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1

Contingency  

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

The chapter discusses contingency guidelines to provide for a standard approach to determining project contingency and improve the understanding of contingency in the project management process.

1997-03-28T23:59:59.000Z

2

Convention on Supplementary Compensation for Nuclear Damage Contingent Cost  

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:YearRound-Up fromDepartmentTieCelebrate EarthEnergy Contractor&3-1 Chapter 13Allocation |

3

Convention on Supplementary Compensation for Nuclear Damage Contingent Cost  

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:YearRound-Up fromDepartmentTieCelebrate EarthEnergy Contractor&3-1 Chapter 13Allocation

4

Convention on Supplementary Compensation for Nuclear Damage Contingent Cost  

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:YearRound-Up fromDepartmentTieCelebrate EarthEnergy Contractor&3-1 Chapter

5

65 Contingency Planning Issues CONTINGENCY PLANNING ISSUES  

E-Print Network [OSTI]

. The plan relies on a mixed strategy response to an energy shortage. The plan uses a free market approach to local jurisdic- tions, economic considerations, revisions to the California Energy Shortage Contingency multiple jurisdictions or agencies. LOCAL GOVERNMENT ASSISTANCE PROGRAM The purpose of the Energy

6

contingency Nominal loading margin  

E-Print Network [OSTI]

is estimated. First a nose curve is computed by continuation to obtain a nominal loading margin. Then linear and the very fast computation of the linear estimates. Keywords: Power system security, contingency analy- sis formulas derived in [4]. The computations are summarized: 1 A pattern of load increase, generator dispatch

7

Hanford facility contingency plan  

SciTech Connect (OSTI)

The Hanford Facility Contingency Plan, together with each TSD unit- specific contingency plan, meets the WAC 173-303 requirements for a contingency plan. Applicability of this plan to Hanford Facility activities is described in the Hanford Facility RCRA Permit, Dangerous Waste Portion, General Condition II.A. General Condition II.A applies to Part III TSD units, Part V TSD units, and to releases of hazardous substances which threaten human health or the environment. Additional information about the applicability of this document may also be found in the Hanford Facility RCRA Permit Handbook (DOE/RL-96-10). This plan includes descriptions of responses to a nonradiological hazardous substance spill or release at Hanford Facility locations not covered by TSD unit-specific contingency plans or building emergency plans. The term hazardous substances is defined in WAC 173-303-040 as: ``any liquid, solid, gas, or sludge, including any material, substance, product, commodity, or waste, regardless of quantity, that exhibits any of the physical, chemical or biological properties described in WAC 173-303-090 or 173-303-100.`` Whenever the term hazardous substances is used in this document, it will be used in the context of this definition. This plan includes descriptions of responses for spills or releases of hazardous substances occurring at areas between TSD units that may, or may not, threaten human health or the environment.

Sutton, L.N.

1996-07-01T23:59:59.000Z

8

Damaged Spent Nuclear Fuel at U.S. DOE Facilities Experience and Lessons Learned  

SciTech Connect (OSTI)

From a handling perspective, any spent nuclear fuel (SNF) that has lost its original technical and functional design capabilities with regard to handling and confinement can be considered as damaged. Some SNF was damaged as a result of experimental activities and destructive examinations; incidents during packaging, handling, and transportation; or degradation that has occurred during storage. Some SNF was mechanically destroyed to protect proprietary SNF designs. Examples of damage to the SNF include failed cladding, failed fuel meat, sectioned test specimens, partially reprocessed SNFs, over-heated elements, dismantled assemblies, and assemblies with lifting fixtures removed. In spite of the challenges involved with handling and storage of damaged SNF, the SNF has been safely handled and stored for many years at DOE storage facilities. This report summarizes a variety of challenges encountered at DOE facilities during interim storage and handling operations along with strategies and solutions that are planned or were implemented to ameliorate those challenges. A discussion of proposed paths forward for moving damaged and nondamaged SNF from interim storage to final disposition in the geologic repository is also presented.

Brett W. Carlsen; Eric Woolstenhulme; Roger McCormack

2005-11-01T23:59:59.000Z

9

Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems  

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.

Stephen M. Bruemmer; Peter L. Andersen; Gary Was

2002-12-27T23:59:59.000Z

10

Nuclear Instruments and Methods in Physics Research A 476 (2002) 565568 Bistable damage in neutron-irradiated silicon diodes  

E-Print Network [OSTI]

Nuclear Instruments and Methods in Physics Research A 476 (2002) 565­568 Bistable damage in neutronE15 kO cm) diodes was irradiated at room temperature with neutrons from a nuclear reactor to fluences about neutron spectrum, dosimetry and irradiation facility can be found elsewhere [9]. After

Zavrtanik, Marko

11

Experience With Damaged Spent Nuclear Fuel at U.S. DOE Facilities  

SciTech Connect (OSTI)

This report summarizes some of the challenges encountered and solutions implemented to ensure safe storage and handling of damaged spent nuclear fuels (SNF). It includes a brief summary of some SNF storage environments and resulting SNF degradation, experience with handling and repackaging significantly degraded SNFs, and the associated lessons learned. This work provides useful insight and resolutions to many engineering challenges facing SNF handling and storage facilities. The context of this report is taken from a report produced at Idaho National Laboratory and further detailed information, such as equipment design and usage, can be found in the appendices to that report. (authors)

Carlsen, Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, P.O. Box 1625 Idaho Falls, ID 83415 (United States); McCormack, Roger L. [Fluor Hanford Site, Richland, Wash. (United States); Sindelar, Robert; Spieker, Timothy [Savannah River National Laboratory, Savannah River Site Aiken, SC 29808 (United States)

2006-07-01T23:59:59.000Z

12

Fundamental Processes of Coupled Radiation Damage and Mechanical Behavior in Nuclear Fuel Materials for High Temperature Reactors  

SciTech Connect (OSTI)

The objective of this work has been to elucidate the relationship among microstructure, radiation damage and mechanical properties for nuclear fuel materials. As representative nuclear materials, we have taken an hcp metal (Mg as a generic metal, and Ti alloys for fast reactors) and UO2 (representing fuel). The degradation of the thermo-mechanical behavior of nuclear fuels under irradiation, both the fissionable material itself and its cladding, is a longstanding issue of critical importance to the nuclear industry. There are experimental indications that nanocrystalline metals and ceramics may be more resistant to radiation damage than their coarse-grained counterparts. The objective of this project look at the effect of microstructure on radiation damage and mechanical behavior in these materials. The approach to be taken was state-of-the-art, large-scale atomic-level simulation. This systematic simulation program of the effects of irradiation on the structure and mechanical properties of polycrystalline Ti and UO2 identified radiation damage mechanisms. Moreover, it will provided important insights into behavior that can be expected in nanocrystalline microstructures and, by extension, nanocomposites. The fundamental insights from this work can be expected to help in the design microstructures that are less susceptible to radiation damage and thermomechanical degradation.

Simon Phillpot; James Tulenko

2011-09-08T23:59:59.000Z

13

Radiation Damage in Nuclear Fuel for Advanced Burner Reactors: Modeling and Experimental Validation  

SciTech Connect (OSTI)

The consortium has completed its existence and we are here highlighting work and accomplishments. As outlined in the proposal, the objective of the work was to advance the theoretical understanding of advanced nuclear fuel materials (oxides) toward a comprehensive modeling strategy that incorporates the different relevant scales involved in radiation damage in oxide fuels. Approaching this we set out to investigate and develop a set of directions: 1) Fission fragment and ion trajectory studies through advanced molecular dynamics methods that allow for statistical multi-scale simulations. This work also includes an investigation of appropriate interatomic force fields useful for the energetic multi-scale phenomena of high energy collisions; 2) Studies of defect and gas bubble formation through electronic structure and Monte Carlo simulations; and 3) an experimental component for the characterization of materials such that comparisons can be obtained between theory and experiment.

Jensen, Niels Gronbech; Asta, Mark; Ozolins, Nigel Browning'Vidvuds; de Walle, Axel van; Wolverton, Christopher

2011-12-29T23:59:59.000Z

14

Safety apparatus for nuclear reactor to prevent structural damage from overheating by core debris  

DOE Patents [OSTI]

The invention teaches safety apparatus that can be included in a nuclear reactor, either when newly fabricated or as a retrofit add-on, that will minimize proliferation of structural damage to the reactor in the event the reactor is experiencing an overheating malfunction whereby radioactive nuclear debris might break away from and be discharged from the reactor core. The invention provides a porous bed or sublayer on the lower surface of the reactor containment vessel so that the debris falls on and piles up on the bed. Vapor release elements upstand from the bed in some laterally spaced array. Thus should the high heat flux of the debris interior vaporize the coolant at that location, the vaporized coolant can be vented downwardly to and laterally through the bed to the vapor release elements and in turn via the release elements upwardly through the debris. This minimizes the pressure buildup in the debris and allows for continuing infiltration of the liquid coolant into the debris interior.

Gabor, John D. (Western Springs, IL); Cassulo, John C. (Stickney, IL); Pedersen, Dean R. (Naperville, IL); Baker, Jr., Louis (Downers Grove, IL)

1986-01-01T23:59:59.000Z

15

Parallel contingency statistics with Titan.  

SciTech Connect (OSTI)

This report summarizes existing statistical engines in VTK/Titan and presents the recently parallelized contingency statistics engine. It is a sequel to [PT08] and [BPRT09] which studied the parallel descriptive, correlative, multi-correlative, and principal component analysis engines. The ease of use of this new parallel engines is illustrated by the means of C++ code snippets. Furthermore, this report justifies the design of these engines with parallel scalability in mind; however, the very nature of contingency tables prevent this new engine from exhibiting optimal parallel speed-up as the aforementioned engines do. This report therefore discusses the design trade-offs we made and study performance with up to 200 processors.

Thompson, David C.; Pebay, Philippe Pierre

2009-09-01T23:59:59.000Z

16

Reduced Rank Models for Contingency Tables  

E-Print Network [OSTI]

Solution problem 73-14, Rank factorization of nonnegativein Great Britain Reduced rank models for contingency tablesclass analysis; Reduced rank models. 1. INTRODUCTION In

Jan de Leeuw; Peter van der Heijden

2011-01-01T23:59:59.000Z

17

Contingency - DOE Directives, Delegations, and Requirements  

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

and improve the understanding of contingency in the project management process. g4301-1chp11.pdf -- PDF Document, 53 KB Writer: John Makepeace Subjects: Administration Management...

18

Contingency in the Direction and Mechanics of Soil Organic Matter...  

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

Contingency in the Direction and Mechanics of Soil Organic Matter Responses to Increased Rainfall. Contingency in the Direction and Mechanics of Soil Organic Matter Responses to...

19

Corporate Governance, State-Contingent Control Rights, and Financial Distress  

E-Print Network [OSTI]

20-6:00 pm, Boalt 13 Corporate Governance, State-ContingentRobert K. Rasmussen Corporate Governance, State-ContingentTraditional accounts of corporate governance focus on how

Rasmussen, Robert K.

2004-01-01T23:59:59.000Z

20

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

Note: This page contains sample records for the topic "nuclear damage contingent" 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

REVISED HYDROGEN SULFIDE DRILLING CONTINGENCY PLAN  

E-Print Network [OSTI]

REVISED HYDROGEN SULFIDE DRILLING CONTINGENCY PLAN OCEAN DRILLING PROGRAM TEXAS A&M UNIVERSITY Technical Note 19 Gien N. Foss Ocean Drilling Program Texas A&M University 1000 Discovery Drive College Station, TX 77845-9547 Bradley D. Julson Ocean Drilling Program Texas A&M University 1000 Discovery Drive

22

HYDROGEN SULFIDE -HIGH TEMPERATURE DRILLING CONTINGENCY PLAN  

E-Print Network [OSTI]

HYDROGEN SULFIDE - HIGH TEMPERATURE DRILLING CONTINGENCY PLAN OCEAN DRILLING PROGRAM TEXAS A&M UNIVERSITY Technical Note 16 Steven P. Howard Ocean Drilling Program Texas A&M University 1000 Discovery Drive College Station, TX 77845-9547 Daniel H. Reudelhuber Ocean Drilling Program Texas A&M University

23

Visual Analytics for Power Grid Contingency Analysis  

SciTech Connect (OSTI)

Contingency analysis is the process of employing different measures to model scenarios, analyze them, and then derive the best response to remove the threats. This application paper focuses on a class of contingency analysis problems found in the power grid management system. A power grid is a geographically distributed interconnected transmission network that transmits and delivers electricity from generators to end users. The power grid contingency analysis problem is increasingly important because of both the growing size of the underlying raw data that need to be analyzed and the urgency to deliver working solutions in an aggressive timeframe. Failure to do so may bring significant financial, economic, and security impacts to all parties involved and the society at large. The paper presents a scalable visual analytics pipeline that transforms about 100 million contingency scenarios to a manageable size and form for grid operators to examine different scenarios and come up with preventive or mitigation strategies to address the problems in a predictive and timely manner. Great attention is given to the computational scalability, information scalability, visual scalability, and display scalability issues surrounding the data analytics pipeline. Most of the large-scale computation requirements of our work are conducted on a Cray XMT multi-threaded parallel computer. The paper demonstrates a number of examples using western North American power grid models and data.

