Environmental report (ER) to aid the NRC in complying with NEPA.

Mark Holbrook

2007-09-01T23:59:59.000Z

10

Update report on the performance of 400 megawatt and larger nuclear and coal-fired generating units. Performance through 1977  

SciTech Connect (OSTI)

Forty-seven nuclear generating units and 125 coal-fired generating plants that have had at least one full year of commercial operation are covered in this report. Their performances are evaluated using the capacity factor, availability factor, equivalent availability, and forced outage rate. The data are arranged by state and utility. (DLC)

None

1981-01-01T23:59:59.000Z

11

Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report  

SciTech Connect (OSTI)

On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

Hebdon, F.J. [Institute of Nuclear Power Operations, Atlanta, GA (United States)

1993-03-01T23:59:59.000Z

12

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 5 Report: Generation IV Reactor Virtual Mockup Proof-of-Principle Study  

SciTech Connect (OSTI)

Task 5 report is part of a 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Created a virtual mockup of PBMR reactor cavity and discussed applications of virtual mockup technology to improve Gen IV design review, construction planning, and maintenance planning.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

13

Nuclear Power Generating Facilities (Maine)  

Broader source: Energy.gov [DOE]

The first subchapter of the statute concerning Nuclear Power Generating Facilities provides for direct citizen participation in the decision to construct any nuclear power generating facility in...

14

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 4 Report: Virtual Mockup Maintenance Task Evaluation  

SciTech Connect (OSTI)

Task 4 report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. This report focuses on using Full-scale virtual mockups for nuclear power plant training applications.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

15

Nuclear Energy Research Initiative (NERI): On-Line Intelligent Self-Diagnostic Monitoring for Next Generation Nuclear Plants - Phase I Annual Report  

SciTech Connect (OSTI)

OAK-B135 This OSTI ID belongs to an IWO and is being released out of the system. The Program Manager Rebecca Richardson has confirmed that all reports have been received. The objective of this project is to design and demonstrate the operation of the real-time intelligent self-diagnostic and prognostic system for next generation nuclear power plant systems. This new self-diagnostic technology is titled, ''On-Line Intelligent Self-Diagnostic Monitoring System'' (SDMS). This project provides a proof-of-principle technology demonstration for SDMS on a pilot plant scale service water system, where a distributed array of sensors is integrated with active components and passive structures typical of next generation nuclear power reactor and plant systems. This project employs state-of-the-art sensors, instrumentation, and computer processing to improve the monitoring and assessment of the power reactor system and to provide diagnostic and automated prognostics capabilities.

L. J. Bond; S. R. Doctor; R. W. Gilbert; D. B. Jarrell; F. L. Greitzer; R. J. Meador

2000-09-01T23:59:59.000Z

16

Generation IV Nuclear Energy Systems ...  

E-Print Network [OSTI]

Generation IV Nuclear Energy Systems ... The U.S. Department of Energy's Office of Nuclear Energy enhance safety and security, and develop nuclear power as an energy source for industrial applications Information ... U.S. Department of Energy www.energy.gov DOE Office of Nuclear Energy www.nuclear

Kemner, Ken

17

Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report  

Broader source: Energy.gov [DOE]

The development of advanced nuclear energy systems in the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new...

18

CONSULTANT REPORT DISTRIBUTED GENERATION  

E-Print Network [OSTI]

CONSULTANT REPORT DISTRIBUTED GENERATION INTEGRATION COST STUDY Analytical Framework energy development, or distributed generation, in California. In May 2012, Southern California Edison Southern California Edison's approach to evaluating distributed generation impacts, and to conduct

19

In-Plant Reliability Data base for nuclear plant components. Interim report: diesel generators, batteries, chargers and inverters  

SciTech Connect (OSTI)

The objective of the In-Plant Reliability Data (IPRD) program is to develop a comprehensive, component-specific reliability data base for probabilistic risk assessment and for other statistical analyses relevant to component reliability evaluations. This document is the product of a pilot study that was undertaken to demonstrate the methodology and feasibility of applying IPRDS techniques to develop and analyze the reliability characteristics of key electrical components in five nuclear power plants. These electrical components include diesel generators, batteries, battery chargers and inverters. The sources used to develop the data base and produce the component failure rates and mean repair times were the plant equipment lists, plant drawings, maintenance work requests, Final Safety Analysis Reports (FSARs), and interviews with plant personnel. The data spanned approximately 33 reactor-years of commercial operation.

Kahl, W.K.; Borkowski, R.J.

1985-01-01T23:59:59.000Z

20

Model of sludge behavior in nuclear plant steam generators. Final report  

SciTech Connect (OSTI)

The accumulation of large amounts of sludge in pressurized water reactor steam generators is thought to be a cause of accelerated corrosion by trace impurities which concentrate in such deposits. Based on fundamental principles, this study develops a mathematical model for predicting the behavior (e.g., deposition and reentrainment) of sludge in steam generators. The calculated sludge behavior shows good agreement with the limited amount of experimental data available. The results suggest that the continued accumulation of sludge on the tubesheet might be preventable, and that if it could be, the incoming sludge would be removed by blowdown. An analysis of the uncertainties in the model led to suggested priorities for further analytical and experimental work to gain a better understanding of sludge behavior. 29 refs., 12 figs., 15 tabs.

Beal, S.K.; Chen, J.H.

1986-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Next Generation Nuclear Plant Phenomena  

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

the U.S. Department of Energy (DOE) to develop jointly a licensing strategy for the Next Generation Nuclear plant (NGNP), a very high temperature gas-cooled reactor (VHTR) for...

22

NUCLEAR SCIENCE ANNUAL REPORT 1975  

E-Print Network [OSTI]

Gove and A. H. Wapstra, Nuclear Data Tables 11, 127 (1972).P. Jackson, Chalk River Nuclear Laboratories Report (1975)national Conference on Nuclear Structure and Spec≠ troscopy,

Authors, Various

2010-01-01T23:59:59.000Z

23

[Nuclear theory: Annual report  

SciTech Connect (OSTI)

This report discusses topics on : nuclear structure models; algebraic models of hadronic structure; nuclear reactions; hot rotating nuclei; chaos in nuclei; signatures of the quark-gluon plasma; hadronic spectroscopy; octupole collectivity in nuclei; finite-temperature methods for the many-body problem; and classical limit of algebraic hamiltonians. (LSP)

Iachello, F.; Alhassid, Y.; Kusnezov, D.

1991-12-31T23:59:59.000Z

24

(Nuclear theory: Annual report)  

SciTech Connect (OSTI)

This report discusses topics on : nuclear structure models; algebraic models of hadronic structure; nuclear reactions; hot rotating nuclei; chaos in nuclei; signatures of the quark-gluon plasma; hadronic spectroscopy; octupole collectivity in nuclei; finite-temperature methods for the many-body problem; and classical limit of algebraic hamiltonians. (LSP)

Iachello, F.; Alhassid, Y.; Kusnezov, D.

1991-01-01T23:59:59.000Z

25

Managing nuclear predominant generating capacity  

SciTech Connect (OSTI)

The most common belief, associated with nuclear power plant, leads to the conclusion that it can only operate, as a base load plant. This observation can be reversed, by just looking at large generating capacity, using an important nuclear generation mix. Nuclear plants may certainly load follow and contribute to the grid frequency control. The French example illustrates these possibilities. The reactor control of French units has been customized to accommodate the grid requests. Managing such a large nuclear plant fleet requires various actions be taken, ranging from a daily to a multi-annual perspective. The paper describes the various contributions leading to safe, reliable, well accepted and cost competitive nuclear plants in France. The combination of all aspects related to operations, maintenance scheduling, nuclear safety management, are presented. The use of PWR units carries considerable weight in economic terms, with several hundred million francs tied in with outage scheduling every year. This necessitates a global view of the entire generating system which can be mobilized to meet demand. There is considerable interaction between units as, on the one hand, they are competing to satisfy the same need, and, on the other hand, reducing maintenance costs means sharing the necessary resources, and thus a coordinated staggering of outages. In addition, nuclear fuel is an energy reserve which remains in the reactor for 3 or 4 years, with some of the fuel renewed each year. Due to the memory effect, the fuel retains a memory of past use, so that today's choices impact upon the future. A medium-term view of fuel management is also necessary.

Bouget, Y.H.; Herbin, H.C.; Carbonnier, D.

1998-07-01T23:59:59.000Z

26

The Next Generation Nuclear Plant  

SciTech Connect (OSTI)

The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950įC) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.

Dr. David A. Petti

2009-01-01T23:59:59.000Z

28

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, jA.V.

2010-01-01T23:59:59.000Z

29

Next Generation Nuclear Plant Licensing Strategy  

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

reactor that is based on research and development (R&D) activities supported by the Generation IV Nuclear Energy Systems Initiative and shall be used to generate electricity,...

30

California Nuclear Profile - San Onofre Nuclear Generating Station  

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

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

31

Report to the NRC on guidance for preparing scenarios for emergency preparedness exercises at nuclear generating stations. Draft report for comment  

SciTech Connect (OSTI)

A scenario guidance handbook was prepared to assist emergency planners in developing scenarios for emergency preparedness exercises at nuclear power plants. The handbook provides guidance for the development of the objectives of an exercise, the descriptions of scenario events and responses, and the instructions to the participants. Information concerning implementation of the scenario, critiques and findings, and generation and format of scenario data are also included. Finally, examples of manual calculational techniques for producing radiological data are included as an appendix.

Martin, G.F.; Hickey, E.E.; Moeller, M.P.; Schultz, D.H.; Bethke, G.W.

1986-03-01T23:59:59.000Z

32

Panel report: nuclear physics  

SciTech Connect (OSTI)

Nuclear science is at the very heart of the NNSA program. The energy produced by nuclear processes is central to the NNSA mission, and nuclear reactions are critical in many applications, including National Ignition Facility (NIF) capsules, energy production, weapons, and in global threat reduction. Nuclear reactions are the source of energy in all these applications, and they can also be crucial in understanding and diagnosing the complex high-energy environments integral to the work of the NNSA. Nuclear processes are complex quantum many-body problems. Modeling and simulation of nuclear reactions and their role in applications, coupled tightly with experiments, have played a key role in NNSA's mission. The science input to NNSA program applications has been heavily reliant on experiment combined with extrapolations and physical models 'just good enough' to provide a starting point to extensive engineering that generated a body of empirical information. This body of information lacks the basic science underpinnings necessary to provide reliable extrapolations beyond the domain in which it was produced and for providing quantifiable error bars. Further, the ability to perform additional engineering tests is no longer possible, especially those tests that produce data in the extreme environments that uniquely characterize these applications. The end of testing has required improvements to the predictive capabilities of codes simulating the reactions and associated applications for both well known and well characterized cases as well as incompletely known cases. Developments in high performance computing, computational physics, applied mathematics and nuclear theory have combined to make spectacular advances in the theory of fission, fusion and nuclear reactions. Current research exploits these developments in a number of Office of Science and NNSA programs, and in joint programs such as the SciDAC (Science Discovery through Advanced Computing) that supports the project Building a Universal Nuclear Energy Density Fuctional whose goals are to provide the unified approach to calculating the properties of nuclei. The successful outcome of this, and similar projects is a first steps toward a predictive nuclear theory based on fundamental interactions between constituent nucleons. The application of this theory to the domain of nuclei important for national security missions will require computational resources at the extreme scale, beyond what will be available in the near term future.

Carlson, Joseph A [Los Alamos National Laboratory; Hartouni, Edward P [LLNL

2010-01-01T23:59:59.000Z

33

Next Generation Nuclear Plant Phenomena  

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

Components," Journal of Nuclear Materials, 212-215, 1223 (1994). 13. Arnold, L, Windscale 1957, Anatomy of a Nuclear Accident, St Martin Press, London, 1992. 14....

34

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER FINAL RECHNICAL REPORT FOR THE PERIOD AUGUST 1, 1999 THROUGH SEPTEMBER 30, 2002 REV. 1  

SciTech Connect (OSTI)

OAK-B135 Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy [1-1,1-2]. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties [1-3,1-4]. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.''

BROWN,LC; BESENBRUCH,GE; LENTSCH, RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-12-01T23:59:59.000Z

35

Proceedings of the 2. MIT international conference on the next generation of nuclear power technology. Final report  

SciTech Connect (OSTI)

The goal of the conference was to try to attract a variety of points of view from well-informed people to debate issues concerning nuclear power. Hopefully from that process a better understanding of what one should be doing will emerge. In organizing the conference lessons learned from the previous one were applied. A continuous effort was made to see to it that the arguments for the alternatives to nuclear power were given abundant time for presentation. This is ultimately because nuclear power is going to have to compete with all of the energy technologies. Thus, in discussing energy strategy all of the alternatives must be considered in a reasonable fashion. The structure the conference used has seven sessions. The first six led up to the final session which was concerned with what the future nuclear power strategy should be. Each session focused upon a question concerning the future. None of these questions has a unique correct answer. Rather, topics are addressed where reasonable people can disagree. In order to state some of the important arguments for each session`s question, the combination of a keynote paper followed by a respondent was used. The respondent`s paper is not necessarily included to be a rebuttal to the keynote; but rather, it was recognized that two people will look at a complex question with different shadings. Through those two papers the intention was to get out the most important arguments affecting the question for the session. The purpose of the papers was to set the stage for about an hour of discussion. The real product of this conference was that discussion.

NONE

1993-12-31T23:59:59.000Z

36

Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems - Final Report , Project 99-0280  

SciTech Connect (OSTI)

The discovery of a damage-resistant alloy based on Hf solute additions to a low-carbon 316SS is the highlight of the Phase II research. This damage resistance is supported by characterization of radiation-induced microstructures and microchemistries along with measurements of environmental cracking. The addition of Hf to a low-carbon 316SS reduced the detrimental impact of radiation by changing the distribution of Hf. Pt additions reduced the impact of radiation on grain boundary segregation but did not alter its effect on microstructural damage development or cracking. Because cracking susceptibility is associated with several material characteristics, separate effect experiments exploring strength effects using non-irradiated stainless steels were conducted. These crack growth tests suggest that irradiation strength by itself can promote environmental cracking. The second concept for developing damage resistant alloys is the use of metastable precipitates to stabilize the microstructure during irradiation. Three alloys have been tailored for evaluation of precipitate stability influences on damage evolution. The first alloy is a Ni-base alloy (alloy 718) that has been characterized at low neutron irradiation doses but has not been characterized at high irradiation doses. The other two alloys are Fe-base alloys (PH 17-7 and PH 17-4) that have similar precipitate structures as alloy 718 but is more practical in nuclear structures because of the lower Ni content and hence lesser transmutation to He.

Bruemmer, Stephen M.; Simonen, Edward P.; Gan, Jian; Garner, Francis A.; Gelles, David S.; Edwards, Danny J.; Andresen, Peter L.; Young, Lisa M.; Was, Gary S.; Fournier, L.; Sencer, Bulent H.

2002-12-27T23:59:59.000Z

37

Next Generation Nuclear Plant Phenomena  

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

and passive heat dissipation to withstand design basis events with minimal fuel damage and source term generation. As such, the NGNP places a burden on the designer to...

38

NEXT GENERATION NUCLEAR PLANT PROJECT IMPLEMENTATION STRATEGY  

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

NEXT GENERATION NUCLEAR PLANT PROJECT IMPLEMENTATION STRATEGY Presented by NGNP Industry Alliance November 30, 2009 I In nd du us st tr ry y A Al ll li ia an nc ce e Clean,...

39

The Fourth Generation of Nuclear Power  

SciTech Connect (OSTI)

The outlook for nuclear power in the U.S. is currently very bright. The economics, operations and safety performance of U.S. nuclear power plants is excellent. In addition, both the safety and economic regulation of nuclear power are being changed to produce better economic parameters for future nuclear plant operations and the licenses for plant operations are being extended to 60 years. There is further a growing awareness of the value of clean, emissions-free nuclear power. These parameters combine to form a firm foundation for continued successful U.S. nuclear plant operations, and even the potential In order to realize a bright future for nuclear power, we must respond successfully to five challenges: ē Nuclear power must remain economically competitive, ē The public must remain confident in the safety of the plants and the fuel cycle. ē Nuclear wastes and spent fuel must be managed and the ultimate disposition pathways for nuclear wastes must be politically settled. ē The proliferation potential of the commercial nuclear fuel cycle must continue to be minimized, and ē We must assure a sustained manpower supply for the future and preserve the critical nuclear technology infrastructure. The Generation IV program is conceived to focus the efforts of the international nuclear community on responding to these challenges.

Lake, James Alan

2000-11-01T23:59:59.000Z

40

Reporting of Nuclear Incidents (Connecticut)  

Broader source: Energy.gov [DOE]

Each operator of a nuclear power generating facility shall notify the Commissioner of Environmental Protection or his designee, which may be another State Agency, as soon as possible but in all...

Note: This page contains sample records for the topic "nuclear generation reported" 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

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]

IMPACTS OF FOSSIL-FUEL NUCLEAR, GEOTHERMAL, AND ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, A.V.

2010-01-01T23:59:59.000Z

42

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, A.V.

2010-01-01T23:59:59.000Z

43

A REVIEW OF AIR QUALITY MODELING TECHNIQUES. VOLUME 8 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Rosen, L.C.

2010-01-01T23:59:59.000Z

44

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

E-Print Network [OSTI]

Charges Relating to Nuclear Reactor Safety," 1976, availableissues impor tant to nuclear reactor safety. This report wasstudies of overall nuclear reactor safety have been

Nero, A.V.

2010-01-01T23:59:59.000Z

45

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]

for sabotage of nuclear plants or the potential forAccidents in Large Nuclear Plants" (AEC Report, WASH-/40),YEAR FROM POTENTIAL NUCLEAR PLANT ACCIDENTS(a) Consequence

Nero, A.V.

2010-01-01T23:59:59.000Z

46

Nuclear Energy Research Initiative (NERI): Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems - Technical Progress Report August 2000 - October 2000  

SciTech Connect (OSTI)

OAK-B135 This ID belongs to an IWO and is being released out of the system. The Program manager Rebecca Richardson has confirmed that all reports have been received. The objective of the proposed research is to develop the scientific basis for a new class of radiation-resistant materials. Two approaches will be evaluated to develop damage resistant materials far superior to current stainless steels: (1) lattice perturbation to catalyze defect recombination within the early stages of cascade formation and defect migration and (2) controlled manipulation of the aggregate defect ensemble through the deliberate introduction of dynamic metastable microstructures. The intrinsic ability of the host matrix to resist displacement damage survival will be optimized in first concept. This approach (Task 1) explores baseline atomic displacement and recovery processes as affected by major and minor alloy constituents selected for the dual purpose of environmental cracking resistance as well as interactions with point defects. Inert oversized solutes known to improve corrosion behavior will be used to create vacancy/interstitial traps and promote defect recombination. Dynamic metastable microstructures tailored to resist damage accumulation will be investigated and optimized in the second concept (Task 2). Unique intermetallic second phases with inherent instabilities under irradiation will be used to create a dynamic microstructure resistant to radiation hardening, swelling and embrittlement. A key aspect of designing this dynamic microstructure will be to ensure the complex, radiation-induced changes do not promote environmental cracking. The underlying radiation materials science for these two approaches is being explored using charged particle irradiations. Radiation damage resistance will be established by isolating the effect of each approach on defect microstructure, grain boundary microchemistries and matrix hardening. The dose dependence of these radiation-induced material changes will be used to identify promising alloys and initial microstructure that effectively delay or eliminate detrimental microstructural and microchemical evolution. Environmental cracking response is being established on non-irradiated alloys with thermomechanical treatments to simulate radiation microstructures and by tests on proton-irradiated specimens. The ultimate goal for these alloys will be resistance to environmental cracking, swelling and embrittlement during the high radiation exposures (>150 dpa) planned for advanced reactors.

None

2000-09-01T23:59:59.000Z

47

Steam Generator Group Project. Annual report, 1982  

SciTech Connect (OSTI)

The Steam Generator Group Project (SGGP) is an NRC program joined by additional sponsors. The SGGP utilizes a steam generator removed from service at a nuclear plant (Surry 2) as a vehicle for research on a variety of safety and reliability issues. This report is an annual summary of progress of the program for 1982. Information is presented on the Steam Generator Examination Facility (SGEF), especially designed and constructed for this research. Loading of the generator into the SGEF is then discussed. The report then presents radiological field mapping results and personnel exposure monitoring. This is followed by information on field reduction achieved by channel head decontaminations. The report then presents results of a secondary side examination through shell penetrations placed prior to transport, confirming no change in generator condition due to transport. Decontamination of the channel head is discussed followed by plans for eddy current testing and removal of the plugs placed during service. Results of a preliminary profilometry examination are then provided.

Clark, R.A.; Lewis, M.

1984-02-01T23:59:59.000Z

48

Independent Activity Report, Defense Nuclear Facilities Safety...  

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

Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October...

49

Generation IV Advanced Nuclear Energy Systems By Jacques Bouchard...  

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

Generation IV Advanced Nuclear Energy Systems By Jacques Bouchard, French Commissariat a l'Energie Atomique, France and Ralph Bennett, Idaho National Laboratory. Generation IV...

50

Nuclear Engineering Student Learning Outcome Assessment Report  

E-Print Network [OSTI]

1 Nuclear Engineering Student Learning Outcome Assessment Report 1. Program mission The Nuclear and graduate education to tomorrow's leaders in nuclear engineering. The program provides well-educated nuclear engineering professionals and leaders to Missouri and the nation in the commercial nuclear industry, national

Missouri-Rolla, University of

52

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSINGEmergency Planning for Nuclear Power Plants Determination ofproposed nuclear power plants . . . . . . . . . ē . . . .

Yen, W.W.S.

2010-01-01T23:59:59.000Z

53

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

and Related Standards for Fossil-Fuel and Geo- thermal Powerposed Nuclear, Geothermal, and Fossil-Fuel Sites and Facili-NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN

Nero, A.V.

2010-01-01T23:59:59.000Z

54

NUCLEAR CHEMISTRY ANNUAL REPORT 1970  

E-Print Network [OSTI]

Nuclear Laboratories, AECL, Chalk River, Ontario, Canada.Nuclear Laboratories, AECL, Chalk River, Ontario, Canada. 1.Nuclear Laboratories, AECL, Chalk River, Ontario, Canada. 1.

Authors, Various

2011-01-01T23:59:59.000Z

55

Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

Nathan V. Hoffer; Piyush Sabharwall; Nolan A. Anderson

2011-01-01T23:59:59.000Z

56

The Next Generation Nuclear Plant (NGNP) Project  

SciTech Connect (OSTI)

The Next Generation Nuclear Power (NGNP) Project will demonstrate emissions-free nuclearassisted electricity and hydrogen production by 2015. The NGNP reactor will be a helium-cooled, graphite moderated, thermal neutron spectrum reactor with a design goal outlet temperature of 1000 C or higher. The reactor thermal power and core configuration will be designed to assure passive decay heat removal without fuel damage during hypothetical accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. This paper provides a description of the project to build the NGNP at the Idaho National Engineering and Environmental Laboratory (INEEL). The NGNP Project includes an overall reactor design activity and four major supporting activities: materials selection and qualification, NRC licensing and regulatory support, fuel development and qualification, and the hydrogen production plant. Each of these activities is discussed in the paper. All the reactor design and construction activities will be managed under the DOEís project management system as outlined in DOE Order 413.3. The key elements of the overall project management system discussed in this paper include the client and project management organization relationship, critical decisions (CDs), acquisition strategy, and the project logic and timeline. The major activities associated with the materials program include development of a plan for managing the selection and qualification of all component materials required for the NGNP; identification of specific materials alternatives for each system component; evaluation of the needed testing, code work, and analysis required to qualify each identified material; preliminary selection of component materials; irradiation of needed sample materials; physical, mechanical, and chemical testing of unirradiated and irradiated materials; and documentation of final materials selections. The NGNP will be licensed by the NRC under 10 CFR 50 or 10 CFR 52, for the purpose of demonstrating the suitability of high-temperature gas-cooled reactors for commercial electric power and hydrogen production. Products that will support the licensing of the NGNP include the environmental impact statement, the preliminary safety analysis report, the NRC construction permit, the final safety analysis report, and the NRC operating license. The fuel development and qualification program consists of five elements: development of improved fuel manufacturing technologies, fuel and materials irradiations, safety testing and post-irradiation examinations, fuel performance modeling, and fission product transport and source term modeling. Two basic approaches will be explored for using the heat from the high-temperature helium coolant to produce hydrogen. The first technology of interest is the thermochemical splitting of water into hydrogen and oxygen. The most promising processes for thermochemical splitting of water are sulfur-based and include the sulfur-iodine, hybrid sulfur-electrolysis, and sulfur-bromine processes. The second technology of interest is thermally assisted electrolysis of water. The efficiency of this process can be substantially improved by heating the water to high-temperature steam before applying electrolysis.

F. H. Southworth; P. E. MacDonald

2003-11-01T23:59:59.000Z

57

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

S. Commercial Nuclear Power Plants. WASH-1400. October 1975.Content of for Nuclear Power Plants. Regulatory Guide 1.101.PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSING PROCESS

Yen, W.W.S.

2010-01-01T23:59:59.000Z

58

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

from the Rancho Seco nuclear plant was simulated, A total ofdistributions around the nuclear plant sites based on thegrowth surrounding nuclear plants after the issuance of the

Yen, W.W.S.

2010-01-01T23:59:59.000Z

59

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

surrounding a nuclear plant, and they are stronglylocation for a nuclear plant, but it is the measures thatand consequences of nuclear plant accidents and would match

Nero, jA.V.

2010-01-01T23:59:59.000Z

60

Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana)  

Broader source: Energy.gov [DOE]

The Incentive Cost Recovery Rule for Nuclear Power Generation establishes guidelines for any utility seeking to develop a nuclear power plant in Louisiana. The rule clarifies, as well as...

Note: This page contains sample records for the topic "nuclear generation reported" 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

NUCLEAR CHEMISTRY ANNUAL REPORT 1970  

E-Print Network [OSTI]

Letters 24, 1507 (1970); Nuclear Data B4, 663 (1970). 5. R.S. Hager and E. C. Seltzer, Nuclear Data A4, 1 (1968). 6. H.J. Nijgh, and R. Van Lieshout, Nuclear Spectroscopy Tables (

Authors, Various

2011-01-01T23:59:59.000Z

62

Power generation from nuclear reactors in aerospace applications  

SciTech Connect (OSTI)

Power generation in nuclear powerplants in space is addressed. In particular, the states of technology of the principal competitive concepts for power generation are assessed. The possible impact of power conditioning on power generation is also discussed. For aircraft nuclear propulsion, the suitability of various technologies is cursorily assessed for flight in the Earth's atmosphere. A program path is suggested to ease the conditions of first use of aircraft nuclear propulsion.

English, R.E.

1982-01-01T23:59:59.000Z

63

Final Technical Report; NUCLEAR ENGINEERING RECRUITMENT EFFORT  

SciTech Connect (OSTI)

This report provides the summary of a project whose purpose was to support the costs of developing a nuclear engineering awareness program, an instruction program for teachers to integrate lessons on nuclear science and technology into their existing curricula, and web sites for the exchange of nuclear engineering career information and classroom materials. The specific objectives of the program were as follows: OBJECTIVE 1: INCREASE AWARENESS AND INTEREST OF NUCLEAR ENGINEERING; OBJECTIVE 2: INSTRUCT TEACHERS ON NUCLEAR TOPICS; OBJECTIVE 3: NUCLEAR EDUCATION PROGRAMS WEB-SITE; OBJECTIVE 4: SUPPORT TO UNIVERSITY/INDUSTRY MATCHING GRANTS AND REACTOR SHARING; OBJECTIVE 5: PILOT PROJECT; OBJECTIVE 6: NUCLEAR ENGINEERING ENROLLMENT SURVEY AT UNIVERSITIES

Kerrick, Sharon S.; Vincent, Charles D.

2007-07-02T23:59:59.000Z

64

Monthly Nuclear Utility Generation by State and Reactor, 2007  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2007" "January through December 2007"...

65

Monthly Nuclear Utility Generation by State and Reactor, 2004  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2004" "January through December 2004"...

66

Monthly Nuclear Utility Generation by State and Reactor, 2005  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2005" "January through December 2005"...

67

Monthly Nuclear Utility Generation by State and Reactor, 2003  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2003" "January through December 2003"...

68

Monthly Nuclear Utility Generation by State and Reactor, 2008  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2008" "January through December 2008"...

69

JPRS report: Nuclear developments, [March 14, 1988  

SciTech Connect (OSTI)

This report contains information concerning the nuclear developments of the following countries: Libya, India, Pakistan, Soviet Union, Austria, Federal Republic of Germany, and Finland.

NONE

1988-03-14T23:59:59.000Z

70

Independent Oversight Activity Report, National Nuclear Security...  

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

10-14, 2014 Contractor Transition Activities for the National Nuclear Security Administration Production Office IAR-NPO-2014-03-10 This Independent Activity Report documents an...

71

Generating Reports & Graphs in Portfolio Manager  

Broader source: Energy.gov [DOE]

This presentation, given through the DOE's Technical Assitance Program (TAP), provides information on how to generate reports and graphs in Portfolio Manager.

72

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, jA.V.

2010-01-01T23:59:59.000Z

73

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.

Nero, jA.V.

2010-01-01T23:59:59.000Z

74

Salt disposal of heat-generating nuclear waste.  

SciTech Connect (OSTI)

This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

2011-01-01T23:59:59.000Z

75

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

2004-06-01T23:59:59.000Z

76

C Produced by Nuclear Power Reactors Generation and Characterization of  

E-Print Network [OSTI]

14 C Produced by Nuclear Power Reactors ¬≠ Generation and Characterization of Gaseous, Liquid and process water from nuclear reactors ¬≠ A method for quantitative determination of organic and inorganic and Solid Waste √?sa Magnusson Division of Nuclear Physics Department of Physics 2007 Akademisk avhandling

Haviland, David

77

Report on Distributed Generation Penetration Study  

SciTech Connect (OSTI)

This report documents part of a multiyear research program dedicated to the development of requirements to support the definition, design, and demonstration of a distributed generation-electric power system interconnection interface concept. The report focuses on the dynamic behavior of power systems when a significant portion of the total energy resource is distributed generation. It also focuses on the near-term reality that the majority of new DG relies on rotating synchronous generators for energy conversion.

Miller, N.; Ye, Z.

2003-08-01T23:59:59.000Z

78

Kansas Nuclear Profile - Wolf Creek Generating Station  

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

April 2012" "Next Release Date: February 2013" "Wolf Creek Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor...

79

Washington Nuclear Profile - Columbia Generating Station  

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

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

80

Illinois Nuclear Profile - Dresden Generating Station  

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

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

Note: This page contains sample records for the topic "nuclear generation reported" 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

Illinois Nuclear Profile - Byron Generating Station  

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

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

82

Illinois Nuclear Profile - Braidwood Generation Station  

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

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

83

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect (OSTI)

Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

Lynne M. Stevens

2010-07-01T23:59:59.000Z

84

Theoretical studies in nuclear reactions and nuclear structure. Progress report  

SciTech Connect (OSTI)

Research in the Maryland Nuclear Theory Group focusses on problems in four basic areas of current relevance. Hadrons in nuclear matter; the structure of hadrons; relativistic nuclear physics and heavy ion dynamics and related processes. The section on hadrons in nuclear matter groups together research items which are aimed at exploring ways in which the properties of nucleons and the mesons which play a role in the nuclear force are modified in the nuclear medium. A very interesting result has been the finding that QCD sum rules supply a new insight into the decrease of the nucleon`s mass in the nuclear medium. The quark condensate, which characterizes spontaneous chiral symmetry breaking of the late QCD vacuum, decreases in nuclear matter and this is responsible for the decrease of the nucleon`s mass. The section on the structure of hadrons contains progress reports on our research aimed at understanding the structure of the nucleon. Widely different approaches are being studied, e.g., lattice gauge calculations, QCD sum rules, quark-meson models with confinement and other hedgehog models. A major goal of this type of research is to develop appropriate links between nuclear physics and QCD. The section on relativistic nuclear physics represents our continuing interest in developing an appropriate relativistic framework for nuclear dynamics. A Lorentz-invariant description of the nuclear force suggests a similar decrease of the nucleon`s mass in the nuclear medium as has been found from QCD sum rules. Work in progress extends previous successes in elastic scattering to inelastic scattering of protons by nuclei. The section on heavy ion dynamics and related processes reports on research into the e{sup +}e{sup {minus}} problem and heavy ion dynamics.

Not Available

1992-05-01T23:59:59.000Z

85

Reports to the DOE Nuclear Data Committee  

SciTech Connect (OSTI)

The report in this document were submitted to the Department of Energy, Nuclear Data Committee (DOE-NDC) in April 1988. The reporting laboratories are those with a substantial program for the measurement of neutron and nuclear cross sections of relevance to the US applied nuclear energy program. Appropriate subjects are microscopic neutron cross sections relevant to the nuclear energy program, including shielding. Inverse reactions where pertinent are included; charged-particle cross sections where relevant to developing and testing nuclear models; gamma ray production, radioactive decay, and theoretical developments in nuclear structure which are applicable to nuclear energy programs; and proton and alpha-particle cross sections, at energies of up to 1 GeV, which are of interest to the space program.

Not Available

1988-05-01T23:59:59.000Z

86

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER  

SciTech Connect (OSTI)

OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could benefit, in terms of efficien

BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-06-01T23:59:59.000Z

87

Nuclear Safety Research and Development Annual Report, December...  

Energy Savers [EERE]

Nuclear Safety Research and Development Annual Report, December 2014 Nuclear Safety Research and Development Annual Report, December 2014 December 8, 2014 This document is the...

88

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network [OSTI]

sector projects, and recently elevated to Best Practice status. However, its current format is inadequate to address the unique challenges of constructing the next generation of nuclear power plants (NPP). To understand and determine the risks...