Wong, Pak C.; Huang, Zhenyu; Chen, Yousu; Mackey, Patrick S.; Jin, Shuangshuang

2014-01-20T23:59:59.000Z

24

Monitoring Thermal Fatigue Damage In Nuclear Power Plant Materials Using Acoustic Emission  

SciTech Connect (OSTI)

Proactive aging management of nuclear power plant passive components requires technologies to enable monitoring and accurate quantification of material condition at early stages of degradation (i.e., pre-macrocrack). Acoustic emission (AE) is well-suited to continuous monitoring of component degradation and is proposed as a method to monitor degradation during accelerated thermal fatigue tests. A key consideration is the ability to separate degradation responses from external sources such as water spray induced during thermal fatigue testing. Water spray provides a significant background of acoustic signals, which can overwhelm AE signals caused by degradation. Analysis of AE signal frequency and energy is proposed in this work as a means for separating degradation signals from background sources. Encouraging results were obtained by applying both frequency and energy filters to preliminary data. The analysis of signals filtered using frequency and energy provides signatures exhibiting several characteristics that are consistent with degradation accumulation in materials. Future work is planned to enable verification of the efficacy of AE for thermal fatigue crack initiation detection. While the emphasis has been placed on the use of AE for crack initiation detection during accelerated aging tests, this work also has implications with respect to the use of AE as a primary tool for early degradation monitoring in nuclear power plant materials. The development of NDE tools for characterization of aging in materials can also benefit from the use of a technology such as AE which can continuously monitor and detect crack initiation during accelerated aging tests.

Meyer, Ryan M.; Ramuhalli, Pradeep; Watson, Bruce E.; Pitman, Stan G.; Roosendaal, Timothy J.; Bond, Leonard J.

2012-04-26T23:59:59.000Z

25

[alpha]-Decay damage effects in curium-doped titanate ceramic containing sodium-free high-level nuclear waste  

SciTech Connect (OSTI)

A polyphase titanate ceramic incorporating sodium-free simulated high-level nuclear waste was doped with 0.91 wt% of [sup 224]Cm to accelerate the effects of long-term self-irradiation arising from [alpha] decays. The ceramic included three main constituent minerals: hollandite, perovskite, and zirconolite, with some minor phases. Although hollandite showed the broadening of its X-ray diffraction lines and small lattice parameter changes during damage in growth, the unit cell was substantially unaltered. Perovskite and zirconolite, which are the primary hosts of curium, showed 2.7% and 2.6% expansions, respectively, of their unit cell volumes after a dose of 12 [times] 10[sup 17] [alpha] decays[center dot]g[sup [minus]1]. Volume swelling due to damage in growth caused an exponential (almost linear) decrease in density, which reached 1.7% after a dose of 12.4 [times] 10[sup 17] [alpha] decays[center dot]g[sup [minus]1]. Leach tests on samples that had incurred doses of 2.0 [times] 10[sup 17] and 4.5 [times] 10[sup 17] [alpha] decays[center dot]g[sup [minus]1] showed that the rates of dissolution of cesium and barium were similar to analogous leach rates from the equivalent cold ceramic, while strontium and calcium leach rates were 2--15 times higher. Although the cerium, molybdenum, strontium, and calcium leach rates in the present material were similar to those in the curium-doped sodium-bearing titanate ceramic reported previously, the cesium leach rate was 3--8 times lower.

Mitamura, Hisayoshi; Matsumoto, Seiichiro; Tsuboi, Takashi; Hashimoto, Masaaki; Togashi, Yoshihiro; Kanazawa, Hiroyuki (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Stewart, M.W.A.; Vance, E.R.; Hart, K.P.; Ball, C.J. (Australian Nuclear Science and Technology Organization, Lucas Heights, New South Wales (Australia). Lucas Heights Research Labs.); White, T.J.

1994-09-01T23:59:59.000Z

26

2256 IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 47, NO. 6, DECEMBER 2000 Characterization of X-Ray Radiation Damage  

E-Print Network [OSTI]

optical methods. I. INTRODUCTION PRESENTLY, characterization of traps due to radiation damage in Si-Ray Radiation Damage in Si/SiO2 Structures Using Second-Harmonic Generation Z. Marka, S. K. Singh, W. Wang, S. C-harmonic generation (SHG) measurements for the characterization of X-ray radiation damage in Si/SiO2 structures

Tolk, Norman H.

27

area contingency plan: Topics by E-print Network  

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

STOCHASTIC PROGRAMMING APPROACH TO QUANTIFYING EFFECTS OF CONTINGENCIES ON LOCATIONAL MARGINAL PRICES Engineering Websites Summary: of planning for contin- gencies typically...

28

Future contingencies and photovoltaic system worth  

SciTech Connect (OSTI)

The value of dispersed photovoltaic systems connected to the utility grid has been calculated using the General Electric Optimized Generation Planning program. The 1986 to 2001 time period was used for this study. Photovoltaic systems were dynamically integrated, up to 5% total capacity, into 9 NERC based regions under a range of future fuel and economic contingencies. Value was determined by the change in revenue requirements due to the photovoltaic additions. Displacement of high cost fuel was paramount to value, while capacity displacement was highly variable and dependent upon regional fuel mix.

Jones, G. J.; Thomas, M. G.; Bonk, G. J.

1982-01-01T23:59:59.000Z

29

Resource Contingency Program : Draft Environmental Impact Statement.  

SciTech Connect (OSTI)

In 1990, the Bonneville Power Administration (BPA) embarked upon the Resource Contingency Program (RCP) to fulfill its statutory responsibilities to supply electrical power to its utility, industrial and other customers in the Pacific Northwest. Instead of buying or building generating plants now, BPA has purchased options to acquire power later if needed. Three option development agreements were signed in September 1993 with three proposed natural gas-fired, combined cycle combustion turbine CT projects near Chehalis and Satsop Washington and near Hermiston, Oregon. This environmental impact statement addresses the environmental consequences of purchasing power from these options. This environmental impact statement addresses the environmental consequences of purchasing power from these options.

United States. Bonneville Power Administration.

1995-02-01T23:59:59.000Z

30

Environment-contingent sexual selection in a colour polymorphic fish  

E-Print Network [OSTI]

Environment-contingent sexual selection in a colour polymorphic fish Suzanne M. Gray1,*, Lawrence M environment can influence sexual selection on colourful male secondary traits such that selective advantage is environment contingent. Using a small fish endemic to Sulawesi, Indonesia (Telmatherina sarasinorum) that has

Dill, Lawrence M.

31

Towards Efficient N ? x Contingency Selection Using Group Betweenness Centrality  

SciTech Connect (OSTI)

The goal of N ?x contingency selection is to pick a subset of critical cases to assess their potential for causing a severe crippling of an electric power grid. Even for a moderate-sized system there can be an overwhelming number of contingency cases that need to be studied. The number grows exponentially with x. This combinatorial explosion renders any exhaustive search strategy computationally infeasible, even for small to medium sized systems. We propose a novel method for N ? x selection for x >1 using group betweenness centrality and show that the amount of computation can be decoupled from the problem size, thus making the contingency analysis for large systems with x > 1 computationally feasible. Consequently, it may be that N ? x (for x > 1) contingency selection can be effectively deployed despite the combinatorial explosion of the number of possible N ? x contingencies. Our strategy replaces computation with storage of intermediate results and therefore relies on high performance computing resources.

Halappanavar, Mahantesh; Chen, Yousu; Adolf, Robert D.; Haglin, David J.; Huang, Zhenyu; Rice, Mark J.

2012-09-11T23:59:59.000Z

32

Investigation of a Novel NDE Method for Monitoring Thermomechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems  

SciTech Connect (OSTI)

The main goal of the proposed project is the development of validated nondestructive evaluation (NDE) techniques for in situ monitoring of ferritic-martensitic steels like Grade 91 9Cr-1Mo, which are candidate materials for Generation IV nuclear energy structural components operating at temperatures up to ~650{degree}C and for steam-generator tubing for sodium-cooled fast reactors. Full assessment of thermomechanical damage requires a clear separation between thermally activated microstructural evolution and creep damage caused by simultaneous mechanical stress. Creep damage can be classified as "negligible" creep without significant plastic strain and "ordinary" creep of the primary, secondary, and tertiary kind that is accompanied by significant plastic deformation and/or cavity nucleation and growth. Under negligible creep conditions of interest in this project, minimal or no plastic strain occurs, and the accumulation of creep damage does not significantly reduce the fatigue life of a structural component so that low-temperature design rules, such as the ASME Section III, Subsection NB, can be applied with confidence. The proposed research project will utilize a multifaceted approach in which the feasibility of electrical conductivity and thermo-electric monitoring methods is researched and coupled with detailed post-thermal/creep exposure characterization of microstructural changes and damage processes using state-of-the-art electron microscopy techniques, with the aim of establishing the most effective nondestructive materials evaluation technique for particular degradation modes in high-temperature alloys that are candidates for use in the Next Generation Nuclear Plant (NGNP) as well as providing the necessary mechanism-based underpinnings for relating the two. Only techniques suitable for practical application in situ will be considered. As the project evolves and results accumulate, we will also study the use of this technique for monitoring other GEN IV materials. Through the results obtained from this integrated materials behavior and NDE study, new insight will be gained into the best nondestructive creep and microstructure monitoring methods for the particular mechanisms identified in these materials. The proposed project includes collaboration with a national laboratory partner and the results will also serve as a foundation to guide the efforts of scientists in the DOE laboratory, university, and industrial communities concerned with the technological challenges of monitoring creep and microstructural evolution in materials planned to be used in Generation IV Nuclear Energy Systems.

Nagy, Peter

2013-09-30T23:59:59.000Z

33

Contingent Self-esteem in Chinese Early and Late Adolescents  

E-Print Network [OSTI]

of the requirements for the degree of Master of Science in Education. Chairperson: Dr. Meagan Patterson Dr. David Hansen Dr. Robert Harrington Date Defended: 12/07/2011 ii The Thesis Committee for Li Chen..., 1997). Park and Maner (2009) noted that whereas low self-esteem (LSE) appearance-contingent individuals want to avoid social contact with others, high self-esteem (HSE) appearance- contingent individuals respond to appearance threats by desiring...

Chen, Li

2011-12-31T23:59:59.000Z

34

Contingency Analysis of Cascading Line Outage Events  

SciTech Connect (OSTI)

As the US power systems continue to increase in size and complexity, including the growth of smart grids, larger blackouts due to cascading outages become more likely. Grid congestion is often associated with a cascading collapse leading to a major blackout. Such a collapse is characterized by a self-sustaining sequence of line outages followed by a topology breakup of the network. This paper addresses the implementation and testing of a process for N-k contingency analysis and sequential cascading outage simulation in order to identify potential cascading modes. A modeling approach described in this paper offers a unique capability to identify initiating events that may lead to cascading outages. It predicts the development of cascading events by identifying and visualizing potential cascading tiers. The proposed approach was implemented using a 328-bus simplified SERC power system network. The results of the study indicate that initiating events and possible cascading chains may be identified, ranked and visualized. This approach may be used to improve the reliability of a transmission grid and reduce its vulnerability to cascading outages.

Thomas L Baldwin; Magdy S Tawfik; Miles McQueen

2011-03-01T23:59:59.000Z

35

Analysis of a Nuclear Accident: Fission and Activation Product Releases from the Fukushima Daiichi Nuclear Facility as Remote Indicators of Source Identification, Extent of Release, and State of Damaged Spent Nuclear Fuel  

SciTech Connect (OSTI)

Measurements of several radionuclides within environmental samples taken from the Fukushima Daiichi nuclear facility and reported on the Tokyo Electric Power Company website following the recent tsunami-initiated catastrophe were evaluated for the purpose of identifying the source term, reconstructing the release mechanisms, and estimating the extent of the release. 136Cs/137Cs and 134Cs/137Cs ratios identified Units 1-3 as the major source of radioactive contamination to the surface soil close to the facility. A trend was observed between the fraction of the total core inventory released for a number of fission product isotopes and their corresponding Gibbs Free Energy of formation for the primary oxide form of the isotope, suggesting that release was dictated primarily by chemical volatility driven by temperature and reduction potential within the primary containment vessels of the vented reactors. The absence of any major fractionation beyond volatilization suggested all coolant had evaporated by the time of venting. High estimates for the fraction of the total inventory released of more volatile species (Te, Cs, I) indicated the damage to fuel bundles was likely extensive, minimizing any potential containment due to physical migration of these species through the fuel matrix and across the cladding wall. 238Pu/239,240Pu ratios close-in and at 30 km from the facility indicated that the damaged reactors were the major contributor of Pu to surface soil at the source but that this contribution likely decreased rapidly with distance from the facility. The fraction of the total Pu inventory released to the environment from venting units 1 and 3 was estimated to be ~0.003% based upon Pu/Cs isotope ratios relative to the within-reactor modeled inventory prior to venting and was consistent with an independent model evaluation that considered chemical volatility based upon measured fission product release trends. Significant volatile radionuclides within the spent fuel at the time of venting but not as yet observed and reported within environmental samples are suggested as potential analytes of concern for future environmental surveys around the site.

Schwantes, Jon M.; Orton, Christopher R.; Clark, Richard A.

2012-09-10T23:59:59.000Z

36

Damages induced by heavy ions in titanium silicon carbide: effects of nuclear and electronic interactions at room temperature  

E-Print Network [OSTI]

, of general formula Mn+1AXn where n = {1,2,3}, M is an early transition metal, A is an A-group (mostly IIIADamages induced by heavy ions in titanium silicon carbide: effects of nuclear and electronic Thanks to their refractoriness, carbides are sensed as fuel coating for the IVth generation of reactors

Paris-Sud XI, Université de

37

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

38

Contingency contractor optimization. phase 3, model description and formulation.  

SciTech Connect (OSTI)

The goal of Phase 3 the OSD ATL Contingency Contractor Optimization (CCO) project is to create an engineering prototype of a tool for the contingency contractor element of total force planning during the Support for Strategic Analysis (SSA). An optimization model was developed to determine the optimal mix of military, Department of Defense (DoD) civilians, and contractors that accomplishes a set of user defined mission requirements at the lowest possible cost while honoring resource limitations and manpower use rules. An additional feature allows the model to understand the variability of the Total Force Mix when there is uncertainty in mission requirements.

Gearhart, Jared Lee; Adair, Kristin Lynn; Jones, Katherine A.; Bandlow, Alisa; Detry, Richard Joseph; Durfee, Justin D.; Jones, Dean A.; Martin, Nathaniel; Nanco, Alan Stewart; Nozick, Linda Karen

2013-06-01T23:59:59.000Z

39

Contingency contractor optimization. Phase 3, model description and formulation.  

SciTech Connect (OSTI)

The goal of Phase 3 the OSD ATL Contingency Contractor Optimization (CCO) project is to create an engineering prototype of a tool for the contingency contractor element of total force planning during the Support for Strategic Analysis (SSA). An optimization model was developed to determine the optimal mix of military, Department of Defense (DoD) civilians, and contractors that accomplishes a set of user defined mission requirements at the lowest possible cost while honoring resource limitations and manpower use rules. An additional feature allows the model to understand the variability of the Total Force Mix when there is uncertainty in mission requirements.

Gearhart, Jared Lee; Adair, Kristin Lynn; Jones, Katherine A.; Bandlow, Alisa; Durfee, Justin D.; Jones, Dean A.; Martin, Nathaniel; Detry, Richard Joseph; Nanco, Alan Stewart; Nozick, Linda Karen [Cornell University

2013-10-01T23:59:59.000Z

40

Guide for Establishment of a Contingency Protective Force  

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

The Guide was developed to provide assistance in ensuring continued safe and secure operation of DOE sites and facilities, protection of Departmental employees, and the public in the event of emergency situations involving the establishment and deployment of a contingency protective force and the conduct of sustained operations. Canceled by DOE N 251.80.

2003-03-27T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Self-irradiation damage of a curium-doped titanate ceramic containing sodium-rich high level nuclear waste  

SciTech Connect (OSTI)

This paper reports on the polyphase titanate ceramic containing sodium-rich simulated high-level nuclear waste doped with 0.69 wt% of {sup 244}Cm to accelerate long-term self-irradiation due to {alpha} decays. {alpha} autoradiography showed that {alpha} emissions were almost uniformly distributed throughout the curium-doped samples on a {gt} 20{mu}m scale although micropore surfaces and titanium oxide agglomerates were free of {alpha} emitting nuclides. The phase assemblage of the curium-doped titanate ceramic included freudenbergite and loveringite in addition to the more abundant oxide phases: hollandite, perovskite, and zirconolite. Accumulation of {alpha} decays was accompanied by a gradual decrease in density. The increment of density was {minus}1% after an equivalent age of 5000 yr. Leach tests showed a slight rend toward higher total release of curium with equivalent age. The release of soluble nonradioactive elements (e.g., Na, Cs, Sr, and Ca) in the oldest specimens (equivalent age, 2000 yr) varied from specimen to specimen but, on average, were higher than specimens that had suffered a lower radiation dose.

Miyazaki, T. (Second Dept. of Nuclear Business, Ibaraki Center, Chiyoda Maintenance Ltd., Asahi, Kashima, Ibaraki 314-14 (JP)); White, T.J. (Electron Microscope Centre, Univ. of Queensland, St. Lucia, Brisbane 4067 (AU)); Mitamura, H.; Matsumoto, S.; Nukaga, K.; Togashi, Y.; Sagawa, T.; Tashiro, S. (Dept. of Environmental Safety Research, Japan Atomic Energy Research Inst., Tokai, Naka, Ibaraki 319-11 (JP)); Levins, D.M. (Environmental Science Program, Australian Nuclear Science and Technology Organisation, Lucas Heights Research Lab., Lucas Heights, New South Wales (AU)); Kikuchi, A. (Dept. of Reactor Fuel Examination, Japan Atomic Energy Research Inst., Tokai, Naka, Ibaraki 319-11 (JP))

1990-11-01T23:59:59.000Z

42

Analysis of a Nuclear Accident: Fission and Activation Product Releases from the Fukushima Daiichi Nuclear Facility as Remote Indicators of Source Identification, Extent of Release, and State of Damaged Spent Nuclear Fuel  

SciTech Connect (OSTI)

Evidence of the release Pu from the Fukushima Daiichi nuclear power station to the local environment and surrounding communities and estimates on fraction of total fuel inventory released

Schwantes, Jon M.; Orton, Christopher R.; Clark, Richard A.

2011-12-05T23:59:59.000Z

43

Improved estimates of separation distances to prevent unacceptable damage to nuclear power plant structures from hydrogen detonation for gaseous hydrogen storage. Technical report  

SciTech Connect (OSTI)

This report provides new estimates of separation distances for nuclear power plant gaseous hydrogen storage facilities. Unacceptable damage to plant structures from hydrogen detonations will be prevented by having hydrogen storage facilities meet separation distance criteria recommended in this report. The revised standoff distances are based on improved calculations on hydrogen gas cloud detonations and structural analysis of reinforced concrete structures. Also, the results presented in this study do not depend upon equivalencing a hydrogen detonation to an equivalent TNT detonation. The static and stagnation pressures, wave velocity, and the shock wave impulse delivered to wall surfaces were computed for several different size hydrogen explosions. Separation distance equations were developed and were used to compute the minimum separation distance for six different wall cases and for seven detonating volumes (from 1.59 to 79.67 lbm of hydrogen). These improved calculation results were compared to previous calculations. The ratio between the separation distance predicted in this report versus that predicted for hydrogen detonation in previous calculations varies from 0 to approximately 4. Thus, the separation distances results from the previous calculations can be either overconservative or unconservative depending upon the set of hydrogen detonation parameters that are used. Consequently, it is concluded that the hydrogen-to-TNT detonation equivalency utilized in previous calculations should no longer be used.

Not Available

1994-05-01T23:59:59.000Z

44

A public health response to the methamphetamine epidemic: the implementation of contingency management to treat methamphetamine dependence  

E-Print Network [OSTI]

contingency management to treat methamphetamine dependencea methamphetamine treat- ment program for methamphetamine-

2006-01-01T23:59:59.000Z

45

Selected components of an oil spill contingency plan model  

E-Print Network [OSTI]

of Responsibility Section 311 of the Clean Water Act or FWPCA gave the President the responsibility for issuing the National Oil and Hazardous Substances Pollution Contingency Plan (The Plan). In turn, this task was delegated to the Council on Environmental... administratively oriented, i. e. management personnel are assigned spill-related tasks but the tools needed to carry out the response are not detailed in the plan. Other plans focus primarily an the response phase, neglecting pre-spill deci- sions. Oil spill...

Starnater, Carol Elizabeth

1985-01-01T23:59:59.000Z

46

Graphical Contingency Analysis for the Nation's Electric Grid  

ScienceCinema (OSTI)

PNNL has developed a new tool to manage the electric grid more effectively, helping prevent blackouts and brownouts--and possibly avoiding millions of dollars in fines for system violations. The Graphical Contingency Analysis tool monitors grid performance, shows prioritized lists of problems, provides visualizations of potential consequences, and helps operators identify the most effective courses of action. This technology yields faster, better decisions and a more stable and reliable power grid.

Zhenyu (Henry) Huang

2012-12-31T23:59:59.000Z

47

Graphical Contingency Analysis for the Nation's Electric Grid  

SciTech Connect (OSTI)

PNNL has developed a new tool to manage the electric grid more effectively, helping prevent blackouts and brownouts--and possibly avoiding millions of dollars in fines for system violations. The Graphical Contingency Analysis tool monitors grid performance, shows prioritized lists of problems, provides visualizations of potential consequences, and helps operators identify the most effective courses of action. This technology yields faster, better decisions and a more stable and reliable power grid.

Zhenyu (Henry) Huang [Henry

2011-04-01T23:59:59.000Z

48

EMEF DMC EFS-95-004 GDP TURNOVER CONTINGENCY PLANNING POWER CONTRACTIN...  

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

111111111111111111111111 EMEF DMC EFS-95-004 GDP TURNOVER CONTINGENCY PLANNING POWER CONTRACTING OPTIONS This document is approved f()i puolic release per review by: er "-...

49

Reducing Contingency through Sampling at the Luckey FUSRAP Site - 13186  

SciTech Connect (OSTI)

Typically, the greatest risk in developing accurate cost estimates for the remediation of hazardous, toxic, and radioactive waste sites is the uncertainty in the estimated volume of contaminated media requiring remediation. Efforts to address this risk in the remediation cost estimate can result in large cost contingencies that are often considered unacceptable when budgeting for site cleanups. Such was the case for the Luckey Formerly Utilized Sites Remedial Action Program (FUSRAP) site near Luckey, Ohio, which had significant uncertainty surrounding the estimated volume of site soils contaminated with radium, uranium, thorium, beryllium, and lead. Funding provided by the American Recovery and Reinvestment Act (ARRA) allowed the U.S. Army Corps of Engineers (USACE) to conduct additional environmental sampling and analysis at the Luckey Site between November 2009 and April 2010, with the objective to further delineate the horizontal and vertical extent of contaminated soils in order to reduce the uncertainty in the soil volume estimate. Investigative work included radiological, geophysical, and topographic field surveys, subsurface borings, and soil sampling. Results from the investigative sampling were used in conjunction with Argonne National Laboratory's Bayesian Approaches for Adaptive Spatial Sampling (BAASS) software to update the contaminated soil volume estimate for the site. This updated volume estimate was then used to update the project cost-to-complete estimate using the USACE Cost and Schedule Risk Analysis process, which develops cost contingencies based on project risks. An investment of $1.1 M of ARRA funds for additional investigative work resulted in a reduction of 135,000 in-situ cubic meters (177,000 in-situ cubic yards) in the estimated base volume estimate. This refinement of the estimated soil volume resulted in a $64.3 M reduction in the estimated project cost-to-complete, through a reduction in the uncertainty in the contaminated soil volume estimate and the associated contingency costs. (authors)

Frothingham, David; Barker, Michelle; Buechi, Steve [U.S. Army Corps of Engineers Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States)] [U.S. Army Corps of Engineers Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States); Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)] [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

2013-07-01T23:59:59.000Z

50

Treatment of anisotropic damage development within a scalar damage formulation  

SciTech Connect (OSTI)

This paper is concerned with describing a damage mechanics formulation which provides for non-isotropic effects using a scalar damage variable. An investigation has been in progress for establishing the constitutive behavior of rock salt at long times and low to moderate confining pressures in relation to the possible use of excavated rooms in rock salt formations as repositories for nuclear waste. An important consideration is the effect of damage manifested principally by the formation of shear induced wing cracks which have a stress dependent orientation. The analytical formulation utilizes a scalar damage parameter, but is capable of indicating the non- isotropic dependence of inelastic straining on the stress state and the confining pressure. Also, the equations indicate the possibility of volumetric expansions leading to the onset of tertiary creep and eventually rupture if the damage variable reaches a critical value.

Chan, K.S. [Southwest Research Inst., San Antonio, TX (United States); Bodner, S.R. [Southwest Research Inst., San Antonio, TX (United States)][Technion-Israel Inst. of Tech., Haifa (Israel). Dept. of Mechanical Engineering; Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States)

1996-11-01T23:59:59.000Z

51

To appear in the ACM APGV 2007 symposium proceedings Hybrid Image-/Model-Based Gaze-Contingent Rendering  

E-Print Network [OSTI]

-Contingent Rendering Hunter Murphy Andrew T. Duchowski School of Computing, Clemson University Figure 1: The original is displayed. Abstract A nonisotropic hybrid image-/model-based gaze-contingent render- ing technique utilizing: gpu, perceptual rendering, gaze-contingent rendering 1 Introduction The contributions of this paper

Duchowski, Andrew T.

52

Public comment re Convention on Supplementary Compensation on...  

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

the Nuclear Energy Institute (NEI) on Convention on Supplementary Compensation on Nuclear Damage Contingent Cost Allocation; Section 934 of the Energy Independence and Security Act...

53

EMEF DMC EFS-95-003 GDP TuRNOVER CONTINGENCY PLANNING POWER CONTRACT...  

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

5 11111111 EMEF DMC EFS-95-003 GDP TuRNOVER CONTINGENCY PLANNING POWER CONTRACT TERMINATION PROVISIONS AND CONSEQUENCES I JULY 1995 B. J. Kirby Power Systems Technology Program...