Yeon, Jaeheum 1981-

2012-12-11T23:59:59.000Z

89

Fourth Generation Nuclear Weapons: Military effectiveness and collateral effects  

E-Print Network [OSTI]

The paper begins with a general introduction and update to Fourth Generation Nuclear Weapons (FGNW), and then addresses some particularly important military aspects on which there has been only limited public discussion so far. These aspects concern the unique military characteristics of FGNWs which make them radically different from both nuclear weapons based on previous-generation nuclear-explosives and from conventional weapons based on chemical-explosives: yields in the 1 to 100 tons range, greatly enhanced coupling to targets, possibility to drive powerful shaped charged jets and forged fragments, enhanced prompt radiation effects, reduced collateral damage and residual radioactivity, etc.

Gsponer, A

2005-01-01T23:59:59.000Z

90

Nuclear spectroscopic studies. Progress report  

SciTech Connect (OSTI)

The Nuclear Physics group at the University of Tennessee, Knoxville is involved in several aspects of heavy-ion physics including both nuclear structure and reaction mechanisms. While our main emphasis is on experimental problems involving heavy-ion accelerators, we have maintained a strong collaboration with several theorists in order to best pursue the physics of our measurements. During the last year we have led several experiments at the Holifield Heavy Ion Research Facility and participated in others at Argonne National Laboratory. Also, we continue to be very active in the collaboration to study ultra-relativistic heavy ion physics utilizing the SPS accelerator at CERN in Geneva, Switzerland and in a RHIC detector R&D project. Our experimental work is in four broad areas: (1) the structure of nuclei at high angular momentum, (2) heavy-ion induced transfer reactions, (3) the structure of nuclei far from stability, and (4) ultra-relativistic heavy-ion physics. The results of studies in these particular areas will be described in this document in sections IIA, IIB, IIC, and IID, respectively. Areas (1), (3), and (4) concentrate on the structure of nuclear matter in extreme conditions of rotational motion, imbalance of neutrons and protons, or very high temperature and density. Area (2) pursues the transfer of nucleons to states with high angular momentum, both to learn about their structure and to understand the transfer of particles, energy, and angular momentum in collisions between heavy ions. An important component of our program is the strong emphasis on the theoretical aspects of nuclear structure and reactions.

Bingham, C.R.; Guidry, M.W.; Riedinger, L.L.; Sorensen, S.P.

1993-02-08T23:59:59.000Z

91

Method and apparatus for generating low energy nuclear particles  

DOE Patents [OSTI]

A particle accelerator (12) generates an input particle beam having an initial energy level above a threshold for generating secondary nuclear particles. A thin target (14) is rotated in the path of the input beam for undergoing nuclear reactions to generate the secondary particles and correspondingly decrease energy of the input beam to about the threshold. The target (14) produces low energy secondary particles and is effectively cooled by radiation and conduction. A neutron scatterer (44) and a neutron filter (42) are also used for preferentially degrading the secondary particles into a lower energy range if desired.

Powell, James R. (Shoreham, NY); Reich, Morris (Flushing, NY); Ludewig, Hans (Brookhaven, NY); Todosow, Michael (Miller Place, NY)

1999-02-09T23:59:59.000Z

92

Method and apparatus for generating low energy nuclear particles  

DOE Patents [OSTI]

A particle accelerator generates an input particle beam having an initial energy level above a threshold for generating secondary nuclear particles. A thin target is rotated in the path of the input beam for undergoing nuclear reactions to generate the secondary particles and correspondingly decrease energy of the input beam to about the threshold. The target produces low energy secondary particles and is effectively cooled by radiation and conduction. A neutron scatterer and a neutron filter are also used for preferentially degrading the secondary particles into a lower energy range if desired. 18 figs.

Powell, J.R.; Reich, M.; Ludewig, H.; Todosow, M.

1999-02-09T23:59:59.000Z

93

An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems  

SciTech Connect (OSTI)

The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated ďtoolkitĒ consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

Timothy J. Leahy

2010-06-01T23:59:59.000Z

94

U.S. Nuclear Generation of Electricity  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sector Transportation EnergyGlossary API5382009 2010Nuclear

95

THE BIRTH OF NUCLEAR-GENERATED ELECTRICITY  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystallineForeign Object DamageSystemsU.S. TALKS1 | ETHANKSGIVINGBIRTH

96

Report to the DOE Nuclear Data Committee, 1989  

SciTech Connect (OSTI)

This report contains short papers on nuclear data measurements, calculations, and evaluations. (LSP)

Struble, G.L.; White, R.M.; Resler, D.A.

1989-02-01T23:59:59.000Z

97

Theoretical nuclear structure. Progress report for 1997  

SciTech Connect (OSTI)

This research effort is directed toward theoretical support and guidance for the fields of radioactive ion beam physics, gamma-ray spectroscopy, and the interface between nuclear structure and nuclear astrophysics. The authors report substantial progress in all these areas. One measure of progress is publications and invited material. The research described here has led to more than 25 papers that are published, accepted, or submitted to refereed journals, and to 25 invited presentations at conferences and workshops.

Nazarewicz, W.; Strayer, M.R.

1997-12-31T23:59:59.000Z

98

Methane generation at Grand Gulf Nuclear Station  

SciTech Connect (OSTI)

The methane generation at Grand Gulf has been brought to light twice. The initial event occurred in February 1990 and the second in December 1993. Both events involved the receipt of a cask at Barnwell Waste Management Facility that when opened indicated a gas escaping. The gas was subsequently sampled and indicated a percentage of explosive gas. Both events involved powdered resin and indicated that the generation was from a bacterial attack of the organic materials (cellulose in the powdered resin mixture). The first event occurred and was believed to be isolated in a particular waste stream. The situation was handled and a biocide was found to be effective in treatment of liners until severe cross contamination of another waste stream occurred. This allowed the shipment of a liner that was required to be sampled for explosive gases. The biocide used by GGNS was allowed reintroduction into the floor drains and this allowed the buildup of immunity of the bacterial population to this particular biocide. The approval of a new biocide has currently allowed GGNS to treat liners and ship them offsite.

Carver, M.L. [Entergy Operations, Inc., Grand Gulf Nuclear Station, Port Gibson, MS (United States)

1995-09-01T23:59:59.000Z

99

ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS  

SciTech Connect (OSTI)

Rising global energy demands coupled with increased environmental concerns point to one solution; they must reduce their dependence on fossil fuels that emit greenhouse gases. As the global community faces the challenge of maintaining sovereign nation security, reducing greenhouse gases, and addressing climate change nuclear power will play a significant and likely growing role. In the US, nuclear energy already provides approximately one-fifth of the electricity used to power factories, offices, homes, and schools with 104 operating nuclear power plants, located at 65 sites in 31 states. Additionally, 19 utilities have applied to the US Nuclear Regulatory Commission (NRC) for construction and operating licenses for 26 new reactors at 17 sites. This planned growth of nuclear power is occurring worldwide and has been termed the 'nuclear renaissance.' As major industrial nations craft their energy future, there are several important factors that must be considered about nuclear energy: (1) it has been proven over the last 40 years to be safe, reliable and affordable (good for Economic Security); (2) its technology and fuel can be domestically produced or obtained from allied nations (good for Energy Security); and (3) it is nearly free of greenhouse gas emissions (good for Environmental Security). Already an important part of worldwide energy security via electricity generation, nuclear energy can also potentially play an important role in industrial processes and supporting the nation's transportation sector. Coal-to-liquid processes, the generation of hydrogen and supporting the growing potential for a greatly increased electric transportation system (i.e. cars and trains) mean that nuclear energy could see dramatic growth in the near future as we seek to meet our growing demand for energy in cleaner, more secure ways. In order to address some of the prominent issues associated with nuclear power generation (i.e., high capital costs, waste management, and proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

Marra, J.

2010-09-29T23:59:59.000Z

100

Safety Reports Series No. 11, Developing Safety Culture in Nuclear...  

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

in Nuclear Activities: Practical Suggestions to Assist Progress, International Atomic Energy Agency Safety Reports Series No. 11, Developing Safety Culture in Nuclear Activities:...

Note: This page contains sample records for the topic "nuclear generation reported" 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

Report to the DOE Nuclear Data Committee, 1982  

SciTech Connect (OSTI)

The report includes summaries of measurements and calculations of nuclear data applications, and use of nuclear data for reactor safety. (GHT)

Haght, R.C.; Struble, G.L.

1982-03-01T23:59:59.000Z

102

Coal based electric generation comparative technologies report  

SciTech Connect (OSTI)

Ohio Clean Fuels, Inc., (OCF) has licensed technology that involves Co-Processing (Co-Pro) poor grade (high sulfur) coal and residual oil feedstocks to produce clean liquid fuels on a commercial scale. Stone Webster is requested to perform a comparative technologies report for grassroot plants utilizing coal as a base fuel. In the case of Co-Processing technology the plant considered is the nth plant in a series of applications. This report presents the results of an economic comparison of this technology with other power generation technologies that use coal. Technologies evaluated were:Co-Processing integrated with simple cycle combustion turbine generators, (CSC); Co-Processing integrated with combined cycle combustion turbine generators, (CCC); pulverized coal-fired boiler with flue gas desulfurization and steam turbine generator, (PC) and Circulating fluidized bed boiler and steam turbine generator, (CFB). Conceptual designs were developed. Designs were based on approximately equivalent net electrical output for each technology. A base case of 310 MWe net for each technology was established. Sensitivity analyses at other net electrical output sizes varying from 220 MWe's to 1770 MWe's were also performed. 4 figs., 9 tabs.

Not Available

1989-10-26T23:59:59.000Z

103

Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect  

E-Print Network [OSTI]

Mallants, D. , 2002. Gas generation and migration in Boomof Post-Disposal Gas Generation in a Repository for SpentCorrosion-Induced Gas Generation in a Nuclear Waste

Xu, T.

2009-01-01T23:59:59.000Z

104

Potential growth of nuclear and coal electricity generation in the US  

SciTech Connect (OSTI)

Electricity demand should continue to grow at about the same rate as GNP, creating a need for large amounts of new generating capacity over the next fifty years. Only coal and nuclear at this time have the abundant domestic resources and assured technology to meet this need. However, large increase in both coal and nuclear usage will require solutions to many of the problems that now deter their increased usage. For coal, the problems center around the safety and environmental impacts of increased coal mining and coal combustion. For nuclear, the problems center around reactor safety, radioactive waste disposal, financial risk, and nuclear materials safeguards. This report assesses the impacts associated with a range of projected growth rates in electricity demand over the next 50 years. The resource requirements and waste generation resulting from pursuing the coal and nuclear fuel options to meet the projected growth rates are estimated. The fuel requirements and waste generation for coal plants are orders of magnitude greater than for nuclear. Improvements in technology and waste management practices must be pursued to mitigate environmental and safety concerns about electricity generation from both options. 34 refs., 18 figs., 14 tabs.

Bloomster, C.H.; Merrill, E.T.

1989-08-01T23:59:59.000Z

105

New Generation Nuclear Plant -- High Level Functions and Requirements  

SciTech Connect (OSTI)

This functions and requirements (F&R) document was prepared for the Next Generation Nuclear Plant (NGNP) Project. The highest-level functions and requirements for the NGNP preconceptual design are identified in this document, which establishes performance definitions for what the NGNP will achieve. NGNP designs will be developed based on these requirements by commercial vendor(s).

J. M. Ryskamp; E. J. Gorski; E. A. Harvego; S. T. Khericha; G. A. Beitel

2003-09-01T23:59:59.000Z

106

Hydrogen Production from the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

The Next Generation Nuclear Plant (NGNP) is a high temperature gas-cooled reactor that will be capable of producing hydrogen, electricity and/or high temperature process heat for industrial use. The project has initiated the conceptual design phase and when completed will demonstrate the viability of hydrogen generation using nuclear produced process heat. This paper explains how industry and the U.S. Government are cooperating to advance nuclear hydrogen technology. It also describes the issues being explored and the results of recent R&D including materials development and testing, thermal-fluids research, and systems analysis. The paper also describes the hydrogen production technologies being considered (including various thermochemical processes and high-temperature electrolysis).

M. Patterson; C. Park

2008-03-01T23:59:59.000Z

107

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect (OSTI)

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

G.O. Hayner; R.L. Bratton; R.N. Wright

2005-09-01T23:59:59.000Z

108

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

R. Doug Hamelin; G. O. Hayner

2004-11-01T23:59:59.000Z

109

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect (OSTI)

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

G. O. Hayner; E.L. Shaber

2004-09-01T23:59:59.000Z

110

US Releases Updated Plutonium Inventory Report | National Nuclear...  

National Nuclear Security Administration (NNSA)

Releases Updated Plutonium Inventory Report | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

111

Closure for the Seventh Generation - A Report from the Stewardship...  

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

Closure for the Seventh Generation - A Report from the Stewardship Committee of the State and Tribal Government Working Group (February 1999) Closure for the Seventh Generation - A...

112

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

E-Print Network [OSTI]

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

Nero, A.V.

2010-01-01T23:59:59.000Z

113

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Removal Equipment (nuclear plant) Turbine Building ClosedCooling Water System (nuclear plant) SteamReheater (nuclear plant) Inspection Water Induction

Nero, A.V.

2010-01-01T23:59:59.000Z

114

What future for nuclear power? Workshop report  

SciTech Connect (OSTI)

A Workshop on this highly controversial subject, organized by the Energy and Environment Programme of the RIIA, was held on 10th November 1997 at Green College, Oxford. The meeting was attended by some forty people from eight countries, coming from the nuclear and electricity generating industry, governments, research organizations, academic institutions, environmental pressure groups and inter-governmental organizations. In addition, subsequent to this Workshop, there have been a number of smaller, more informal discussions on various aspects of the subject. This paper summarizes the main conclusions arising from the Workshop and from these later discussions.

NONE

1998-12-31T23:59:59.000Z

115

NUCLEAR SCIENCE ANNUAL REPORT 1977-1978  

E-Print Network [OSTI]

A Relation Between Nuclear Dynamics and the RenormalizationMultiplicity Distributions in Nuclear Collision M. GyulassyHigh Energy Nuclear Collisions in the Resonance Dominated

Schroeder, L.S.

2011-01-01T23:59:59.000Z

116

Nuclear Chemistry Division annual report FY83  

SciTech Connect (OSTI)

The purpose of the annual reports of the Nuclear Chemistry Division is to provide a timely summary of research activities pursued by members of the Division during the preceding year. Throughout, details are kept to a minimum; readers desiring additional information are encouraged to read the referenced documents or contact the authors. The Introduction presents an overview of the Division's scientific and technical programs. Next is a section of short articles describing recent upgrades of the Division's major facilities, followed by sections highlighting scientific and technical advances. These are grouped under the following sections: nuclear explosives diagnostics; geochemistry and environmental sciences; safeguards technology and radiation effect; and supporting fundamental science. A brief overview introduces each section. Reports on research supported by a particular program are generally grouped together in the same section. The last section lists the scientific, administrative, and technical staff in the Division, along with visitors, consultants, and postdoctoral fellows. It also contains a list of recent publications and presentations. Some contributions to the annual report are classified and only their abstracts are included in this unclassified portion of the report (UCAR-10062-83/1); the full article appears in the classified portion (UCAR-10062-83/2).

Struble, G. (ed.)

1983-01-01T23:59:59.000Z

117

Generation IV Nuclear Energy Systems Construction Cost Reductions Through the Use of Virtual Environments  

SciTech Connect (OSTI)

The objective of this multi-phase project is to demonstrate the feasibility and effectiveness of using full-scale virtual reality simulation in the design, construction, and maintenance of future nuclear power plants. The project will test the suitability of immersive virtual reality technology to aid engineers in the design of the next generation nuclear power plant and to evaluate potential cost reductions that can be realized by optimization of installation and construction sequences. The intent is to see if this type of information technology can be used in capacities similar to those currently filled by full-scale physical mockups. This report presents the results of the completed project.

Timothy Shaw; Vaugh Whisker

2004-02-28T23:59:59.000Z

118

Technological Transfer from Research Nuclear Reactors to New Generation Nuclear Power Reactors  

SciTech Connect (OSTI)

The goal of this paper is the analysis of the technological transfer role in the nuclear field, with particular emphasis on nuclear reactors domain. The presentation is sustained by historical arguments. In this frame, it is very important to start with the achievements of the first nuclear systems, for instant those with natural uranium as fuel and heavy water as moderator, following in time through the history until the New Generation Nuclear Power Reactors.Starting with 1940, the accelerated development of the industry has implied the increase of the global demand for energy. In this respect, the nuclear energy could play an important role, being essentially an unlimited source of energy. However, the nuclear option faces the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide, a significant amount of experience has been accumulated during development, licensing, construction, and operation of nuclear power reactors. The experience gained is a strong basis for further improvements. Actually, the nuclear programs of many countries are addressing the development of advanced reactors, which are intended to have better economics, higher reliability, improved safety, and proliferation-resistant characteristics in order to overcome the current concerns about nuclear power. Advanced reactors, now under development, may help to meet the demand for energy power of both developed and developing countries as well as for district heating, desalination and for process heat.The paper gives historical examples that illustrate the steps pursued from first research nuclear reactors to present advanced power reactors. Emphasis was laid upon the fact that the progress is due to the great discoveries of the nuclear scientists using the technological transfer.

Radulescu, Laura ['Horia Hulubei' National Institute of Nuclear Physics and Engineering, PO BOX MG-6, Bucharest 077125 (Romania); Pavelescu, Margarit [Academy of Romanian Scientists, Bucharest (Romania)

2010-01-21T23:59:59.000Z

119

SHORT REPORT Open Access Nuclear lipid droplets identified by electron  

E-Print Network [OSTI]

SHORT REPORT Open Access Nuclear lipid droplets identified by electron microscopy of serial that nuclear lipid droplets (LDs) are organized into domains similar to those of cytoplasmic LDs with the nuclear envelope, it could be suggested however that nuclear LDs are cytoplamic LDs trapped within

Boyer, Edmond

120

Alternative similarity renormalization group generators in nuclear structure calculations  

E-Print Network [OSTI]

The similarity renormalization group (SRG) has been successfully applied to soften interactions for ab initio nuclear calculations. In almost all practical applications in nuclear physics, an SRG generator with the kinetic energy operator is used. With this choice, a fast convergence of many-body calculations can be achieved, but at the same time substantial three-body interactions are induced even if one starts from a purely two-nucleon (NN) Hamiltonian. Three-nucleon (3N) interactions can be handled by modern many-body methods. However, it has been observed that when including initial chiral 3N forces in the Hamiltonian, the SRG transformations induce a non-negligible four-nucleon interaction that cannot be currently included in the calculations for technical reasons. Consequently, it is essential to investigate alternative SRG generators that might suppress the induction of many-body forces while at the same time might preserve the good convergence. In this work we test two alternative generators with operators of block structure in the harmonic oscillator basis. In the no-core shell model calculations for 3H, 4He and 6Li with chiral NN force, we demonstrate that their performances appear quite promising.

Nuiok M. Dicaire; Conor Omand; Petr Navratil

2014-08-22T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Removal of deposited copper from nuclear steam generators  

SciTech Connect (OSTI)

A review of the copper-removal process implemented during the cleaning of the NPD nuclear steam generator in Ontario revealed that major shortcomings in the process were depletion of the strong ammonia solution and relatively poor copper removal. Tests have shown that the concentration of the ammonia solution can be preserved close to its initial value, and high concentrations of complexed copper obtained, by sparging the ammonia solution with oxygen recirculating through a gas recirculation loop. Using recirculating oxygen for sparging at ambient air temperature, approximately 11 g/l of copper were dissolved by 100 g/l ammonia solution while the gaseous ammonia content of the recirculating gas remained well below the lower flammability limit. The corrosion rates of mild steel and commonly used nuclear steam generator tube materials in oxygenated ammonia solution were less than 30 mil/yr and no intergranular attack of samples was observed during tests. A second technique studied for the removal of copper is to ammoniate the spent iron-removal solvent to approximately pH 9.5 and sparge with recirculating oxygen. Complexed ferric iron in the spent iron-removal solvent was found to be the major oxidizing agent for metallic copper. The ferric iron can be derived from oxidation of dissolved ferrous iron to the ferric state or from dissolved oxides of iron directly. To extract copper from the secondary sides of nuclear steam generators, strong ammonia solution sparged with recirculating oxygen is recommended as the first stage, while ammoniated spent iron-removal solvent sparged with recirculating oxygen may be used to remove the copper freshly exposed during the removal of iron.

McSweeney, P.

1982-05-01T23:59:59.000Z

122

2009 UK/US Nuclear Engineering Workshop Report  

SciTech Connect (OSTI)

This report summarizes the 2009 UK/US Nuclear Engineering Workshop held April 20-21, 2010, in Washington, D.C. to discuss opportunities for nuclear engineering collaboration between researchers in the United States and the United Kingdom.

Richard Rankin

2009-04-01T23:59:59.000Z

123

Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators - Interim Report for FY 2013  

SciTech Connect (OSTI)

The Light Water Reactor Sustainability program at Idaho National Laboratory is actively conducting research to develop and demonstrate online monitoring capabilities for active components in existing nuclear power plants. Idaho National Laboratory and the Electric Power Research Institute are working jointly to implement a pilot project to apply these capabilities to emergency diesel generators and generator step-up transformers. The Electric Power Research Institute Fleet-Wide Prognostic and Health Management Software Suite will be used to implement monitoring in conjunction with utility partners: Braidwood Generating Station (owned by Exelon Corporation) for emergency diesel generators, and Shearon Harris Nuclear Generating Station (owned by Duke Energy Progress) for generator step-up transformers. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for emergency diesel generators. Emergency diesel generators provide backup power to the nuclear power plant, allowing operation of essential equipment such as pumps in the emergency core coolant system during catastrophic events, including loss of offsite power. Technical experts from Braidwood are assisting Idaho National Laboratory and Electric Power Research Institute in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the Fleet-Wide Prognostic and Health Management Software Suite and tested using data from Braidwood. Parallel research on generator step-up transformers was summarized in an interim report during the fourth quarter of fiscal year 2012.

Binh T. Pham; Nancy J. Lybeck; Vivek Agarwal

2012-12-01T23:59:59.000Z

124

Nuclear Nonproliferation Ontology Assessment Team Final Report  

SciTech Connect (OSTI)

Final Report for the NA22 Simulations, Algorithm and Modeling (SAM) Ontology Assessment Team's efforts from FY09-FY11. The Ontology Assessment Team began in May 2009 and concluded in September 2011. During this two-year time frame, the Ontology Assessment team had two objectives: (1) Assessing the utility of knowledge representation and semantic technologies for addressing nuclear nonproliferation challenges; and (2) Developing ontological support tools that would provide a framework for integrating across the Simulation, Algorithm and Modeling (SAM) program. The SAM Program was going through a large assessment and strategic planning effort during this time and as a result, the relative importance of these two objectives changed, altering the focus of the Ontology Assessment Team. In the end, the team conducted an assessment of the state of art, created an annotated bibliography, and developed a series of ontological support tools, demonstrations and presentations. A total of more than 35 individuals from 12 different research institutions participated in the Ontology Assessment Team. These included subject matter experts in several nuclear nonproliferation-related domains as well as experts in semantic technologies. Despite the diverse backgrounds and perspectives, the Ontology Assessment team functioned very well together and aspects could serve as a model for future inter-laboratory collaborations and working groups. While the team encountered several challenges and learned many lessons along the way, the Ontology Assessment effort was ultimately a success that led to several multi-lab research projects and opened up a new area of scientific exploration within the Office of Nuclear Nonproliferation and Verification.

Strasburg, Jana D.; Hohimer, Ryan E.

2012-01-01T23:59:59.000Z

125

NUCLEAR POWER IN CALIFORNIA: 2007 STATUS REPORT  

E-Print Network [OSTI]

reprocessing program, and issues related to the transportation of nuclear waste. The costs of nuclear power, the future of nuclear power is addressed by considering the safety and reliability of the aging U.S. nuclear ............................................................................................ 3 Storage and Disposal of Spent Fuel

126

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, A.V.

2010-01-01T23:59:59.000Z

127

Nuclear waste management. Semiannual progress report, October 1983-March 1984  

SciTech Connect (OSTI)

Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; waste isolation; and supporting studies. 58 figures, 22 tables.

McElroy, J.L.; Powell, J.A.

1984-06-01T23:59:59.000Z

128

ORISE: Report shows nuclear engineering graduation rates on the...  

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

ORISE report shows nuclear engineering graduation rates on the rise in 2013 Number of graduate degrees expected to remain consistent, but undergraduate degrees could see decrease...

129

Nuclear Waste Management. Semiannual progress report, October 1984-March 1985  

SciTech Connect (OSTI)

Progress reports are presented for the following studies on radioactive waste management: defense waste technology; nuclear waste materials characterization center; and supporting studies. 19 figs., 29 tabs.

McElroy, J.L.; Powell, J.A. (comps.)

1985-06-01T23:59:59.000Z

130

Working Group Report on - Space Nuclear Power Systems and Nuclear...  

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

addressed long-term planning for disposition of radioactive materials, development of space nuclear systems, and general needs related to these areas. The following are the...

131

A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats  

SciTech Connect (OSTI)

This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the range of possibilities. Once an object is generated, its radiation signature is calculated using a 1-dimensional deterministic transport code. Objects that do not make sense based on physics principles or other constraints are rejected. Thus, the model can be used to generate a population of spectral signatures that spans a large space, including smuggled nuclear material and nuclear weapons.

Nelson, K; Sokkappa, P

2008-10-29T23:59:59.000Z

132

Annual report of waste generation and pollution prevention progress 1995  

SciTech Connect (OSTI)

This fourth Annual Report presents and analyzes 1995 DOE complex-wide waste generation and pollution prevention activities at 40 reporting sites in 25 States, and trends DOE waste generation from 1991 through 1995. DOE has established a 50% reduction goal (relative to the 1993 baseline) for routine operations radioactive and hazardous waste generation, due by December 31, 1999. Routine operations waste generation decreased 37% from 1994 to 1995, and 43% overall from 1993--1995.

NONE

1997-02-01T23:59:59.000Z

133

Fiscal Year 2014 Annual Report on BNLs Next Generation Safeguards Initiative Human Capital Development Activities  

SciTech Connect (OSTI)

Brookhaven National Laboratoryís (BNLís) Nonproliferation and National Security Department contributes to the National Nuclear Security Administration Office of Nonproliferation and International Security Next Generation Safeguards Initiative (NGSI) through university engagement, safeguards internships, safeguards courses, professional development, recruitment, and other activities aimed at ensuring the next generation of international safeguards professionals is adequately prepared to support the U.S. safeguards mission. This report is a summary of BNL s work under the NGSI program in Fiscal Year 2014.

Pepper S. E.

2014-10-10T23:59:59.000Z

134

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

nuclear, geothermal, and fossil-fuel power plants. However,power plants, which are reviewed and licensed by the Nuclear Regulatory Commission (NRC), and relatively few areas of geothermal and

Nero, A.V.

2010-01-01T23:59:59.000Z

135

Dependable Hydrogen and Industrial Heat Generation from the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

The Department of Energy is working with industry to develop a next generation, high-temperature gas-cooled nuclear reactor (HTGR) as a part of the effort to supply the US with abundant, clean and secure energy. The Next Generation Nuclear Plant (NGNP) project, led by the Idaho National Laboratory, will demonstrate the ability of the HTGR to generate hydrogen, electricity, and high-quality process heat for a wide range of industrial applications. Substituting HTGR power for traditional fossil fuel resources reduces the cost and supply vulnerability of natural gas and oil, and reduces or eliminates greenhouse gas emissions. As authorized by the Energy Policy Act of 2005, industry leaders are developing designs for the construction of a commercial prototype producing up to 600 MWt of power by 2021. This paper describes a variety of critical applications that are appropriate for the HTGR with an emphasis placed on applications requiring a clean and reliable source of hydrogen. An overview of the NGNP project status and its significant technology development efforts are also presented.

Charles V. Park; Michael W. Patterson; Vincent C. Maio; Piyush Sabharwall

2009-03-01T23:59:59.000Z

136

Nuclear technology programs; Semiannual progress report, October 1989--March 1990  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

Harmon, J.E. [ed.

1992-01-01T23:59:59.000Z

137

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]

Nuclear Power Reactors PROTECTION AGAINST SABOTAGE Protection Against Industrial Sabotage I1C-4 Decominarion and Decommissioning

Nero, A.V.

2010-01-01T23:59:59.000Z

138

NNSA Administrator Addresses the Next Generation of Nuclear Security Professionals: Part 1  

ScienceCinema (OSTI)

Administrator Thomas DAgostino of the National Nuclear Security Administration addressed the next generation of nuclear security professionals during the opening session of todays 2009 Department of Energy (DOE) Computational Science Graduate Fellowship Annual Conference. Administrator DAgostino discussed NNSAs role in implementing President Obamas nuclear security agenda and encouraged the computing science fellows to consider careers in nuclear security.

Thomas D'Agostino

2010-09-01T23:59:59.000Z

139

Decision-support tool for assessing future nuclear reactor generation portfolios.  

E-Print Network [OSTI]

Decision-support tool for assessing future nuclear reactor generation portfolios. Shashi Jain, where especially capital costs are known to be highly uncertain. Differ- ent nuclear reactor types uncertainties in the cost elements of a nuclear power plant, to provide an optimal portfolio of nuclear reactors

Oosterlee, Cornelis W. "Kees"

140

NNSA Administrator Addresses the Next Generation of Nuclear Security Professionals: Part 2  

ScienceCinema (OSTI)

Administrator Thomas DAgostino of the National Nuclear Security Administration addressed the next generation of nuclear security professionals during the opening session of todays 2009 Department of Energy (DOE) Computational Science Graduate Fellowship Annual Conference. Administrator DAgostino discussed NNSAs role in implementing President Obamas nuclear security agenda and encouraged the computing science fellows to consider careers in nuclear security.

Thomas D'Agostino

2010-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

ICF Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

142

Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)  

SciTech Connect (OSTI)

The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01T23:59:59.000Z

143

Nuclear waste management. Quarterly progress report, April-June 1981  

SciTech Connect (OSTI)

Reports and summaries are presented for the following: high-level waste process development; alternative waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; and analysis of spent fuel policy implementation.

Chikalla, T.D.; Powell, J.A.

1981-09-01T23:59:59.000Z

144

Annual report of waste generation and pollution prevention progress 1999  

SciTech Connect (OSTI)

This Annual Report summarizes and highlights waste generation, waste reduction, pollution prevention accomplishments, and cost avoidance for 44 U.S. Department of Energy reporting sites for Calendar Year 1999. This section summarizes Calendar Year 1999 Complex-wide waste generation and pollution prevention accomplishments.

NONE

2000-09-01T23:59:59.000Z

145

26 CURA REPORTER Hydrogen Generation Using Magnetite to Store  

E-Print Network [OSTI]

26 CURA REPORTER Hydrogen Generation Using Magnetite to Store Energy from Alternative Sources by J of hydrogen generation and storage in the growing wind energy industry could be especially useful in a future sustainable energy economy in the state. The generated hydrogen also might be used onsite in the mining

Levinson, David M.

146

Next Generation Nuclear Plant Research and Development Program Plan  

SciTech Connect (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

None

2005-01-01T23:59:59.000Z

147

[Electroweak and other interactions in medium-energy nuclear physics]. Progress report  

SciTech Connect (OSTI)

This report discusses the following topics: spectrum generating algebra; vibrational spectra in the heavy quarkonia; chiral soliton model; pion neutral photoproduction from proton with polarized photons in the delta-1232 region; compton scattering in the delta- 1232 region; nucleon magnetic polarizability and the role of the delta resonance; eta photo- and electroproduction; perturbative QCD; and nuclear muon capture.

Mukhopadhyay, N.C.

1993-12-01T23:59:59.000Z

148

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site  

SciTech Connect (OSTI)

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

L.E. Demick

2011-10-01T23:59:59.000Z

149

Nuclear Science Division 1994 annual report  

SciTech Connect (OSTI)

This report describes the activities of the Nuclear Science Division for the period of January 1, 1994, to December 31, 1994. This was a time of significant accomplishment for all of the programs in the Division. Assembly of the solar neutrino detector at the Sudbury Neutrino Observatory is well under way. All of the components fabricated by LBL were shipped to Sudbury early in the year and our efforts are now divided between assisting the assembly of the detector and preparing software for data analysis once the detector is operational in 1996. Much of the activity at the 88-Inch Cyclotron centered on Gammasphere. The {open_quotes}early implementation{close_quotes} phase of the detector ended in September. This phase was extremely successful, involving over 60 experiments with nearly 200 users from 37 institutions worldwide. The mechanical structure was installed and the final electronic system is expected to operate in March 1995. The Division concurrently hosted a conference on physics for large {gamma}-ray detector arrays at the Clark Kerr Campus at UC Berkeley in August. This was a very successful meeting, reflecting the enthusiasm for this field worldwide. Also at the Cyclotron, the progress toward weak interaction experiments using ultra-thin sources passed a major milestone with the trapping of radioactive {sup 21}Na atoms. We are now engaged in a major upgrade of the experimental area and the outlook is very promising for these novel experiments. Another highlight of research at the Cyclotron was the confirmation of element 106. This development allowed the original LLNL/LBL discovery team to move forward with their proposal to name this element seaborgium.

Myers, W.D. [ed.

1995-06-01T23:59:59.000Z

150

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

generate steam to drive a steam turbine, giving rise to theValves and Pi~ing STEAM TURBINE COMPONENT OUTAGE CAUSESbasically of a steam-driven turbine, an electric generator

Nero, A.V.

2010-01-01T23:59:59.000Z

151

White paper report on using nuclear reactors to search for a value of theta13  

E-Print Network [OSTI]

PAPER REPORT on Using Nuclear Reactors to Search for a valuetimely new experiment at a nuclear reactor sensitive to theand judicious choice of a nuclear reactor. The dominant

2004-01-01T23:59:59.000Z

152

Next Generation Nuclear Plant Methods Technical Program Plan  

SciTech Connect (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the ďhighly rankedĒ phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2007-01-01T23:59:59.000Z

153

Next Generation Nuclear Plant Methods Technical Program Plan  

SciTech Connect (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the ďhighly rankedĒ phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-12-01T23:59:59.000Z

154

Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498  

SciTech Connect (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the ďhighly rankedĒ phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-09-01T23:59:59.000Z

155

Report of the State of Nevada Commission on Nuclear Projects  

SciTech Connect (OSTI)

This third biennial Report of the Nevada Commission on Nuclear Projects has been prepared in fulfillment of the requirements of NRS 459.0092, which stipulates that the Commission shall report to the Governor and Legislature on any matter relating to radioactive waste disposal the Commission deems appropriate and advise and make recommendations on the policy of the State concerning nuclear waste disposal projects. Chapter One of the Report presents a brief overview of the Commission`s functions and statutory charges. It also contains a summary of developments which have affected the overall nuclear waste disposl issue since the last Commission Report was published in November, 1988. Chapter Two contains a synthesis of Commission activities and reports on the findings of the Commission relative to the geotechnical, environmental, socioeconomic, transportation, intergovernmental and legal aspects of federal and State nuclear waste program efforts.

NONE

1990-12-01T23:59:59.000Z

156

Nuclear Science & Engineering Monthly Reports | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguards and Nuclear Science

157

Institute of Nuclear Power Operations 1994 annual report  

SciTech Connect (OSTI)

This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1994 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

NONE

1994-12-31T23:59:59.000Z

158

Nuclear science. Annual report, July 1, 1980-June 30, 1981  

SciTech Connect (OSTI)

This annual report describes the scientific research carried out within the Nuclear Science Division between July 1, 1980 and June 30, 1981. The principal activity of the division continues to be the experimental and theoretical investigation of the interaction of heavy ions with target nuclei. Complementary research programs in light-ion nuclear science, in nuclear data evaluations, and in the development of advanced instrumentation are also carried out.

Friedlander, E.M. (ed.)

1982-06-01T23:59:59.000Z

159

Automatic code generation enables nuclear gradient computations for fully internally contracted multireference theory  

E-Print Network [OSTI]

Analytical nuclear gradients for fully internally contracted complete active space second-order perturbation theory (CASPT2) are reported. This implementation has been realized by an automated code generator that can handle spin-free formulas for the CASPT2 energy and its derivatives with respect to variations of molecular orbitals and reference coefficients. The underlying complete active space self-consistent field and the so-called Z-vector equations are solved using density fitting. With full internal contraction the size of first-order wave functions scales polynomially with the number of active orbitals. The CASPT2 gradient program and the code generator are both publicly available. This work enables the CASPT2 geometry optimization of molecules as complex as those investigated by respective single-point calculations.

MacLeod, Matthew K

2015-01-01T23:59:59.000Z

160

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

emergencies, Le. , accidents at nuclear facilities, there isas a result of nuclear accidents; these are the Protectiveassociated with a nuclear accident is of greater importance

Nero, A.V.

2010-01-01T23:59:59.000Z

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


161

Radioactive Effluents from Nuclear Power Plants Annual Report 2007  

SciTech Connect (OSTI)

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

162

Radioactive Effluents from Nuclear Power Plants Annual Report 2008  

SciTech Connect (OSTI)

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

163

Granular flow in pebble-bed nuclear reactors: Scaling, Dust Generation, and Stress  

E-Print Network [OSTI]

Granular flow in pebble-bed nuclear reactors: Scaling, Dust Generation, and Stress Chris H. Keywords: granular flow, dust generation, numerical methods 1. Introduction Pebble-bed nuclear reactors prototypes of pebble-bed reactors, significant quantities of graphite dust have been observed due to rubbing

Rycroft, Chris H.

164

Nuclear Materials Management and Safeguards System Reporting and Data Submission  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The manual provides clear and detailed instructions and procedures for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE 5633.3B. Canceled by DOE M 474.1-2A.

1998-02-10T23:59:59.000Z

165

Heat Exchangers for the Next Generation of Nuclear Reactors  

SciTech Connect (OSTI)

The realisation that fossil fuel resources are finite, the associated rising price and a growing concern about greenhouse gas emissions, has resulted in renewed interest in nuclear energy. Generation IV and other programmes are looking at a variety of new reactors. These reactors vary in type from Very High Temperature Gas Cooled Reactors (VHTR) to Liquid Metal Fast Reactors (LFR and SFR) with cooling mediums that include: - Helium, - Supercritical carbon dioxide, - Sodium, - Lead, - Molten salts. In addition interest is not just focused on production of electrical power with an efficiency greater than that associated with the Rankine Cycle (typically 30 -35%); there is now genuine interest in nuclear energy as a heat source for hydrogen production, via the Sulphur Iodine Process (SI) or high temperature electrolysis. The production of electrical power at higher efficiency via a Brayton Cycle, and hydrogen production requires both heat at higher temperatures, up to 1000 deg C and high effectiveness heat exchange to transfer the heat to either the power or process cycle. This presents new challenges for the heat exchangers. If plant efficiencies are to be improved there is a need for: - High effectiveness heat exchange at minimal pressure drop; - Compact heat exchange to improve safety and economics; - An ability to build coded heat exchangers in a variety of nickel based alloys, oxide dispersion strengthened alloys (ODS) and ceramic materials to address the temperature, life and corrosion issues associated with these demanding duties. Heatric has already given consideration to many of these challenges. Their Print Circuit Heat Exchanger (PCHE) and Formed Plate Heat Exchanger (FPHE) technology which are commercially available today, will fulfill all of the duties up to temperatures of 950 deg C. In addition products currently under development will further increase the temperature and pressure range, while offering greater corrosion resistance and operational life. This paper outlines the challenges for the heat exchangers and the development required, with particular attention given to material selection. It is further the objective of this study to demonstrate that heat exchangers such as PCHE and FPHE are able to meet the above challenges. (authors)

Xiuqing, Li; Le Pierres, Renaud; Dewson, Stephen John [Heatric Division of Meggitt (UK) Ltd., 46 Holton Road, Holton Heath, Poole, Dorset BH16 6LT (United Kingdom)

2006-07-01T23:59:59.000Z

166

Next Generation Nuclear Plant Research and Development Program Plan  

SciTech Connect (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

P. E. MacDonald

2005-01-01T23:59:59.000Z

167

A Technology Roadmap for Generation IV Nuclear Energy Systems Executive Summary  

SciTech Connect (OSTI)

To meet future energy needs, ten countries--Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, Switzerland, the United Kingdom, and the United States--have agreed on a framework for international cooperation in research for an advanced generation of nuclear energy systems, known as Generation IV. These ten countries have joined together to form the Generation IV International Forum (GIF) to develop future-generation nuclear energy systems that can be licensed, constructed, and operated in a manner that will provide competitively priced and reliable energy products while satisfactorily addressing nuclear safety, waste, proliferation, and public perception concerns. The objective for Generation IV nuclear energy systems is to be available for international deployment before the year 2030, when many of the world's currently operating nuclear power plants will be at or near the end of their operating licenses.

None

2003-03-01T23:59:59.000Z

168

NUCLEAR MATERIALS RESEARCH PROGRESS REPORTS FROM 1977  

E-Print Network [OSTI]

Chemical Effects of Thermonuclear Plasma Interactions Withfor Controlled Thermonuclear Reactor (CTR), USAEC Report LA-

Olander, D.R.

2012-01-01T23:59:59.000Z

169

New Jersey Nuclear Profile - PSEG Salem Generating Station  

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

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

170

New Jersey Nuclear Profile - PSEG Hope Creek Generating Station  

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

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

171

Illinois Nuclear Profile - LaSalle Generating Station  

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

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

172

Alternative electric generation impact simulator : final summary report  

E-Print Network [OSTI]

This report is a short summary of three related research tasks that were conducted during the project "Alternative Electric Generation Impact Simulator." The first of these tasks combines several different types of ...

Gruhl, Jim

1981-01-01T23:59:59.000Z

173

Nuclear Science | Publications and Reports | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |Navy NuclearNuclear Science NSED

174

Generation-IV Roadmap Report of the Fuel Cycle Crosscut Group...  

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

Charter of the Generation IV Roadmap Fuel Cycle Crosscut Group (FCCG) is to (1) examine the fuel cycle implications for alternative nuclear power scenarios in terms of Generation...

175

Dynamic Systems Analysis Report for Nuclear Fuel Recycle  

SciTech Connect (OSTI)

This report examines the time-dependent dynamics of transitioning from the current United States (U.S.) nuclear fuel cycle where used nuclear fuel is disposed in a repository to a closed fuel cycle where the used fuel is recycled and only fission products and waste are disposed. The report is intended to help inform policy developers, decision makers, and program managers of system-level options and constraints as they guide the formulation and implementation of advanced fuel cycle development and demonstration efforts and move toward deployment of nuclear fuel recycling infrastructure.

Brent Dixon; Sonny Kim; David Shropshire; Steven Piet; Gretchen Matthern; Bill Halsey

2008-12-01T23:59:59.000Z

176

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

entry are u Table 4-6 GAS TURBINE FOR 1965-1974 (OUTAGES)AVERAGE utage Cause Code GAS TURBINE GENERATOR FORCED OUTAGEof fossil units, and for gas turbine units, the basic data

Nero, A.V.

2010-01-01T23:59:59.000Z

177

Strategic Nuclear Research Collaboration - FY99 Annual Report  

SciTech Connect (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) has created the Strategic Nuclear Research Collaboration. The SNRC brings together some of America's finest laboratory and university nuclear researchers in a carefully focused research program intended to produce ''breakthrough'' solutions to the difficult issues of nuclear economics, safety, non-proliferation, and nuclear waste. This integrated program aims to address obstacles that stand in the way of nuclear power development in the US These include fuel cycle concerns related to waste and proliferation, the need for more efficient regulatory practices, and the high cost of constructing and operating nuclear power plants. Funded at an FY99 level of $2.58M, the SNRC is focusing the efforts of scientists and engineers from the INEEL and the Massachusetts Institute of Technology to solve complex nuclear energy challenges in a carefully chosen, integrated portfolio of research topics. The result of this collaboration will be research that serves as a catalyst for future direct-funded nuclear research and technology development and which preserves and enhances the INEEL's role as America's leading national laboratory for nuclear power research. In its first year, the SNRC has focused on four research projects each of which address one or more of the four issues facing further nuclear power development (economics, safety, waste disposition and proliferation-resistance). This Annual Report describes technical work and accomplishments during the first year of the SNRC's existence.

T. J. Leahy

1999-07-01T23:59:59.000Z

178

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs  

SciTech Connect (OSTI)

Here we report the outcome of the application of the Nuclear Regulatory Commission (NRC) Phenomena Identification and Ranking Table (PIRT) process to the issue of nuclear-grade graphite for the moderator and structural components of a next generation nuclear plant (NGNP), considering both routine (normal operation) and postulated accident conditions for the NGNP. The NGNP is assumed to be a modular high-temperature gas-cooled reactor (HTGR), either a gas-turbine modular helium reactor (GTMHR) version [a prismatic-core modular reactor (PMR)] or a pebble-bed modular reactor (PBMR) version [a pebble bed reactor (PBR)] design, with either a direct- or indirect-cycle gas turbine (Brayton cycle) system for electric power production, and an indirect-cycle component for hydrogen production. NGNP design options with a high-pressure steam generator (Rankine cycle) in the primary loop are not considered in this PIRT. This graphite PIRT was conducted in parallel with four other NRC PIRT activities, taking advantage of the relationships and overlaps in subject matter. The graphite PIRT panel identified numerous phenomena, five of which were ranked high importance-low knowledge. A further nine were ranked with high importance and medium knowledge rank. Two phenomena were ranked with medium importance and low knowledge, and a further 14 were ranked medium importance and medium knowledge rank. The last 12 phenomena were ranked with low importance and high knowledge rank (or similar combinations suggesting they have low priority). The ranking/scoring rationale for the reported graphite phenomena is discussed. Much has been learned about the behavior of graphite in reactor environments in the 60-plus years since the first graphite rectors went into service. The extensive list of references in the Bibliography is plainly testament to this fact. Our current knowledge base is well developed. Although data are lacking for the specific grades being considered for Generation IV (Gen IV) concepts, such as the NGNP, it is fully expected that the behavior of these graphites will conform to the recognized trends for near isotropic nuclear graphite. Thus, much of the data needed is confirmatory in nature. Theories that can explain graphite behavior have been postulated and, in many cases, shown to represent experimental data well. However, these theories need to be tested against data for the new graphites and extended to higher neutron doses and temperatures pertinent to the new Gen IV reactor concepts. It is anticipated that current and planned future graphite irradiation experiments will provide the data needed to validate many of the currently accepted models, as well as providing the needed data for design confirmation.

Burchell, Timothy D [ORNL; Bratton, Rob [Idaho National Laboratory (INL); Marsden, Barry [University of Manchester, UK; Srinivasan, Makuteswara [U.S. Nuclear Regulatory Commission; Penfield, Scott [Technology Insights; Mitchell, Mark [PBMR (Pty) Ltd.; Windes, Will [Idaho National Laboratory (INL)

2008-03-01T23:59:59.000Z

179

NUCLEAR MATERIALS RESEARCH PROGRESS REPORTS FOR 1979  

E-Print Network [OSTI]

Chemical E f f e c t s of Thermonuclear Plasma I n t e r a cfor Controlled Thermonuclear Reactor (CTR), USAEC Report LA

Olander, D.R.

2010-01-01T23:59:59.000Z

180

Membranes for H2 generation from nuclear powered thermochemical cycles.  

SciTech Connect (OSTI)

In an effort to produce hydrogen without the unwanted greenhouse gas byproducts, high-temperature thermochemical cycles driven by heat from solar energy or next-generation nuclear power plants are being explored. The process being developed is the thermochemical production of Hydrogen. The Sulfur-Iodide (SI) cycle was deemed to be one of the most promising cycles to explore. The first step of the SI cycle involves the decomposition of H{sub 2}SO{sub 4} into O{sub 2}, SO{sub 2}, and H{sub 2}O at temperatures around 850 C. In-situ removal of O{sub 2} from this reaction pushes the equilibrium towards dissociation, thus increasing the overall efficiency of the decomposition reaction. A membrane is required for this oxygen separation step that is capable of withstanding the high temperatures and corrosive conditions inherent in this process. Mixed ionic-electronic perovskites and perovskite-related structures are potential materials for oxygen separation membranes owing to their robustness, ability to form dense ceramics, capacity to stabilize oxygen nonstoichiometry, and mixed ionic/electronic conductivity. Two oxide families with promising results were studied: the double-substituted perovskite A{sub x}Sr{sub 1-x}Co{sub 1-y}B{sub y}O{sub 3-{delta}} (A=La, Y; B=Cr-Ni), in particular the family La{sub x}Sr{sub 1-x}Co{sub 1-y}Mn{sub y}O{sub 3-{delta}} (LSCM), and doped La{sub 2}Ni{sub 1-x}M{sub x}O{sub 4} (M = Cu, Zn). Materials and membranes were synthesized by solid state methods and characterized by X-ray and neutron diffraction, SEM, thermal analyses, calorimetry and conductivity. Furthermore, we were able to leverage our program with a DOE/NE sponsored H{sub 2}SO{sub 4} decomposition reactor study (at Sandia), in which our membranes were tested in the actual H{sub 2}SO{sub 4} decomposition step.

Nenoff, Tina Maria; Ambrosini, Andrea; Garino, Terry J.; Gelbard, Fred; Leung, Kevin; Navrotsky, Alexandra (University of California, Davis, CA); Iyer, Ratnasabapathy G. (University of California, Davis, CA); Axness, Marlene

2006-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Nuclear Science Division, 1995--1996 annual report  

SciTech Connect (OSTI)

This report describes the activities of the Nuclear Science Division (NSD) for the two-year period, January 1, 1995 to January 1, 1997. This was a time of major accomplishments for all research programs in the Division-many of which are highlighted in the reports of this document.

Poskanzer, A.M. [ed.

1997-02-01T23:59:59.000Z

182

Nuclear materials 1993 annual report. Volume 8, No. 2  

SciTech Connect (OSTI)

This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC`s Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ``Nonreactors`` to ``Nuclear Materials.`` Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993.

NONE

1995-05-01T23:59:59.000Z

183

DEPARTMENf OF NUCLEAR PHYSICS TANK OPENING REPORT NO 62  

E-Print Network [OSTI]

DEPARTMENf OF NUCLEAR PHYSICS TANK OPENING REPORT NO 62 This report covers three tank openings; 2 history. We were plagued throughout these tank openings by poor beam transmission and spent most of our have, were manufactured and installed. The first tank opening2 May t.o 6 May 1988. This tank opening

Chen, Ying

184

NEXT GENERATION NUCLEAR PLANT NGNP Technology Development Roadmapping  

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

ISR Inner Side Reflector Kc Fracture Toughness kg Kilogram K-T Kepner-Tregoe KTA German nuclear technical committee kW Kilowatt LANL Los Alamos National Laboratory LBE Licensing...

185

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

in U. S. Conunercial Nuclear Power Plants", Report WASH-Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"

Nero, A.V.

2010-01-01T23:59:59.000Z

186

Nuclear Separations Technologies Workshop Report 2011  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced ScorecardReactor Technology Subcommittee of NEACSummary Nucleari NUCLEAR

187

Nuclear waste management. Quarterly progress report, January-March, 1981  

SciTech Connect (OSTI)

Reports and summaries are provided for the following programs: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclide in soils; low-level waste generation reduction handbook; waste management system studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

Chikalla, T.D.; Powell, J.A. (comp.)

1981-06-01T23:59:59.000Z

188

Paving the path for next-generation nuclear energy | Department...  

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

heat that could be used for industrial processes such as seawater desalination or plastics production. Today, China has begun construction of a prototype Generation-IV reactor,...

189

Life Cycle Greenhouse Gas Emissions of Nuclear Electricity Generation: Systematic Review and Harmonization  

SciTech Connect (OSTI)

A systematic review and harmonization of life cycle assessment (LCA) literature of nuclear electricity generation technologies was performed to determine causes of and, where possible, reduce variability in estimates of life cycle greenhouse gas (GHG) emissions to clarify the state of knowledge and inform decision making. LCA literature indicates that life cycle GHG emissions from nuclear power are a fraction of traditional fossil sources, but the conditions and assumptions under which nuclear power are deployed can have a significant impact on the magnitude of life cycle GHG emissions relative to renewable technologies. Screening 274 references yielded 27 that reported 99 independent estimates of life cycle GHG emissions from light water reactors (LWRs). The published median, interquartile range (IQR), and range for the pool of LWR life cycle GHG emission estimates were 13, 23, and 220 grams of carbon dioxide equivalent per kilowatt-hour (g CO{sub 2}-eq/kWh), respectively. After harmonizing methods to use consistent gross system boundaries and values for several important system parameters, the same statistics were 12, 17, and 110 g CO{sub 2}-eq/kWh, respectively. Harmonization (especially of performance characteristics) clarifies the estimation of central tendency and variability. To explain the remaining variability, several additional, highly influential consequential factors were examined using other methods. These factors included the primary source energy mix, uranium ore grade, and the selected LCA method. For example, a scenario analysis of future global nuclear development examined the effects of a decreasing global uranium market-average ore grade on life cycle GHG emissions. Depending on conditions, median life cycle GHG emissions could be 9 to 110 g CO{sub 2}-eq/kWh by 2050.

Warner, E. S.; Heath, G. A.

2012-04-01T23:59:59.000Z

190

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward  

SciTech Connect (OSTI)

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

John Collins

2009-01-01T23:59:59.000Z

191

Maintenance practices for emergency diesel generator engines onboard United States Navy Los Angeles class nuclear submarines  

E-Print Network [OSTI]

The United States Navy has recognized the rising age of its nuclear reactors. With this increasing age comes increasing importance of backup generators. In addition to the need for decay heat removal common to all (naval ...

Hawks, Matthew Arthur

2006-01-01T23:59:59.000Z

192

Guidance for identifying, reporting and tracking nuclear safety noncompliances  

SciTech Connect (OSTI)

This document provides Department of Energy (DOE) contractors, subcontractors and suppliers with guidance in the effective use of DOE`s Price-Anderson nuclear safety Noncompliance Tracking System (NTS). Prompt contractor identification, reporting to DOE, and correction of nuclear safety noncompliances provides DOE with a basis to exercise enforcement discretion to mitigate civil penalties, and suspend the issuance of Notices of Violation for certain violations. Use of this reporting methodology is elective by contractors; however, this methodology is intended to reflect DOE`s philosophy on effective identification and reporting of nuclear safety noncompliances. To the extent that these expectations are met for particular noncompliances, DOE intends to appropriately exercise its enforcement discretion in considering whether, and to what extent, to undertake enforcement action.

NONE

1995-12-01T23:59:59.000Z

193

Theoretical nuclear physics. 1998 progress report  

SciTech Connect (OSTI)

Summaries of progress made on the following topics are given: (1) nonresonant contributions to inelastic N{r_arrow}{Delta}(1232) parity violation; (2) neutron distribution effects in elastic nuclear parity violation; (3) Wilson RG for scalar-plus-fermion field theories at finite density; (4) Perturbation theory for spin ladders using angular momentum coupled bases; (5) mean-field theory for spin ladders using angular momentum density; (6) finite temperature renormalization group effective potentials for the linear Sigma model; (7) negative-parity baryon resonances from lattice QCD; (8) the N{r_arrow}{Delta} electromagnetic transition amplitudes from QCD sum rules; and (9) higher nucleon resonances in exclusive reactions ({gamma}, {pi}N) on nuclei.

NONE

1998-09-01T23:59:59.000Z

194

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Report LBL-5287. "Power Plant Reliability-Availability andConunercial Nuclear Power Plants", Report WASH-1400 (NUREG-Standards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

195

Short-term hydroelectric generation model. Model documentation report  

SciTech Connect (OSTI)

The purpose of this report is to define the objectives of the Energy Information Administration`s (EIA) Short-Term Hydroelectric Generation Model (STHGM), describe its basic approach, and to provide details on the model structure. This report is intended as a reference document for model analysts, users, and the general public. Documentation of the model is in accordance with the EIA`s legal obligation to provide adequate documentation in support of its models.

NONE

1996-12-01T23:59:59.000Z

196

Validated Models for Radiation Response and Signal Generation in Scintillators: Final Report  

SciTech Connect (OSTI)

This Final Report presents work carried out at Pacific Northwest National Laboratory (PNNL) under the project entitled ďValidated Models for Radiation Response and Signal Generation in ScintillatorsĒ (Project number: PL10-Scin-theor-PD2Jf) and led by Drs. Fei Gao and Sebastien N. Kerisit. This project was divided into four tasks: 1) Electronic response functions (ab initio data model) 2) Electron-hole yield, variance, and spatial distribution 3) Ab initio calculations of information carrier properties 4) Transport of electron-hole pairs and scintillation efficiency Detailed information on the results obtained in each of the four tasks is provided in this Final Report. Furthermore, published peer-reviewed articles based on the work carried under this project are included in Appendix. This work was supported by the National Nuclear Security Administration, Office of Nuclear Nonproliferation Research and Development (DNN R&D/NA-22), of the U.S. Department of Energy (DOE).

Kerisit, Sebastien N.; Gao, Fei; Xie, YuLong; Campbell, Luke W.; Van Ginhoven, Renee M.; Wang, Zhiguo; Prange, Micah P.; Wu, Dangxin

2014-12-01T23:59:59.000Z

197

Annual report of waste generation and pollution prevention progress 1998  

SciTech Connect (OSTI)

This seventh Annual Report presents and analyzes DOE Complex-wide waste generation and pollution prevention activities at 45 reporting sites from 1993 through 1998. This section summarizes Calendar Year 1998 Complex-wide waste generation and pollution prevention accomplishments. More detailed information follows this section in the body of the Report. In May 1996, the Secretary of Energy established a 50 percent Complex-Wide Waste Reduction Goal (relative to the 1993 baseline) for routine operations radioactive, mixed, and hazardous waste generation, to be achieved by December31, 1999. DOE has achieved its Complex-Wide Waste Reduction Goals for routine operations based upon a comparison of 1998 waste generation to the 1993 baseline. Excluding sanitary waste, routine operations waste generation decreased 67 percent overall from 1993 to 1998. However, for the first time since 1994, the total amount of materials recycled by the Complex decreased from 109,600 metric tons in 1997 to 92,800 metric tons in 1998. This decrease is attributed to the fact that in 1997, several large ''one-time only'' recycling projects were conducted throughout the Complex. In order to demonstrate commitment to DOE's Complex-wide recycling goal, it is important for sites to identify all potential large-scale recycling/reuse opportunities.

NONE

1999-09-01T23:59:59.000Z

198

Seismic risk assessment as applied to the Zion Nuclear Generating Station  

SciTech Connect (OSTI)

To assist the US Nuclear Regulatory Commission (NRC) in its licensing and evaluation role, the NRC funded the Seismic Safety Margins Research Program (SSMRP) at Lawrence Livermore National Laboratory (LLNL) with the goal of developing tools and data bases to evaluate the risk of earthquake caused radioactive release from a commercial nuclear power plant. This paper describes the SSMRP risk assessment methodology and the results generated by applying this methodology to the Zion Nuclear Generating Station. In addition to describing the failure probabilities and risk values, the effects of assumptions about plant configuration, plant operation, and dependence will be given.

Wells, J.

1984-08-01T23:59:59.000Z

199

Integrated Nuclear-Renewable Energy Systems: Foundational Workshop Report  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) recognizes the need to transform the energy infrastructure of the U.S. and elsewhere to systems that can drastically reduce environmental impacts in an efficient and economically viable manner while utilizing both hydrocarbon resources and clean energy generation sources. Thus, DOE is supporting research and development that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options. A concept being advanced by the DOE Offices of Nuclear Energy (NE) and Energy Efficiency and Renewable Energy (EERE) is tighter coupling of nuclear and renewable energy sources in a manner that produces new energy currency for the combined electricity grid, industrial manufacturing, and the transportation energy sectors. This integration concept has been referred to as a ďhybrid systemĒ that is capable of providing the right type of energy, at the right time, in the right place. At the direction of DOE-NE and DOE-EERE leadership, project leads at Idaho National Laboratory (INL), National Renewable Energy Laboratory (NREL) and Massachusetts Institute of Technology (MIT) have identified and engaged stakeholders in discussing integrated energy systems that would optimize renewable and nuclear energy integration on a region-by-region basis. Subsequent work will entail conduct of technical, economic, environmental and socio-political evaluations of the leading integrated system options based on a set of criteria established with stakeholder input. The Foundational Workshop for Integrated Nuclear Ė Renewable Energy Systems was organized around the following objectives: 1. Identify and refine priority region-specific opportunities for integrated nuclear-renewable energy systems in the U.S.; 2. Select Figures of Merit (FOM) to rank and prioritize candidate systems; 3. Discuss enabling technology development needs; 4. Identify analysis requirements, capabilities and gaps to estimate FOM for integrated system options; 5. Identify experimental needs to develop and demonstrate nuclear-renewable energy systems.

Shannon Bragg-Sitton; Richard Boardman; John Collins; Mark Ruth; Owen Zinaman; Charles Forsberg

2014-08-01T23:59:59.000Z

200

Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings  

SciTech Connect (OSTI)

Two of the major challenges the U.S. energy sector faces are greenhouse gas emissions and oil that is both imported and potentially reaching a peak (the point at which maximum extraction is reached). Interest in development of both renewable and nuclear energy has been strong because both have potential for overcoming these challenges. Research in both energy sources is ongoing, but relatively little research has focused on the potential benefits of combining nuclear and renewable energy. In September 2011, the Joint Institute for Strategic Energy Analysis (JISEA) convened the Nuclear and Renewable Energy Synergies Workshop at the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to identify potential synergies and strategic leveraging opportunities between nuclear energy and renewable energy. Industry, government, and academic thought leaders gathered to identify potential broad categories of synergies and brainstorm topic areas for additional analysis and research and development (R&D). This report records the proceedings and outcomes of the workshop.

Ruth, M.; Antkowiak, M.; Gossett, S.

2011-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

Ian McKirdy

2011-07-01T23:59:59.000Z

202

Nuclear Theory and Applications progress report, January 1, 1989-- April 1, 1990  

SciTech Connect (OSTI)

This report contains brief papers on the following topics: data evaluation and libraries; data processing; nuclear applications; reactions; fission; and nuclear structure.

Strottman, D.D.; Mutschlecner, A.D. (comps.)

1990-12-01T23:59:59.000Z

203

Strategic special nuclear material inventory differences. Semi-annual report  

SciTech Connect (OSTI)

This report provides and explains the generally small differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. These Inventory Differences, previously called Material Unaccounted For (MUF), are being publicly released on a semiannual basis. This report covers data for the period from October 1, 1978, through March 31, 1979, and includes accounting corrections for data from earlier periods.

None

1980-01-01T23:59:59.000Z

204

Space nuclear safety program. Progress report, July 1983  

SciTech Connect (OSTI)

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.

Bronisz, S.E. (comp.)

1983-11-01T23:59:59.000Z

205

Raytheon explores thorium for next generation nuclear reactor  

SciTech Connect (OSTI)

Few new orders for nuclear power plants have been placed anywhere in the world in the last 20 years, but that is not discouraging Raytheon Engineers Constructors from making plans to explore new light water reactor technologies for commercial markets. The Lexington, Mass.-based company, which has extensive experience in nuclear power engineering and construction, has a vision for the light water reactor of the future - one that is based on the use of thorium-232, an element that decays over several steps to uranium-233. The use of thorium and a small amount of uranium that is 20 percent enriched is seen as providing operational, environmental, and safety advantages over reactors using the standard fuel mixture of uranium-238 and enriched uranium-235. According to Raytheon, the system could improve the economics of some reactors' operations by reducing fuel costs and lowering related waste volumes. At the same time, reactor safety could be improved by simpler control rod systems and the absence from reactor coolant of corrosive boric acid, which is used to slow neutrons in order to enhance reactions. Using thorium is also attractive because more of the fuel is burned up by the reactor, an estimated 12 percent as compared to about 4 percent for U-235. However, the technology's greatest attraction may well be its implications for nuclear proliferation. Growing plutonium inventories embedded in spent fuel rods from light water reactors have sparked concern worldwide. But according to Raytheon, using a thorium-based fuel core would alleviate this concern because it would produce only small quantities of plutonium. A thorium-based fuel system would produce 12 kilograms of plutonium over a decade versus 2,235 kilograms for an equivalent reactor operating with conventional uranium fuel.

Crawford, M.

1994-03-08T23:59:59.000Z

206

Next-generation nuclear fuel withstands high-temperature accident  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions andDataNationalNewport News Business55NewsNext

207

Annual report of waste generation and pollution prevention progress, 1994  

SciTech Connect (OSTI)

This Report summarizes the waste generation and pollution prevention activities of the major operational sites in the Department of Energy (DOE). We are witnessing progress in waste reduction from routine operations that are the focus of Department-wide reduction goals set by the Secretary on May 3,1996. The goals require that by the end of 1999, we reduce, recycle, reuse, and otherwise avoid waste generation to achieve a 50 percent reduction over 1993 levels. This Report provides the first measure of our progress in waste reduction and recycling against our 1993 waste generation baseline. While we see progress in reducing waste from our normal operations, we must begin to focus attention on waste generated by cleanup and facilities stabilization activities that are the major functions of the Office of Environmental Management. Reducing the generation of waste is one of the seven principles that I have established for the Office of Environmental Management Ten Year Plan. As part of our vision to complete a major portion of the environmental cleanup at DOE sites over the next ten years, we must utilize the potential of the pollution prevention program to reduce the cost of our cleanup program. We have included the Secretarial goals as part of the performance measures for the Ten Year Plan, and we are committed to implementing pollution prevention ideas. Through the efforts of both Federal and contractor employees, our pollution prevention program has reduced waste and the cost of our operations. I applaud their efforts and look forward to reporting further waste reduction progress in the next annual update of this Report.

NONE

1996-09-01T23:59:59.000Z

208

Report on aging of nuclear power plant reinforced concrete structures  

SciTech Connect (OSTI)

The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs.

Naus, D.J.; Oland, C.B. [Oak Ridge National Lab., TN (United States); Ellingwood, B.R. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

1996-03-01T23:59:59.000Z

209

State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, January 1992  

SciTech Connect (OSTI)

The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada`s responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency`s oversight responsibilities: (1) Assure that the health and safety of Nevada`s citizens are adequately protected with regard to any federal high-level radioactive waste program within the State; (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987; (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State; (4) Work closely and consult with affected local governments and State agencies; (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository.

NONE

1992-12-31T23:59:59.000Z

210

11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation  

E-Print Network [OSTI]

Search 11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation to employ nuclear fusion technologies in power generation by 2050. China will adopt a three-step strategy with thermonuclear reactors; the second step aims to raise the utilization rate of nuclear fuels from the current 1

211

Present and future nuclear power generation as a reflection of individual countries' resources and objectives  

SciTech Connect (OSTI)

The nuclear reactor industry has been in a state of decline for more than a decade in most of the world. The reasons are numerous and often unique to the energy situation of individual countries. Two commonly cited issues influence decisions relating to construction of reactors: costs and the need, or lack thereof, for additional generating capacity. Public concern has ''politicized'' the nuclear industry in many non-communist countries, causing a profound effect on the economics of the option. The nuclear installations and future plans are reviewed on a country-by-country basis for 36 countries in the light of the resources and objectives of each. Because oil and gas for power production throughout the world are being phased out as much as possible, coal-fired generation currently tends to be the chosen alternative to nuclear power production. Exceptions occur in many of the less developed countries that collectively have a very limited operating experience with nuclear reactors. The Chernobyl accident in the USSR alarmed the public; however, national strategies and plans to build reactors have not changed markedly in the interim. Assuming that the next decade of nuclear power generation is uneventful, additional electrical demand would cause the nuclear power industry to experience a rejuvenation in Europe as well as in the US. 80 refs., 3 figs., 22 tabs.