54

High-Level Architectures for Contingency Planning in Air Traffic Management Chris. W. Johnson, DPhil;  

E-Print Network [OSTI]

was conducted to identify current and best practice in contingency planning. This paper provides a brief and implement drills/tabletop exercises to assess adequacy of plans for different scenarios. Fail to safe Phase

Johnson, Chris

55

A reactive contingency analysis algorithm using MW and MVAR distribution factors  

SciTech Connect (OSTI)

This paper describes an algorithm that can be used in analyzing reactive power flow contingencies. This approach uses MW distribution factors (DFAX) in conjunction with newly developed VAR distribution factors (RDFAX) to solve for the post-contingency bus voltage magnitude changes of an interconnecter EHV system. A prototype version of the algorithm described in this paper is presently being tested at the Pennsylvania-New Jersey-Maryland (PJM) interconnection office.

Taylor, D.G.; Maahs, L.J. (Pennsylvania-New Jersey-Maryland Interconnection, Norristown, PA (US))

1991-02-01T23:59:59.000Z

56

Contingency Visualization for Real-Time Decision Support in Grid Operation  

SciTech Connect (OSTI)

Contingency analysis is a key function in control centers to assess the impact of various combinations of power system component failures based on state estimates. Today's practice analyzes only a limited set of contingency cases and lacks of capabilities in presenting the results in a way that is easy to be understood by grid operators in a short time frame of seconds to minutes. This limits the ability to operate the power grid for better reliability and efficiency. Faster analysis of more cases is required to safely and reliably operate today's power grids which have a less margin and more intermittent renewable energy sources. This paper explores the advancements in high performance computing and visual analytics for improving the computational speed and the information representation in contingency analysis. A framework of advanced contingency analysis is proposed. Case studies using the Western Electricity Coordinating Council (WECC) system are presented to demonstrate the feasibility of the proposed framework. Comparative assessment by real power grid operators has been performed as part of a WECC operator training class. The assessment results demonstrate the validity of the proposed contingency analysis and visualization approach.

Huang, Zhenyu; Chen, Yousu; Greitzer, Frank L.; Eubank, Robert

2011-10-17T23:59:59.000Z

57

Environmental Stigma Damages: Speculative Damages in Environmental Tort Cases  

E-Print Network [OSTI]

contami- nation causing environmental damage cannot be seen,Damages: Speculative Damages in Environmental Tort Cases E.in cases of environmental damage, primar- ily because it is

Johnson, E. Jean

1997-01-01T23:59:59.000Z

58

Expected Utility Theory as a Guide to Contingency (Allowance or Management Reserve) Allocation  

SciTech Connect (OSTI)

In this paper, I view a project from the perspective of utility theory. I suggest that, by determining an optimal percent contingency (relative to remaining work) and identifying and enforcing a required change in behavior, from one that is risk-seeking to one that is risk-averse, a project's contingency can be managed more effectively. I argue that early on in a project, risk-seeking behavior dominates. During this period, requests for contingency are less rigorously scrutinized. As the design evolves, more accurate information becomes available. Once the designs have been finalized, the project team must transition from a free-thinking, exploratory mode to an execution mode. If projects do not transition fast enough from a risk-seeking to a risk-averse organization, an inappropriate allocation of project contingency could occur (too much too early in the project). I show that the behavioral patterns used to characterize utility theory are those that exist in the project environment. I define a project's utility and thus, provide project managers with a metric against which all gambles (requests for contingency) can be evaluated. I discuss other research as it relates to utility and project management. From empirical data analysis, I demonstrate that there is a direct correlation between progress on a project's design activities and the rate at which project contingency is allocated and recommend a transition time frame during which the rate of allocation should decrease and the project should transition from risk-seeking to risk-averse. I show that these data are already available from a project's earned value management system and thus, inclusion of this information in the standard monthly reporting suite can enhance a project manager's decision making capability.

Thibadeau, Barbara M [ORNL] [ORNL

2006-01-01T23:59:59.000Z

59

Evaluation of Counter-Based Dynamic Load Balancing Schemes for Massive Contingency Analysis on Over 10,000 Cores  

SciTech Connect (OSTI)

Contingency analysis studies are necessary to assess the impact of possible power system component failures. The results of the contingency analysis are used to ensure the grid reliability, and in power market operation for the feasibility test of market solutions. Currently, these studies are performed in real time based on the current operating conditions of the grid with a set of pre-selected contingency list, which might result in overlooking some critical contingencies caused by variable system status. To have a complete picture of a power grid, more contingencies need to be studied to improve grid reliability. High-performance computing techniques hold the promise of being able to perform the analysis for more contingency cases within a much shorter time frame. This paper evaluates the performance of counter-based dynamic load balancing schemes for a massive contingency analysis program on 10,000+ cores. One million N-2 contingency analysis cases with a Western Electricity Coordinating Council power grid model have been used to demonstrate the performance. The speedup of 3964 with 4096 cores and 7877 with 10240 cores are obtained. This paper reports the performance of the load balancing scheme with a single counter and two counters, describes disk I/O issues, and discusses other potential techniques for further improving the performance.

Chen, Yousu; Huang, Zhenyu; Rice, Mark J.

2012-12-27T23:59:59.000Z

60

Cournot Equilibria in Two-Settlement Electricity Markets with System Contingencies  

E-Print Network [OSTI]

1 Cournot Equilibria in Two-Settlement Electricity Markets with System Contingencies Jian Yao}@ieor.berkeley.edu Abstract-- We study Nash equilibrium in two-settlement com- petitive electricity markets with horizontal in the markets. I. INTRODUCTION The last decade has witnessed a fundamental transformation of the electric power

Note: This page contains sample records for the topic "nuclear damage contingent" 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

A STOCHASTIC PROGRAMMING APPROACH TO QUANTIFYING EFFECTS OF CONTINGENCIES ON LOCATIONAL MARGINAL PRICES  

E-Print Network [OSTI]

on varia- tions of Locational Marginal Prices (LMPs) in restruc- tured power markets. The process: Locational marginal prices (LMPs), Un- certainty, Power system security, Optimization meth- ods, StochasticA STOCHASTIC PROGRAMMING APPROACH TO QUANTIFYING EFFECTS OF CONTINGENCIES ON LOCATIONAL MARGINAL

Stankoviæ, Aleksandar

62

Leibniz's Optics and Contingency in Nature Jeffrey K. McDonough  

E-Print Network [OSTI]

Leibniz's Optics and Contingency in Nature Jeffrey K. McDonough Department of Philosophy Harvard and opportunistically carries them over to the domain of optics gets things essentially the wrong way around has its most intelligible roots in his optical derivations, which appear to have paved the way ­ both

McDonough, Jeffrey

63

Damage susceptibility tables  

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

conditions, 3) that x-ray induced damage rates for a common material (relatively pure PVC in this example 7,8 ) can be used to normalize different sets of XPS damage...

64

E-Print Network 3.0 - ameliorate ischemic damage Sample Search...  

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

the nuclear enzyme poly... . (1996) Role of oxidants in ischemic brain damage. Stroke 27, ... Source: Cossart, Rosa - Institut de Neurobiologie de la Mditerrane, Inserm...

65

Guest Editorial: Laser Damage  

SciTech Connect (OSTI)

Laser damage of optical materials, first reported in 1964, continues to limit the output energy and power of pulsed and continuous-wave laser systems. In spite of some 48 years of research in this area, interest from the international laser community to laser damage issues remains at a very high level and does not show any sign of decreasing. Moreover, it grows with the development of novel laser systems, for example, ultrafast and short-wavelength lasers that involve new damage effects and specific mechanisms not studied before. This interest is evident from the high level of attendance and presentations at the annual SPIE Laser Damage Symposium (aka, Boulder Damage Symposium) that has been held in Boulder, Colorado, since 1969. This special section of Optical Engineering is the first one devoted to the entire field of laser damage rather than to a specific part. It is prepared in response to growing interest from the international laser-damage community. Some papers in this special section were presented at the Laser Damage Symposium; others were submitted in response to the general call for papers for this special section. The 18 papers compiled into this special section represent many sides of the broad field of laser-damage research. They consider theoretical studies of the fundamental mechanisms of laser damage including laser-driven electron dynamics in solids (O. Brenk and B. Rethfeld; A. Nikiforov, A. Epifanov, and S. Garnov; T. Apostolova et al.), modeling of propagation effects for ultrashort high-intensity laser pulses (J. Gulley), an overview of mechanisms of inclusion-induced damage (M. Koldunov and A. Manenkov), the formation of specific periodic ripples on a metal surface by femtosecond laser pulses (M. Ahsan and M. Lee), and the laser-plasma effects on damage in glass (Y. Li et al). Material characterization is represented by the papers devoted to accurate and reliable measurements of absorption with special emphasis on thin films (C. Mhlig and S. Bublitz; B. Cho, E. Danielewicz, and J. Rudisill; W. Palm et al; and J. Lu et al.). Statistical treatment of measurements of the laser-damage threshold (J. Arenberg) and the relationship to damage mechanisms (F. Wagner et al.) represent the large subfield of laser-damage measurements. Various aspects of multilayer coating and thin-film characterization are considered in papers by B. Cho, J. Rudisill, and E. Danielewicz (spectral shift in multilayer mirrors) and R. Weber et al. (novel approach to damage studies based on third-harmonic generation microscopy). Of special interest for readers is the paper by C. Stolz that summarizes the results of four thin-film damage competitions organized as a part of the Laser Damage Symposium. Another paper is devoted to thermal annealing of damage precursors (N. Shen et al.). Finally, the influence of nano-size contamination on initiation of laser damage by ultrashort pulses is considered in paper of V. Komolov et al.

Vitaly Gruzdev, Michelle D. Shinn

2012-12-01T23:59:59.000Z

66

Cell damage seen from Chernobyl  

SciTech Connect (OSTI)

The 30 kilometer radius forbidden zone around the Chernobyl atomic plant serves as a sobering reminder of the world's worst nuclear accident. But for former Soviet biologists, it's also a unique natural laboratory. And one scientist, Nadejda Gulaya of Kiev's Pallaguine Institute of Biochemistry, has been doing studies that she claims offer surprising evidence of Chernobyl's after-effects. Prolonged exposure to radioactive fallout from the 1986 accident, she says, has caused damage to cell membranes in both animals and humans. For the past year, Gulaya has been comparing tissues from animals such as mink, pigs, and rodents inhabiting the Chernobyl area with those from other parts of Ukraine. Her conclusion: Exposure to radiation has, in many cases, caused alterations to membrane phospholipids. These changes, are similar to those that disrupt cellular metabolism following exposure to oxidizing free radicals. Gulaya also has preliminary data from human studies. She claims to have found similar alterations in the neurons of people who have died since being exposed to Chernobyl radiation. That leads her to speculate that the frequent psychiatric disorders may not just be from mental stress or radiophobia, but might reflect actual damage to the central nervous system.

Not Available

1992-07-24T23:59:59.000Z

67

Controlling Beaver Damage  

E-Print Network [OSTI]

Beavers are important because their dams stabilize creek flow, slow runoff and create ponds. However, these same dams can negatively alter the flow of creeks. Damage prevention, control and various trapping methods are discussed in this publication....

Texas Wildlife Services

2007-03-13T23:59:59.000Z

68

Controlling Opossum Damage  

E-Print Network [OSTI]

damage; however, their pelts can be sold only during the furbearer season and with the proper licenses. Other furbearers include beaver, otter, mink, nutria, ringtailed cat, badger, skunk, weasel, raccoon, muskrat, fox and civet cat. Homeowners...

Texas Wildlife Services

2007-05-23T23:59:59.000Z

69

Composite heat damage assessment  

SciTech Connect (OSTI)

The effects of heat damage were determined on the residual mechanical, physical, and chemical properties of IM6/3501-6 laminates, and potential nondestructive techniques to detect and assess material heat damage were evaluated. About one thousand preconditioned specimens were exposed to elevated temperatures, then cooled to room temperature and tested in compression, flexure, interlaminar shear, shore-D hardness, weight loss, and change in thickness. Specimens experienced significant and irreversible reduction in their residual properties when exposed to temperatures exceeding the material upper service temperature of this material (350{degrees}F). The Diffuse Reflectance Infrared Fourier Transform and Laser-Pumped Fluorescence techniques were found to be capable of rapid, in-service, nondestructive detection and quantitation of heat damage in IM6/3501- 6. These techniques also have the potential applicability to detect and assess heat damage effects in other polymer matrix composites.

Janke, C.J.; Wachter, E.A. [Oak Ridge National Lab., TN (United States); Philpot, H.E. [Oak Ridge K-25 Site, TN (United States); Powell, G.L. [Oak Ridge Y-12 Plant, TN (United States)

1993-12-31T23:59:59.000Z

70

A Finite Volume Approach For Contingent Claims R. Zvan \\Lambda , P.A. Forsyth y , and K.R. Vetzal z  

E-Print Network [OSTI]

A Finite Volume Approach For Contingent Claims Valuation R. Zvan \\Lambda , P.A. Forsyth y , and K presents a nonconservative finite volume approach for solving two dimensional contingent claims valuation problems. The finite volume method is more flexible than finite difference schemes which are often

Forsyth, Peter A.

71

FY 2015 -Rates for Self-Sustaining Services Rates are contingent upon approval by UW Management Accounting & Analysis.  

E-Print Network [OSTI]

Pager Feature - Group Call Retiring $2.30 Group Monthly Mobile Technology Basic Smartphone Support - iFY 2015 - Rates for Self-Sustaining Services Rates are contingent upon approval by UW Management Nebula Managed Desktop $36.50 $39.90 Computer Monthly Nebula Hourly Support $109.00 $109.00 Hour Each

Kaminsky, Werner

72

Nuclear Weapons Complex reconfiguration study  

SciTech Connect (OSTI)

Shortly after assuming duties as Secretary of Energy, I reviewed the Nuclear Weapons Complex Modernization Report'' submitted to the Congress in January 1989 as required by the National Defense Authorization Act of 1988 and 1989. My review showed that several of the report's assumptions needed to be re-evaluated. During this eighteen-month review, dramatic world changes forced further reassessments of the future Nuclear Weapons Complex. These changes are reflected in the new report. The new report presents a plan to achieve a reconfigured complex, called Complex-21. Complex-21 would be smaller, less diverse, and less expensive to operated than the Complex of today. Complex-21 would be able to safely and reliability support nuclear deterrent stockpile objectives set forth by the President and funded by the Congress. It would be consistent with realities of the emerging international security environment and flexible enough to accommodate the likely range of deterrent contingencies. In addition, Complex-21 would be constructed and operated to comply with all applicable federal, state, and local laws, regulations, and orders. Achieving Complex-21 will require significant resources. This report provides and organized approach toward selecting the most appropriate configuration for Complex-21, satisfying environmental requirements, and minimizing costs. The alternative -- to continue to use piecemeal fixes to run an antiquated complex -- will be more expensive and provide a less reliable Nuclear Weapons Complex. As a consequence, implementation of the Complex-21 plan is considered necessary to ensure continued viability of our nuclear deterrent.

Not Available

1991-01-01T23:59:59.000Z

73

Radiation damage evolution in ceramics. | EMSL  

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

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74

Regulation with anticipated learning about environmental damages  

E-Print Network [OSTI]

abatement costs and environmental damages, and a generalemissions. 2.2 Environmental damages and learning Let S t begas stocks and environmental damages. In some respects these

Karp, L; Zhang, J

2006-01-01T23:59:59.000Z

75

Contingency theory of group communication effectiveness in Korean organizations: influence of fit between organizational structural variables and group relational climate on communication effectiveness  

E-Print Network [OSTI]

This study developed and tested a contingency model of group communication in Korean workgroups that posited that the communication effectiveness and group performance of workgroups is determined by the â??fitâ? of communication practices...

Cho, WoonYoung

2006-10-30T23:59:59.000Z

76

High-energy radiation damage in zirconia: modeling results  

SciTech Connect (OSTI)

Zirconia is viewed as a material of exceptional resistance to amorphization by radiation damage, and consequently proposed as a candidate to immobilize nuclear waste and serve as an inert nuclear fuel matrix. Here, we perform molecular dynamics simulations of radiation damage in zirconia in the range of 0.1-0.5 MeV energies with account of electronic energy losses. We nd that the lack of amorphizability co-exists with a large number of point defects and their clusters. These, importantly, are largely isolated from each other and therefore represent a dilute damage that does not result in the loss of long-range structural coherence and amorphization. We document the nature of these defects in detail, including their sizes, distribution and morphology, and discuss practical implications of using zirconia in intense radiation environments.

Zarkadoula, Evangelia [Queen Mary, University of London] [Queen Mary, University of London; Devanathan, Ram [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Weber, William J [ORNL] [ORNL; Seaton, M [Daresbury Laboratory, UK] [Daresbury Laboratory, UK; Todorov, I T [Daresbury Laboratory, UK] [Daresbury Laboratory, UK; Nordlund, Kai [University of Helsinki] [University of Helsinki; Dove, Martin T [Queen Mary, University of London] [Queen Mary, University of London; Trachenko, Kostya [Queen Mary, University of London] [Queen Mary, University of London

2014-01-01T23:59:59.000Z

77

Damage evolution in Au-implanted Ho2Ti2O7 titanate pyrochlore...  

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

Zhang Y, J Jagielski, IT Bae, X Xiang, L Thome, G Balakrishnan, DM Paul, and WJ Weber.2010."Damage evolution in Au-implanted Ho2Ti2O7 titanate pyrochlore."Nuclear...

78

Public comment re Convention on Supplementary Compensation on Nuclear  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Careerlumens_placard-green.epsEnergy1.pdfMarket37963 Vol. 79, No.and/or8-458-DEC.Damage Contingent

79

Nuclear threats from small states  

SciTech Connect (OSTI)

What are the policy implications regarding proliferation and counter proliferation of nuclear weapons among Third World states. How does deterrence operate outside the parameters of superpower confrontation as defined by the cold war elaborate system of constraints enforced by concepts like mutual assured destruction, and counter-value and counter-force targeting. How can US policymakers devise contingencies for dealing with nuclear threats posed by countries like North Korea, Libya, Iraq, Iran, and Syria. These are some of the unsettling but nevertheless important questions addressed by the author in this monograph. In his analysis, Mr. Jerome Kahan examines the likelihood that one or more of these countries will use nuclear weapons before the year 2000. He also offers a framework that policymakers and planners might use in assessing US interests in preempting the use of nuclear weapons or in retaliating for their use. Ironically, with the end of the cold war, it is imperative that defense strategists, policymakers, and military professionals think about the `unthinkable`. In the interest of fostering debate on this important subject, the Strategic Studies Institute commends this insightful monograph.

Kahan, J.H.

1994-06-13T23:59:59.000Z

80

NEUTRON DAMAGE IN REACTOR PRESSURE-VESSEL STEEL EXAMINED WITH POSITRON ANNIHILATION LIFETIME SPECTROSCOPY  

E-Print Network [OSTI]

NEUTRON DAMAGE IN REACTOR PRESSURE-VESSEL STEEL EXAMINED WITH POSITRON ANNIHILATION LIFETIME-vessel steels. We irradiated samples ofASTM A508 nuclear reactor pressure-vessel steel to fast neutron 17 2 (PALS) to study the effects of neutron damage in the steels on positron lifetimes. Non

Motta, Arthur T.

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Deterring regional threats from nuclear proliferation  

SciTech Connect (OSTI)

The most prominent shift in the National Military Strategy is from the global Soviet threat to a new focus on regional contingencies. No threat looms larger in these contingencies than the proliferation of nuclear weapons and ballistic missiles. This study examines proliferation trends and proposes a predominately diplomatic strategy for containing the problem. Dr. Spector identifies three waves of proliferation: the first is the five states with declared weapons and doctrine-the United States, Russia, Great Britain, France, and China; the second includes a less visible group that developed a covert capability, without testing weapons or declaring a doctrine of deterrence-for example, Israel, India, and probably Pakistan; and, a third wave of would-be proliferators includes radical states like Iraq, Iran, Libya, and North Korea. Spector's political approach is based on the common interest of wave one and two states to prevent further proliferation. Political-economic incentives have already worked in the cases of Brazil, Argentina, Taiwan, and South Africa-states which appear to have abandoned their nuclear weapons programs. Spector does not rule out the option of military force. Force, especially under international sanctions, can be a powerful tool to back diplomatic efforts. Use of force, however, remains a last resort.

Spector, L.S.

1992-03-12T23:59:59.000Z

82

Resource Contingency Program - Oregon : Final Environmental Impact Statement, Hermiston Power Project.  

SciTech Connect (OSTI)

The Bonneville Power Administration (BPA) has statutory responsibilities to supply electrical power to its utility, industrial, and other customers in the Pacific Northwest. In 1990, to cover the outer range of potential load growth with new resources, BPA embarked upon the Resource Contingency Program (RCP). Instead of buying or building generating plants now, BPA has purchased options to acquire power later, if and when it is needed. The decision to acquire any of these option energy projects to fulfill statutory supply obligations will be influenced by Federal system load growth, the outcome of BPA`s Business Plan, required operational changes in Columbia-Snake River Hydroelectric facilities, and the loss of major generating resources. In September 1993, three option development agreements were signed with three proposed natural gas-fired, combined cycle combustion turbine CT projects near Chehalis and Satsop, Washington, and near Hermiston, Oregon. Together these three projects could supply BPA with 1,090 average megawatts (aMW) of power. Under these agreements, sponsors are obtaining permits and conducting project design work, and BPA is completing this EIS process. In September 1993, BPA published a Notice of Intent to prepare an environmental impact statement (EIS) on these three proposed gas-fired combustion turbine projects and held public scoping meetings in October 1993 at each site. In February 1994, BPA released an Implementation Plan on the proposed scope of the EIS. A draft EIS on the three proposed projects was published in February 1995. The impacts of the Chehalis and Satsop projects located in Washington State will be covered in one EIS document, while the impacts of the Hermiston project located in Oregon are covered in this final EIS document. It is BPA`s intent to continue to base the analysis of impacts on the assumption that all three projects may be constructed at some point in the future.

United States. Bonneville Power Administration.

1995-09-01T23:59:59.000Z

83

Underground infrastructure damage for a Chicago scenario  

SciTech Connect (OSTI)

Estimating effects due to an urban IND (improvised nuclear device) on underground structures and underground utilities is a challenging task. Nuclear effects tests performed at the Nevada Test Site (NTS) during the era of nuclear weapons testing provides much information on how underground military structures respond. Transferring this knowledge to answer questions about the urban civilian environment is needed to help plan responses to IND scenarios. Explosions just above the ground surface can only couple a small fraction of the blast energy into an underground shock. The various forms of nuclear radiation have limited penetration into the ground. While the shock transmitted into the ground carries only a small fraction of the blast energy, peak stresses are generally higher and peak ground displacement is lower than in the air blast. While underground military structures are often designed to resist stresses substantially higher than due to the overlying rocks and soils (overburden), civilian structures such as subways and tunnels would generally only need to resist overburden conditions with a suitable safety factor. Just as we expect the buildings themselves to channel and shield air blast above ground, basements and other underground openings as well as changes of geology will channel and shield the underground shock wave. While a weaker shock is expected in an urban environment, small displacements on very close-by faults, and more likely, soils being displaced past building foundations where utility lines enter could readily damaged or disable these services. Immediately near an explosion, the blast can 'liquefy' a saturated soil creating a quicksand-like condition for a period of time. We extrapolate the nuclear effects experience to a Chicago-based scenario. We consider the TARP (Tunnel and Reservoir Project) and subway system and the underground lifeline (electric, gas, water, etc) system and provide guidance for planning this scenario.

Dey, Thomas N [Los Alamos National Laboratory; Bos, Rabdall J [Los Alamos National Laboratory

2011-01-25T23:59:59.000Z

84

Thermal Decomposition of Radiation-Damaged Polystyrene  

SciTech Connect (OSTI)

The radiation-damaged polystyrene material (''polycube'') used in this study was synthesized by mixing a high-density polystyrene (''Dylene Fines No. 100'') with plutonium and uranium oxides. The polycubes were used on the Hanford Site in the 1960s for criticality studies to determine the hydrogen-to-fissile atom ratios for neutron moderation during processing of spent nuclear fuel. Upon completion of the studies, two methods were developed to reclaim the transuranic (TRU) oxides from the polymer matrix: (1) burning the polycubes in air at 873 K; and (2) heating the polycubes in the absence of oxygen and scrubbing the released monomer and other volatile organics using carbon tetrachloride. Neither of these methods was satisfactory in separating the TRU oxides from the polystyrene. Consequently, the remaining polycubes were sent to the Hanford Plutonium Finishing Plant (PFP) for storage. Over time, the high dose of alpha and gamma radiation has resulted in a polystyrene matrix that is highly cross-linked and hydrogen deficient and a stabilization process is being developed in support of Defense Nuclear Facility Safety Board Recommendation 94-1. Baseline processes involve thermal treatment to pyrolyze the polycubes in a furnace to decompose the polystyrene and separate out the TRU oxides. Thermal decomposition products from this degraded polystyrene matrix were characterized by Pacific Northwest National Laboratory to provide information for determining the environmental impact of the process and for optimizing the process parameters. A gas chromatography/mass spectrometry (GC/MS) system coupled to a horizontal tube furnace was used for the characterization studies. The decomposition studies were performed both in air and helium atmospheres at 773 K, the planned processing temperature. The volatile and semi-volatile organic products identified for the radiation-damaged polystyrene were different from those observed for virgin polystyrene. The differences were in the n umber of organic species generated and their concentrations.

J Abrefah GS Klinger

2000-09-26T23:59:59.000Z

85

Building Damage, Death and Downtime Risk Attenuation in Earthquakes  

E-Print Network [OSTI]

value over a specified amount of time, can be obtained. This was a great development in the field of probabilistic seismic hazard analysis. Kennedy et al. (1980) conducted research to study the safety of the Oyster Creek nuclear power plant... 2D structural model developed in SAP 2000; and (c) plan of ?Redbook Building? ....... 16 Figure 4 ?Scenario-based? 3d loss model: (a) seismic hazard intensity-attenuation model; (b) structural analysis; (c) damage analysis; and (d) loss...

Huang, Yinghui

2012-07-16T23:59:59.000Z

86

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network [OSTI]

Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

87

BDS thin film damage competition  

SciTech Connect (OSTI)

A laser damage competition was held at the 2008 Boulder Damage Symposium in order to determine the current status of thin film laser resistance within the private, academic, and government sectors. This damage competition allows a direct comparison of the current state-of-the-art of high laser resistance coatings since they are all tested using the same damage test setup and the same protocol. A normal incidence high reflector multilayer coating was selected at a wavelength of 1064 nm. The substrates were provided by the submitters. A double blind test assured sample and submitter anonymity so only a summary of the results are presented here. In addition to the laser resistance results, details of deposition processes, coating materials, and layer count will also be shared.