Borg, I.Y.

1987-06-26T23:59:59.000Z

212

Report on discussions with utility engineers about superconducting generators  

SciTech Connect (OSTI)

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

none,

1996-03-01T23:59:59.000Z

213

Isotope and Nuclear Chemistry Division annual report, FY 1983  

SciTech Connect (OSTI)

This report describes progress in the major research and development programs carried out in FY 1983 by the Isotope and Nuclear Chemistry Division. It covers radiochemical diagnostics of weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production, separation, and applications (including biomedical applications); element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced analytical techniques; development and applications; atmospheric chemistry and transport; and earth and planetary processes.

Heiken, J.H.; Lindberg, H.A. (eds.)

1984-05-01T23:59:59.000Z

214

Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports  

SciTech Connect (OSTI)

A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of 67 of the reports issued on these in-depth team inspections were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant systems, structures, and components. Relevant information was extracted from these inspection reports and sorted into several categories, including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J. [Brookhaven National Lab., Upton, NY (United States)

1993-12-01T23:59:59.000Z

215

Spent nuclear fuel project - criteria document spent nuclear fuel final safety analysis report  

SciTech Connect (OSTI)

The criteria document provides the criteria and planning guidance for developing the Spent Nuclear Fuel (SNF) Final Safety Analysis Report (FSAR). This FSAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, installation acceptance testing, startup, and operation of the SNF Project facilities (K Basins, Cold Vacuum Drying Facility, and Canister Storage Building).

MORGAN, R.G.

1999-02-23T23:59:59.000Z

216

Milliwatt Generator Project: April 1988--September 1996. Progress report  

SciTech Connect (OSTI)

This report covers progress on the Milliwatt Generator (MWG) Project from April 1988 to September 1996. Manufacturing of heat sources for the project ended by September 1990. Beginning in October 1990, the major activities of the project have been surveillance and testing of MWGs, disposal of excess MWGs, and reclamation of the PuO{sub 2} from excess MWG heat sources. Reported activities include fuel processing and characterization, production of heat sources, compatibility studies, impact testing, examination and electrical testing of surveillance units, and recovery of PuO{sub 2} from heat sources.

Latimer, T.W.

1997-07-01T23:59:59.000Z

217

Risk perception & strategic decision making :general insights, a framework, and specific application to electricity generation using nuclear energy.  

SciTech Connect (OSTI)

The objective of this report is to promote increased understanding of decision making processes and hopefully to enable improved decision making regarding high-consequence, highly sophisticated technological systems. This report brings together insights regarding risk perception and decision making across domains ranging from nuclear power technology safety, cognitive psychology, economics, science education, public policy, and neural science (to name a few). It forms them into a unique, coherent, concise framework, and list of strategies to aid in decision making. It is suggested that all decision makers, whether ordinary citizens, academics, or political leaders, ought to cultivate their abilities to separate the wheat from the chaff in these types of decision making instances. The wheat includes proper data sources and helpful human decision making heuristics; these should be sought. The chaff includes ''unhelpful biases'' that hinder proper interpretation of available data and lead people unwittingly toward inappropriate decision making ''strategies''; obviously, these should be avoided. It is further proposed that successfully accomplishing the wheat vs. chaff separation is very difficult, yet tenable. This report hopes to expose and facilitate navigation away from decision-making traps which often ensnare the unwary. Furthermore, it is emphasized that one's personal decision making biases can be examined, and tools can be provided allowing better means to generate, evaluate, and select among decision options. Many examples in this report are tailored to the energy domain (esp. nuclear power for electricity generation). The decision making framework and approach presented here are applicable to any high-consequence, highly sophisticated technological system.

Brewer, Jeffrey D.

2005-11-01T23:59:59.000Z

218

Audit Report on "The Department's Management of Nuclear Materials Provided to Domestic Licensees"  

SciTech Connect (OSTI)

The objective if to determine whether the Department of Energy (Department) was adequately managing its nuclear materials provided to domestic licensees. The audit was performed from February 2007 to September 2008 at Department Headquarters in Washington, DC, and Germantown, MD; the Oak Ridge Office and the Oak Ridge National Laboratory in Oak Ridge, TN. In addition, we visited or obtained data from 40 different non-Departmental facilities in various states. To accomplish the audit objective, we: (1) Reviewed Departmental and Nuclear Regulatory Commission (NRC) requirements for the control and accountability of nuclear materials; (2) Analyzed a Nuclear Materials Management and Safeguards System (NMMSS) report with ending inventory balances for Department-owned nuclear materials dated September 30, 2007, to determine the amount and types of nuclear materials located at non-Department domestic facilities; (3) Held discussions with Department and NRC personnel that used NMMSS information to determine their roles and responsibilities related to the control and accountability over nuclear materials; (4) Selected a judgmental sample of 40 non-Department domestic facilities; (5) Met with licensee officials and sent confirmations to determine whether their actual inventories of Department-owned nuclear materials were consistent with inventories reported in the NMMSS; and, (6) Analyzed historical information related to the 2004 NMMSS inventory rebaselining initiative to determine the quantity of Department-owned nuclear materials that were written off from the domestic licensees inventory balances. This performance audit was conducted in accordance with generally accepted Government auditing standards. Those standards require that we plan and perform the audit to obtain sufficient, appropriate evidence to provide a reasonable basis for our findings and conclusions based on our audit objective. We believe that the evidence obtained provides a reasonable basis for our findings and conclusions based on our audit objectives. The audit included tests of controls and compliance with laws and regulations related to managing the Department-owned nuclear materials provided to non-Departmental domestic licensees. Because our review was limited it would not necessarily have disclosed all internal control deficiencies that may have existed at the time of our audit. We examined the establishment of performance measures in accordance with Government Performance and Results Act of 1993, as they related to the audit objective. We found that the Department had established performance measures related to removing or disposing of nuclear materials and radiological sources around the world. We utilized computer generated data during our audit and performed procedures to validate the reliability of the information as necessary to satisfy our audit objective. As noted in the report, we questioned the reliability of the NMMSS data.

None

2009-02-01T23:59:59.000Z

219

CCN 217493 - Provide a Progress Report Describing the Status...  

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

1 of 6 Next Generation Nuclear Plant Licensing NGNP FUEL QUALIFICATION WHITE PAPER DEVELOPMENT STATUS REPORT August 2009 Introduction The Next Generation Nuclear Plant (NGNP)...

220

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux  

DOE Patents [OSTI]

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

Bowman, C.D.

1992-11-03T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux  

DOE Patents [OSTI]

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

Bowman, Charles D. (Los Alamos, NM)

1992-01-01T23:59:59.000Z

222

Nuclear waste treatment program. Annual report for FY 1985  

SciTech Connect (OSTI)

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are: (1) to ensure that waste management is not an obstacle to the further deployment of light-water reactors (LWR) and the closure of the nuclear fuel cycle and (2) to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Terminal Waste Disposal and Remedial Action of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory (PNL) during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide (1) documented technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and (2) problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required, to treat existing wastes. This annual report describes progress during FY 1985 toward meeting these two objectives. The detailed presentation is organized according to the task structure of the program.

Powell, J.A. (ed.)

1986-04-01T23:59:59.000Z

223

Nuclear waste treatment program: Annual report for FY 1987  

SciTech Connect (OSTI)

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs.

Brouns, R.A.; Powell, J.A. (comps.)

1988-09-01T23:59:59.000Z

224

Nuclear waste management. Quarterly progress report, January-March 1980  

SciTech Connect (OSTI)

Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-06-01T23:59:59.000Z

225

Nuclear waste management. Quarterly progress report, October-December 1979  

SciTech Connect (OSTI)

Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-04-01T23:59:59.000Z

226

Summary for the Next Generation Nuclear Plant Project in Review  

SciTech Connect (OSTI)

This paper reports on the major progress that the NGNP Project has made toward developing and commercializing the HTGR technology. Significant R&D progress has been made in addressing key technical issues for qualification of the HTGR fuel and graphite, codification of high temperature materials and verification and validation of design codes. Work is also progressing in heat transfer/transport design and testing and in development of the high temperature steam electrolysis hydrogen production process. A viable licensing strategy has been formulated in coordination with the NRC and DOE. White papers covering key licensing issues have been and will continue to be submitted and necessary discussions of these key issues have begun with the NRC. Continued government support is needed to complete the Project objectives as established in the 2005 Energy Policy Act.

L.E. Demick

2010-09-01T23:59:59.000Z

227

Energy Storage and Distributed Energy Generation Project, Final Project Report  

SciTech Connect (OSTI)

This report serves as a Final Report under the ďEnergy Storage and Distribution Energy Generation ProjectĒ carried out by the Transportation Energy Center (TEC) at the University of Michigan (UM). An interdisciplinary research team has been working on fundamental and applied research on: -distributed power generation and microgrids, -power electronics, and -advanced energy storage. The long-term objective of the project was to provide a framework for identifying fundamental research solutions to technology challenges of transmission and distribution, with special emphasis on distributed power generation, energy storage, control methodologies, and power electronics for microgrids, and to develop enabling technologies for novel energy storage and harvesting concepts that can be simulated, tested, and scaled up to provide relief for both underserved and overstressed portions of the Nationís grid. TECís research is closely associated with Sections 5.0 and 6.0 of the DOE "Five-year Program Plan for FY2008 to FY2012 for Electric Transmission and Distribution Programs, August 2006.Ē

Schwank, Johannes; Mader, Jerry; Chen, Xiaoyin; Mi, Chris; Linic, Suljo; Sastry, Ann Marie; Stefanopoulou, Anna; Thompson, Levi; Varde, Keshav

2008-03-31T23:59:59.000Z

228

Analysis of nuclear reactor instability phenomena. Progress report  

SciTech Connect (OSTI)

The phenomena known as density-wave instability often occurs in phase change systems, such as boiling water nuclear reactors (BWRS). Our current understanding of density-wave oscillations is in fairly good shape for linear phenomena (eg, the onset of instabilities) but is not very advanced for non-linear phenomena [Lahey and Podowski, 1989]. In particular, limit cycle and chaotic instability modes are not well understood in boiling systems such as current and advanced generation BWRs (eg, SBWR). In particular, the SBWR relies on natural circulation and is thus inherently prone to problems with density-wave instabilities. The purpose of this research is to develop a quantitative understanding of nonlinear nuclear-coupled density-wave instability phenomena in BWRS. This research builds on the work of Achard et al [1985] and Clausse et al [1991] who showed, respectively, that Hopf bifurcations and chaotic oscillations may occur in boiling systems.

Lahey, R.T. Jr.

1993-03-01T23:59:59.000Z

229

Report to Congress on Plan for Interim Storage of Spent Nuclear...  

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

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors More Documents & Publications Information Request, "THE REPORT TO THE PRESIDENT...

230

NUCLEAR CHEMISTRY DIV. ANNUAL REPORT 1980-81  

E-Print Network [OSTI]

Polarization Phenomena in Nuclear Physics-1980, AIP Conf.Barrett and D.F. Jackson, Nuclear Sizes and Structure, (K Production in Relativistic Nuclear Collisions A. Shor, K.

Cerny, J.

2010-01-01T23:59:59.000Z

231

* This reference number refers to the recommendation number given in the EPSRC/STFC Review of Nuclear Physics and Nuclear Engineering Report Action Plan for the EPSRC/STFC Review of Nuclear Physics and Nuclear Engineering  

E-Print Network [OSTI]

of Nuclear Physics and Nuclear Engineering Report Action Plan for the EPSRC/STFC Review of Nuclear Physics and Nuclear Engineering Preface This document will outline the recommendations in order of importance skills provision in nuclear engineering and related areas. Although these two areas have significant

232

D.McNew/GettyIMaGes San Onofre Nuclear Generating Station, California.  

E-Print Network [OSTI]

D.McNew/GettyIMaGes San Onofre Nuclear Generating Station, California. CORRESPONDENCE Checklist be supplied by solar power plants covering about 36,000 square kilometres of land in the desert southwest,theycanberampedupquickly.Annualinstallationofwind- energy capacity in the United States has quadrupled from Counterpoint Not wanted, not needed J. Doyne

233

Qualification of Class 1E static battery charges and inverters for nuclear power generating stations  

SciTech Connect (OSTI)

This standard describes methods for qualifying static battery chargers and inverters for Class 1E installations in environmentally controlled areas outside containment in nuclear power generating stations. The purpose of this standard is to provide specific procedures to meet the requirements of IEEE Std. 323-1974.

Not Available

1981-01-01T23:59:59.000Z

234

Generation IV Nuclear Energy Systems Ten-Year Program Plan Fiscal Year 2005, Volume 1  

SciTech Connect (OSTI)

As reflected in the U.S. ''National Energy Policy'', nuclear energy has a strong role to play in satisfying our nation's future energy security and environmental quality needs. The desirable environmental, economic, and sustainability attributes of nuclear energy give it a cornerstone position, not only in the U.S. energy portfolio, but also in the world's future energy portfolio. Accordingly, on September 20, 2002, U.S. Energy Secretary Spencer Abraham announced that, ''The United States and nine other countries have agreed to develop six Generation IV nuclear energy concepts''. The Secretary also noted that the systems are expected to ''represent significant advances in economics, safety, reliability, proliferation resistance, and waste minimization''. The six systems and their broad, worldwide research and development (R&D) needs are described in ''A Technology Roadmap for Generation IV Nuclear Energy Systems'' (hereafter referred to as the Generation IV Roadmap). The first 10 years of required U.S. R&D contributions to achieve the goals described in the Generation IV Roadmap are outlined in this Program Plan.

None

2005-03-01T23:59:59.000Z

235

Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.  

SciTech Connect (OSTI)

In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for both the PBMR and prismatic design. The main focus of this report is the RPV for both design concepts with emphasis on material selection.

Natesan, K.; Majumdar, S.; Shankar, P. S.; Shah, V. N.; Nuclear Engineering Division

2007-03-21T23:59:59.000Z

236

Nuclear structure studies. Progress report, [1988--1994  

SciTech Connect (OSTI)

In this report, newly initiated work at the FMA is described where the use of double-sided strip detectors for charged particle spectroscopy on nuclides near the proton drip line has been investigated. Half lives for proton emitting nuclides have been determined with improved uncertainties. Several sections report on the results of studies of model parameters in the Z = 50 region for even-even nuclides, for odd-mass nuclides and for odd-odd nuclides. Other studies are reported for nuclear orientation in Br and for structure of Pr-147 which lies in a transition zone between reflection-asymmetric, spherical, and prolate nuclides. And there is a section in which the positions of the single Particle levels in the A = 100 region are discussed.

Walters, W.B.

1993-07-31T23:59:59.000Z

237

Steam generator tube integrity program: Annual report, August 1995--September 1996. Volume 2  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on the Steam Generator Tube Integrity Program from the inception of the program in August 1995 through September 1996. The program is divided into five tasks: (1) assessment of inspection reliability, (2) research on ISI (inservice-inspection) technology, (3) research on degradation modes and integrity, (4) tube removals from steam generators, and (5) program management. Under Task 1, progress is reported on the preparation of facilities and evaluation of nondestructive evaluation techniques for inspecting a mock-up steam generator for round-robin testing, the development of better ways to correlate failure pressure and leak rate with eddy current (EC) signals, the inspection of sleeved tubes, workshop and training activities, and the evaluation of emerging NDE technology. Results are reported in Task 2 on closed-form solutions and finite-element electromagnetic modeling of EC probe responses for various probe designs and flaw characteristics. In Task 3, facilities are being designed and built for the production of cracked tubes under aggressive and near-prototypical conditions and for the testing of flawed and unflawed tubes under normal operating, accident, and severe-accident conditions. Crack behavior and stability are also being modeled to provide guidance for test facility design, develop an improved understanding of the expected rupture behavior of tubes with circumferential cracks, and predict the behavior of flawed and unflawed tubes under severe accident conditions. Task 4 is concerned with the acquisition of tubes and tube sections from retired steam generators for use in the other research tasks. Progress on the acquisition of tubes from the Salem and McGuire 1 nuclear plants is reported.

Diercks, D.R.; Bakhtiari, S.; Kasza, K.E.; Kupperman, D.S.; Majumdar, S.; Park, J.Y.; Shack, W.J. [Argonne National Lab., IL (United States)

1998-02-01T23:59:59.000Z

238

Magnetic Field Generation in Planets and Satellites by Natural Nuclear Fission Reactors  

E-Print Network [OSTI]

One of the most fundamental problems in physics has been to understand the nature of the mechanism that generates the geomagnetic field and the magnetic fields of other planets and satellites. For decades, the dynamo mechanism, thought to be responsible for generating the geomagnetic field and other planetary magnetic fields, has been ascribed to convection in each planet's iron-alloy core. Recently, I described the problems inherent in Earth-core convection and proposed instead that the geomagnetic field is produced by a dynamo mechanism involving convection, not in the fluid core, but in the electrically conductive, fluid, fission-product sub-shell of a natural nuclear fission reactor at the center of the Earth, called the georeactor. Here I set forth in detail the commonality in the Solar System of the matter like that of the inside of the Earth, which is my basis for generalizing the concept of planetary magnetic field generation by natural planetocentric nuclear fission reactors.

J. Marvin Herndon

2007-09-27T23:59:59.000Z

239

NUCLEAR SCIENCE DIVISION ANNUAL REPORT 1979-1980  

E-Print Network [OSTI]

of Square Law for Ceuteron Formation in Relavistic NuclearOF SQUARE LAW FOR DEUTERON FORMATION IN RELATIVISTIC NUCLEAR

Cerny, J.

2010-01-01T23:59:59.000Z

240

Milliwatt Generator Project. Progress report, April 1986--March 1988  

SciTech Connect (OSTI)

This report covers progress on the Milliwatt Generator Project from April 1986 through March 1988. Activities included fuel processing and characterization, production of heat sources, fabrication of pressure-burst test units, compatibility studies, impact testing, and examination of surveillance units. The major task of the Los Alamos Milliwatt Generator Project is to fabricate MC2893A heat sources (4.0 W) for MC2730A radioisotope thermoelectric generators (RTGS) and MC3599 heat sources (4.5 W) for MC3500 RTGs. The MWG Project interfaces with the following contractors: Sandia National Laboratories, Albuquerque (designer); E.I. du Pont de Nemours and Co. (Inc.), Savannah River Plant (fuel); Monsanto Research Corporation, Mound Facility (metal hardware); and General Electric Company, Neutron Devices Department (RTGs). In addition to MWG fabrication activities, Los Alamos is involved in (1) fabrication of pressure-burst test units, (2) compatibility testing and evaluation, (3) examination of surveillance units, and (4) impact testing and subsequent examination of compatibility and surveillance units.

Latimer, T.W.; Rinehart, G.H.

1992-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program  

SciTech Connect (OSTI)

Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

Not Available

1994-02-01T23:59:59.000Z

242

Worldwide assessment of steam-generator problems in pressurized-water-reactor nuclear power plants  

SciTech Connect (OSTI)

Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of PWR plant operations, plant types, and materials used in PWR plants. A review of the worldwide distribution of PWR plants is also given. The report describes in detail the degradation problems discovered in PWR steam generators: their causes, their impacts on the performance of steam generators, and the actions to mitigate and avoid them. One chapter is devoted to operating experience of PWR steam generators in foreign countries. Another discusses the improvements in future steam generator design.

Woo, H.H.; Lu, S.C.

1981-09-15T23:59:59.000Z

243

Nuclear Science Division annual report, October 1, 1984-September 30, 1985  

SciTech Connect (OSTI)

This report summarizes the activities of the Nuclear Science Division during the period October 1, 1984 to September 30, 1985. As in previous years, experimental research has for the most part been carried out using three local accelerators, the Bevalac, the SuperHILAC and the 88-Inch Cyclotron. However, during this time, preparations began for a new generation of relativistic heavy-ion experiments at CERN. The Nuclear Science Division is involved in three major experiments at CERN and several smaller ones. The report is divided into 5 sections. Part I describes the research programs and operations, and Part II contains condensations of experimental papers arranged roughly according to program and in order of increasing energy, without any further subdivisions. Part III contains condensations of theoretical papers, again ordered according to program but in order of decreasing energy. Improvements and innovations in instrumentation and in experimental or analytical techniques are presented in Part IV. Part V consists of appendices, the first listing publications by author for this period, in which the LBL report number only is given for papers that have not yet appeared in journals; the second contains abstracts of PhD theses awarded during this period; and the third gives the titles and speakers of the NSD Monday seminars, the Bevatron Research Meetings and the theory seminars that were given during the report period. The last appendix is an author index for this report.

Mahoney, J. (ed.)

1986-09-01T23:59:59.000Z

244

1 hour, 59 minutes ago President Jacques Chirac announced plans to build a prototype fourth-generation nuclear reactor by 2020 as well as symbolic targets  

E-Print Network [OSTI]

-generation nuclear reactor by 2020 as well as symbolic targets for cutting France's reliance on oil in the coming and is conducting research into several new models of nuclear reactor. Business leaders in the French energy sector-generation nuclear reactor 1/5/06 3:19 PMPrint Story: France to develop fourth-generation nuclear reactor on Yahoo

245

Nuclear Technology Programs semiannual progress report, April-- September 1990  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

Harmon, J.E. [ed.

1992-06-01T23:59:59.000Z

246

Nuclear Technology Programs semiannual progress report, April-- September 1990  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

Harmon, J.E. (ed.)

1992-06-01T23:59:59.000Z

247

Nuclear Technology Programs semiannual progress report, October 1988--March 1989  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1988--March 1989. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories. 127 refs., 76 figs., 103 tabs.

Harmon, J.E. [ed.

1990-12-01T23:59:59.000Z

248

Nuclear technology programs. Semiannual progress report, April--September 1991  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April through September 1991. These programs involve R & D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

Not Available

1993-07-01T23:59:59.000Z

249

Nuclear Technology Programs semiannual progress report, October 1990--March 1991  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1990--March 1991. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transpose of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

NONE

1992-12-01T23:59:59.000Z

250

Letter Report: Looking Ahead at Nuclear Fuel Resources  

SciTech Connect (OSTI)

The future of nuclear energy and its ability to fulfill part of the worldís energy needs for centuries to come depend on a reliable input of nuclear fuel, either thorium or uranium. Obviously, the present nuclear fuel cycle is completely dependent on uranium. Future thorium cycles will also depend on 235U or fissile isotopes separated from used fuel to breed 232Th into fissile 233U. This letter report discusses several emerging areas of scientific understanding and technology development that will clarify and enable assured supplies of uranium and thorium well into the future. At the most fundamental level, the nuclear energy community needs to appreciate the origins of uranium and thorium and the processes of planetary accretion by which those materials have coalesced to form the earth and other planets. Secondly, the studies of geophysics and geochemistry are increasing understanding of the processes by which uranium and thorium are concentrated in various locations in the earthís crust. Thirdly, the study of neutrinos and particularly geoneutrinos (neutrinos emitted by radioactive materials within the earth) has given an indication of the overall global inventories of uranium and thorium, though little indication for those materialsí locations. Crustal temperature measurements have also given hints of the vertical distribution of radioactive heat sources, primarily 238U and 232Th, within the continental crust. Finally, the evolving technologies for laser isotope separation are indicating methods for reducing the energy input to uranium enrichment but also for tailoring the isotopic vectors of fuels, burnable poisons and structural materials, thereby adding another tool for dealing with long-term waste management.

J. Stephen Herring

2013-09-01T23:59:59.000Z

251

Institute for Nuclear Theory annual report No. 2, 1 March 1991--29 February 1992  

SciTech Connect (OSTI)

This report discusses research on the following topics in Nuclear physics: electromagnetic interactions and few-nucleon systems; N*'s and nucleon structure; mesons and fields in nuclei; and nuclear astrophysics of type II supernovae. (LSP).

Haxton, W.; Henley, E.M. (Washington Univ., Seattle, WA (United States). Dept. of Physics)

1992-01-01T23:59:59.000Z

252

Nuclear Science Division, Annual report, October 1, 1988--December 31, 1990  

SciTech Connect (OSTI)

This report contains short papers of research conducted in the following areas: Low energy research program; bevalac research program; ultrarelativistic research program; nuclear theory program; nuclear data evaluation; and, 88-inch cyclotron operations.

Poskanzer, A.M.; Deleplanque, M.A.; Firestone, R.B.; Lofdahl, J.B. (eds.)

1991-04-01T23:59:59.000Z

253

Nuclear Science Division Annual Report 1984-85  

E-Print Network [OSTI]

M. Xcssi. and W. Wolf. Nuclear-Reaction-Time Studies of U +Kį Produced in Relativistic Nuclear Collisions Phys. Lett.Momentum Distributions of Nuclear Fragments in im Collisions

Mahoney Editor, Jeannette

2010-01-01T23:59:59.000Z

254

NUCLEAR SCIENCE DIVISION ANNUAL REPORT 1979-1980  

E-Print Network [OSTI]

1979). {Laboratory for Nuclear Studies, Osaka University,D. Loveland, and G. T. Seaborg, Nuclear Science Div. AnnualBohr and B. R. Hottel son. Nuclear Structure Vol. 1 (W. A.

Cerny, J.

2010-01-01T23:59:59.000Z

255

Nuclear Science Division Annual Report 1995-1996  

E-Print Network [OSTI]

Saladin5, and C.H. Yu6 Nuclear Science Division, LawrenceMoretto, G.J. Wozniak, Nuclear Science Division, LawrenceComment on ďProbing the Nuclear Liquid-Gas Phase TransitionĒ

Authors, Various

2010-01-01T23:59:59.000Z

256

IEEE Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations  

SciTech Connect (OSTI)

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard.

Not Available

1980-01-01T23:59:59.000Z

257

Confirmatory Survey Results for the Reactor Building Dome Upper Surfaces, Rancho Saco Nuclear Generating Station  

SciTech Connect (OSTI)

Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006.

Wade C. Adams

2006-10-25T23:59:59.000Z

258

Ris Energy Report 4 Distributed generation 1 What is distributed generation?  

E-Print Network [OSTI]

generation (DG) refers to an emerging evolu- tion of the electric power generation systems, in which all electricity generation it is obviously understood as consisting of small size generation units only, but when referred to as large-scale electricity generation it is usually understood as containing a high proportion

259

Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory  

SciTech Connect (OSTI)

One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

J. D. Bess; J. B. Briggs; A. S. Garcia

2011-09-01T23:59:59.000Z

260

October 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE  

Broader source: Energy.gov [DOE]

The Global Nuclear Energy Partnership (GNEP) program is still evolving. Since our report of March 22, 2006 the DOE has sought to gauge industry interest in participation in the program from its...

Note: This page contains sample records for the topic "nuclear generation reported" 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

Locating hot and cold-legs in a nuclear powered steam generation system  

DOE Patents [OSTI]

A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet.

Ekeroth, Douglas E. (Delmont, PA); Corletti, Michael M. (New Kensington, PA)

1993-01-01T23:59:59.000Z

262

Locating hot and cold-legs in a nuclear powered steam generation system  

DOE Patents [OSTI]

A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet. 2 figures.

Ekeroth, D.E.; Corletti, M.M.

1993-11-16T23:59:59.000Z

263

Agile Machining and Inspection Non-Nuclear Report (NNR) Project  

SciTech Connect (OSTI)

This report is a high level summary of the eight major projects funded by the Agile Machining and Inspection Non-Nuclear Readiness (NNR) project (FY06.0422.3.04.R1). The largest project of the group is the Rapid Response project in which the six major sub categories are summarized. This project focused on the operations of the machining departments that will comprise Special Applications Machining (SAM) in the Kansas City Responsive Infrastructure Manufacturing & Sourcing (KCRIMS) project. This project was aimed at upgrading older machine tools, developing new inspection tools, eliminating Classified Removable Electronic Media (CREM) in the handling of classified Numerical Control (NC) programs by installing the CRONOS network, and developing methods to automatically load Coordinated-Measuring Machine (CMM) inspection data into bomb books and product score cards. Finally, the project personnel leaned perations of some of the machine tool cells, and now have the model to continue this activity.

Lazarus, Lloyd

2009-02-19T23:59:59.000Z

264

Nuclear waste management. Quarterly progress report, April-June 1980  

SciTech Connect (OSTI)

The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

Platt, A.M.; Powell, J.A. (comps.)

1980-09-01T23:59:59.000Z

265

Nuclear waste management. Quarterly progress report, October through December 1980  

SciTech Connect (OSTI)

Progress reports and summaries are presented under the following headings: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of radionuclides in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; high level waste form preparation; development of backfill material; development of structural engineered barriers; ONWI disposal charge analysis; spent fuel and fuel component integrity program; analysis of spent fuel policy implementation; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; revegetation of inactive uranium tailing sites; verification instrument development.

Chikalla, T.D.; Powell, J.A. (comps.)

1981-03-01T23:59:59.000Z

266

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 6: Process Heat and Hydrogen Co-Generation PIRTs  

SciTech Connect (OSTI)

A Phenomena Identification and Ranking Table (PIRT) exercise was conducted to identify potential safety-0-related physical phenomena for the Next Generation Nuclear Plant (NGNP) when coupled to a hydrogen production or similar chemical plant. The NGNP is a very high-temperature reactor (VHTR) with the design goal to produce high-temperature heat and electricity for nearby chemical plants. Because high-temperature heat can only be transported limited distances, the two plants will be close to each other. One of the primary applications for the VHTR would be to supply heat and electricity for the production of hydrogen. There was no assessment of chemical plant safety challenges. The primary application of this PIRT is to support the safety analysis of the NGNP coupled one or more small hydrogen production pilot plants. However, the chemical plant processes to be coupled to the NGNP have not yet been chosen; thus, a broad PIRT assessment was conducted to scope alternative potential applications and test facilities associated with the NGNP. The hazards associated with various chemicals and methods to minimize risks from those hazards are well understood within the chemical industry. Much but not all of the information required to assure safe conditions (separation distance, relative elevation, berms) is known for a reactor coupled to a chemical plant. There is also some experience with nuclear plants in several countries that have produced steam for industrial applications. The specific characteristics of the chemical plant, site layout, and the maximum stored inventories of chemicals can provide the starting point for the safety assessments. While the panel identified events and phenomena of safety significance, there is one added caveat. Multiple high-temperature reactors provide safety-related experience and understanding of reactor safety. In contrast, there have been only limited safety studies of coupled chemical and nuclear plants. The work herein provides a starting point for those studies; but, the general level of understanding of safety in coupling nuclear and chemical plants is less than in other areas of high-temperature reactor safety.

Forsberg, Charles W [ORNL; Gorensek, M. B. [Savannah River National Laboratory (SRNL); Herring, S. [Idaho National Laboratory (INL); Pickard, P. [Sandia National Laboratories (SNL)

2008-03-01T23:59:59.000Z

267

HYDROGEN GENERATION FROM ELECTROLYSIS - REVISED FINAL TECHNICAL REPORT  

SciTech Connect (OSTI)

DOE GO13028-0001 DESCRIPTION/ABSTRACT This report is a summary of the work performed by Teledyne Energy Systems to understand high pressure electrolysis mechanisms, investigate and address safety concerns related to high pressure electrolysis, develop methods to test components and systems of a high pressure electrolyzer, and produce design specifications for a low cost high pressure electrolysis system using lessons learned throughout the project. Included in this report are data on separator materials, electrode materials, structural cell design, and dissolved gas tests. Also included are the results of trade studies for active area, component design analysis, high pressure hydrogen/oxygen reactions, and control systems design. Several key pieces of a high pressure electrolysis system were investigated in this project and the results will be useful in further attempts at high pressure and/or low cost hydrogen generator projects. An important portion of the testing and research performed in this study are the safety issues that are present in a high pressure electrolyzer system and that they can not easily be simplified to a level where units can be manufactured at the cost goals specified, or operated by other than trained personnel in a well safeguarded environment. The two key objectives of the program were to develop a system to supply hydrogen at a rate of at least 10,000 scf/day at a pressure of 5000psi, and to meet cost goals of $600/ kW in production quantities of 10,000/year. On these two points TESI was not successful. The project was halted due to concerns over safety of high pressure gas electrolysis and the associated costs of a system which reduced the safety concerns.

IBRAHIM, SAMIR; STICHTER, MICHAEL

2008-07-31T23:59:59.000Z

268

Composite Materials under Extreme Radiation and Temperature Environments of the Next Generation Nuclear Reactors  

SciTech Connect (OSTI)

In the nuclear energy renaissance, driven by fission reactor concepts utilizing very high temperatures and fast neutron spectra, materials with enhanced performance that exceeds are expected to play a central role. With the operating temperatures of the Generation III reactors bringing the classical reactor materials close to their performance limits there is an urgent need to develop and qualify new alloys and composites. Efforts have been focused on the intricate relations and the high demands placed on materials at the anticipated extreme states within the next generation fusion and fission reactors which combine high radiation fluxes, elevated temperatures and aggressive environments. While nuclear reactors have been in operation for several decades, the structural materials associated with the next generation options need to endure much higher temperatures (1200 C), higher neutron doses (tens of displacements per atom, dpa), and extremely corrosive environments, which are beyond the experience on materials accumulated to-date. The most important consideration is the performance and reliability of structural materials for both in-core and out-of-core functions. While there exists a great body of nuclear materials research and operating experience/performance from fission reactors where epithermal and thermal neutrons interact with materials and alter their physio-mechanical properties, a process that is well understood by now, there are no operating or even experimental facilities that will facilitate the extreme conditions of flux and temperature anticipated and thus provide insights into the behaviour of these well understood materials. Materials, however, still need to be developed and their interaction and damage potential or lifetime to be quantified for the next generation nuclear energy. Based on material development advances, composites, and in particular ceramic composites, seem to inherently possess properties suitable for key functions within the operating envelope of both fission and fusion reactors. In advanced fission reactors composite materials are being designed in an effort to extend the life and improve the reliability of fuel rod cladding as well as structural materials. Composites are being considered for use as core internals in the next generation of gas-cooled reactors. Further, next-generation plasma-fusion reactors, such as the International Thermonuclear Experimental Reactor (ITER) will rely on the capabilities of advanced composites to safely withstand extremely high neutron fluxes while providing superior thermal shock resistance.