Stolz, C J; Thomas, M D; Griffin, A J

2008-10-24T23:59:59.000Z

88

Damage from the impacts of small asteroids  

SciTech Connect (OSTI)

The fragmentation of a small asteroid in the atmosphere greatly increases its aerodynamic drag and rate of energy dissipation. The differential atmospheric pressure across it disperses its fragments at a velocity that increases with atmospheric density and impact velocity and decreases with asteroid density. Extending our previous work, we use a spherical atmosphere and a fitted curve to its density profile to find the damage done by an asteroid entering the atmosphere at various zenith angles. In previous work we estimated the blast damage by scaling from data on nuclear explosions in the atmosphere during the 1940s, 1950s and early 1960s. This underestimated the blast from asteroid impacts because nuclear fireballs radiate away a larger fraction of their energy than do meteors, so less of their energy goes into the blast wave. We have redone the calculations to allow for this effect. We have found the area of destruction around the impact point in which the over pressure in the blast wave exceeds 4 pounds/inch{sup 2} = 2.8 X 10{sup 5} dynes/cm{sup 3}, which is enough to knock over trees and destroy buildings. About every 100 years an impactor should blast an area of 300 km{sup 2} or more somewhere on the land area of Earth. The optical flux from asteroids 60 meters or more in diameter is enough to ignite pine forests. However, the blast from an impacting asteroid goes beyond the radius within which the fire starts. It tends to blow out the fire, so it is likely that the impact will char the forest (as at Tunguska), but it will not produce a sustained fire. Because of the atmosphere, asteroids less than about 200 m in diameter are not effective in producing craters and earthquakes. They are also not effective in producing water waves and tsunami in ocean impacts. Tsunami is probably the most devastating type of damage for asteroids that are between 200 meters and 1 km in diameter.

Hills, J.G.; Goda, M.P.

1996-08-15T23:59:59.000Z

89

Nuclear Nonproliferation  

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

Nuclear Nonproliferation As more countries embrace nuclear power as a cost-effective and clean alternative to fossil fuels, the need exists to ensure that the nuclear fuel cycle is...

90

Nuclear Engineering Nuclear Criticality Safety  

E-Print Network [OSTI]

Nuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear, and neutron spectra. The NE nuclear criticality safety (NCS) capabilities are based on a staff with decades

Kemner, Ken

91

Natural Resource Damage Assessment Cooperation and Integration  

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

The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), 42 U.S.C. 9601, et seq., Executive Order 12580, and CERCLA's implementing regulations in the National Contingency Plan (NCP), 40 CFR Part 300, give the DOE three roles at DOE facilities undergoing environmental cleanup: lead response agency, natural resource trustee, and the party responsible for releases and threatened releases of hazardous substances. Does not cancel other directives.

2012-06-19T23:59:59.000Z

92

Nuclear Physics  

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

Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

93

Nuclear Energy  

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

Nuclear Energy Idaho National Laboratory is the Department of Energy's lead nuclear energy research and development facility. Building upon its legacy responsibilities,...

94

Japanese Ratify Convention on Supplementary Compensation for Nuclear Damage  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomentheATLANTA,Fermi NationalBusinessDepartmentat LargerJanuary2005Plant Cleanup

95

Nuclear Matter and Nuclear Dynamics  

E-Print Network [OSTI]

Highlights on the recent research activity, carried out by the Italian Community involved in the "Nuclear Matter and Nuclear Dynamics" field, will be presented.

M Colonna

2009-02-26T23:59:59.000Z

96

Cost & Contingency | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

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 SecurityTensile Strain Switched5 Industrial CarbonArticlesHumanJune 2008Contractor Human Resources IntegratedCost

97

ANALYTICAL NEUTRONIC STUDIES CORRELATING FAST NEUTRON FLUENCE TO MATERIAL DAMAGE IN CARBON, SILICON, AND SILICON CARBIDE  

SciTech Connect (OSTI)

This study evaluates how fast neutron fluence >0.1 MeV correlates to material damage (i.e., the total fluence spectrum folded with the respective materials displacements-per- atom [dpa] damage response function) for the specific material fluence spectra encountered in Next Generation Nuclear Plant (NGNP) service and the irradiation tests conducted in material test reactors (MTRs) for the fuel materials addressed in the white paper. It also reports how the evaluated correlations of >0.1 MeV fluence to material damage vary between the different spectral conditions encountered in material service versus testing.

Jim Sterbentz

2011-06-01T23:59:59.000Z

98

Remote sensing and forest damage  

SciTech Connect (OSTI)

Each year, damage to North American forests caused by insects, diseases, pollution, and fire results in multibillion dollar losses of revenue and resources. To respond to these losses effectively, forest managers need timely information on the location, extent, and spread of the damage. Traditional techniques for monitoring forest damage include high-resolution aerial photography, color infrared photography, and visual reconnaissance mapping. These techniques require visual interpretation of the data and often are somewhat subjective. In addition, because such analyses are time-consuming and costly, many areas of forest are never mapped, and in cases where maps exist, they often are obsolete or incomplete. An airborne imager has been developed to solve the problems of time-consuming visual analysis and interpretations. The Programmable Multispectral Imager measures small changes - invisible by conventional detection methods - in light reflected by the forest canopy. The PMI measures the color an intensity of reflected light and records this information digitally in computer tape aboard an aircraft. This information is then available for later entry into a computer for processing and enhancement. Although airborne imagers have been available for nearly three decades, they have not been used extensively for forest damage assessment or other forestry applications because of their poor sensitivity and their limited number of fixed spectral channels. The PMI is the first of a new generation of imagers that combine high sensitivity with the flexibility of continuous spectral coverage. This allows scientists to evaluate the potential causes and effects of stress on vegetation.

Reid, N.J.

1987-05-01T23:59:59.000Z

99

Thermal Decomposition of Radiation-Damaged Polystyrene  

SciTech Connect (OSTI)

The radiation-damaged polystyrene (given the identification name of 'polycube') was fabricated by mixing high-density polystyrene material ("Dylene Fines # 100") with plutonium and uranium oxides. The polycubes were used in the 1960s for criticality studies during processing of spent nuclear fuel. The polycubes have since been stored for almost 40 years at the Hanford Plutonium Finishing Plant (PFP) after failure of two processes to reclaim the plutonium and uranium oxides from the polystyrene matrix. Thermal decomposition products from this highly cross-linked polystyrene matrix were characterized using Gas Chromatograph/Mass Spectroscopy (GC/MS) system coupled to a horizontal furnace. The decomposition studies were performed in air and helium atmospheres at about 773 K. The volatile and semi-volatile organic products for the radiation-damaged polystyrene were different compared to virgin polystyrene. The differences were in the number of organic species generated and their concentrations. In the inert (i.e., helium) atmosphere, the major volatile organic products identified (in order of decreasing concentrations) were styrene, benzene, toluene, ethylbenzene, xylene, nathphalene, propane, .alpha.-methylbenzene, indene and 1,2,3-trimethylbenzene. But in air, the major volatile organic species identified changed slightly. Concentrations of the organic species in the inert atmosphere were significantly higher than those for the air atmosphere processing. Overall, 38 volatile organic species were identified in the inert atmosphere compared to 49 species in air. Twenty of the 38 species in the inert conditions were also products in the air atmosphere. Twenty-two oxidized organic products were identified during thermal processing in air.

Abrefah, John; Klinger, George S.

2000-09-26T23:59:59.000Z

100

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

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Fusion Nuclear Science and Technology (FNST) Mohamed Abdou  

E-Print Network [OSTI]

Material degradation by radiation and other damage Fabrication and joining for reliable components at IFE pulse repetition rate · Incremental effects of repetitive pulses (e.g., radiation damage Components divertor, limiter and nuclear aspects of plasma heating/fueling and IFE final optics Blanket

102

Method for producing damage resistant optics  

DOE Patents [OSTI]

The present invention provides a system that mitigates the growth of surface damage in an optic. Damage to the optic is minimally initiated. In an embodiment of the invention, damage sites in the optic are initiated, located, and then treated to stop the growth of the damage sites. The step of initiating damage sites in the optic includes a scan of the optic using a laser to initiate defects. The exact positions of the initiated sites are identified. A mitigation process is performed that locally or globally removes the cause of subsequent growth of the damaged sites.

Hackel, Lloyd A. (Livermore, CA); Burnham, Alan K. (Livermore, CA); Penetrante, Bernardino M. (San Ramon, CA); Brusasco, Raymond M. (Livermore, CA); Wegner, Paul J. (Livermore, CA); Hrubesh, Lawrence W. (Pleasanton, CA); Kozlowski, Mark R. (Windsor, CA); Feit, Michael D. (Livermore, CA)

2003-01-01T23:59:59.000Z

103

Constitutive representation of damage development and healing in WIPP salt  

SciTech Connect (OSTI)

There has been considerable interest in characterizing and modeling the constitutive behavior of rock salt with particular reference to long-term creep and creep failure. The interest is motivated by the projected use of excavated rooms in salt rock formations as repositories for nuclear waste. It is presumed that closure of those rooms by creep ultimately would encapsulate the waste material, resulting in its effective isolation. A continuum mechanics approach for treating damage healing is formulated as part of a constitutive model for describing coupled creep, fracture, and healing in rock salt. Formulation of the healing term is, described and the constitutive model is evaluated against experimental data of rock salt from the Waste Isolation Pilot Plant (WIPP) site. The results indicate that healing anistropy in WIPP salt can be modeled with an appropriate power-conjugate equivalent stress, kinetic equation, and evolution equation for damage healing.

Chan, K.S.; Bodner, S.R. [Southwest Research Inst., San Antonio, TX (United States); Fossum, A.F [RE/SPEC, Inc., Rapid City, SD (United States); Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States)

1994-12-31T23:59:59.000Z

104

A damage model for fracking  

E-Print Network [OSTI]

Injections of large volumes of water into tight shale reservoirs allows the extraction of oil and gas not previously accessible. This large volume "super" fracking induces damage that allows the oil and/or gas to flow to an extraction well. The purpose of this paper is to provide a model for understanding super fracking. We assume that water is injected from a small spherical cavity into a homogeneous elastic medium. The high pressure of the injected water generates hoop stresses that reactivate natural fractures in the tight shales. These fractures migrate outward as water is added creating a spherical shell of damaged rock. The porosity associated with these fractures is equal to the water volume injected. We obtain an analytic expression for this volume. We apply our model to a typical tight shale reservoir and show that the predicted water volumes are in good agreement with the volumes used in super fracking.

Norris, J Quinn; Rundle, John B

2015-01-01T23:59:59.000Z

105

Nuclear Engineer (Nuclear Safety Specialist)  

Broader source: Energy.gov [DOE]

A successful candidate of this position will serve as a Nuclear Engineer (Nuclear Safety Specialist) responsible for day-to-day technical monitoring, and evaluation of aspects of authorization...

106

Propellant actuated nuclear reactor steam depressurization valve  

DOE Patents [OSTI]

A nuclear fission reactor combined with a propellant actuated depressurization and/or water injection valve is disclosed. The depressurization valve releases pressure from a water cooled, steam producing nuclear reactor when required to insure the safety of the reactor. Depressurization of the reactor pressure vessel enables gravity feeding of supplementary coolant water through the water injection valve to the reactor pressure vessel to prevent damage to the fuel core.

Ehrke, Alan C. (San Jose, CA); Knepp, John B. (San Jose, CA); Skoda, George I. (Santa Clara, CA)

1992-01-01T23:59:59.000Z

107

International Trade and the Internalization of Environmental Damages  

E-Print Network [OSTI]

estimates of environmental damages efficiently and quickly,an overview of environmental damages and internalizationdo little to decrease environmental damage, and may actually

Karp, Larry; Dumas, Christopher F.; Koo, Bonwoo; Sacheti, Sandeep

1995-01-01T23:59:59.000Z

108

Competition between mesoplasticity and damage under HCF Elasticity/damage shakedown concept  

E-Print Network [OSTI]

during all the sample lifetime of the plasticity and damage effects. The plasticity mechanisms induce in the framework of the continuum damage mechanics, according to the identified physical mechanisms during, the damage growth arrest. Keywords High cycle fatigue; Multiaxial loading; Continuum damage mechanics

Boyer, Edmond

109

QUANTIFICATION OF ACTINIDE ALPHA-RADIATION DAMAGE IN MINERALS AND CERAMICS  

SciTech Connect (OSTI)

There are large amounts of heavy alpha-emitters in nuclear waste and nuclear materials inventories stored in various sites around the world. These include plutonium and minor actinides such as americium and curium. In preparation for geological disposal there is a consensus that actinides that have been separated from spent nuclear fuel should be immobilised within mineral-based ceramics rather than glass. Over the long-term, the alpha-decay taking place in these ceramics will severely disrupt their crystalline structure and reduce their durability. A fundamental property in predicting cumulative radiation damage is the number of atoms permanently displaced per alphadecay. Currently, this number is estimated as 1000-2000 atoms/alpha decay event. Here, we report nuclear magnetic resonance, spin-counting experiments that measure close to 5000 atoms/alpha decay event in radiation damaged natural zircons. New radiological NMR measurements on highly radioactive, 239Pu zircon show damage similar to that created by 238U and 232Th in mineral zircons at the same dose, indicating no significant effect of dose rate. Based on these measurements, the initially crystalline structure of a 10 wt% 239Pu zircon would be amorphous after only 1400 years in a geological repository. These measurements establish a basis for assessing the long-term structural durability of actinide-containing ceramics based on an atomistic understanding of the fundamental damage event.

Farnan, Ian E.; Cho, Herman M.; Weber, William J.

2007-01-11T23:59:59.000Z

110

28-nm laser damage testing of LIF  

SciTech Connect (OSTI)

We have tested several samples of LIF, both single crystal and press forged, for damage resistance to 10-ns 248-nm pulses at 35 pps. The damage thresholds - the highest levels at which no damage could be produced - ranged from 4 to 6 J/cm/sup 2/ although some test sites survived irradiation at approx. 30 J/cm/sup 2/. We observed that bulk damage is the primary failure mechanism in single crystal and press forged samples and that both types exhibit the same resistance to laser damage.

Foltyn, S.R.; Newman, B.E.

1981-01-01T23:59:59.000Z

111

Damage experiments in a cylindrical geometry  

SciTech Connect (OSTI)

Studying spallation damage with a cylindrical configuration allows for a natural recollection of the damaged material under proper driving conditions. Additionally, the damaged material can come to a complete rest without the application of further stopping forces. Specific areas of research include the damage initiation regime in convergent geometry, behavior of material recollected after damage, and effects of convergent geometry on the material response. Such experiments produce unique strain and shear stress states, motivating improvements in existing computational material models and increasing the predictive capabilities of codes. A LANL/VNIIEF joint experimental series has produced cylindrical aluminum failure initiation data and studied the behavior of material recollected after damage initiation and after complete failure. In addition to post-shot collection of the damaged target material for subsequent metallographic analysis, dynamic in-situ experimental diagnostics include velocimetry and transverse radial radiography. This paper will discuss the current experimental status.

Kaul, Ann M [Los Alamos National Laboratory

2010-09-21T23:59:59.000Z

112

The Fukushima Nuclear Event and its Implications for Nuclear Power  

SciTech Connect (OSTI)

The combined strong earthquake and super tsunami of 12 March 2011 at the Fukushima nuclear power plant imposed the most severe challenges ever experienced at such a facility. Information regarding the plant response and status remains uncertain, but it is clear that severe damage has been sustained, that the plant staff have responded creatively and that the offsite implications are unlikely to be seriously threatening to the health, if not the prosperity, of the surrounding population. Re-examination of the regulatory constraints of nuclear power will occur worldwide, and some changes are likely, particularly concerning reliance upon active systems for achieving critical safety functions and concerning treatments of used reactor fuel. Whether worldwide expansion of the nuclear power economy will be slowed in the long run is perhaps unlikely and worth discussion.

Golay, Michael (MIT) [MIT

2011-07-06T23:59:59.000Z

113

Nuclear Counterterrorism  

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

The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information.) Appendices A and B are Official Use Only. Point of contact is Adam Boyd (NA-82), 202-586-0010. Cancels DOE O 457.1 and DOE M 457.1-1.

2013-08-26T23:59:59.000Z

114

nuclear controls  

National Nuclear Security Administration (NNSA)

the Office of Nonproliferation and International Security (NIS) is to prevent the proliferation of nuclear weapons, materials, technology, and expertise. NIS applies technical...

115

Emulation of reactor irradiation damage using ion beams  

SciTech Connect (OSTI)

The continued operation of existing light water nuclear reactors and the development of advanced nuclear reactor depend heavily on understanding how damage by radiation to levels degrades materials that serve as the structural components in reactor cores. The first high dose ion irradiation experiments on a ferritic-martensitic steel showing that ion irradiation closely emulates the full radiation damage microstructure created in-reactor are described. Ferritic-martensitic alloy HT9 (heat 84425) in the form of a hexagonal fuel bundle duct (ACO-3) accumulated 155 dpa at an average temperature of 443C in the Fast Flux Test Facility (FFTF). Using invariance theory as a guide, irradiation of the same heat was conducted using self-ions (Fe++) at 5 MeV at a temperature of 460C and to a dose of 188 displacements per atom. The void swelling was nearly identical between the two irradiations and the size and density of precipitates and loops following ion irradiation are within a factor of two of those for neutron irradiation. The level of agreement across all of the principal microstructure changes between ion and reactor irradiations establishes the capability of tailoring ion irradiations to emulate the reactor-irradiated microstructure.

G. S. Was; Z. Jiao; E. Beckett; A. M. Monterrosa; O. Anderoglu; B. H. Sencer; M. Hackett

2014-10-01T23:59:59.000Z

116

PRELIMINARY NUCLEAR CRITICALITY NUCLEAR SAFETY EVLAUATION FOR THE CONTAINER SURVEILLANCE AND STORAGE CAPABILITY PROJECT  

SciTech Connect (OSTI)

Washington Safety Management Solutions (WSMS) provides criticality safety services to Washington Savannah River Company (WSRC) at the Savannah River Site. One activity at SRS is the Container Surveillance and Storage Capability (CSSC) Project, which will perform surveillances on 3013 containers (hereafter referred to as 3013s) to verify that they meet the Department of Energy (DOE) Standard (STD) 3013 for plutonium storage. The project will handle quantities of material that are greater than ANS/ANSI-8.1 single parameter mass limits, and thus required a Nuclear Criticality Safety Evaluation (NCSE). The WSMS methodology for conducting an NCSE is outlined in the WSMS methods manual. The WSMS methods manual currently follows the requirements of DOE-O-420.1B, DOE-STD-3007-2007, and the Washington Savannah River Company (WSRC) SCD-3 manual. DOE-STD-3007-2007 describes how a NCSE should be performed, while DOE-O-420.1B outlines the requirements for a Criticality Safety Program (CSP). The WSRC SCD-3 manual implements DOE requirements and ANS standards. NCSEs do not address the Nuclear Criticality Safety (NCS) of non-reactor nuclear facilities that may be affected by overt or covert activities of sabotage, espionage, terrorism or other security malevolence. Events which are beyond the Design Basis Accidents (DBAs) are outside the scope of a double contingency analysis.

Low, M; Matthew02 Miller, M; Thomas Reilly, T

2007-04-30T23:59:59.000Z

117

Nanofoams Response to Radiation Damage  

SciTech Connect (OSTI)

Conclusions of this presentation are: (1) np-Au foams were successfully synthesized by de-alloying process; (2) np-Au foams remain porous structure after Ne ion irradiation to 1 dpa; (3) SFTs were observed in irradiated np-Au foams with highest and intermediate flux, while no SFTs were observed with lowest flux; (4) SFTs were observed in irradiated np-Au foams at RT, whereas no SFTs were observed at LNT irradiation; (5) The diffusivity of vacancies in Au at RT is high enough so that the vacancies have enough time to agglomerate and thus collapse. As a result, SFTs were formed; (6) The high flux created much more damage/time, vacancies don't have enough time to diffuse or recombine. As a result, SFTs were formed.

Fu, Engang [Los Alamos National Laboratory; Serrano De Caro, Magdalena [Los Alamos National Laboratory; Wang, Yongqiang [Los Alamos National Laboratory; Nastasi, Michael [Nebraska Center for Energy Sciences Research, University of Nebraska-Lincoln, NE 68508; Zepeda-Ruiz, Luis [PLS, Lawrence Livermore National Laboratory, Livermore, CA 94551; Bringa, Eduardo M. [CONICET and Inst. Ciencias Basicas, Universidad Nacional de Cuyo, Mendoza, 5500 Argentina; Baldwin, Jon K. [Los Alamos National Laboratory; Caro, Jose A. [Los Alamos National Laboratory

2012-07-30T23:59:59.000Z

118

PROBING DENSE NUCLEAR MATTER VIA NUCLEAR COLLISIONS  

E-Print Network [OSTI]

University of California. LBL-12095 Probing Dense NuclearMatter Nuclear Collisions* v~a H. Stocker, M.Gyulassy and J. Boguta Nuclear Science Division Lawrence

Stocker, H.

2012-01-01T23:59:59.000Z

119

Insulator damage endangers public, power reliability; ratepayers...  

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

Insulator-damage-endangers-public-power-reliability-ratepayers-foot-repair-bill Sign In About | Careers | Contact | Investors | bpa.gov Search News & Us Expand News & Us...

120

DEMONSTRATION OF LONG-TERM STORAGE CAPABILITY FOR SPENT NUCLEAR FUEL IN L BASIN  

SciTech Connect (OSTI)

The U.S. Department of Energy decisions for the ultimate disposition of its inventory of used nuclear fuel presently in, and to be received and stored in, the L Basin at the Savannah River Site, and schedule for project execution have not been established. A logical decision timeframe for the DOE is following the review of the overall options for fuel management and disposition by the Blue Ribbon Commission on America's Nuclear Future (BRC). The focus of the BRC review is commercial fuel; however, the BRC has included the DOE fuel inventory in their review. Even though the final report by the BRC to the U.S. Department of Energy is expected in January 2012, no timetable has been established for decisions by the U.S. Department of Energy on alternatives selection. Furthermore, with the imminent lay-up and potential closure of H-canyon, no ready path for fuel disposition would be available, and new technologies and/or facilities would need to be established. The fuel inventory in wet storage in the 3.375 million gallon L Basin is primarily aluminum-clad, aluminum-based fuel of the Materials Test Reactor equivalent design. An inventory of non-aluminum-clad fuel of various designs is also stored in L Basin. Safe storage of fuel in wet storage mandates several high-level 'safety functions' that would be provided by the Structures, Systems, and Components (SSCs) of the storage system. A large inventory of aluminum-clad, aluminum-based spent nuclear fuel, and other nonaluminum fuel owned by the U.S. Department of Energy is in wet storage in L Basin at the Savannah River Site. An evaluation of the present condition of the fuel, and the Structures, Systems, or Components (SSCs) necessary for its wet storage, and the present programs and storage practices for fuel management have been performed. Activities necessary to validate the technical bases for, and verify the condition of the fuel and the SSCs under long-term wet storage have also been identified. The overall conclusion is that the fuel can be stored in L Basin, meeting general safety functions for fuel storage, for an additional 50 years and possibly beyond contingent upon continuation of existing fuel management activities and several augmented program activities. It is concluded that the technical bases and well-founded technologies have been established to store spent nuclear fuel in the L Basin. Methodologies to evaluate the fuel condition and characteristics, and systems to prepare fuel, isolate damaged fuel, and maintain water quality storage conditions have been established. Basin structural analyses have been performed against present NPH criteria. The aluminum fuel storage experience to date, supported by the understanding of the effects of environmental variables on materials performance, demonstrates that storage systems that minimize degradation and provide full retrievability of the fuel up to and greater than 50 additional years will require maintaining the present management programs, and with the recommended augmented/additional activities in this report.

Sindelar, R.; Deible, R.

2011-04-27T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Nuclear Astrophysics  

E-Print Network [OSTI]

Nuclear physics has a long and productive history of application to astrophysics which continues today. Advances in the accuracy and breadth of astrophysical data and theory drive the need for better experimental and theoretical understanding of the underlying nuclear physics. This paper will review some of the scenarios where nuclear physics plays an important role, including Big Bang Nucleosynthesis, neutrino production by our sun, nucleosynthesis in novae, the creation of elements heavier than iron, and neutron stars. Big-bang nucleosynthesis is concerned with the formation of elements with A nuclear physics inputs required are few-nucleon reaction cross sections. The nucleosynthesis of heavier elements involves a variety of proton-, alpha-, neutron-, and photon-induced reactions, coupled with radioactive decay. The advent of radioactive ion beam facilities has opened an important new avenue for studying these processes, as many involve radioactive species. Nuclear physics also plays an important role in neutron stars: both the nuclear equation of state and cooling processes involving neutrino emission play a very important role. Recent developments and also the interplay between nuclear physics and astrophysics will be highlighted.

Carl R. Brune

2005-02-28T23:59:59.000Z

122

Nuclear Counterterrorism  

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

The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information. The Manual is Official Use Only, and is not available on the Directives Portal. The point of contact for the Manual is Randall Weidman, NA-121.2, 202-586-4582.) Canceled by DOE O 457.1A

2006-02-07T23:59:59.000Z

123

Countering Nuclear Terrorism and Trafficking | National Nuclear...  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism and Trafficking | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

124

NUCLEAR PLANT OPERATIONS AND  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: neutron flux, cur- rent noise, vibration diagnostics: Swedish Nuclear Powe

Pzsit, Imre

125

Space Nuclear  

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

Space Nuclear Today the INL is preparing to assist with the Multi-Mission RTG (MMRTG). The INL is assigned the final assembly and testing of the RTG for the project which is...

126

Nuclear Golf  

E-Print Network [OSTI]

Broadcast Transcript: Pay no attention to that nuclear warhead behind the 18th hole; just shout "Fore!" and drive your Titleist down the fairway. In a development that is bizarre even by North Korean standards, the country ...

Hacker, Randi; Tsutsui, William

2006-12-06T23:59:59.000Z

127

Nuclear Hydrogen  

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

Hydrogen High temperature options for nuclear generation of hydrogen on a commercial basis are several years in the future. Thermo-chemical water splitting has been proven to be...

128

Nuclear forces  

SciTech Connect (OSTI)

These lectures present an introduction into the theory of nuclear forces. We focus mainly on the modern approach, in which the forces between nucleons emerge from low-energy QCD via chiral effective field theory.