Simos, N.

2011-05-01T23:59:59.000Z

269

CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS  

SciTech Connect (OSTI)

The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and attempts to answer this question: What type of SNF cask would be produced if we were to start over and design SNF casks based on today's requirements? The characteristics for a next-generation SNF cask system are examined and are found to be essentially the same in Russia and the United States. It appears that the new depleted uranium dioxide (DUO2)-steel cermet material will enable these requirements to be met. Depleted uranium (DU) is uranium in which a portion of the 235U isotope has been removed during a uranium enrichment process. The DUO2-steel cermet material is described. The United States and Russia are cooperating toward the development of a next-generation, dual-purpose, storage and transport SNF system.

Haire, M.J.; Forsberg, C.W.; Matveev, V.Z.; Shapovalov, V.I.

2004-10-03T23:59:59.000Z

270

Institute for Nuclear Theory. Annual report No. 3, 1 March 1992--28 February 1993  

SciTech Connect (OSTI)

This report briefly discussion the following programs of the Institute for Nuclear Theory: fundamental interactions in nuclei; strangeness in hadrons and nuclei; microscopic nuclear structure theory; nuclear physics in atoms and molecules; phenomenology and lattice QCD; and large amplitude collective motion.

Haxton, W.; Bertsch, G.; Henley, E.M.

1993-07-01T23:59:59.000Z

271

U.N. report concludes that Syrian site destroyed in 2007 was a nuclear reactor  

E-Print Network [OSTI]

U.N. report concludes that Syrian site destroyed in 2007 was a nuclear reactor Joby Warrick, 24 May.N. claims was a nuclear plant before and after a Sept. 6 Israeli airstrike. The left image is from 5 Aug that Syria "very likely" was building a secret nuclear reactor in 2007 when the partially completed project

272

REPORT OF THE TASK FORCE ON NUCLEAR NONPROLIFERATION  

Broader source: Energy.gov [DOE]

The Secretary of Energy on December 20, 2013 established the Secretary of Energy Advisory Board (SEAB) Task Force on Nuclear Nonproliferation and charged the Task Force to advise the DOE on future areas of emphasis for its nuclear nonproliferation activities

273

NNSA Releases New Nuclear Prevent, Counter, and Respond Report...  

National Nuclear Security Administration (NNSA)

Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

274

Potential Applications for Nuclear Energy besides Electricity Generation: AREVA Global Perspective of HTR Potential Market  

SciTech Connect (OSTI)

Energy supply is increasingly showing up as a major issue for electricity supply, transportation, settlement, and process heat industrial supply including hydrogen production. Nuclear power is part of the solution. For electricity supply, as exemplified in Finland and France, the EPR brings an immediate answer; HTR could bring another solution in some specific cases. For other supply, mostly heat, the HTR brings a solution inaccessible to conventional nuclear power plants for very high or even high temperature. As fossil fuels costs increase and efforts to avoid generation of Greenhouse gases are implemented, a market for nuclear generated process heat will develop. Following active developments in the 80's, HTR have been put on the back burner up to 5 years ago. Light water reactors are widely dominating the nuclear production field today. However, interest in the HTR technology was renewed in the past few years. Several commercial projects are actively promoted, most of them aiming at electricity production. ANTARES is today AREVA's response to the cogeneration market. It distinguishes itself from other concepts with its indirect cycle design powering a combined cycle power plant. Several reasons support this design choice, one of the most important of which is the design flexibility to adapt readily to combined heat and power applications. From the start, AREVA made the choice of such flexibility with the belief that the HTR market is not so much in competition with LWR in the sole electricity market but in the specific added value market of cogeneration and process heat. In view of the volatility of the costs of fossil fuels, AREVA's choice brings to the large industrial heat applications the fuel cost predictability of nuclear fuel with the efficiency of a high temperature heat source free of greenhouse gases emissions. The ANTARES module produces 600 MWth which can be split into the required process heat, the remaining power drives an adapted prorated electric plant. Depending on the process heat temperature and power needs, up to 80 % of the nuclear heat is converted into useful power. An important feature of the design is the standardization of the heat source, as independent as possible of the process heat application. This should expedite licensing. The essential conditions for success include: 1. Timely adapted licensing process and regulations, codes and standards for such application and design; 2. An industry oriented R and D program to meet the technological challenges making the best use of the international collaboration. Gen IV could be the vector; 3. Identification of an end user (or a consortium of) willing to fund a FOAK. (authors)

Soutworth, Finis; Gauthier, Jean-Claude; Lecomte, Michel [AREVA, 3315 Old Forest Road, Lynchburg, Virginia, 24506 (United States); Carre, Franck [CEA, Saclay (France)

2007-07-01T23:59:59.000Z

275

Method and apparatus for steam mixing a nuclear fueled electricity generation system  

DOE Patents [OSTI]

A method and apparatus for improving the efficiency and performance of a nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a micro-jet high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life. An additional advantage is the reduction in erosion/corrosion of secondary system components including turbine blades and diaphragms. The gas turbine generator used in the instant invention can also replace or augment existing peak or emergency power needs. Another benefit of the instant invention is the extension of plant life and the reduction of downtime due to refueling.

Tsiklauri, Georgi V. (Richland, WA); Durst, Bruce M. (Kennewick, WA)

1996-01-01T23:59:59.000Z

276

Method and apparatus for improving the performance of a nuclear power electrical generation system  

DOE Patents [OSTI]

A method and apparatus for improving the efficiency and performance a of nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life. An additional advantage is the reduction in erosion/corrosion of secondary system components including turbine blades and diaphragms. The gas turbine generator used in the instant invention can also replace or augment existing peak or emergency power needs.

Tsiklauri, Georgi V. (Richland, WA); Durst, Bruce M. (Kennewick, WA)

1995-01-01T23:59:59.000Z

277

Nuclear Hybrid Energy System: Molten Salt Energy Storage (Summer Report 2013)  

SciTech Connect (OSTI)

Effective energy use is a main focus and concern in the world today because of the growing demand for energy. The nuclear hybrid energy system (NHES) is a valuable technical concept that can potentially diversify and leverage existing energy technologies. This report considers a particular NHES design that combines multiple energy systems including a nuclear reactor, energy storage system (ESS), variable renewable generator (VRG), and additional process heat applications. Energy storage is an essential component of this particular NHES because its design allows the system to produce peak power while the nuclear reactor operates at constant power output. Many energy storage options are available, but this study mainly focuses on a molten salt ESS. The primary purpose of the molten salt ESS is to enable the nuclear reactor to be a purely constant heat source by acting as a heat storage component for the reactor during times of low demand, and providing additional capacity for thermo-electric power generation during times of peak electricity demand. This report will describe the rationale behind using a molten salt ESS and identify an efficient molten salt ESS configuration that may be used in load following power applications. Several criteria are considered for effective energy storage and are used to identify the most effective ESS within the NHES. Different types of energy storage are briefly described with their advantages and disadvantages. The general analysis to determine the most efficient molten salt ESS involves two parts: thermodynamic, in which energetic and exergetic efficiencies are considered; and economic. Within the molten salt ESS, the two-part analysis covers three major system elements: molten salt ESS designs (two tank direct and thermocline), the molten salt choice, and the different power cycles coupled with the molten salt ESS. Analysis models are formulated and analyzed to determine the most effective ESS. The results show that the most efficient idealized energy storage system is the two tank direct molten salt ESS with an Air Brayton combined cycle using LiF-NaF-KF as the molten salt, and the most economical is the same design with KCl MgCl2 as the molten salt. With energy production being a major worldwide industry, understanding the most efficient molten salt ESS boosts development of an effective NHES with cheap, clean, and steady power.

Piyush Sabharwall; Michael George mckellar; Su-Jong Yoon

2013-11-01T23:59:59.000Z

278

Report of the Nuclear Energy Research Advisory Committee, Subcommittee on Nuclear Laboratory Requirements  

Broader source: Energy.gov [DOE]

As an element of its plans to return the U.S. Department of Energy (DOE) site in eastern Idaho to its historic mission of nuclear technology development, the DOE asked its Nuclear Energy Research...

279

Nuclear Plant Feedwater Heater Handbook. Volume 3. Operation and maintenance guidelines. Final report  

SciTech Connect (OSTI)

This document is the third part of a three-volume handbook covering closed feedwater heaters for nuclear electric power generating plants. This third volume covers the operation and maintenance of closed feedwater heaters. 11 refs., 23 figs., 5 tabs.

Bell, R.J.; Hardy, C.D. Jr.

1985-06-01T23:59:59.000Z

280

Report on the Savannah River Site aluminum-based spent nuclear fuel alternatives cost study  

SciTech Connect (OSTI)

Initial estimates of costs for the interim management and disposal of aluminum-based spent nuclear fuel (SNF) were developed during preparation of the Environmental Impact Statement (EIS) on the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. The Task Team evaluated multiple alternatives, assessing programmatic, technical, and schedule risks, and generated life-cycle cost projections for each alternative. The eight technology alternatives evaluated were: direct co-disposal; melt and dilute; reprocessing; press and dilute; glass material oxidation dissolution system (GMODS); electrometallurgical treatment; dissolve and vitrify; and plasma arc. In followup to the Business Plan that was developed to look at SNF dry storage, WSRC prepared an addendum to the cost study. This addendum estimated the costs for the modification and use of an existing (105L) reactor facility versus a greenfield approach for new facilities (for the Direct Co-Disposal and Melt and Dilute alternatives). WSRC assessed the impacts of a delay in reprocessing due to the potential reservation of H-Canyon for other missions (i.e., down blending HEU for commercial use or the conversion of plutonium to either MOX fuel or an immobilized repository disposal form). This report presents the relevant results from these WSRC cost studies, consistent with the most recent project policy, technology implementation, canyon utilization, and inventory assumptions. As this is a summary report, detailed information on the technical alternatives or the cost assumptions raised in each of the above-mentioned cost studies is not provided. A comparison table that briefly describes the bases used for the WSRC analyses is included as Appendix A.

NONE

1998-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Audit Report on "The National Nuclear Security Administration...  

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

Department of Energy's Sandia National Laboratories are refurbishing the Spin Rocket Motor, a prime component of the B61 nuclear weapon system. Both the original motor produced...

282

A compilation of reports of the Advisory Committee on nuclear waste, July 1996--June 1997  

SciTech Connect (OSTI)

This compilation contains 11 reports issued by the Advisory Committee on Nuclear Waste (ACNW) during the ninth year of its operation. The reports were submitted to the Chairman and Commissioners of the U.S. Nuclear Regulatory Commission. All reports prepared by the Committee have been made available to the public through the NRC Public Document Room, the U.S. Library of Congress, and the internet at http://www.nrc.gov/ACRSACNW.

NONE

1997-08-01T23:59:59.000Z

283

Chemistry-Nuclear Chemistry Division. Progress report, October 1980-September 1981  

SciTech Connect (OSTI)

This report describes major progress in the research and development programs pursued by the Chemistry-Nuclear Chemistry Division of the Los Alamos National Laboratory during FY 1981. Topics covered include advanced analytical methods, atmospheric chemistry and transport, biochemistry, biomedical research, medical radioisotopes research, element migration and fixation, nuclear waste isolation research, inorganic and structural chemistry, isotope separation, analysis and applications, the newly established Nuclear Magnetic Resonance Center, atomic and molecular collisions, molecular spectroscopy, nuclear cosmochemistry, nuclear structure and reactions, pion charge exchange, radiochemical separations, theoretical chemistry, and unclassified weapons research.

Ryan, R.R. (comp.)

1982-05-01T23:59:59.000Z

284

Safety research programs sponsored by Office of Nuclear Regulatory Research: Quarterly progress report, July 1-September 30, 1986  

SciTech Connect (OSTI)

This progress report will describe current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Accident Evaluation, Division of Engineering Technology, and Division of Risk Analysis and Operations of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The projects reported are the following: High Temperature Reactor Research, SSC code improvements, Thermal-Hydraulic Reactor Safety Experiments, Thermodynamic Core-Concrete Interaction Experiments and Analysis, Plant Analyzer, Code Assessment and Application, Code Maintenance (RAMONA-3B), MELCOR Verification and Benchmarking, Source Term Code Package Verification and Benchmarking, Uncertainty Analysis of the Source Term; Stress Corrosion Cracking of PWR Steam Generator Tubing, Soil-Structure Interaction Evaluation and Structural Benchmarks, Identification of Age Related Failure Modes; Application of HRA/PRA Results to Support Resolution of Generic Safety Issues Involving Human Performance, Protective Action Decisionmaking, Rebaseling of Risk for Zion, Containment Performance Design Objective, and Operational Safety Reliability Research.

Bari, R.A.; Bezler, P.; Boccio, J.L.; Ginsberg, T.; Greene, G.A.; Guppy, J.G.; Hall, R.E.; Hofmayer, C.H.; Khatib-Rahbar, H.; Luckas, W.J. Jr.

1987-03-01T23:59:59.000Z

285

Nuclear moments and nuclear structure. Annual progress report, August 1, 1981-August 31, 1982  

SciTech Connect (OSTI)

This report is a review of the activities of the period from August 1, 1981 through August 31, 1982. The final analysis of pi-zero production in heavy ion collisions representing experiments at the Bevalac with a system previously described is completed. The main results involve cross sections for central collisions resulting in the production of pi-zeros, charged pions, and proton multiplicities, and some results of correlations and low energy gamma radiation. Results from the alpha-alpha experiment at the CERN ISR are included in the form of a published paper and an outline of papers that are in press. A short report of a collision effect in an anomalon experiment is included as well. The energetic particle spectra from ..mu../sup -/-capture in medium heavy nuclei were studied at TRIUMF, using the large scintillation counters for neutron and proton detection and multiple Ge(Li) and NaI(Tl) counters. The preliminary analysis indicates the presence of such an unusual energetic component. The measurement of the particle and ..gamma..-ray correlation in ..pi../sup -/-capture in /sup 165/Ho was completed during this year, and the data analysis is continuing in order to elucidate the discrete spectral features, high spin generation and other correlations. A measurement was finished in our search for a new type of strong perturbation of pionic x-ray by the use of coincidences between pionic x-rays and ..gamma..-rays from a deformed nuclei.

Madansky, L.; Lee, Y.K.

1982-01-01T23:59:59.000Z

286

Joint electric power alternatives study. Appendix G. Joint parallel nuclear alternatives study for Russia. Final report  

SciTech Connect (OSTI)

The Joint Parallel Nuclear Alternatives Study for Russia (JPNAS) is a parallel study to the Joint Electric Power Alternatives Study (JEPAS). The JPNAS assessed the costs of enhancing the safety level of Russian nuclear power plants (NPPs), decommissioning of RBMK-1000 and first generation VVER-440 units, completion of NPP construction, NPP repowering into fossil fuel plants, and construction of new generation NPPs. In the framework of the JEPAS, the JPNAS provides data on the nuclear sector which is needed to formulate an integrated resources plan and schedule for investments for the development of Russia`s power sector.

NONE

1995-06-01T23:59:59.000Z

287

Next generation geothermal power plants. Draft final report  

SciTech Connect (OSTI)

The goal of this project is to develop concepts for the next generation geothermal power plant(s) (NGGPP). This plant, compared to existing plants, will generate power for a lower levelized cost and will be more competitive with fossil fuel fired power plants. The NGGPP will utilize geothermal resources efficiently and will be equipped with contingencies to mitigate the risk of reservoir performance. The NGGPP design will attempt to minimize emission of pollutants and consumption of surface water and/or geothermal fluids for cooling service.

Brugman, John; Hattar, John; Nichols, Kenneth; Esaki, Yuri

1994-12-01T23:59:59.000Z

288

Safety Reports Series No. 11, Developing Safety Culture in Nuclear Activities: Practical Suggestions to Assist Progress, International Atomic Energy Agency  

Broader source: Energy.gov [DOE]

Safety Reports Series No. 11, Developing Safety Culture in Nuclear Activities: Practical Suggestions to Assist Progress, International Atomic Energy Agency

289

EVALUATION METHODOLOGY FOR PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION OF GENERATION IV NUCLEAR ENERGY SYSTEMS: AN OVERVIEW.  

SciTech Connect (OSTI)

This paper provides an overview of the methodology approach developed by the Generation IV International Forum Expert Group on Proliferation Resistance & Physical Protection for evaluation of Proliferation Resistance and Physical Protection robustness of Generation IV nuclear energy systems options. The methodology considers a set of alternative systems and evaluates their resistance or robustness to a collection of potential threats. For the challenges considered, the response of the system to these challenges is assessed and expressed in terms of outcomes. The challenges to the system are given by the threats posed by potential proliferant States and sub-national adversaries on the nuclear systems. The characteristics of the Generation IV systems, both technical and institutional, are used to evaluate their response to the threats and determine their resistance against the proliferation threats and robustness against sabotage and theft threats. System response encompasses three main elements: (1) System Element Identification. The nuclear energy system is decomposed into smaller elements (subsystems) at a level amenable to further analysis. (2) Target Identification and Categorization. A systematic process is used to identify and select representative targets for different categories of pathways, within each system element, that actors (proliferant States or adversaries) might choose to use or attack. (3) Pathway Identification and Refinement. Pathways are defined as potential sequences of events and actions followed by the proliferant State or adversary to achieve its objectives (proliferation, theft or sabotage). For each target, individual pathway segments are developed through a systematic process, analyzed at a high level, and screened where possible. Segments are connected into full pathways and analyzed in detail. The outcomes of the system response are expressed in terms of PR&PP measures. Measures are high-level characteristics of a pathway that include information important to the evaluation methodology users and to the decisions of a proliferant State or adversary. They are first evaluated for segments and then aggregated for complete pathways. Results are aggregated as appropriate to permit pathway comparisons and system assessment. The paper highlights the current achievements in the development of the Proliferation Resistance and Physical Protection Evaluation Methodology. The way forward is also briefly presented together with some conclusions.

BARI, R.; ET AL.

2006-03-01T23:59:59.000Z

290

Evaluation Methodology For Proliferation Resistance And Physical Protection Of Generation IV Nuclear Energy Systems: An Overview  

SciTech Connect (OSTI)

This paper provides an overview of the methodology approach developed by the Generation IV International Forum Expert Group on Proliferation Resistance & Physical Protection for evaluation of Proliferation Resistance and Physical Protection robustness of Generation IV nuclear energy systems options. The methodology considers a set of alternative systems and evaluates their resistance or robustness to a collection of potential threats. For the challenges considered, the response of the system to these challenges is assessed and expressed in terms of outcomes. The challenges to the system are given by the threats posed by potential proliferant States and sub-national adversaries on the nuclear systems. The characteristics of the Generation IV systems, both technical and institutional, are used to evaluate their response to the threats and determine their resistance against the proliferation threats and robustness against sabotage and theft threats. System response encompasses three main elements: 1.System Element Identification. The nuclear energy system is decomposed into smaller elements (subsystems) at a level amenable to further analysis. 2.Target Identification and Categorization. A systematic process is used to identify and select representative targets for different categories of pathways, within each system element, that actors (proliferant States or adversaries) might choose to use or attack. 3.Pathway Identification and Refinement. Pathways are defined as potential sequences of events and actions followed by the proliferant State or adversary to achieve its objectives (proliferation, theft or sabotage). For each target, individual pathway segments are developed through a systematic process, analyzed at a high level, and screened where possible. Segments are connected into full pathways and analyzed in detail. The outcomes of the system response are expressed in terms of PR&PP measures. Measures are high-level characteristics of a pathway that include information important to the evaluation methodology users and to the decisions of a proliferant State or adversary. They are first evaluated for segments and then aggregated for complete pathways. Results are aggregated as appropriate to permit pathway comparisons and system assessment. The paper highlights the current achievements in the development of the Proliferation Resistance and Physical Protection Evaluation Methodology. The way forward is also briefly presented together with some conclusions.

T. Bjornard; R. Bari; R. Nishimura; P. Peterson; J. Roglans; D. Bley; J. Cazalet; G.G.M. Cojazzi; P. Delaune; M. Golay; G. Rendad; G. Rochau; M. Senzaki; I. Therios; M. Zentner

2006-05-01T23:59:59.000Z

291

Studies of nuclear processes at the Triangle Universities Nuclear Laboratory. Progress report, 1 September 1994--31 August 1995  

SciTech Connect (OSTI)

The Triangle Universities Nuclear Laboratory (TUNL)--a collaboration of Duke University, North Carolina State University, and the University of North Carolina at Chapel Hill--has had a very productive year. This report covers the second year of a three-year grant between the US Department of Energy and the three collaborating universities. The TUNL research program focuses on the following areas of nuclear physics: parity violation in neutron and charged-particle resonances--the mass and energy dependence of the weak interaction spreading width; chaotic behavior in {sup 30}P from studies of eigenvalue fluctuations in nuclear level schemes; studies of few-body systems; nuclear astrophysics; nuclear data evaluation for A = 3--20, for which TUNL is now the international center; high-spin spectroscopy and superdeformation in nuclei, involving collaborations at Argonne National Laboratory. Developments in technology and instrumentation have been vital to the research and training program. In this progress report the author describes: a proposed polarized {gamma}-beam facility at the Duke Free Electron Laser Laboratory; cryogenic systems and microcalorimeter development; continuing development of the Low Energy Beam Facility. The research summaries presented in this progress report are preliminary.

Ludwig, E.J.

1995-09-01T23:59:59.000Z

292

Procedure for Generating Data Quality Reports for SIRS Radiometric Measurements  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FORPoints ofProbingDewetting anditsquantum2

293

Power Generation Subprogram status report, 1988-1989  

SciTech Connect (OSTI)

The status of individual contracts are described for projects within GRI's Power Generation Subprogram. The funding rationale, goals and objectives, accomplishments, and strategy are described for projects in cogeneration and power systems, prime mover and component development, and natural gas vehicles research. These project areas cut across the residential, commercial, industrial, transportation, and electric utility sectors.

Not Available

1989-09-01T23:59:59.000Z

294

State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, October 1--December 31, 1991  

SciTech Connect (OSTI)

The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada`s responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency`s oversight responsibilities. (1) Assure that the health and safety of Nevada`s citizens are adequately protected with regard to any federal high-level radioactive waste program within the State. (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987. (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State. (4) Work closely and consult with affected local governments and State agencies. (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository.

NONE

1991-12-31T23:59:59.000Z

295

Can Next-Generation Reactors Power a Safe Nuclear Futur By Clay Dillow Posted 03.17.2011 at 12:18 pm  

E-Print Network [OSTI]

Can Next-Generation Reactors Power a Safe Nuclear Futur By Clay Dillow Posted 03.17.2011 at 12 of nuclear reactors are designed to prevent exactly what we old Fukushima Daiichi plant. Which is good the world rush to reconsider their nuclear plans, nuclear experts look toward a future of smaller, safer

Danon, Yaron

296

Nuclear Science Division Annual Report 1995-1996  

E-Print Network [OSTI]

generator produced approximately 1 ' 14-MeV neutrons per second which irradiated a target cell through which oxygen

Authors, Various

2010-01-01T23:59:59.000Z

297

Commercial nuclear power 1990  

SciTech Connect (OSTI)

This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs.

Not Available

1990-09-28T23:59:59.000Z

298

World Nuclear Industry Status Report 2007, p. 19 Craig A. Severance, CPA is co-author of The  

E-Print Network [OSTI]

generation of nuclear power plants. Though massive cost overruns and construction delays in the 1970's and 1980's caused U.S. utilities to cancel over 130 nuclear plant orders 1 , the nuclear industry is now beenforgotten that the reason U.S. utilities stopped ordering nuclear power plants was their conclusion

Laughlin, Robert B.

299

Nuclear Fuel Cycle Reasoner: PNNL FY12 Report  

SciTech Connect (OSTI)

Building on previous internal investments and leveraging ongoing advancements in semantic technologies, PNNL implemented a formal reasoning framework and applied it to a specific challenge in nuclear nonproliferation. The Semantic Nonproliferation Analysis Platform (SNAP) was developed as a preliminary graphical user interface to demonstrate the potential power of the underlying semantic technologies to analyze and explore facts and relationships relating to the nuclear fuel cycle (NFC). In developing this proof of concept prototype, the utility and relevancy of semantic technologies to the Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D) has been better understood.

Hohimer, Ryan E.; Pomiak, Yekaterina G.; Neorr, Peter A.; Gastelum, Zoe N.; Strasburg, Jana D.

2013-05-03T23:59:59.000Z

300

On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers.  

SciTech Connect (OSTI)

The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001-September 2004. (1) Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. (2) Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. (3) Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. (4) Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. (5) Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. (6) Development and implementation of a new nonlinear and non-stationary signal processing method, called the Hilbert-Huang transform (HHT), for flaw detection and location. This is a more robust and adaptive approach compared to the wavelet transform. (7) Implementation of a moving-window technique in the time domain for detecting and quantifying flaw types in tubular structures. A window zooming technique was also developed for flaw location in tubes. (8) Theoretical study of elastic wave propagation (longitudinal and shear waves) in metallic flat plates and tubing with and without flaws. (9) Simulation of the Lamb wave propagation using the finite-element code ABAQUS. This enabled the verification of the experimental results. The research tasks included both analytical research and experimental studies. The experimental results helped to enhance the robustness of fault monitoring methods and to provide a systematic verification of the analytical results. The results of this research were disseminated in scientific meetings. A journal manuscript was submitted for publication. The new findings of this research have potential applications in aerospace and civil structures. The report contains a complete bibliography that was developed during the course of the project.

Belle R. Upadhyaya; J. Wesley Hines

2004-09-27T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Chemistry-nuclear chemistry division. Progress report, October 1979-September 1980  

SciTech Connect (OSTI)

This report presents the research and development programs pursued by the Chemistry-Nuclear Chemistry Division of the Los Alamos National Laboratory. Topics covered include advanced analytical methods, atmospheric chemistry and transport, biochemistry, biomedical research, element migration and fixation, inorganic chemistry, isotope separation and analysis, atomic and molecular collisions, molecular spectroscopy, muonic x rays, nuclear cosmochemistry, nuclear structure and reactions, radiochemical separations, theoretical chemistry, and unclassified weapons research.

Ryan, R.R. (comp.)

1981-05-01T23:59:59.000Z

302

Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production, with an outlet gas temperature in the range of 750įC, and a design service life of 60 years. The reactor design will be a graphite-moderated, helium-cooled, prismatic, or pebble bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. This technology development plan details the additional research and development (R&D) required to design and license the NGNP RPV, assuming that A 508/A 533 is the material of construction. The majority of additional information that is required is related to long-term aging behavior at NGNP vessel temperatures, which are somewhat above those commonly encountered in the existing database from LWR experience. Additional data are also required for the anticipated NGNP environment. An assessment of required R&D for a Grade 91 vessel has been retained from the first revision of the R&D plan in Appendix B in somewhat less detail. Considerably more development is required for this steel compared to A 508/A 533 including additional irradiation testing for expected NGNP operating temperatures, high-temperature mechanical properties, and extensive studies of long-term microstructural stability.

J. K. Wright; R. N. Wright

2010-07-01T23:59:59.000Z

303

New generation nuclear fuel structures: dense particles in selectively soluble matrix  

SciTech Connect (OSTI)

We have developed a technology for dispersing sub-millimeter sized fuel particles within a bulk matrix that can be selectively dissolved. This may enable the generation of advanced nuclear fuels with easy separation of actinides and fission products. The large kinetic energy of the fission products results in most of them escaping from the sub-millimeter sized fuel particles and depositing in the matrix during burning of the fuel in the reactor. After the fuel is used and allowed to cool for a period of time, the matrix can be dissolved and the fission products removed for disposal while the fuel particles are collected by filtration for recycle. The success of such an approach would meet a major goal of the GNEP program to provide advanced recycle technology for nuclear energy production. The benefits of such an approach include (1) greatly reduced cost of the actinide/fission product separation process, (2) ease of recycle of the fuel particles, and (3) a radiation barrier to prevent theft or diversion of the recycled fuel particles during the time they are re-fabricated into new fuel. In this study we describe a method to make surrogate nuclear fuels of micrometer scale W (shell)/Mo (core) or HfO2 particles embedded in an MgO matrix that allows easy separation of the fission products and their embedded particles. In brief, the method consists of physically mixing W-Mo or hafnia particles with an MgO precursor. Heating the mixture, in air or argon, without agitation, to a temperature is required for complete decomposition of the precursor. The resulting material was examined using chemical analysis, scanning electron microscopy, X-ray diffraction and micro X-ray computed tomography and found to consist of evenly dispersed particles in an MgO + matrix. We believe this methodology can be extended to actinides and other matrix materials.

Sickafus, Kurt E [Los Alamos National Laboratory; Devlin, David J [Los Alamos National Laboratory; Jarvinen, Gordon D [Los Alamos National Laboratory; Patterson, Brian M [Los Alamos National Laboratory; Pattillo, Steve G [Los Alamos National Laboratory; Valdez, James [Los Alamos National Laboratory; Phillips, Jonathan [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

304

Blue Ribbon Commission on America's Nuclear Future Report to...  

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

Blue Ribbon Commission on America's Nuclear Future (BRC) was formed by the Secretary of Energy at the request of the President to conduct a comprehensive review of policies for...

305

Final Report for CORBA for Fourth Generation Language  

SciTech Connect (OSTI)

The standard for object based networking is the Common Object Request Broker Architecture (CORBA). However, CORBA is not available for Fourth Generation Languages (4GL's) such as Visual Numerics? PV-WAVE or Research Systems? Interactive Data Language (RSI-IDL), which are widely used by scientists and engineers for data visualization and analysis. The proposed work would provide a set of tools to allow 4GL's to interoperate with CORBA.

Svetlana Shasharina

2005-06-28T23:59:59.000Z

306

Nuclear Fuel Cycle Reasoner: PNNL FY13 Report  

SciTech Connect (OSTI)

In Fiscal Year 2012 (FY12) PNNL implemented a formal reasoning framework and applied it to a specific challenge in nuclear nonproliferation. The Semantic Nonproliferation Analysis Platform (SNAP) was developed as a preliminary graphical user interface to demonstrate the potential power of the underlying semantic technologies to analyze and explore facts and relationships relating to the nuclear fuel cycle (NFC). In Fiscal Year 2013 (FY13) the SNAP demonstration was enhanced with respect to query and navigation usability issues.

Hohimer, Ryan E.; Strasburg, Jana D.

2013-09-30T23:59:59.000Z

307

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010:  

Broader source: Energy.gov [DOE]

Nuclear power plants in the United States currently produce about 20 percent of the nationís electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit...

308

A Preliminary Report on Static Analysis of C Code for Nuclear Reactor Protection System  

E-Print Network [OSTI]

A Preliminary Report on Static Analysis of C Code for Nuclear Reactor Protection System Jong: Cybersecurity regulations require new I&C (Instrumentation & Control) systems in nuclear power plants to develop Controller) is used to implement digital I&Cs, C programs are often translated automatically from design

309

Manual for Nuclear Materials Management and Safeguards System Reporting and Data Submission  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The manual provides detailed instructions for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE M 474.1-2. Canceled by DOE M 470.4-6.

2003-08-19T23:59:59.000Z

310

Report to Congress on stockpile reliability, weapon remanufacture, and the role of nuclear testing  

SciTech Connect (OSTI)

This report analyzes two issues: (1) ''whether past warhead reliability problems demonstrate that nuclear explosive testing is needed to identify or to correct stockpile reliability,'' or (2) ''whether a program of stockpile inspection, nonnuclear testing, and remanufacture would be sufficient to deal with stockpile reliability problems.'' Chapter 1 examines the reasons for nuclear testing. Although the thrust of the request from Congressman Aspin et al., has to do with the need for nuclear testing as it relates to stockpile reliability and remanufacture, there are other very important reasons for nuclear testing. Since there has been increasing interest in the US Congress for more restrictive nuclear test limits, we have addressed the overall need for nuclear testing and the potential impact of further nuclear test limitations. Chapter 1 also summarizes the major conclusions of a recent study conducted by the Scientific and Academic Advisory Committee (SAAC) for the President of the University of California; the SAAC report is entitled, ''Nuclear Weapon Tests: The Role of the University of California-Department of Energy Laboratories.'' Chapter 2 presents a brief history of stockpile problems that involved post-deployment nuclear testing for their resolution. Chapter 3 addresses the problems involved in remanufacturing nuclear weapons, and Chapter 4 discusses measures that should be taken to prepare for possible future restrictive test limits.

Miller, G.H.; Brown, P.S.; Alonso, C.T.

1987-10-01T23:59:59.000Z

311

The NOx system in nuclear waste. 1997 annual progress report  

SciTech Connect (OSTI)

'The authors highlight their results from the title project. The project is a coordinated effort of the three Co-PIs to assist the Safety Programs at the Hanford and other DOE Environmental Management Sites. The authors present in the report their observations and interactively discuss their implications for safety concerns. They focus on three issues: (1) Reducing radicals in the NOx system The authors show that the only reducing radical that lasts longer than a few ns in typical waste solutions, and is capable of generating hydrogen, is NO{sub 3}{sup 2-}. The authors measured the lifetime of this species across the whole pH range (3 {le} pH {le} 14) and found it to be shorter than -15 \\265s, before it dissociates to give the strongly oxidizing NO, radicals. They found that it reacts with many proton donors (H{sup +}, phosphate, borate, NH{prime}, amines) in a reaction that is not merely an acid-base equilibrium reaction but is probably a dissociative proton transfer. They estimate the redox potential from theoretical considerations and obtain an experimental verification. They conclude that it is highly unlikely, although thermodynamically possible, that this radi-cal will generate hydrogen in waste solutions. (2) Aging of organic chelators and their degradation products by NO, Methodologies to study the degradation of organic substrates (including the important waste components, formate and oxalate) to CO;, or carbonate, by NO, were developed. This radical dimerizes and disproportionates to nitrate and nitrite. Therefore, mineraliza-tion of the organic substrates competes with the disproportionation of NO,. Among the organic substrates, formate and oxalate are also mineralized but because they are of low fuel value their mineralization is not very helpful, yet it consumes NO,. (3) Interfacial processes in aqueous suspensions Yields of charge transfer from solid silica particles to water and other liquids were meas-ured. If the particles are small enough, essentially all of the charge that is originally depos-ited in the solid escapes into the liquid. This implies that the solid/liquid interface does not provide a significant barrier to the transfer of charges into the solution when the particles are very small (I 20 nm). Electrons may reach the liquid and generate hydrogen, for example. On the other hand, the same mechanism may also provide a pathway for oxidative aging of organics by holes even when the organic is dissolved in the liquid or adsorbed on the solid surface. The authors have started to study reactions of NO,. Methodology and instrumentation to measure reactions of relevant organic radicals with NO, and with its parent NO, were developed. Because of low extinction coefficients, conductivity will be the method of choice.'

Meisel, D. [Argonne National Lab., IL (US). Chemistry Div.; Camaioni, D.; Orlando, T. [Pacific Northwest National Lab., Richland, WA (US)

1997-01-01T23:59:59.000Z

312

Institute for Nuclear Theory annual report No. 4, 1 March 1993--28 February 1994  

SciTech Connect (OSTI)

The Institute for Nuclear Theory was created as a national center by the Department of Energy. It began operations March 1, 1990. This annual report summarizes the INT`s activities during its fourth year of operations.

Haxton, W.; Bertsch, G.; Henley, E.M.

1994-06-01T23:59:59.000Z

313

WHEN A PAIR of nuclear-powered Russian submarines was reported patrolling  

E-Print Network [OSTI]

WHEN A PAIR of nuclear-powered Russian submarines was reported patrolling off the eastern seaboard as "explaining-away." Although several algorithms were later developed to perform Bayesian updating in general

California at Los Angeles, University of

314

Modular Radioisotope Thermoelectric Generator (RTG) Program. Final technical report  

SciTech Connect (OSTI)

Section 2.0 of this report summarizes the MOD-RTG reference flight design, and Section 3.0 discusses the Ground Demonstration System design. Multicouple technology development is discussed in Section 4.0, and Section 5.0 lists all published technical papers prepared during the course of the contract.

Not Available

1992-12-31T23:59:59.000Z

315

Next Generation Reactors  

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

Nuclear Advances We are coordinating the Generation IV Nuclear Systems Initiative - an international effort to develop the next generation of nuclear power reactors. Skip...

316

Considerations Associated with Reactor Technology Selection for the Next Generation Nuclear Plant Project  

SciTech Connect (OSTI)

At the inception of the Next Generation Nuclear Plant Project and during predecessor activities, alternative reactor technologies have been evaluated to determine the technology that best fulfills the functional and performance requirements of the targeted energy applications and market. Unlike the case of electric power generation where the reactor performance is primarily expressed in terms of economics, the targeted energy applications involve industrial applications that have specific needs in terms of acceptable heat transport fluids and the associated thermodynamic conditions. Hence, to be of interest to these industrial energy applications, the alternative reactor technologies are weighed in terms of the reactor coolant/heat transport fluid, achievable reactor outlet temperature, and practicality of operations to achieve the very high reliability demands associated with the petrochemical, petroleum, metals and related industries. These evaluations have concluded that the high temperature gas-cooled reactor (HTGR) can uniquely provide the required ranges of energy needs for these target applications, do so with promising economics, and can be commercialized with reasonable development risk in the time frames of current industry interest Ė i.e., within the next 10-15 years.

L.E. Demick

2010-09-01T23:59:59.000Z

317

Annual report on strategic special nuclear material inventory differences, April 1, 1990--March 31, 1991  

SciTech Connect (OSTI)

This report of unclassified Inventory Difference (ID's) covers the twelve months from April 1, 1990 through March 31, 1991 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses as the included data.

Not Available

1992-01-01T23:59:59.000Z

318

Milliwatt generator heat source progress report, January--December 1989  

SciTech Connect (OSTI)

All hardware shipments to LANL were made on or ahead of schedule, thus satisfying all War Reserve and other hardware/yttrium requirements for the reporting period January--December 1989. A special investigation was conducted to determine the source of a surface staining'' problem observed on some T-111 components. Although the cause was not positively identified, the actions taken as a result of the investigation dramatically reduced both the frequency of occurrence and the magnitude of the problem. Hardware fabrication activates continued in an efficient and timely manner, with production losses at a minimal level. During the reporting period, a 99.4% utilization yield was realized, with a 0.8 dollar percent defectiveness. 1 ref., 15 figs., 5 tabs.

Saylor, R.W.

1990-09-10T23:59:59.000Z

319

Nuclear Test-Experimental Science: Annual report, fiscal year 1988  

SciTech Connect (OSTI)

Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program.

Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B. (eds.)

1988-01-01T23:59:59.000Z

320

University of Washington, Nuclear Physics Laboratory annual report, 1995  

SciTech Connect (OSTI)

The Nuclear Physics Laboratory of the University of Washington supports a broad program of experimental physics research. The current program includes in-house research using the local tandem Van de Graff and superconducting linac accelerators and non-accelerator research in double beta decay and gravitation as well as user-mode research at large accelerator and reactor facilities around the world. This book is divided into the following areas: nuclear astrophysics; neutrino physics; nucleus-nucleus reactions; fundamental symmetries and weak interactions; accelerator mass spectrometry; atomic and molecular clusters; ultra-relativistic heavy ion collisions; external users; electronics, computing, and detector infrastructure; Van de Graff, superconducting booster and ion sources; nuclear physics laboratory personnel; degrees granted for 1994--1995; and list of publications from 1994--1995.

NONE

1995-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

NNSA Releases New Nuclear Prevent, Counter, and Respond Report | National  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recovery challengeMultiscaleLogosAdministrationNetworkNuclear SecurityNuclear

322

Final Report for "Analyzing and visualizing next generation climate data"  

SciTech Connect (OSTI)

The project "Analyzing and visualizing next generation climate data" adds block-structured (mosaic) grid support, parallel processing, and 2D/3D curvilinear interpolation to the open-source UV-CDAT climate data analysis tool. Block structured grid support complies to the Gridspec extension submitted to the Climate and Forecast metadata conventions. It contains two parts: aggregation of data spread over multiple mosaic tiles (M-SPEC) and aggregation of temporal data stored in different files (F-SPEC). Together, M-SPEC and F-SPEC allow users to interact with data stored in multiple files as if the data were in a single file. For computational expensive tasks, a flexible, multi-dimensional, multi-type distributed array class allows users to process data in parallel using remote memory access. Both nodal and cell based interpolation is supported; users can choose between different interpolation libraries including ESMF and LibCF depending on the their particular needs.

Pletzer, Alexander

2012-11-13T23:59:59.000Z

323

Isotope and Nuclear Chemistry Division annual report FY 1986, October 1985-September 1986  

SciTech Connect (OSTI)

This report describes progress in the major research and development programs carried out in FY 1986 by the Isotope and Nuclear Chemistry Division. The report includes articles on radiochemical diagnostics and weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production and separation; chemical biology and nuclear medicine; element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced concepts and technology; and atmospheric chemistry.

Heiken, J.H. (ed.)

1987-06-01T23:59:59.000Z

324

Coal-fired high performance power generating system. Final report  

SciTech Connect (OSTI)

As a result of the investigations carried out during Phase 1 of the Engineering Development of Coal-Fired High-Performance Power Generation Systems (Combustion 2000), the UTRC-led Combustion 2000 Team is recommending the development of an advanced high performance power generation system (HIPPS) whose high efficiency and minimal pollutant emissions will enable the US to use its abundant coal resources to satisfy current and future demand for electric power. The high efficiency of the power plant, which is the key to minimizing the environmental impact of coal, can only be achieved using a modern gas turbine system. Minimization of emissions can be achieved by combustor design, and advanced air pollution control devices. The commercial plant design described herein is a combined cycle using either a frame-type gas turbine or an intercooled aeroderivative with clean air as the working fluid. The air is heated by a coal-fired high temperature advanced furnace (HITAF). The best performance from the cycle is achieved by using a modern aeroderivative gas turbine, such as the intercooled FT4000. A simplified schematic is shown. In the UTRC HIPPS, the conversion efficiency for the heavy frame gas turbine version will be 47.4% (HHV) compared to the approximately 35% that is achieved in conventional coal-fired plants. This cycle is based on a gas turbine operating at turbine inlet temperatures approaching 2,500 F. Using an aeroderivative type gas turbine, efficiencies of over 49% could be realized in advanced cycle configuration (Humid Air Turbine, or HAT). Performance of these power plants is given in a table.

NONE

1995-08-31T23:59:59.000Z

325

Messiah College Biodiesel Fuel Generation Project Final Technical Report  

SciTech Connect (OSTI)

Many obvious and significant concerns arise when considering the concept of small-scale biodiesel production. Does the fuel produced meet the stringent requirements set by the commercial biodiesel industry? Is the process safe? How are small-scale producers collecting and transporting waste vegetable oil? How is waste from the biodiesel production process handled by small-scale producers? These concerns and many others were the focus of the research preformed in the Messiah College Biodiesel Fuel Generation project over the last three years. This project was a unique research program in which undergraduate engineering students at Messiah College set out to research the feasibility of small-biodiesel production for application on a campus of approximately 3000 students. This Department of Energy (DOE) funded research program developed out of almost a decade of small-scale biodiesel research and development work performed by students at Messiah College. Over the course of the last three years the research team focused on four key areas related to small-scale biodiesel production: Quality Testing and Assurance, Process and Processor Research, Process and Processor Development, and Community Education. The objectives for the Messiah College Biodiesel Fuel Generation Project included the following: 1. Preparing a laboratory facility for the development and optimization of processors and processes, ASTM quality assurance, and performance testing of biodiesel fuels. 2. Developing scalable processor and process designs suitable for ASTM certifiable small-scale biodiesel production, with the goals of cost reduction and increased quality. 3. Conduct research into biodiesel process improvement and cost optimization using various biodiesel feedstocks and production ingredients.

Zummo, Michael M; Munson, J; Derr, A; Zemple, T; Bray, S; Studer, B; Miller, J; Beckler, J; Hahn, A; Martinez, P; Herndon, B; Lee, T; Newswanger, T; Wassall, M

2012-03-30T23:59:59.000Z

326

On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers, Volumes 1, 2.  

SciTech Connect (OSTI)

The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001 √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬? September 2004. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development and implementation of a new nonlinear and non-stationary signal processing method, called the Hilbert-Huang transform (HHT), for flaw detection and location. This is a more robust and adaptive approach compared to the wavelet transform

Upadhyaya, Belle R.; Hines, J. Wesley; Lu, Baofu; Huang, Xuedong; Penha, Rosani, L.; Perillo, Sergio, R.; Zhao, Ke

2005-06-03T23:59:59.000Z

327

Nuclear waste management. Semiannual progress report, October 1982-March 1983  

SciTech Connect (OSTI)

This document is one of a series of technical progress reports designed to report radioactive waste management programs at the Pacific Northwest Laboratory. Accomplishments in the following programs are reported: waste stabilization; Materials Characterization Center; waste isolation; low-level waste management; remedial action; and supporting studies.

Chikalla, T.D.; Powell, J.A. (comps.)

1983-06-01T23:59:59.000Z

328

Design acceptance summary report for the new generation transfer pump (NGTP)  

SciTech Connect (OSTI)

This report documents design review of the New Generation Transfer Pump versus the functions and requirements of the SY-101 Rapid Mitigation Project. Previously unpublished documentation for the pump is included in support of the design.

IRONS, J.

1999-10-27T23:59:59.000Z

329

Threatened and endangered species evaluation for 75 licensed commercial nuclear power generating plants  

SciTech Connect (OSTI)

The Endangered Species Act (ESA) of 1973, as amended, and related implementing regulations of the jurisdictional federal agencies, the U.S. Departments of Commerce and Interior, at 50 CFR Part 17. 1, et seq., require that federal agencies ensure that any action authorized, funded, or carried out under their jurisdiction is not likely to jeopardize the continued existence of any threatened or endangered species or result in the destruction or adverse modification of critical habitats for such species. The issuance and maintenance of a federal license, such as a construction permit or operating license issued by the U.S. Nuclear Regulatory Commission (NRC) for a commercial nuclear power generating facility is a federal action under the jurisdiction of a federal agency, and is therefore subject to the provisions of the ESA. The U.S. Department of the Interior (through the Fish and Wildlife Service), and the U.S. Department of Commerce, share responsibility for administration of the ESA. The National Marine Fisheries Service (NMFS) deals with species that inhabit marine environments and anadromous fish, while the U.S. Fish and Wildlife Service (USFWS) is responsible for terrestrial and freshwater species and migratory birds. A species (or other distinct taxonomic unit such as subspecies, variety, and for vertebrates, distinct population units) may be classified for protection as `endangered` when it is in danger of extinction within the foreseeable future throughout all or a significant portion of its range. A `threatened` classification is provided to those animals and plants likely to become endangered within the foreseeable future throughout all or a significant portion of their ranges. As of February 1997, there were about 1067 species listed under the ESA in the United States. Additionally there were approximately 125 species currently proposed for listing as threatened or endangered, and another 183 species considered to be candidates for formal listing proposals.

Sackschewsky, M.R.

1997-03-01T23:59:59.000Z

330

Modeling a Printed Circuit Heat Exchanger with RELAP5-3D for the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

The main purpose of this report is to design a printed circuit heat exchanger (PCHE) for the Next Generation Nuclear Plant and carry out Loss of Coolant Accident (LOCA) simulation using RELAP5-3D. Helium was chosen as the coolant in the primary and secondary sides of the heat exchanger. The design of PCHE is critical for the LOCA simulations. For purposes of simplicity, a straight channel configuration was assumed. A parallel intermediate heat exchanger configuration was assumed for the RELAP5 model design. The RELAP5 modeling also required the semicircular channels in the heat exchanger to be mapped to rectangular channels. The initial RELAP5 run outputs steady state conditions which were then compared to the heat exchanger performance theory to ensure accurate design is being simulated. An exponential loss of pressure transient was simulated. This LOCA describes a loss of coolant pressure in the primary side over a 20 second time period. The results for the simulation indicate that heat is initially transferred from the primary loop to the secondary loop, but after the loss of pressure occurs, heat transfers from the secondary loop to the primary loop.

Not Available

2010-12-01T23:59:59.000Z

331

Second-generation-heliostat optimization studies. Final report  

SciTech Connect (OSTI)

The objective of this study was to define and quantify cost reductions in the Martin Marietta Denver Aerospace Second Generation Heliostat resulting from design and cost optimization. These cost reductions were based on optimizing the heliostat performance vs. cost and engineering design, and reviewing the design specification in selected technological areas with a goal of removing nonrealistic requirements and eliminating or minimizing overdesign. Specific technological areas investigated were: (1) designing the heliostat for survival strength rather than stiffness and reducing the operational wind requirements as dictated by this design approach; (2) reducing the pointing accuracy and/or beam quality required for some fraction or all of the heliostat field; (3) modifying the operational temperature range; (4) relaxing the rate at which the heliostat must move in the slew mode; (5) using alternate beam safety strategies; (6) analyzing actual wind data for selected sites in the southwest United States vs. the heliostat design specification survival wind requirements; (7) estimating heliostat damage for winds in excess of the design specification over a 30 year period; (8) evaluating the impact of designing the heliostat for higher wind loads; and (9) investigating the applicability to heliostat design of the standard engineering practices for designing buildings.

Not Available

1982-05-01T23:59:59.000Z

332

PHYSICAL REVIEW A 90, 063412 (2014) Effect of nuclear vibration on high-order-harmonic generation of aligned H2  

E-Print Network [OSTI]

PHYSICAL REVIEW A 90, 063412 (2014) Effect of nuclear vibration on high-order-harmonic generation of aligned H2 + molecules Dmitry A. Telnov,1,* John Heslar,2, and Shih-I Chu2,3, 1 Department of Physics, St. Petersburg State University, St. Petersburg 198504, Russia 2 Department of Physics, Center for Quantum

Chu, Shih-I

333

Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)  

SciTech Connect (OSTI)

The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900įC and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2ľCr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

334

Nuclear Plant Feedwater Heater Handbook. Volume 1. Primer. Final report  

SciTech Connect (OSTI)

This document is the first part of a three volume handbook covering closed feedwater heaters for electric power generating plants. This volume is a primer to the subject of feedwater heaters and their integration into the plant. 24 refs.

Bell, R.J.; Wells, T.G. Jr.

1985-06-01T23:59:59.000Z

335

Temperature and thermal stress distributions for the HFIR permanent reflector generated by nuclear heating  

SciTech Connect (OSTI)

The beryllium permanent reflector of the High Flux Isotope Reactor has the main functions for slowing down and reflecting the neutrons and housing the experimental facilities. The reflector is heated as a result of the nuclear reaction. Heat is removed mainly by the cooling water passing through the densely distributed coolant holes along the vertical or axial direction of the reflector. The reflector neutronic distribution and its heating rate are calculated by J.C. Gehin of the Oak Ridge National Laboratory by applying the Monte Carlo Code MCNP. The heat transfer boundary conditions along several reflector interfaces are estimated to remove additional heat from the reflector. The present paper is to report the calculation results of the temperature and the thermal stress distributions of the permanent reflector by applying the computer aided design code I-DEAS and the finite element code ABAQUS. The present calculation is to estimate the high stress areas as a result of the new beam tube cutouts along the horizontal mid-plane of the reflector of the recent reactor upgrade project. These high stresses were not able to be calculated in the preliminary design analysis in earlier 60`s. The heat transfer boundary conditions are used in this redesigned calculation. The material constants and the acceptance criteria for the allowable stresses are mainly based on that assumed in the preliminary design report.

Chang, S.J.

1998-04-01T23:59:59.000Z

336

Studies of nuclear processes at the Triangle Universities Nuclear Laboratory. Progress report, 1 September 1995--31 August 1996  

SciTech Connect (OSTI)

The Triangle Universities Nuclear Laboratory (TUNL)--a collaboration of Duke University, North Carolina State University, and the University of North Carolina at Chapel Hill--has had a very productive year. This report covers parts of the second and third year of a three-year grant between the US Department of Energy and the three collaborating universities. The TUNL research program focuses on the following areas: precision test of parity-invariance violation in resonance neutron scattering at LANSCE/LANL; parity violation measurements using charged-particle resonances in A = 20--40 targets and the A = 4 system at TUNL; chaotic behavior in the nuclei {sup 30}P and {sup 34}Cl from studies of eigenvalue fluctuations in nuclear level schemes; search for anomalies in the level density (pairing phase transition) in 1f-2p shell nuclei using GEANIE at LANSCE/LANL; parity-conserving time-reversal noninvariance tests using {sup 166}Ho resonances at Geel, ORELA, or LANSCE/LANL; nuclear astrophysics; few-body nuclear systems; Nuclear Data evaluation for A = 3--20 for which TUNL is now the international center. Developments in technology and instrumentation are vital to the research and training program. Innovative work was continued in: polarized beam development; polarized target development; designing new cryogenic systems; designing new detectors; improving high-resolution beams for the KN and FN accelerators; development of an unpolarized Low-Energy Beam Facility for radiative capture studies of astrophysical interest. Preliminary research summaries are presented.

Ludwig, E.J.

1996-09-01T23:59:59.000Z

337

Next Generation Nuclear Plant Methods Research and Development Technical Program Plan -- PLN-2498  

SciTech Connect (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the ďhighly rankedĒ phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2008-09-01T23:59:59.000Z

338

Nuclear waste management. Semiannual progress report, April 1983-September 1983  

SciTech Connect (OSTI)

The status of the following programs is reported: waste stabilization; waste isolation; low-level waste management; remedial action; and supporting studies. 58 figures, 39 tables.

McElroy, J.L.; Powell, J.A. (comps.)

1984-01-01T23:59:59.000Z

339

Reaching the hip-hop generation: Final (symposium proceedings) report  

SciTech Connect (OSTI)

The goal of this final (closing) report is to capture the flavor of the symposium held March 1 and 2, 1993 in New York City convened by Motivational Educational Entertainment, Inc. (MEE), a black-owned communications research, consulting, and video production company based in Philadelphia, Pennsylvania. The mission of MEE is to understand, reach, and positively affect inner-city youth. Traditional communication approaches from mainstream sources to at-risk youth often don`t account for the unique way youth communicate among themselves and how they relate to the media. This understanding, however, is crucial. To understand youth communication, the people who create and send both entertaining and educational messages to urban youth must be brought into the dialogue. The meeting in New York was intended to provide an important opportunity for senders to meet and evaluate the appropriateness and effectiveness of their messages. In addition, the MEE symposium provided a forum for the continuing public debate about what needs to be done to reach today`s urban teens. Included in this document is a description of symposium goals/objectives, symposium activities, the reaction to and analysis of the symposium, recommendations for future MEE courses of action, and an appendix containing copies of press articles.

Not Available

1993-05-01T23:59:59.000Z

340

Nuclear materials stabilization and packaging. Quarterly progress report, October 1--December 31, 1995  

SciTech Connect (OSTI)

Progress is reported for Los Alamos Nuclear Materials Stabilization and Packaging projects for the first quarter of Fiscal Year 1996. Development and production activities in Plutonium Recovery and Processing, Plutonium Packaging, and Uranium Recovery and Processing are covered. Packaging quality assurance activities are reported.

Chidester, K.M. [comp.

1996-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Multimegawatt space nuclear power supply, Phase 1 Final report  

SciTech Connect (OSTI)

This Specification establishes the performance, design, development, and test requirements for the Boeing Multimegawatt Space Nuclear Power System (MSNPS). The Boeing Multimegawatt Space Power System is part of the DOE/SDIO Multimegawatt Space Nuclear Power Program. The purpose of this program is to provide a space-based nuclear power system to meet the needs of SDIO missions. The Boeing MSNPS is a category 1 concept which is capable of delivering 10's of MW(e) for 100's of seconds with effluent permitted. A design goal is for the system to have growth or downscale capability for other power system concepts. The growth objective is to meet the category 3 capability of 100's of MW(e) for 100's of seconds, also with effluent permitted. The purpose of this preliminary document is to guide the conceptual design effort throughout the Phase 1 study effort. This document will be updated through out the study. It will thus result in a record of the development of the design effort.

Not Available

1989-02-17T23:59:59.000Z

342

Property exempt from taxation: nuclear generation facility property: K.S.A. 79-230 (Kansas)  

Broader source: Energy.gov [DOE]

This legislation would exempt from state property taxes any property purchased, constructed or installed to expand capacity at an existing nuclear plant or to build a new nuclear plant. A...

343

World nuclear outlook 1995  

SciTech Connect (OSTI)

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

NONE

1995-09-29T23:59:59.000Z

344

World nuclear outlook 1994  

SciTech Connect (OSTI)

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2010 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for three different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

NONE

1994-12-01T23:59:59.000Z

345

The Long-Life Core Encapsulated Nuclear Heat Source (ENHS) Generation IV Reactor  

SciTech Connect (OSTI)

The long-life core for the Encapsulated Nuclear Heat Source (ENHS) reactor has been redesigned so as to provide for fuel rod clad integrity up to the discharge burnup design goal. It was found feasible to design a nearly zero burnup reactivity swing long-life core that will maintain the fuel rod integrity up to the peak discharge burnup while enabling to handle the rated power using natural circulation. The core life is limited by radiation damage to its structural material. The core power shape is exceptionally constant throughout the core life. The new reference core design can deliver 125 MW{sub th} while having very generous margins for maximum acceptable temperatures or temperature differences. Using a cover-gas lift-pump it may be possible to design an ENHS module to deliver {approx}50% more power than the set goal. Briefly reviewed are unique features of the ENHS reactor along with the potential of this reactor to meet the goals set for Generation IV reactors. (authors)

Greenspan, E.; Barak, A.; Saphier, D. [Department of Nuclear Engineering, University of California, Berkeley, CA 94720 (United States); Buongiorno, J. [Idaho National Engineering and Environmental Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Brown, N.W.; Hossain, Q. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, CA 94550 (United States); Carelli, M.D.; Conway, L.; Dzodzo, M. [Westinghouse Electric Co., Sci. and Tech., 1344 Beulah Rd., Pittsburgh, PA 15235 (United States); Feldman, E.; Sienicki, J.J.; Sofu, T.; Wade, D.C. [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Hong, S.G.; Kim, Y.I. [Korea Atomic Energy Research Institute, Yusong, Taejon 305-600, Rep. of Korea (Korea, Republic of)

2002-07-01T23:59:59.000Z

346

Report to the US Nuclear Regulatory Commission on Analysis and Evaluation of Operational Data, 1986  

SciTech Connect (OSTI)

This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during calendar year 1986. Comments and observations are provided on operating experience at nuclear power plants and other NRC licensees, including results from selected AEOD studies; summaries of abnormal occurrences involving US nuclear plants; reviews of licensee event reports and their quality, reactor scram experience from 1984 to 1986, engineered safety features actuations, and the trends and patterns analysis program; and assessments of nonreactor and medical misadministration events. In addition, the report provides the year-end status of all recommendations included in AEOD studies, and listings of all AEOD reports issued from 1980 through 1986.

none,

1987-05-01T23:59:59.000Z

347

Nuclear Medicine Program progress report for quarter ending June 30, 1991  

SciTech Connect (OSTI)

In this report the excitation functions for production of gallium-66 via {alpha}-induced nuclear reactions on enriched zinc-66 have been measured with E{sub {alpha}}{le}27.3 Mev and E{sub {alpha}}{le}43.7 MeV employing the stack thin-target technique. In addition, the induced activity of gallium-67 in the same sets of targets allowed an evaluation of the excitation functions of the corresponding nuclear reactions. These preliminary studies have demonstrated that sufficient levels of gallium-66 can be produced by {alpha}-induced reactions on enriched zinc targets. A series of radioiodinated analogues of 1-azabicyclo(2.2.2)oct-3-yl {alpha}-hydroxy-{alpha}, {alpha}-diphenylacetate (QNB) have been prepared. These new analogues include 1-azabicyclo-(2.2.2)oct-3-yl{alpha}-hydroxy-{alpha}-(4-iodophenyl)-{alpha}-methylacetate(2,I-WNA), 1-azabicyclo(2.2.2)oct-3-yl (3-iodo)-xanthene-9-carboxylate (3,I-QNX), and 1-azabicyclo(2.2.2)oct-3-yl {alpha}-hydroxy-{alpha}-(E-1-iodo-1-propen-3-yl)-{alpha}-phenylacetate (4,I-QNP), which have also been radiolabeled with iodine-125 with high specific activity. The biodistribution, brain uptake, and receptor specificity of these new analogues are currently being studied. Shipments of radioactive agents made to collaborators during this period included. One shipment of iodine-125-labeled 15-(p-iodophenyl)-3-R,S-methylpentadecanoic acid (BMIPP) and tungsten-188/rhenium-188 generator. 16 refs., 7 figs., 1 tab.

Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Srivastava, P.C.; Hasan, A.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

1991-09-01T23:59:59.000Z

348

Nuclear Science Division: Annual report for the period October 1, 1985-September 30, 1986  

SciTech Connect (OSTI)

Research has for the most part been carried out using three local accelerators, the Bevalac, the SuperHILAC and the 88-Inch Cyclotron. However, at CERN, oxygen-16 beams were accelerated to 3.2 TeV using the LBL-GSI heavy ion injector into the CERN SPS. First results obtained during the beam test period are presented in this report. Bevalac research has probed new regions of the nuclear matter equation of state. Studies of collisions between the most massive nuclei have revealed rich new phenomena such as collective flow, where the pressures generated force the emerging particles away from the beam direction. Experiments on dileptons e/sup +/e/sup -/ pairs) utilizing the newly completed Dilepton Spectrometer (DLS) are being carried out to glean new insights into the hot, high-density stage of the collision. Major new results on the nuclear structure of exotic, very neutron-rich light nuclei are being obtained by exploiting the projectile fragmentation process to produce secondary radioactive beams. The Laboratory has proposed the Bevalac Upgrade Project to replace the Bevalac's weak-focusing synchrotron with a modern, strong-focusing synchrotron to provide higher intensity and higher quality beams. The significant enhancement of the heavy ion capability at the 88-Inch Cyclotron as a result of the recent development of the ECR source has led to a renaissance of the cyclotron as indicated by the increased demand for beam time. A variety of other scientific activities were also carried out during this period. The Isotopes Project published the first edition of a new radioactivity reference book for applied users-The Table of Radioactive Isotopes and division members organized several major scientific meetings.

Mahoney, J. (ed.)

1987-07-01T23:59:59.000Z

349

Next Generation Nuclear Plant Intermediate Heat Exchanger Materials Research and Development Plan (PLN-2804)  

SciTech Connect (OSTI)

DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900įC and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Todayís high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760įC. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.

J. K. Wright

2008-04-01T23:59:59.000Z

350

Monitoring attosecond dynamics of coherent electron-nuclear wave packets by molecular high-order-harmonic generation  

SciTech Connect (OSTI)

A pump-probe scheme for preparing and monitoring electron-nuclear motion in a dissociative coherent electron-nuclear wave packet is explored from numerical solutions of a non-Born-Oppenheimer time-dependent Schroedinger equation. A mid-ir intense few-cycle probe pulse is used to generate molecular high-order-harmonic generation (MHOHG) from a coherent superposition of two or more dissociative coherent electronic-nuclear wave packets, prepared by a femtosecond uv pump pulse. Varying the time delay between the intense ir probe pulse and the uv pump pulse by a few hundreds of attoseconds, the MHOHG signal intensity is shown to vary by orders of magnitude, thus showing the high sensitivity to electron-nuclear dynamics in coherent electron-nuclear wave packets. We relate this high sensitivity of MHOHG spectra to opposing electron velocities (fluxes) in the electron wave packets of the recombining (recolliding) ionized electron and of the bound electron in the initial coherent superposition of two electronic states.

Bredtmann, Timm [Laboratoire de Chimie Theorique, Faculte des Sciences, Universite de Sherbrooke, Sherbrooke, Quebec, J1K 2R1 (Canada); Institut fuer Chemie und Biochemie, Freie Universitaet Berlin, Takustrasse 3, D-14195 Berlin (Germany); Chelkowski, Szczepan; Bandrauk, Andre D. [Laboratoire de Chimie Theorique, Faculte des Sciences, Universite de Sherbrooke, Sherbrooke, Quebec, J1K 2R1 (Canada)

2011-08-15T23:59:59.000Z

351

Nuclear Material Transaction Report NRC 741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1 1

352

Nuclear Material Transaction Report NRC 741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1

353

Nuclear Material Transaction Report NRC741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1C

354

Nuclear Material Transaction Report nrc741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1C

355

Nuclear Material Transaction Report nrc741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1C

356

Nuclear Material Transaction Report nrc741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1C

357

Nuclear Material Transaction Report nrc741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1C

358

Nuclear Material Transaction Report nrc741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1C

359

Nuclear Material Transaction Report nrc741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB 1C

360

Nuclear Material Transaction Report nrc741_1  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature of7379583ForensicsB

Note: This page contains sample records for the topic "nuclear generation reported" 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

Nuclear Safety Research and Development Annual Report, December 2014 |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in3.pdfEnergyDepartment of Energy Advanced1, 2014NuclearCommission, OfficeDepartment

362

Nuclear Separations Technologies Workshop Report | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in3.pdfEnergyDepartment of Energy Advanced1, 2014NuclearCommission,Science

363

How Do You Report A Concern? | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77Nuclear SecurityFAPAC-NMNRC 741

364

Institutional Research & Development Reports | National Nuclear Security  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77Nuclear

365

NMMSS Information, Reports & Forms | National Nuclear Security  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational Nuclear SecurityNationalApplyMaintaining ForN x NSecurity| National

366

Radioactive materials released from nuclear power plants: Annual report, 1993. Volume 14  

SciTech Connect (OSTI)

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1993 have been compiled and reported. The summary data for the years 1974 through 1992 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1993 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Tichler, J.; Doty, K.; Lucadamo, K. [Brookhaven National Lab., Upton, NY (United States)

1995-12-01T23:59:59.000Z

367

Nuclear-waste-management. Quarterly progress report, July-September 1981  

SciTech Connect (OSTI)

Progress reports and summaries are presented for the following: high-level waste process development, alternate waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and fuel pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

Chikalla, T.D.; Powell, J.A. (comps.)

1981-12-01T23:59:59.000Z

368

Nuclear Plant Feedwater Heater Handbook. Volume 2. Design and procurement guidelines. Final report  

SciTech Connect (OSTI)

This document is the second part of a three volume handbook covering closed feedwater heaters for nuclear electric power generating plants. This second volume covers the engineering, design, specification, bid, procurement, fabrication, installation and commissioning of the heater. 22 refs., 12 figs., 17 tabs.

Bell, R.J.; Wells, T.G. Jr.

1985-06-01T23:59:59.000Z

369

WASTE PROCESSING ANNUAL NUCLEAR SAFETY RELATED R AND D REPORT FOR CY2008  

SciTech Connect (OSTI)

The Engineering and Technology Office of Waste Processing identifies and reduces engineering and technical risks associated with key waste processing project decisions. The risks, and actions taken to mitigate those risks, are determined through technology readiness assessments, program reviews, technology information exchanges, external technical reviews, technical assistance, and targeted technology development and deployment (TDD). The Office of Waste Processing TDD program prioritizes and approves research and development scopes of work that address nuclear safety related to processing of highly radioactive nuclear wastes. Thirteen of the thirty-five R&D approved work scopes in FY2009 relate directly to nuclear safety, and are presented in this report.

Fellinger, A.

2009-10-15T23:59:59.000Z

370

Space nuclear safety and fuels program. Progress report, December 1980  

SciTech Connect (OSTI)

This formal monthly report covers the studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Space and Terrestrial Systems Division of the US Department of Energy by the Los Alamos National Laboratory. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

Bronisz, S.E. (comp.)

1981-02-01T23:59:59.000Z

371

Space nuclear safety and fuels program. Progress report, February 1980  

SciTech Connect (OSTI)

This formal monthly report covers the studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Space and Terrestrial Systems Division of the US Department of Energy by the Los Alamos National Laboratory. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

Bronisz, S.E. (comp.)

1981-05-01T23:59:59.000Z

372

STARLIB: A NEXT-GENERATION REACTION-RATE LIBRARY FOR NUCLEAR ASTROPHYSICS  

SciTech Connect (OSTI)

STARLIB is a next-generation, all-purpose nuclear reaction-rate library. For the first time, this library provides the rate probability density at all temperature grid points for convenient implementation in models of stellar phenomena. The recommended rate and its associated uncertainties are also included. Currently, uncertainties are absent from all other rate libraries, and, although estimates have been attempted in previous evaluations and compilations, these are generally not based on rigorous statistical definitions. A common standard for deriving uncertainties is clearly warranted. STARLIB represents a first step in addressing this deficiency by providing a tabular, up-to-date database that supplies not only the rate and its uncertainty but also its distribution. Because a majority of rates are lognormally distributed, this allows the construction of rate probability densities from the columns of STARLIB. This structure is based on a recently suggested Monte Carlo method to calculate reaction rates, where uncertainties are rigorously defined. In STARLIB, experimental rates are supplemented with: (1) theoretical TALYS rates for reactions for which no experimental input is available, and (2) laboratory and theoretical weak rates. STARLIB includes all types of reactions of astrophysical interest to Z = 83, such as (p, {gamma}), (p, {alpha}), ({alpha}, n), and corresponding reverse rates. Strong rates account for thermal target excitations. Here, we summarize our Monte Carlo formalism, introduce the library, compare methods of correcting rates for stellar environments, and discuss how to implement our library in Monte Carlo nucleosynthesis studies. We also present a method for accessing STARLIB on the Internet and outline updated Monte Carlo-based rates.

Sallaska, A. L. [National Institute of Standards and Technology, Gaithersburg, MD 20899-8462 (United States); Iliadis, C.; Champange, A. E. [University of North Carolina at Chapel Hill, Chapel Hill, NC 27599-3255 (United States); Goriely, S. [Institut d'Astronomie et d'Astrophysique, Universite Libre de Bruxelles, C.P. 226, B-1050 Brussels (Belgium); Starrfield, S.; Timmes, F. X., E-mail: anne.sallaska@nist.gov [Arizona State University, Tempe, AZ 85287-1504 (United States)

2013-07-15T23:59:59.000Z

373

Annual Report on Waste Generation and Waste Minimization Progress, 1991--1992  

SciTech Connect (OSTI)

This report is DOE`s first annual report on waste generation and waste minimization progress. Data presented in this report were collected from all DOE sites which met minimum threshold criteria established for this report. The fifty-seven site submittals contained herein represent data from over 100 reporting sites within 25 states. Radioactive, hazardous and sanitary waste quantities and the efforts to minimize these wastes are highlighted within the fifty-seven site submittals. In general, sites have made progress in moving beyond the planning phase of their waste minimization programs. This is evident by the overall 28 percent increase in the total amount of materials recycled from 1991 to 1992, as well as individual site initiatives. During 1991 and 1992, DOE generated a total of 279,000 cubic meters of radioactive waste and 243,000 metric tons of non-radioactive waste. These waste amounts include significant portions of process wastewater required to be reported to regulatory agencies in the state of Texas and the state of Tennessee. Specifically, the Pantex Plant in Texas treats an industrial wastewater that is considered by the Texas Water Commission to be a hazardous waste. In 1992, State regulated wastewater from the Pantex Plant represented 3,620 metric tons, 10 percent of the total hazardous waste generated by DOE. Similarly, mixed low-level wastewater from the TSCA Incinerator Facility at the Oak Ridge K-25 Site in Tennessee represented 55 percent of the total radioactive waste generated by DOE in 1992.

Not Available

1994-02-01T23:59:59.000Z

374

Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems  

SciTech Connect (OSTI)

This project will use proton irradiation to further understand the microstructural stability of ceramics being considered as matrix material for advanced nuclear fuels.

Todd R. Allen

2009-06-30T23:59:59.000Z

375

Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste  

SciTech Connect (OSTI)

This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

376

General-purpose heat source project and space nuclear safety fuels program. Progress report, February 1980  

SciTech Connect (OSTI)

This formal monthly report covers the studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are: General-Purpose Heat Source Development and Space Nuclear Safety and Fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

Maraman, W.J. (comp.)

1980-05-01T23:59:59.000Z

377

Space Nuclear Power Plant Pre-Conceptual Design Report, For Information  

SciTech Connect (OSTI)

This letter transmits, for information, the Project Prometheus Space Nuclear Power Plant (SNPP) Pre-Conceptual Design Report completed by the Naval Reactors Prime Contractor Team (NRPCT). This report documents the work pertaining to the Reactor Module, which includes integration of the space nuclear reactor with the reactor radiation shield, energy conversion, and instrumentation and control segments. This document also describes integration of the Reactor Module with the Heat Rejection segment, the Power Conditioning and Distribution subsystem (which comprise the SNPP), and the remainder of the Prometheus spaceship.

B. Levine

2006-01-27T23:59:59.000Z

378

Annual report on strategic special nuclear material inventory differences, April 1, 1990--March 31, 1991  

SciTech Connect (OSTI)

This report of unclassified Inventory Difference (ID`s) covers the twelve months from April 1, 1990 through March 31, 1991 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses as the included data.

Not Available

1992-01-01T23:59:59.000Z

379

Theoretical studies in hadronic and nuclear physics. Progress report, December 1, 1992--June 30 , 1993  

SciTech Connect (OSTI)

Research in the Maryland Nuclear Theory Group focusses on problems in four basic areas of current relevance. The section on Hadrons in Nuclei reports research into the ways in which the properties of nucleons and the mesons which play a role in the nuclear force are modified in the nuclear medium. QCD sum rules supply a new insight into the decrease of the nucleon`s mass in the nuclear medium. The quark condensate decreases in nuclear matter, and this is responsible for the decrease of the nucleon`s mass. The section on the Structure of Hadrons reports progress in understanding the structure of the nucleon. These results cover widely different approaches -- lattice gauge calculations, QCD sum rules, quark-meson models with confinement and other hedgehog models. Progress in Relativistic Nuclear Physics is reported on electromagnetic interactions in a relativistic bound state formalism, with applications to elastic electron scattering by deuterium, and on application of a two-body quasipotential equation to calculate the spectrum of mesons formed as bound states of a quark and antiquark. A Lorentz-invariant description of the nuclear force suggests a decrease of the nucleon`s mass in the nuclear medium similar to that found from QCD sum rules. Calculations of three-body bound states with simple forms of relativistic dynamics are also discussed. The section on Heavy Ion Dynamics and Related Processes describes progress on the (e{sup +}e{sup {minus}}) problem and heavy-on dynamics. In particular, the sharp electrons observed in {beta}{sup +} irradiation of heavy atoms have recently been subsumed into the ``Composite Particle Scenario,`` generalizing the ``(e{sup +}e{sup {minus}}-Puzzle`` of the pairs from heavy ion collisions to the ``Sharp Lepton Problem.``

Griffin, J.J.; Cohen, T.D.

1993-07-01T23:59:59.000Z

380

Annual report of waste generation and pollution prevention progress 2000 [USDOE] [9th edition  

SciTech Connect (OSTI)

This ninth edition of the Annual Report of Waste Generation and Pollution Prevention Progress highlights waste reduction, pollution prevention accomplishments, and cost savings/avoidance for the U.S. Department of Energy (DOE) Pollution Prevention Program for Fiscal Year 2000. This edition marks the first time that progress toward meeting the 2005 Pollution Prevention Goals, issued by the Secretary of Energy in November 1999, is being reported. In addition, the Annual Report has a new format, and now contains information on a fiscal year basis, which is consistent with other DOE reports.

None

2001-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Office of Nuclear Energy Knowledge Management Program Situational Analysis Report  

SciTech Connect (OSTI)

Knowledge management (KM) has been a high priority for the Department of Energy (DOE) Office of Nuclear Energy (NE) for the past several years. NE Programs are moving toward well-established knowledge management practices and a formal knowledge management program has been established. Knowledge management is being practiced to some level within each of the NE programs. Although it continues to evolve as NE programs evolve, a formal strategic plan that guides the implementation of KM has been developed. Despite the acceptance of KM within DOE NE, more work is necessary before the NE KM program can be considered fully successful. Per Dr. David J. Skyrme[1], an organization typically moves through the following evolutionary phases: (1) Ad-hoc - KM is being practiced to some level in some parts of the organization; (2) Formal - KM is established as a formal project or program; (3) Expanding - the use of KM as a discipline grows in practice across different parts of the organization; (4) Cohesive - there is a degree of coordination of KM; (5) Integrated - there are formal standards and approaches that give every individual access to most organizational knowledge through common interfaces; and (6) Embedded - KM is part-and-parcel of everyday tasks; it blends seamlessly into the background. According to the evolutionary phases, the NE KM program is operating at the two lower levels, Ad-hoc and Formal. Although KM is being practiced to some level, it is not being practiced in a consistent manner across the NE programs. To be fully successful, more emphasis must be placed on establishing KM standards and processes for collecting, organizing, sharing and accessing NE knowledge. Existing knowledge needs to be prioritized and gathered on a routine basis, its existence formally recorded in a knowledge inventory. Governance to ensure the quality of the knowledge being used must also be considered. For easy retrieval, knowledge must be organized according to a taxonomy that mimics nuclear energy programs. Technologies need to be established to make accessing the knowledge easier for the user. Finally, knowledge needs to be used as part of a well defined work process.

Kimberlyn C. Mousseau

2011-12-01T23:59:59.000Z

382

Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

NONE

1995-09-01T23:59:59.000Z

383

Characterization of a Stochastic Procedure for the Generation and Transport of Fission Fragments within Nuclear Fuels  

E-Print Network [OSTI]

With the ever-increasing demands of the nuclear power community to extend fuel cycles and overall core-lifetimes in a safe and economic manner, it is becoming more necessary to extend the working knowledge of nuclear fuel performance. From...

Hackemack, Michael Wayne

2013-04-15T23:59:59.000Z

384

Modeling of a second-generation solar-driven Rankine air conditioner. Final report  

SciTech Connect (OSTI)

Ten configurations of a second-generation (2G), solar-powered, Rankine-driven air conditioner were simulated and the data presented for use in companion studies. The results of the analysis show that the boiling-in-collector (BIC) configuration generates more power per collector area than the other configurations. The models used to simulate the configuration are presented in this report. The generated data are also presented. Experimental work was done under this study to both improve a novel refrigerant and oil lubrication system for the centrifugal compressor and investigate the aerodynamic unloading characteristics of the centrifugal compressor. The information generated was used to define possible turbo-gearbox configurations for use in the second generation computer simulation.

Denius, M.W.; Batton, W.D.

1984-07-01T23:59:59.000Z

385

Nuclear thermal rocket plume interactions with spacecraft. Final report  

SciTech Connect (OSTI)

This is the first study that has treated the Nuclear Thermal Rocket (NTR) effluent problem in its entirety, beginning with the reactor core, through the nozzle flow, to the plume backflow. The summary of major accomplishments is given below: (1) Determined the NTR effluents that include neutral, ionized and radioactive species, under typical NTR chamber conditions. Applied an NTR chamber chemistry model that includes conditions and used nozzle geometries and chamber conditions typical of NTR configurations. (2) Performed NTR nozzle flow simulations using a Navier-Stokes solver. We assumed frozen chemistry at the chamber conditions and used nozzle geometries and chamber conditions typical of NTR configurations. (3) Performed plume simulations using a Direct Simulation Monte Carlo (DSMC) code with chemistry. In order to account for radioactive trace species that may be important for contamination purposes we developed a multi-weighted DSMC methodology. The domain in our simulations included large regions downstream and upstream of the exit. Inputs were taken from the Navier-Stokes solutions.

Mauk, B.H. [Johns Hopkins Univ., Laurel, MD (United States); Gatsonis, N.A.; Buzby, J.; Yin, X. [Worcester Polytechnic Inst., MA (United States). Mechanical Engineering Department

1997-05-01T23:59:59.000Z

386

Separation of technetium from nuclear waste stream simulants. Final report  

SciTech Connect (OSTI)

The author studied liquid anion exchangers, such as Aliquat-336 nitrate, various pyridinium nitrates, and related salts, so that they may be applied toward a specific process for extracting (partitioning) and recovering {sup 99}TcO{sub 4}{sup {minus}} from nuclear waste streams. Many of the waste streams are caustic and contain a variety of other ions. For this reason, the author studied waste stream simulants that are caustic and contain appropriate concentrations of selected, relevant ions. Methods of measuring the performance of the exchangers and extractant systems included contact experiments. Batch contact experiments were used to determine the forward and reverse extraction parameters as a function of temperature, contact time, phase ratio, concentration, solvent (diluent), and other physical properties. They were also used for stability and competition studies. Specifically, the author investigated the solvent extraction behavior of salts of perrhenate (ReO{sub 4}{sup {minus}}), a stable (non-radioactive) chemical surrogate for {sup 99}TcO{sub 4}{sup {minus}}. Results are discussed for alternate organic solvents; metalloporphyrins, ferrocenes, and N-cetyl pyridium nitrate as alternate extractant salts; electroactive polymers; and recovery of ReO{sub 4}{sup {minus}} and TcO{sub 4}{sup {minus}}.

Strauss, S.H. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Chemistry

1995-09-11T23:59:59.000Z

387

Report to the DOE Nuclear Data Committee, 1983  

SciTech Connect (OSTI)

Measurements for nuclear data applicactions are described including branching ratio in /sup 7/Be decay, kerma factor for carbon, photoneutron cross sections, neutron differential scattering cross sections, half-life of /sup 77/Kr, stellar neutron capture rates for /sup 86/ /sup 87/ /sup 88/Sr, neutron total cross sections, /sup 142/ /sup 143/ /sup 144/Nd neutron capture nucleo-synthesis, half-life of /sup 163/Ho, thermal neutron fission of /sup 236/Np, revised branching ratios in /sup 237/U and /sup 238/Pu decays, and levels of /sup 244/Cm populated by the beta decay of 10-hour /sup 244/Am and 26-minute /sup 244m/Am. Calculations discussed include systematic test of microscopic optical models for nucleon scattering in the range 7 to 60 MeV, Lanczos method shell-model calculations of GamowTeller strength functions, explosive nucleosynthesis and direct radiative capture rates, and calculation of fission cross sections. Evaluated data libraries are briefly discussed. (WHK)

Haight, R.C.; Struble, G.L.

1983-02-01T23:59:59.000Z

388

Report to the DOE Nuclear Data Committee, 1984  

SciTech Connect (OSTI)

Experimental results are discussed for: /sup 6/ /sup 7/Li(n,/sup 4/He) cross sections at 14 MeV, neutron elastic and inelastic scattering from carbon near 14 MeV, neutron capture cross sections for /sup 46/Ca and /sup 48/Ca at stellar temperatures, revised neutron cross sections for /sup 142/ /sup 143/ /sup 144/Nd, fragment angular distribution for neutron fission of /sup 232/Th, neutron differential scattering measurements in the actinide region, nuclear structure of /sup 244/Am, conversion coefficients of the M4 transition in /sup 193m/Ir, gamma-ray and conversion-electron decay of the /sup 238/U shape isomer, and levels of /sup 244/Cm populated by the beta decay of 10-hr /sup 244g/Am and 26-minute /sup 244m/Am. Calculations described include tests of microscopic optical models for neutron and proton scattering on light nuclei in the range 14 to 45 MeV, a new dynamic model for fission, and the necessity of discrete-level modeling in isomer ratio calculations for neutron-induced reactions on deformed nuclei. Also, a reevaluation for ENDL of sigma(n,f) and anti nu p for /sup 235/U and /sup 239/Pu from 100 keV to 20 MeV is described. 31 references. (WHK)

Wong, C.; Haight, R.C.; Struble, G.L.

1984-02-01T23:59:59.000Z

389

Nuclear Science Division annual report, July 1, 1981-September 30, 1982  

SciTech Connect (OSTI)

This report summarizes the scientific research carried out within the Nuclear Science Division between July 1, 1981, and September 30, 1982. Heavy-ion investigations continue to dominate the experimental and theoretical research efforts. Complementary programs in light-ion nuclear science, in nuclear data evaluation, and in the development of advanced instrumentation are also carried out. Results from Bevalac experiments employing a wide variety of heavy ion beams, along with new or upgraded detector facilities (HISS, the Plastic Ball, and the streamer chamber) are contained in this report. These relativistic experiments have shed important light on the degree of equilibration for central collisions, the time evolution of a nuclear collision, the nuclear density and compressional energy of these collisions, and strange particle production. Reaction mechanism work dominates the heavy-ion research at the 88-Inch Cyclotron and the SuperHILAC. Recent experiments have contributed to our understanding of the nature of light-particle emission in deep-inelastic collisions, of peripheral reactions, incomplete fusion, fission, and evaporation. Nuclear structure investigations at these accelerators continue to be directed toward the understanding of the behavior of nuclei at high angular momentum. Research in the area of exotic nuclei has led to the observation at the 88-Inch Cyclotron of the ..beta..-delayed proton decay of odd-odd T/sub z/ = -2 nuclides; ..beta..-delayed proton emitters in the rare earth region are being investigated at the SuperHILAC.

Mahoney, J. (ed.)

1983-06-01T23:59:59.000Z

390

Research in nuclear physics. Progress report, 1992--1993  

SciTech Connect (OSTI)

This report discusses the following topics: Search for Massive Neutrinos in the Recoil Spectrum of {sup 37}Cl following Electron Capture Decay of {sup 37}Ar; A Monte Carlo Simulation of the Electron Capture Decay of {sup 37}Ar with an Admixture of Massive Neutrinos: Search for 17-keV Neutrinos in the Internal Bremsstrahlung Spectrum of {sup 125}I; {beta}{sup +} Decay and Cosmic-Ray Half-Lives of {sup 143}Pm and {sup 144}Pm; and Production Cross Sections from the Bombardment of Natural Mo with Protons.

Kozub, R.L.; Hindi, M.M.

1993-06-01T23:59:59.000Z

391

International Nuclear Energy Research Initiative: 2010 Annual Report |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel2007 | Department7 U.S.Department of Energy 10 Annual Report

392

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste  

SciTech Connect (OSTI)

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

393

Research in heavy-ion nuclear physics. Annual progress report, May 1, 1991--April 30, 1992  

SciTech Connect (OSTI)

This report discusses the following topics: Fusion-fission in light nuclear systems; High-resolution Q-value measurement for the {sup 24}Mg+{sup 24}Mg reaction; Heavy-ion reactions and limits to fusion; and Hybrid MWPC-Bragg curve detector development.

Sanders, S.J.; Prosser, F.W.

1992-01-01T23:59:59.000Z

394

Intermediate/high energy nuclear physics. Technical progress report, June 15, 1991--June 14, 1992  

SciTech Connect (OSTI)

This report discusses progress on the following research: quark cluster model; solving quantum field theories in non-perturbative regime;relativistic wave equations, quarkonia and electron-positron resonances; nuclear dependence at large transverse momentum; factorization at the order of power corrections; single-spin asymmetries; and hadronic photon production. (LSP)

Vary, J.P.

1992-07-01T23:59:59.000Z

395

Special committee review of the Nuclear Regulatory Commission's severe accident risks report (NUREG--1150)  

SciTech Connect (OSTI)

In April 1989, the Nuclear Regulatory Commission's (NRC) Office of Nuclear Regulatory Research (RES) published a draft report Severe Accident Risks: An Assessment for Five US Nuclear Power Plants,'' NUREG-1150. This report updated, extended and improved upon the information presented in the 1974 Reactor Safety Study,'' WASH-1400. Because the information in NUREG-1150 will play a significant role in implementing the NRC's Severe Accident Policy, its quality and credibility are of critical importance. Accordingly, the Commission requested that the RES conduct a peer review of NUREG-1150 to ensure that the methods, safety insights and conclusions presented are appropriate and adequately reflect the current state of knowledge with respect to reactor safety. To this end, RES formed a special committee in June of 1989 under the provisions of the Federal Advisory Committee Act. The Committee, composed of a group of recognized national and international experts in nuclear reactor safety, was charged with preparing a report reflecting their review of NUREG-1150 with respect to the adequacy of the methods, data, analysis and conclusions it set forth. The report which precedes reflects the results of this peer review.

Kouts, H.J.C. (Defense Nuclear Facility Safety Board (USA)); Apostolakis, G.; Kastenberg, W.E. (California Univ., Los Angeles, CA (USA)); Birkhofer, E.H.A. (Gesellschaft fuer Reaktorsicherheit mbH (GRS), Koeln (Germany, F.R.)); Hoegberg, L.G. (Swedish Nuclear Power Inspectorate, Stockholm (Sweden)); LeSage, L.G. (Argonne National Lab., IL (USA)); Rasmussen, N.C. (Massachusetts Inst. of Tech., Camb

1990-08-01T23:59:59.000Z

396

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

On other hand, accidents at nuclear facilities could nott ed expos ur e from a nuclear accident which would warrantresulting from accidents at nuclear facilities. Average

Nero, A.V.

2010-01-01T23:59:59.000Z

397

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

average value for nuclear plants) aFinal Envir. Statement (Statement, Koshkonong Nuclear Plant, August 1976. U. S.rem; operation of the nuclear plants themselves only *Other

Nero, A.V.

2010-01-01T23:59:59.000Z

398

Nuclear Physics Science Network Requirements Workshop, May 2008 - Final Report  

SciTech Connect (OSTI)

The Energy Sciences Network (ESnet) is the primary provider of network connectivity for the US Department of Energy Office of Science, the single largest supporter of basic research in the physical sciences in the United States of America. In support of the Office of Science programs, ESnet regularly updates and refreshes its understanding of the networking requirements of the instruments, facilities, scientists, and science programs that it serves. This focus has helped ESnet to be a highly successful enabler of scientific discovery for over 20 years. In May 2008, ESnet and the Nuclear Physics (NP) Program Office of the DOE Office of Science organized a workshop to characterize the networking requirements of the science programs funded by the NP Program Office. Most of the key DOE sites for NP related work will require significant increases in network bandwidth in the 5 year time frame. This includes roughly 40 Gbps for BNL, and 20 Gbps for NERSC. Total transatlantic requirements are on the order of 40 Gbps, and transpacific requirements are on the order of 30 Gbps. Other key sites are Vanderbilt University and MIT, which will need on the order of 20 Gbps bandwidth to support data transfers for the CMS Heavy Ion program. In addition to bandwidth requirements, the workshop emphasized several points in regard to science process and collaboration. One key point is the heavy reliance on Grid tools and infrastructure (both PKI and tools such as GridFTP) by the NP community. The reliance on Grid software is expected to increase in the future. Therefore, continued development and support of Grid software is very important to the NP science community. Another key finding is that scientific productivity is greatly enhanced by easy researcher-local access to instrument data. This is driving the creation of distributed repositories for instrument data at collaborating institutions, along with a corresponding increase in demand for network-based data transfers and the tools to manage those transfers effectively. Network reliability is also becoming more important as there is often a narrow window between data collection and data archiving when transfer and analysis can be done. The instruments do not stop producing data, so extended network outages can result in data loss due to analysis pipeline stalls. Finally, as the scope of collaboration continues to increase, collaboration tools such as audio and video conferencing are becoming ever more critical to the productivity of scientific collaborations.

Tierney, Ed., Brian L; Dart, Ed., Eli; Carlson, Rich; Dattoria, Vince; Ernest, Michael; Hitchcock, Daniel; Johnston, William; Kowalski, Andy; Lauret, Jerome; Maguire, Charles; Olson, Douglas; Purschke, Martin; Rai, Gulshan; Watson, Chip; Vale, Carla

2008-11-10T23:59:59.000Z

399

[Heavy ion nuclear physics research]. Progress report, 1991--1992  

SciTech Connect (OSTI)

We have continued working on essentially the same projects during the period 1991--92 as reported on in our previous progress report. That is, R&D work on a dimuon detector for RHIC and work with the group at LANL on neutron induced fission measurements using the white neutron source at LAMPF. Our work has included participation in the RD-10 experiment at the AGS to study calorimeter/absorber optimization for a RHIC experiment. We have actively participated in the setup of the apparatus, the data-taking and the subsequent data analysis. We have used the Vax computer system in our department and the eight-processor Silicon Graphics system in the GSU computer center for most of the data analysis work. We have also continued our work on Monte Carlo simulations of various configurations of absorber/calorimeters for detection of electrons and muons in RHIC experiments. We have made increasing use of the Silicon Graphics computer for our work. Each processor has approximately the same power as a Decstation 5000 and we usually have essentially exclusive simultaneous use of three of the processors. We have installed GEANT 315 and PAW on this system. Since our Vaxstation was purchased before DECWINDOWS was a standard part of the Vax software we have been unable to use the Silicon Graphics computer for doing graphics with PAW and GEANT. We are attempting to solve this problem by installing X-Windows software on our 386SX system which is connected to the campus network. Our work at Los Alamos has consisted of participation in the LAMPF run during the summer of 1991 including constructing and setting up two new neutron detectors for the experiment. These projects are discussed in further detail in this paper.

Liu, X.T.; Petitt, G.A.; Zhang, Ziyang

1992-12-31T23:59:59.000Z

400

Wind Turbine Generator System Safety and Function Test Report for the Entegrity EW50 Wind Turbine  

SciTech Connect (OSTI)

This report summarizes the results of a safety and function test that NREL conducted on the Entegrity EW50 wind turbine. This test was conducted in accordance with the International Electrotechnical Commissions' (IEC) standard, Wind Turbine Generator System Part 2: Design requirements for small wind turbines, IEC 61400-2 Ed.2.0, 2006-03.

Smith, J.; Huskey, A.; Jager, D.; Hur, J.

2012-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Wind Turbine Generator System Safety and Function Test Report for the Ventera VT10 Wind Turbine  

SciTech Connect (OSTI)

This report summarizes the results of a safety and function test that NREL conducted on the Ventera VT10 wind turbine. This test was conducted in accordance with the International Electrotechnical Commissions' (IEC) standard, Wind Turbine Generator System Part 2: Design requirements for small wind turbines, IEC 61400-2 Ed.2.0, 2006-03.

Smith, J.; Huskey, A.; Jager, D.; Hur, J.

2012-11-01T23:59:59.000Z

402

Determination of torsional fatigue life of large turbine generator shafts. Final report  

SciTech Connect (OSTI)

This report presents the results of a study to develop a methodology for predicting torsional fatigue damage to a turbine generator rotor subjected to transient electrical disturbances. This methodology used torsional properties obtained from constant amplitude tests on one-inch diameter specimens. The predictions were verified with constant amplitude and variable amplitude tests of specimens up to six inches in diameter.

Placek, R.J.; Williams, R.A.; Adams, S.L.; Klufas, O.

1984-04-01T23:59:59.000Z

403

Final environmental impact statement. Management of commercially generated radioactive waste. Volume 3. Public comments hearing board report  

SciTech Connect (OSTI)

This EIS analyzes the significant environmental impacts that could occur if various technologies for management and disposal of high-level and transuranic wastes from commercial nuclear power reactors were to be developed and implemented. This EIS will serve as the environmental input for the decision on which technology, or technologies, will be emphasized in further research and development activities in the commercial waste management program. The action proposed in this EIS is to (1) adopt a national strategy to develop mined geologic repositories for disposal of commercially generated high-level and transuranic radioactive waste (while continuing to examine subseabed and very deep hole disposal as potential backup technologies) and (2) conduct a R and D program to develop such facilities and the necessary technology to ensure the safe long-term containment and isolation of these wastes. The Department has considered in this statement: development of conventionally mined deep geologic repositories for disposal of spent fuel from nuclear power reactors and/or radioactive fuel reprocessing wastes; balanced development of several alternative disposal methods; and no waste disposal action. This volume contains written public comments and hearing board responses and reports offered on the draft statement.

Not Available

1980-10-01T23:59:59.000Z

404

WTEC panel report on European nuclear instrumentation and controls. Final report  

SciTech Connect (OSTI)

A study of instrumentation and controls (I and C) technology used in nuclear power plants in Europe was conducted by a panel of US specialists. This study plants in Europe was conducted by a panel of US specialists. This study included a review of the literature on the subject, followed by a visit to some of the leading organizations in Europe in the field nuclear I and C. Areas covered are: (1) role of the operator and control room design; (2) transition from analog to digital technology; (3) computerized operator support systems for fault management; (4) control strategies and techniques; (5) Nuclear power plant I and C architecture; (6) instrumentation and (7) computer standards and tools. The finding relate to poor reactions.

White, J.D.; Lanning, D.D.; Johnson, P.M.H. [eds.] [World Technology Evaluation Center, Baltimore, MD (United States); Shelton, R.D. [World Technology Evaluation Center, Baltimore, MD (United States)

1991-12-01T23:59:59.000Z

405

Preliminary evaluation of a fluorescence and radioisotope nuclear smuggling deterrence tag - final report (IL500E)  

SciTech Connect (OSTI)

This report summarizes the efforts completed in identifying candidate fluorescence compounds and radioisotopes for a developing tagging system. The tagging system is being developed as a deterrent to nuclear smuggling, by providing a means of: (1) tracing materials and pilferers to the facility of origin for any recovered special nuclear materials, (2) inventory control of long-term stored items containing special nuclear materials, and (3) tracking materials transferred between facilities. The system uses three types of materials to cover a range of applications intended to prevent the pilfering of special nuclear materials. One material, fluorescent compounds which are invisible without ultraviolet or near-infrared detection systems, is marked on controlled items with a tracking pattern that corresponds to a specified item in a specified location in the data control system. The tagging system uses an invisible, fluorescent dusting powder to mark equipment and personnel who inappropriately handle the tagged material. The tagging system also uses unique combinations of radionuclides to identify the facility of origin for any special nuclear material. This report also summarizes the efforts completed in identifying hardware that will be used for the tagging system. This hardware includes the devices for applying the tagging materials, the commercially available fluorescence detection systems, and gamma ray detection systems assembled from existing, commercially available technologies.

Hartenstein, S.D.; Aryaeinejad, R.; Delmastro, J.R. [and others

1997-04-01T23:59:59.000Z

406

Modeling and Verification of Distributed Generation and Voltage Regulation Equipment for Unbalanced Distribution Power Systems; Annual Subcontract Report, June 2007  

SciTech Connect (OSTI)

This report summarizes the development of models for distributed generation and distribution circuit voltage regulation equipment for unbalanced power systems and their verification through actual field measurements.

Davis, M. W.; Broadwater, R.; Hambrick, J.

2007-07-01T23:59:59.000Z

407

Nuclear containment steel liner corrosion workshop : final summary and recommendation report.  

SciTech Connect (OSTI)

This report documents the proceedings of an expert panel workshop conducted to evaluate the mechanisms of corrosion for the steel liner in nuclear containment buildings. The U.S. Nuclear Regulatory Commission (NRC) sponsored this work which was conducted by Sandia National Laboratories. A workshop was conducted at the NRC Headquarters in Rockville, Maryland on September 2 and 3, 2010. Due to the safety function performed by the liner, the expert panel was assembled in order to address the full range of issues that may contribute to liner corrosion. This report is focused on corrosion that initiates from the outer surface of the liner, the surface that is in contact with the concrete containment building wall. Liner corrosion initiating on the outer diameter (OD) surface has been identified at several nuclear power plants, always associated with foreign material left embedded in the concrete. The potential contributing factors to liner corrosion were broken into five areas for discussion during the workshop. Those include nuclear power plant design and operation, corrosion of steel in contact with concrete, concrete aging and degradation, concrete/steel non-destructive examination (NDE), and concrete repair and corrosion mitigation. This report also includes the expert panel member's recommendations for future research.

Erler, Bryan A. (Erler Engineering Ltd., Chicago, IL); Weyers, Richard E. (Virginia Tech University, Blacksburg, VA); Sagues, Alberto (University of South Florida, Tampa, FL); Petti, Jason P.; Berke, Neal Steven (Tourney Consulting Group, LLC, Kalamazoo, MI); Naus, Dan J. (Oak Ridge National Laboratory, Oak Ridge, TN)

2011-07-01T23:59:59.000Z

408

Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report  

SciTech Connect (OSTI)

Since 1962, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site, but a limited number of experiments were conducted in other locations. One of these is the subject of this report, the Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada. The Shoal test consisted of a 12-kiloton-yield nuclear detonation which occurred on October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in particular, in active earthquake areas. Characterization of groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE) under the Federal Facility Agreement and Consent Order (FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense (DOD). This order prescribes a Corrective Action Strategy (Appendix VI), which, as applied to underground nuclear tests, involves preparing a Corrective Action Investigation Plan (CAIP), Corrective Action Decision Document (CADD), Corrective Action Plan, and Closure Report. The scope of the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and the environment. This interim report describes the current status of the flow and transport modeling for the PSA.

Pohll, G.; Chapman, J.; Hassan, A.; Papelis, C.; Andricevic, R.; Shirley, C.

1998-07-01T23:59:59.000Z

409

Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report  

SciTech Connect (OSTI)

OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

NONE

2000-08-01T23:59:59.000Z

410

Test and evaluation of computerized nuclear material accounting methods. Final report  

SciTech Connect (OSTI)

In accordance with the definition of a Material Balance Area (MBA) as a well-defined geographical area involving an Integral operation, the building housing the BFS-1 and BFS-1 critical facilities is considered to consist of one MBA. The BFS materials are in the form of small disks clad in stainless steel and each disk with nuclear material has its own serial number. Fissile material disks in the BFS MBA can be located at three key monitoring points: BFS-1 facility, BFS-2 facility and main storage of BFS fissile materials (storage 1). When used in the BFS-1 or BFS-2 critical facilities, the fissile material disks are loaded in tubes (fuel rods) forming critical assembly cores. The following specific features of the BFS MBA should be taken into account for the purpose of computerized accounting of nuclear material: (1) very large number of nuclear material items (about 70,000 fissile material items); and (2) periodically very intensive shuffling of nuclear material items. Requirements for the computerized system are determined by basic objectives of nuclear material accounting: (1) providing accurate information on the identity and location of all items in the BFS material balance area; (2) providing accurate information on location and identity of tamper-indicating devices; (3) tracking nuclear material inventories; (4) issuing periodic reports; (5) assisting with the detection of material gains or losses; (6) providing a history of nuclear material transactions; (7) preventing unauthorized access to the system and data falsification. In August 1995, the prototype computerized accounting system was installed on the BFS facility for trial operation. Information on two nuclear material types was entered into the data base: weapon-grade plutonium metal and 36% enriched uranium dioxide. The total number of the weapon-grade plutonium disks is 12,690 and the total number of the uranium dioxide disks is 1,700.

NONE

1995-12-31T23:59:59.000Z

411

A comparison of delayed radiobiological effects of depleted-uranium munitions versus fourth-generation nuclear weapons  

E-Print Network [OSTI]

It is shown that the radiological burden due to the battle-field use of circa 400 tons of depleted-uranium munitions in Iraq (and of about 40 tons in Yugoslavia) is comparable to that arising from the hypothetical battle-field use of more than 600 kt (respectively 60 kt) of high-explosive equivalent pure-fusion fourth-generation nuclear weapons. Despite the limited knowledge openly available on existing and future nuclear weapons, there is sufficient published information on their physical principles and radiological effects to make such a comparison. In fact, it is shown that this comparison can be made with very simple and convincing arguments so that the main technical conclusions of the paper are undisputable -- although it would be worthwhile to supplement the hand calculations presented in the paper by more detailed computer simulations in order to consolidate the conclusions and refute any possible objections.

Gsponer, A; Vitale, B; Gsponer, Andre; Hurni, Jean-Pierre; Vitale, Bruno

2002-01-01T23:59:59.000Z

412

Electronic constant current and current pulse signal generator for nuclear instrumentation testing  

DOE Patents [OSTI]

Circuitry is described for testing the ability of an intermediate range nuclear instrument to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on. 1 figures.

Brown, R.A.

1994-04-19T23:59:59.000Z

413

Electronic constant current and current pulse signal generator for nuclear instrumentation testing  

DOE Patents [OSTI]

Circuitry for testing the ability of an intermediate range nuclear instrut to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on.

Brown, Roger A. (Amsterdam, NY)

1994-01-01T23:59:59.000Z

414

REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS  

SciTech Connect (OSTI)

Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEAís Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facilityís general character, purpose, capacity, and location; (2) Description of the facilityís layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future. Consequently, the NNSA Office of International Regimes and Agreements (NA-243) sponsored a team of U.S. Department of Energy National Laboratory nuclear safeguards experts and technologists to conduct a workshop on methods and technologies for improving this activity, under the ASA-100 Advanced Safeguards Approaches Project. The workshop focused on reviewing and discussing the fundamental safeguards needs, and presented technology and/or methods that could potentially address those needs more effectively and efficiently. Conclusions and Recommendations for technology to enhance the performance of DIV inspections are presented by the workshop team.

Richard Metcalf; Robert Bean

2009-10-01T23:59:59.000Z

415

U.S. Nuclear Regulatory Commission accountability report, fiscal year 1995. Volume 1  

SciTech Connect (OSTI)

The US Nuclear Regulatory Commission (NRC) is one of six Federal agencies participating in a pilot project to streamline financial management reporting. The goal of this pilot is to consolidate performance-related reporting into a single accountability report. The project, which is being carried out under the guidance of the Chief Financial Officers Council, was undertaken in accordance with the Government Management Reform Act (GMRA) of 1994. The GMRA permits the streamlining of financial management reports in consultation with the appropriate Congressional Committees through a liaison in the US Office of Management and Budget (OMB). The results of the pilot project will determine the method to be used for reporting financial management information for fiscal year (FY) 1996. This report consolidates the information previously reported in the following documents: (1) the NRC`s annual financial statement required by the Chief Financial Officers Act of 1990; (2) the Chairman`s annual report to the President and the Congress, required by the Federal Managers` Financial Integrity Act of 1982; (3) the Chairman`s semiannual report to the Congress on management decisions and final actions on Office of Inspector General audit recommendations, required by the Inspector General Act of 1978, as amended. This report also includes performance measures, as required by the Chief Financial Officers Act of 1990.

NONE

1996-05-01T23:59:59.000Z

416

Staff Draft Report. Comparative Cost of California Central Station Electricity Generation Technologies.  

SciTech Connect (OSTI)

This Energy Commission staff draft report presents preliminary levelized cost estimates for several generic central-station electricity generation technologies. California has traditionally adopted energy policies that balance the goals of supporting economic development, improving environmental quality and promoting resource diversity. In order to be effective, such policies must be based on comprehensive and timely gathering of information. With this goal in mind, the purpose of the report is to provide comparative levelized cost estimates for a set of renewable (e.g., solar) and nonrenewable (e.g., natural gas-fired) central-station electricity generation resources, based on each technology's operation and capital cost. Decision-makers and others can use this information to compare the generic cost to build specific technology. These costs are not site specific. If a developer builds a specific power plant at a specific location, the cost of siting that plant at that specific location must be considered. The Energy Commission staff also identifies the type of fuel used by each technology and a description of the manner in which the technology operates in the generation system. The target audiences of this report are both policy-makers and anyone wishing to understand some of the fundamental attributes that are generally considered when evaluating the cost of building and operating different electricity generation technology resources. These costs do not reflect the total cost to consumers of adding these technologies to a resources portfolio. These technology characterizations do not capture all of the system, environmental or other relevant attributes that would typically be needed by a portfolio manager to conduct a comprehensive ''comparative value analysis''. A portfolio analysis will vary depending on the particular criteria and measurement goals of each study. For example, some form of firm capacity is typically needed with wind generation to support system reliability. [DJE-2005

Badr, Magdy; Benjamin, Richard

2003-02-11T23:59:59.000Z

417

Studies of nuclear processes; Progress report, 1 September 1992--31 August 1993  

SciTech Connect (OSTI)

Results for the period 1 Sep 92 through 31 Aug 93 are presented in nearly a hundred brief papers, some of which present new but preliminary data. Activities reported may be grouped as follows: Fundamental symmetries in the nucleus (parity-mixing measurements, time reversal invariance measurements, signatures of quantum chaos in nuclei), Internucleon reactions (neutron -- proton interactions, the neutron -- neutron scattering length, reactions between deuterons and very light nuclei), Dynamics of very light nuclei (measurements of D states of very light nuclei by transfer reactions, nuclear reactions between very light nuclei, radiative capture reactions with polarized sources), The many-nucleon problem (nuclear astrophysics, high-spin spectroscopy and superdeformation, the nuclear mean field: Dispersive relations and nucleon scattering, configuration mixing in {sup 56}Co and {sup 46}Sc using (d,{alpha}) reactions, radiative capture studies, high energy resolution resonance studies at 100--400 keV, nuclear data evaluation for A=3--20), Nuclear instruments and methods (FN tandem accelerator operation, KN accelerator operation and maintenance, atomic beam polarized ion source, development of techniques for determining the concentration of SF{sub 6} in the accelerator insulating gas mixture, production of beams and targets, detector systems, updating of TeX, Psprint, and associated programs on the VAX cluster), and Educational Activities.

Ludwig, E.J.

1993-09-01T23:59:59.000Z

418

New approaches to interfacing thermoelectric generators to the load bus in a nuclear space vehicle  

E-Print Network [OSTI]

reactor and the thermoelectrics. This type oi' system wastes the excess power generated as heat. Heat dissipation in space is very difficult. In the reference design TCAs (thermoelectric converter assembly) and shunt regulators connect directly... ballast load. The variable ballast compensa, tes 1' or the variation of the load. This type of control philosophy is very inefficient. Of the power generated, some is wasted in the variable ballast by heat dissipation. New architectures of controlling...

Brohlin, Paul LeRoy

1988-01-01T23:59:59.000Z

419

Antares prototype 300-kJ, 250-kA Marx generator. Final report  

SciTech Connect (OSTI)

A high-energy, low-inductance, low prefire rate, low trigger jitter, high-voltage, pulsed-power supply was needed to drive the gas discharge in the Antares laser power amplifier. This report describes the design and testing of a Marx generator that meets these requirements, the development and testing of a high-capacity spark gap, and the selection of suitable capacitors and resistors.

Riepe, K.B.; Barrone, L.L.; Bickford, K.J.; Livermore, G.H.

1981-01-01T23:59:59.000Z

420

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report  

SciTech Connect (OSTI)

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation reported" 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

Improving the regulation of safety at DOE nuclear facilities. Final report  

SciTech Connect (OSTI)

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by DOE itself. The three major recommendations are: under any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

NONE

1995-12-01T23:59:59.000Z

422

Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices  

SciTech Connect (OSTI)

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

NONE

1995-12-01T23:59:59.000Z

423

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance  

SciTech Connect (OSTI)

The purpose of this volume is limited to an assessment of the relative effects that particular choices of nuclear-power systems, for whatever reasons, may have on the possible spread of nuclear-weapons capabilities. This volume addresses the concern that non-nuclear-weapons states may be able to initiate efforts to acquire or to improve nuclear-weapons capabilities through civilian nuclear-power programs; it also addresses the concern that subnational groups may obtain and abuse the nuclear materials or facilities of such programs, whether in nuclear-weapons states (NWS's) or nonnuclear-weapons states (NNW's). Accordingly, this volume emphasizes one important factor in such decisions, the resistance of nuclear-power systems to the proliferation of nuclear-weapons capabilities.

Not Available

1980-06-01T23:59:59.000Z

424

Integrated data base report--1995: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The information in this report summarizes the U.S. Department of Energy (DOE) data base for inventories, projections, and characteristics of domestic spent nuclear fuel and radioactive waste. This report is updated annually to keep abreast of continual waste inventory and projection changes in both the government and commercial sectors. Baseline information is provided for DOE program planning purposes and to support DOE program decisions. Although the primary purpose of this document is to provide background information for program planning within the DOE community, it has also been found useful by state and local governments, the academic community, and some private citizens.

NONE

1996-12-01T23:59:59.000Z

425

Nuclear power plant Generic Aging Lessons Learned (GALL). Main report and appendix A  

SciTech Connect (OSTI)

The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This document is Volume 1, consisting of the executive summary, summary and observations, and an appendix listing the GALL literature review tables.

Kaza, K.E.; Diercks, D.R.; Holland, J.W.; Choi, S.U. [and others

1996-12-01T23:59:59.000Z

426

Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

NONE

1997-12-01T23:59:59.000Z

427

Design of the Next Generation Nuclear Plant Graphite Creep Experiments for Irradiation in the Advanced Test Reactor  

SciTech Connect (OSTI)

The United States Department of Energyís Next Generation Nuclear Plant (NGNP) Program will be irradiating six gas reactor graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energyís lead laboratory for nuclear energy development. The ATR is one of the worldís premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These graphite irradiations are being accomplished to support development of the next generation reactors in the United States. The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain seven separate stacks of graphite specimens. Six of the specimen stacks will have half of their graphite specimens under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six stacks will be organized into pairs with a different compressive load being applied to the top half of each pair of specimen stacks. The seventh stack will not have a compressive load on the graphite specimens during irradiation. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be the capability of sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during initial start-up of the experiment. The final design phase for the first experiment was completed in September 2008, and the fabrication and assembly of the experiment test train as well as installation and testing of the control and support systems that will monitor and control the experiment during irradiation are being completed in early calendar 2009. The first experiment is scheduled to be ready for insertion in the ATR by April 30, 2009. This paper will discuss the design of the experiment including the test train and the temperature and compressive load monitoring, control, and data collection systems.

S. Blaine Grover

2009-05-01T23:59:59.000Z

428

Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design  

SciTech Connect (OSTI)

Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design & performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program implementation as LANL moves forward into production and use of the SAVY-3000 will all be addressed. The SAVY-3000 is intended as a work horse package for the DOE complex as a vented storage container primarily for plutonium in solid form.

Stone, Timothy Amos [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

429

National Nuclear Security Administration Nonproliferation Graduate Fellowship Program Annual Report in Brief: October 2007 - May 2008  

SciTech Connect (OSTI)

This abbreviated Annual Report covers program activities of the National Nuclear Security Administration (NNSA) Nonproliferation Graduate Fellowship Program (NGFP) from October 2007 through May 2008--the timeframe between the last Annual Report (which covered activities through September 2007) and the next report (which will begin with June 2008 activities). In that timeframe, the NGFP continued building a solid foundation as the program began reaping the benefits of recently implemented changes. This report is organized by Fellowship class and the pertinent program activities for each, including: October 2007 Recruiting events and final applications (Class of 2008) Winter 2007 Selection and hiring (Class of 2008) Spring 2008 Career development roundtables (Class of 2007) Orientation planning (Class of 2008) Recruitment planning and university outreach (Class of 2009) May 2008 Closing ceremony (Class of 2007)

Berkman, Clarissa O.; Fankhauser, Jana G.; Sandusky, Jessica A.

2009-05-01T23:59:59.000Z

430

SRNL CRP progress report [Development of Melt Processed Ceramics for Nuclear Waste Immobilization  

SciTech Connect (OSTI)

A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multiphase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing.

Amoroso, J.; Marra, J.

2014-10-02T23:59:59.000Z

431

New technology for purging the steam generators of nuclear power plants  

SciTech Connect (OSTI)

A technology for removal of undissolved impurities from a horizontal steam generator using purge water is developed on the basis of a theoretical analysis. A purge with a maximal flow rate is drawn off from the zone with the highest accumulation of sludge in the lower part of the steam generator after the main circulation pump of the corresponding loop is shut off and the temperatures of the heat transfer medium at the inlet and outlet of the steam generator have equilibrated. An improved purge configuration is used for this technology; it employs shutoff and regulator valves, periodic purge lines separated by a cutoff fixture, and a D{sub y} 100 drain union as a connector for the periodic purge. Field tests show that the efficiency of this technology for sludge removal by purge water is several times that for the standard method.

Budko, I. O.; Kutdjusov, Yu. F.; Gorburov, V. I. [Scientific-Research Center for Energy Technology 'NICE Centrenergo' (Russian Federation); Rjasnyj, S. I. [JSC 'The All-Rissia Nuklear Power Engineering Research and Development Institute' (VNIIAM) (Russian Federation)

2011-07-15T23:59:59.000Z

432

Small Reactor Designs Suitable for Direct Nuclear Thermal Propulsion: Interim Report  

SciTech Connect (OSTI)

Advancement of U.S. scientific, security, and economic interests requires high performance propulsion systems to support missions beyond low Earth orbit. A robust space exploration program will include robotic outer planet and crewed missions to a variety of destinations including the moon, near Earth objects, and eventually Mars. Past studies, in particular those in support of both the Strategic Defense Initiative (SDI) and the Space Exploration Initiative (SEI), have shown nuclear thermal propulsion systems provide superior performance for high mass high propulsive delta-V missions. In NASA's recent Mars Design Reference Architecture (DRA) 5.0 study, nuclear thermal propulsion (NTP) was again selected over chemical propulsion as the preferred in-space transportation system option for the human exploration of Mars because of its high thrust and high specific impulse ({approx}900 s) capability, increased tolerance to payload mass growth and architecture changes, and lower total initial mass in low Earth orbit. The recently announced national space policy2 supports the development and use of space nuclear power systems where such systems safely enable or significantly enhance space exploration or operational capabilities. An extensive nuclear thermal rocket technology development effort was conducted under the Rover/NERVA, GE-710 and ANL nuclear rocket programs (1955-1973). Both graphite and refractory metal alloy fuel types were pursued. The primary and significantly larger Rover/NERVA program focused on graphite type fuels. Research, development, and testing of high temperature graphite fuels was conducted. Reactors and engines employing these fuels were designed, built, and ground tested. The GE-710 and ANL programs focused on an alternative ceramic-metallic 'cermet' fuel type consisting of UO2 (or UN) fuel embedded in a refractory metal matrix such as tungsten. The General Electric program examined closed loop concepts for space or terrestrial applications as well as open loop systems for direct nuclear thermal propulsion. Although a number of fast spectrum reactor and engine designs suitable for direct nuclear thermal propulsion were proposed and designed, none were built. This report summarizes status results of evaluations of small nuclear reactor designs suitable for direct nuclear thermal propulsion.

Bruce G. Schnitzler

2012-01-01T23:59:59.000Z

433

Evaluation Metrics for Intermediate Heat Exchangers for Next Generation Nuclear Reactors  

SciTech Connect (OSTI)

The Department of Energy (DOE) is working with industry to develop a next generation, high-temperature gas-cooled reactor (HTGR) as a part of the effort to supply the United States with abundant, clean, and secure energy as initiated by the Energy Policy Act of 2005 (EPAct; Public Law 109-58,2005). The NGNP Project, led by the Idaho National Laboratory (INL), will demonstrate the ability of the HTGR to generate hydrogen, electricity, and/or high-quality process heat for a wide range of industrial applications.

Piyush Sabharwall; Eung Soo Kim; Nolan Anderson

2011-06-01T23:59:59.000Z

434

Evaluation of the electromagnetic effects due to direct lighting to nuclear explosive areas at Pantex. Final report  

SciTech Connect (OSTI)

This report summarizes the effort to quantify the electromagnetic environments in the nuclear explosive areas at Pantex due to direct lightning. The fundamental measure of the threat to nuclear safety is assumed to be the maximum voltage between any two points in an assembly area, which is then available for producing arcing or for driving current into critical subsystems of a nuclear weapon. This maximum voltage has been computed with simple analytical models and with three-dimensional finite-difference computer codes.

Merewether, K.O.; Chen, K.C.

1993-11-01T23:59:59.000Z

435

The Transmutation of Nuclear Waste in the Two-Zone Subcritical System Driven by High- Intensity Neutron Generator - 12098  

SciTech Connect (OSTI)

The main problems of transmutation of high-level radioactive waste (minor actinides and long-lived fission products) are considered in our work. The range of radioactive waste of nuclear power is analyzed. The conditions under which the transmutation of radioactive waste will be most effective are analyzed too. The modeling results of a transmutation of the main radioactive isotopes are presented and discussed. The transmutation of minor actinides and long-lived fission products are modeled in our work (minor actinides - Np-237, Am-241, Am-242, Am-243, Cm-244, Cm-245; long-lived fission products - I-129, Tc-99). The two-zone subcritical system is calculated with help of different neutron-physical codes (MCNP, Scale, Montebarn, Origen). The ENDF/B-VI nuclear data library used in above calculations. Thus, radioactive wastes can be divided into two main groups that need to be transmuted. The minor actinides form the first group and the long-lived fission products form the second one. For the purpose of effective transmutation these isotopes must be extracted from the spent nuclear fuel with the help of either PUREX technology or pyrometallurgical technology. The two-zone reactor system with fast and thermal regions is more effective for nuclear waste transmutation than the one-zone reactor. Modeling results show that nearly all radioactive wastes can be transmuted in the two-zone subcritical system driven by a high-intensity neutron generator with the external neutron source strength of 1.10{sup 13} n/sec. Obviously, transmutation rate will increase with a rise of the external neutron source strength. From the results above we can also see that the initial loading of radioactive isotopes into the reactor system should exceed by mass those isotopes that are finally produced. (authors)

Babenko, V.O. [Bogolyubov Institute for Theoretical Physics, Metrolohichna str. 14-b, Kiev, 03680 (Ukraine); Gulik, V.I.; Pavlovych, V.M. [Institute for Nuclear Research, pr. Nauky 47, Kyiv, 03680 (Ukraine)

2012-07-01T23:59:59.000Z

436

March 2006, Report of the ADVANCED NUCLEAR TRANSFORMATION TECHNOLOGY SUBCOMMITTEE of the NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE  

Broader source: Energy.gov [DOE]

The Global Nuclear Energy Partnership (GNEP) marks a major change in the direction of the DOEís nuclear energy R&D program. It is a coherent plan to test technologies that promise to markedly...

437

Nuclear physics research at the University of Richmond. Progress report, November 1, 1994--October 31, 1995  

SciTech Connect (OSTI)

Summarized in this report is the progress achieved during the period from November 1, 1994 to October 31, 1995. The experimental work described in this report is in electromagnetic and heavy-ion nuclear physics. The effort in electromagnetic nuclear physics is in preparation for the research program at the Continuous Electron Beam Accelerator Facility (CEBAF) and is focused on the construction and use of the CEBAF Large Acceptance Spectrometer (CLAS). The heavy-ion experiments were performed at the Argonne National Laboratory ATLAS facility and SUNY, Stony Brook. The physics interests driving these efforts at CEBAF are in the study of the structure, interactions, and nuclear-medium modifications of mesons and baryons. This year, an extension of the experiment to measure the magnetic form factor of the neutron was approved by the CEBAF Program Advisory Committee Nine (PAC9) for beam at 6 GeV. The authors also submitted updates to PAC9 on the experiments to measure inclusive {eta} photoproduction in nuclei and electroproduction of the {Lambda}, {Lambda}*(1520), and f{sub 0}(975). In addition to these experiments, the authors collaborated on a proposal to measure rare radiative decays of the {phi} meson which was also approved by PAC9. Their contributions to the construction of the CLAS include the development of the drift-chamber gas system, drift-chamber software, and controls software. Major has been leading the effort in the construction of the gas system. In the last year, the Hall B gas shed was constructed and the installation of the gas system components built at the University of Richmond has begun. Over the last six years, the efforts in low-energy heavy-ion physics have decreased due to the change in focus to electromagnetic nuclear physics at CEBAF. Most of the heavy-ion work is completed and there are now new experiments planned. Included in this report are two papers resulting from collaborations on heavy-ion experiments.

Vineyard, M.F.; Gilfoyle, G.P.; Major, R.W.

1995-12-31T23:59:59.000Z

438

Nuclear Science Division annual report, October 1, 1986--September 30, 1987  

SciTech Connect (OSTI)

This report summarizes the activities of the Nuclear Science Division during the period October 1, 1986 to September 30, 1987. A highlight of the experimental program during this time was the completion of the first round of heavy-ion running at CERN with ultrarelativistic oxygen and sulfur beams. Very rapid progress is being made in the analysis of these important experiments and preliminary results are presented in this report. During this period, the Bevalac also continued to produce significant new physics results, while demand for beam time remained high. An important new community of users has arrived on the scene, eager to exploit the unique low-energy heavy-beam capabilities of the Bevalac. Another major highlight of the program has been the performance of the Dilepton Spectrometer which has entered into production running. Dileptons have been observed in the p + Be and Ca + Ca reactions at several bombarding energies. New data on pion production with heavy beams measured in the streamer chamber to shed light on the question of nuclear compressibility, while posing some new questions concerning the role of Coulomb forces on the observed pion spectra. In another quite different area, the pioneering research with radioactive beams is continuing and is proving to be one of the fastest growing programs at the Bevalac. Exotic secondary beams (e.g., 8He, 11Li, and 14Be) have been produced for fundamental nuclear physics studies. In order to further enhance the scientific research program and ensure the continued vitality of the facility, the Laboratory has proposed an upgrade of the existing Bevalac. Specifically, the Upgrade would replace the Bevatron with a modern, strong-focusing synchrotron to provide higher intensity and higher quality beams to continue the forefront research program. Other papers on nuclear physics research are included in this report.

Mahoney, J. (ed.)

1988-09-01T23:59:59.000Z

439

DHS National Technical Nuclear Forensics Program FY 10 Summary Report: Graduate Mentoring Assistance Program (GMAP)  

SciTech Connect (OSTI)

This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. The summary report details the student/mentor experience and future plans after the first summer practicum. This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. This final written report includes information concerning the overall mentoring experience, including benefits (to the lab, the mentors, and the students), challenges, student research contributions, and lab mentor interactions with students home universities. Idaho National Laboratory hosted two DHS Nuclear Forensics graduate Fellows (nuclear engineering) in summer 2011. Two more Fellows (radiochemistry) are expected to conduct research at the INL under this program starting in 2012. An undergraduate Fellow (nuclear engineering) who worked in summer 2011 at the laboratory is keenly interested in applying for the NF Graduate Fellowship this winter with the aim of returning to INL. In summary, this program appears to have great potential for success in supporting graduate level students who pursue careers in nuclear forensics. This relatively specialized field may not have been an obvious choice for some who have already shown talent in the traditional areas of chemistry or nuclear engineering. The active recruiting for this scholarship program for candidates at universities across the U.S. brings needed visibility to this field. Not only does this program offer critical practical training to these students, it brings attention to a very attractive field of work where young professionals are urgently required in order for the future. The effectiveness of retaining such talent remains to be seen and may be primarily controlled by the availability of DOE laboratory research funding in this field in the years to come.

Martha R. Finck Ph.D.

2011-10-01T23:59:59.000Z

440

Activation cross sections of $?$-particle induced nuclear reactions on hafnium and deuteron induced nuclear reaction on tantalum: production of $^{178}$W/$^{178m}$Ta generator  

E-Print Network [OSTI]

In the frame of a systematic study of charged particle production routes of medically relevant radionuclei, the excitation function for indirect production of $^{178m}$Ta through $^{nat}$Hf($\\alpha$,xn)$^{178}$W-$^{178m}$Ta nuclear reaction was measured for the first time up to 40 MeV. In parallel, the side reactions $^{nat}$Hf($\\alpha$,x)$^{179,177,176,175}$W, $^{183,182,178g,177,176,175}$Ta, $^{179m,177m,175}$Hf were also assessed. Stacked foil irradiation technique and $\\gamma$-ray spectrometry were used. New experimental cross section data for the $^{nat}$Ta(d,xn)$^{178}$W reaction are also reported up to 40 MeV. The measured excitation functions are compared with the results of the ALICE-IPPE, and EMPIRE nuclear reaction model codes and with the TALYS 1.4 based data in the TENDL-2013 library. The thick target yields were deduced and compared with yields of other charged particle ((p,4n), (d,5n) and ($^3$He,x)) production routes for $^{178}$W.

F. TŠrk'anyi; S. Tak'acs; F. Ditrůi; A. Hermanne; A. V. Ignatyuk; M. S. Uddin

2014-12-01T23:59:59.000Z

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441

Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

he purpose of this DOE Standard is to establish guidance for the preparation and review of hazard categorization and accident analyses techniques as required in DOE Order 5480.23, Nuclear Safety Analysis Reports.

1997-12-12T23:59:59.000Z

442

Report of workshop on radiological effects of nuclear war, SCOPE-ENUWAR workshop, Moscow, USSR, March 21-25, 1988  

SciTech Connect (OSTI)

The workshop on radiological consequences of nuclear war addressed specific issues that built on the foundation of the results that were published in the SCOPE-ENUWAR report (SCOPE-28) in 1986. 14 refs.

Shapiro, C.S.

1988-03-01T23:59:59.000Z

443

Nuclear Power Overview  

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

San Onofre Nuclear Generating Station San Onofre Nuclear Generating Station Bob Ashe-Everest Southern California Edison 10 Incoming New Fuel Inspecting New Fuel SONGS Unit 1 Fuel...

444

Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--March 31, 1989  

SciTech Connect (OSTI)

This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1988.

Weiss, A.J. (comp.)

1989-08-01T23:59:59.000Z

445

Report on the September 2011 Meeting of the Next Generation Safegaurds Professional Network  

SciTech Connect (OSTI)

The Next Generation Safeguards Professional Network (NGSPN) was established in 2009 by Oak Ridge National Laboratory targeted towards the engagement of young professionals employed in safeguards across the many national laboratories. NGSPN focuses on providing a mechanism for young safeguards professionals to connect and foster professional relationships, facilitating knowledge transfer between current safeguards experts and the next generation of experts, and acting as an entity to represent the interests of the international community of young and mid-career safeguards professionals. This is accomplished in part with a yearly meeting held at a national laboratory site. In 2011, this meeting was held at Pacific Northwest National Laboratory. This report documents the events and results of that meeting.

Gitau, Ernest TN; Benz, Jacob M.

2011-12-19T23:59:59.000Z

446

Role of Energy Storage with Renewable Electricity Generation (Report Summary) (Presentation)  

SciTech Connect (OSTI)

Renewable energy sources, such as wind and solar, have vast potential to reduce dependence on fossil fuels and greenhouse gas emissions in the electric sector. Climate change concerns, state initiatives including renewable portfolio standards, and consumer efforts are resulting in increased deployments of both technologies. Both solar photovoltaics (PV) and wind energy have variable and uncertain (sometimes referred to as "intermittent") output, which are unlike the dispatchable sources used for the majority of electricity generation in the United States. The variability of these sources has led to concerns regarding the reliability of an electric grid that derives a large fraction of its energy from these sources as well as the cost of reliably integrating large amounts of variable generation into the electric grid. In this report, we explore the role of energy storage in the electricity grid, focusing on the effects of large-scale deployment of variable renewable sources (primarily wind and solar energy).

Denholm, P.; Ela, E.; Kirby, B.; Milligan, M.

2010-03-01T23:59:59.000Z

447

Monitoring equipment environment during nuclear plant operation at Salem and Hope Creek generating stations  

SciTech Connect (OSTI)

Monitoring of environmental parameters has become a significant issue for operating nuclear power plants. While the long-term benefits of plant life extension programs are being pursued with comprehensive environmental monitoring programs, the potential effect of local hot spots at various plant locations needs to be evaluated for its effect on equipment degradation and shortening of equipment qualified life. A significant benefit can be experienced from temperature monitoring when a margin exists between the design versus actual operating temperature. This margin can be translated into longer equipment qualified life and significant reduction in maintenance activities. At PSE and G, the immediate need for monitoring environmental parameters is being accomplished via the use of a Logic Beach Bitlogger. The Bitlogger is a portable data loggings system consisting of a system base, input modules and a communication software package. Thermocouples are installed on selected electrical equipment and cables are run from the thermocouples to the input module of the Bitlogger. Temperature readings are taken at selected intervals, stored in memory, and downloaded periodically to a PC software program, i.e., Lotus. The data is formatted into tabular or graphical documents. Because of their versatility, Bitloggers are being used differently at the authors Nuclear facility. At the Salem Station (2 Units-4 loop Westinghouse PWR), a battery powered, fully portable, calibrated Bitlogger is located in an accessible area inside Containment where it monitors the temperature of various electrical equipment within the Pressurizer Enclosure. It is planned that close monitoring of the local hot spot temperatures in this area will allow them to adjust and reconcile the environmental qualification of the equipment.

Blum, A.; Smith, R.J. [Public Service Electric and Gas Co., Hancocks Bridge, NJ (United States)

1991-06-01T23:59:59.000Z

448

Theoretical nuclear structure and astrophysics. Progress report for 1993--1995  

SciTech Connect (OSTI)

This research effort is directed toward theoretical support and guidance for the developing fields of radioactive ion beam (RIB) physics, computational and nuclear astrophysics, and the interface between these disciplines. The authors are concerned both with the application of existing technologies and concepts to guide the initial RIB program, and the development of new ideas and new technologies to influence the longer-term future of nuclear structure physics and astrophysics. The authors report substantial progress in both areas. One measure of progress is publications and invited material. The research described here has led to more than 70 papers that are published, accepted, or submitted to refereed journals, and to 46 invited presentations at conferences and workshops.

Guidry, M.W.; Nazarewicz, W.; Strayer, M.R.

1995-12-31T23:59:59.000Z

449

Operation Cornerstone onsite radiological safety report for announced nuclear tests, October 1988--September 1989  

SciTech Connect (OSTI)

Cornerstone was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site (NTS) from October 1, 1988, through September 30, 1989. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Radiation Protection Technicians (RPT) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage were provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined.

Not Available

1990-08-01T23:59:59.000Z

450

The design and construction of a low cost Van de Graaff generator for nuclear research  

E-Print Network [OSTI]

silk belt rtxudng between a pulley in its interior arxf a grour?ed motor driven pulley at the bass of . he rod, 'hc ascending surface of the belt is charged near the lower pulley by a brush discharzw& maintained by a 10w000 volt transformer kenotron... tubes rather than the Tesla coil. After they oon- str xcted a one meter diameter generatcrx this smae group reconstructed an emlier outdoor two meter generator in sn appropriate indoor labora- 17 toxy, he high volta!w terminal consisted of the two...

Riggs, James Willborn

1953-01-01T23:59:59.000Z

451

Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro`s Bruce Nuclear Generating Station `A`  

SciTech Connect (OSTI)

Ontario Hydro at the Bruce Nuclear Generating Station `A` has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The disch