Machleidt, R. [Department of Physics, University of Idaho, Moscow, Idaho 83844 (United States)

2013-06-10T23:59:59.000Z

129

A new damage testing system for detailed evaluation of damage behavior of bulk KDP and DKDP  

SciTech Connect (OSTI)

We describe a new damage testing approach and instrumentation that provides quantitative measurements of bulk damage performance versus fluence for several frequencies. A major advantage of this method is that it can simultaneously provide direct information on pinpoint density and size, and beam obscuration. This allows for more accurate evaluation of material performance under operational conditions. Protocols for laser conditioning to improve damage performance can also be easily and rapidly evaluated.This damage testing approach has enabled us to perform complex experiments toward probing the fundamental mechanisms of damage initiation and conditioning.

DeMange, P; Negres, R A; Carr, C W; Radousky, H B; Demos, S G

2004-11-17T23:59:59.000Z

130

The emergent contingent workforce  

E-Print Network [OSTI]

through the Current Employment Statistics of the BLS existhires. Current Employment Statistics series. Personnelused the Current Employment Statistics Survey combined with

Wallace, Leslie Renee

2008-01-01T23:59:59.000Z

131

Pathogenic Mechanisms in Ischemic Damage: A Computational Study  

E-Print Network [OSTI]

Pathogenic Mechanisms in Ischemic Damage: A Computational Study Eytan Ruppin and Elad Ofer Depts of ischemic tissue damage during acute stroke. Two prime pathogenic mechanisms, cor- tical spreading the patterns of damage that arise if damage is caused by either mechanism are generated. These damaged tissue

Ruppin, Eytan

132

Carbon Fiber Damage in Accelerator Beam  

E-Print Network [OSTI]

Carbon fibers are commonly used as moving targets in Beam Wire Scanners. Because of their thermomechanical properties they are very resistant to particle beams. Their strength deteriorates with time due to radiation damage and low-cycle thermal fatigue. In case of high intensity beams this process can accelerate and in extreme cases the fiber is damaged during a single scan. In this work a model describing the fiber temperature, thermionic emission and sublimation is discussed. Results are compared with fiber damage test performed on SPS beam in November 2008. In conclusions the limits of Wire Scanner operation on high intensity beams are drawn.

Sapinski, M; Guerrero, A; Koopman, J; Mtral, E

2009-01-01T23:59:59.000Z

133

War damages and reconstruction of Peruca dam  

SciTech Connect (OSTI)

The paper describes the heavy damages caused by blasting in the Peruca rockfill dam in Croatia in January 1993. Complete collapse of the dam by overtopping was prevented through quick action of the dam owner by dumping clayey gravel on the lowest sections of the dam crest and opening the bottom outlet of the reservoir, thus efficiently lowering the water level. After the damages were sufficiently established and alternatives for restoration of the dam were evaluated, it was decided to construct a diaphragm wall through the damaged core in the central dam part as the impermeable dam element and to rebuild the central clay core at the dam abutments. Reconstruction works are described.

Nonveiller, E. [Univ. of Zagreb (Croatia). Faculty of Civil Engineering] [Univ. of Zagreb (Croatia). Faculty of Civil Engineering; Rupcic, J. [Univ. of Zagreb (Croatia). Faculty of Civil Engineering] [Univ. of Zagreb (Croatia). Faculty of Civil Engineering; [Elektroprojekt Consulting Engineering, Zagreb (Croatia); Sever, Z. [Elektroprojekt Consulting Engineering, Zagreb (Croatia)] [Elektroprojekt Consulting Engineering, Zagreb (Croatia)

1999-04-01T23:59:59.000Z

134

Radiation damage of a glass-bonded zeolite waste form using ion irradiation.  

SciTech Connect (OSTI)

Glass-bonded zeolite is being considered as a candidate ceramic waste form for storing radioactive isotopes separated from spent nuclear fuel in the electrorefining process. To determine the stability of glass-bonded zeolite under irradiation, transmission electron microscope samples were irradiated using high energy helium, lead, and krypton. The major crystalline phase of the waste form, which retains alkaline and alkaline earth fission products, loses its long range order under both helium and krypton irradiation. The dose at which the long range crystalline structure is lost is about 0.4 dpa for helium and 0.1 dpa for krypton. Because the damage from lead is localized in such a small region of the sample, damage could not be recognized even at a peak damage of 50 dpa. Because the crystalline phase loses its long range structure due to irradiation, the effect on retention capacity needs to be further evaluated.

Allen, T. R.; Storey, B. G.

1997-12-05T23:59:59.000Z

135

Radiation Damage Study in Natural Zircon Using Neutrons Irradiation  

SciTech Connect (OSTI)

Changes of atomic displacements in crystalline structure of natural zircon (ZrSiO{sub 4}) can be studied by using neutron irradiation on the surface of zircon and compared the data from XRD measurements before and after irradiation. The results of neutron irradiation on natural zircon using Pneumatic Transfer System (PTS) at PUSPATI TRIGA Research Reactor in the Malaysian Nuclear Agency are discussed in this work. The reactor produces maximum thermal power output of 1 MWatt and the neutron flux of up to 1x10{sup 13} ncm{sup -2}s{sup -1}. From serial decay processes of uranium and thorium radionuclides in zircon crystalline structure, the emission of alpha particles can produce damage in terms of atomic displacements in zircon. Hence, zircon has been extensively studied as a possible candidate for immobilization of fission products and actinides.

Lwin, Maung Tin Moe; Amin, Yusoff Mohd.; Kassim, Hasan Abu [Department of Physics, University of Malaya, 50603 Kuala Lumpur (Malaysia); Mohamed, Abdul Aziz [Materials Technology Group, Industrial Technology Division, Malaysian Nuclear Agency Bangi, 43000 Kajang, Selangor Darul Ehsan (Malaysia); Karim, Julia Abdul [Reactor Physics Section, Nuclear Power Division, Malaysian Nuclear Agency Bangi, 43000 Kajang, Selangor Darul Ehsan (Malaysia)

2011-03-30T23:59:59.000Z

136

Nuclear scales  

SciTech Connect (OSTI)

Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the {pi}-{gamma} force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

Friar, J.L.

1998-12-01T23:59:59.000Z

137

Assessing United States hurricane damage under different environmental conditions  

E-Print Network [OSTI]

Hurricane activity between 1979 and 2011 was studied to determine damage statistics under different environmental conditions. Hurricanes cause billions of dollars of damage every year in the United States, but damage ...

Maheras, Anastasia Francis

2012-01-01T23:59:59.000Z

138

Beam damage of poly(2-chloroethyl methylacrylate) [PCEMA] films...  

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

evaluating x-ray damage. PCEMA has been shown to be more sensitive to degradation than PVC which has also been used as a damage sensitive material useful for comparison of damage...

139

Analysis of core damage frequency from internal events: Peach Bottom, Unit 2  

SciTech Connect (OSTI)

This document contains the internal event initiated accident sequence analyses for Peach Bottom, Unit 2; one of the reference plants being examined as part of the NUREG-1150 effort by the Nuclear Regulatory Commission. NUREG-1150 will document the risk of a selected group of nuclear power plants. As part of that work, this report contains the overall core damage frequency estimate for Peach Bottom, Unit 2, and the accompanying plant damage state frequencies. Sensitivity and uncertainty analyses provided additional insights regarding the dominant contributors to the Peach Bottom core damage frequency estimate. The mean core damage frequency at Peach Bottom was calculated to be 8.2E-6. Station blackout type accidents (loss of all ac power) were found to dominate the overall results. Anticipated Transient Without Scram accidents were also found to be non-negligible contributors. The numerical results are largely driven by common mode failure probability estimates and to some extent, human error. Because of significant data and analysis uncertainties in these two areas (important, for instance, to the most dominant scenario in this study), it is recommended that the results of the uncertainty and sensitivity analyses be considered before any actions are taken based on this analysis.

Kolaczkowski, A.M.; Lambright, J.A.; Ferrell, W.L.; Cathey, N.G.; Najafi, B.; Harper, F.T.

1986-10-01T23:59:59.000Z

140

Nuclear Physics  

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 Nuclear NavyNuclear Physics

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Nuclear Structure  

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 |NavyNuclear Speed-Dating Nuclear

142

Nuclear Forensics  

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 Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchives Events/NewsYouNuclearNuclear Forensics

143

Formation damage in underbalanced drilling operations  

E-Print Network [OSTI]

Formation damage has long been recognized as a potential source of reduced productivity and injectivity in both horizontal and vertical wells. From the moment that the pay zone is being drilled until the well is put on production, a formation...

Reyes Serpa, Carlos Alberto

2003-01-01T23:59:59.000Z

144

Laser Damage Precursors in Fused Silica  

SciTech Connect (OSTI)

There is a longstanding, and largely unexplained, correlation between the laser damage susceptibility of optical components and both the surface quality of the optics, and the presence of near surface fractures in an optic. In the present work, a combination of acid leaching, acid etching, and confocal time resolved photoluminescence (CTP) microscopy has been used to study laser damage initiation at indentation sites. The combination of localized polishing and variations in indentation loads allows one to isolate and characterize the laser damage susceptibility of densified, plastically flowed and fractured fused silica. The present results suggest that: (1) laser damage initiation and growth are strongly correlated with fracture surfaces, while densified and plastically flowed material is relatively benign, and (2) fracture events result in the formation of an electronically defective rich surface layer which promotes energy transfer from the optical beam to the glass matrix.

Miller, P; Suratwala, T; Bude, J; Laurence, T A; Shen, N; Steele, W A; Feit, M; Menapace, J; Wong, L

2009-11-11T23:59:59.000Z

145

Thin Film Femtosecond Laser Damage Competition  

SciTech Connect (OSTI)

In order to determine the current status of thin film laser resistance within the private, academic, and government sectors, a damage competition was started at the 2008 Boulder Damage Symposium. This damage competition allows a direct comparison of the current state of the art of high laser resistance coatings since they are tested using the same damage test setup and the same protocol. In 2009 a high reflector coating was selected at a wavelength of 786 nm at normal incidence at a pulse length of 180 femtoseconds. A double blind test assured sample and submitter anonymity so only a summary of the results are presented here. In addition to the laser resistance results, details of deposition processes, coating materials and layer count, and spectral results will also be shared.

Stolz, C J; Ristau, D; Turowski, M; Blaschke, H

2009-11-14T23:59:59.000Z

146

Micropatterned cell arrays for detecting DNA damage  

E-Print Network [OSTI]

Numerous agents are capable of interacting with DNA and damaging it. Permanent changes in the DNA structure can be both mutagenic and cytotoxic; therefore, methods to measure the susceptibility of cells to mutations are ...

Mittal, Sukant

2008-01-01T23:59:59.000Z

147

Structural damage detection using frequency response functions  

E-Print Network [OSTI]

.........................90 5.1.2 Case 3: 1 st - 3 rd Story Braces Are Damaged .................................................92 5.1.2.1 All Four Modes Are Used for Damage Detection..........................95 5.1.2.2 The Last Two Modes... for Trial #2 with Hillclimbing #739 .......................................................................................................... 92 Figure 5.8 FRF for the 1 st Floor 1 st - 3 rd Story Braces Are Broken SIMO 12 DOF Symmetric...

Dincal, Selcuk

2006-04-12T23:59:59.000Z

148

Quantitative damage evaluation of localized deep pitting  

SciTech Connect (OSTI)

Localized deep pitting is considered difficult to precisely measure and evaluate using simple techniques and daily-use analysis approaches. A case study was made of carbon steel heat exchangers in a typical fresh cooling water environment that experienced severe pitting. To effectively and precisely evaluate the encountered pitting damage, a simple measurement and analyses approach was devised. In this article, the pitting measurement technique and the damage evaluation approach are presented and discussed in detail.

Al Beed, A.A.; Al Garni, M.A.

2000-04-01T23:59:59.000Z

149

Correlating Radioactive Material to Sea Surface Temperature off the Coast of Japan: The Fukushima Daiichi Nuclear Disaster  

E-Print Network [OSTI]

, causing a loss-of-coolant accident which eventually led to nuclear meltdown. Over the course Daiichi Nuclear Disaster Maya R. Pincus Department of Geology, University of Puerto Rico-Mayagüez e on the island. One of the most devastating results of this was the damage to the Fukushima Daiichi nuclear plant

Gilbes, Fernando

150

Atomic-Scale Simulations of Cascade Overlap and Damage Evolution...  

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

Atomic-Scale Simulations of Cascade Overlap and Damage Evolution in Silicon Carbide. Atomic-Scale Simulations of Cascade Overlap and Damage Evolution in Silicon Carbide. Abstract:...

151

Exemplary Hurricane Damage Cleanup Earns Petroleum Reserve Coveted...  

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

Exemplary Hurricane Damage Cleanup Earns Petroleum Reserve Coveted Environmental Award Exemplary Hurricane Damage Cleanup Earns Petroleum Reserve Coveted Environmental Award April...

152

Nuclear Nonproliferation Programs | ORNL  

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

Nuclear Nonproliferation Programs SHARE Nuclear Nonproliferation Programs image Oak Ridge National Laboratory covers the entire spectrum of nuclear nonproliferation work, from...

153

NUCLEAR PROXIMITY FORCES  

E-Print Network [OSTI]

One might summarize of nuclear potential energy has beendegree of freedom) for the nuclear interaction between anyUniversity of California. Nuclear Proximity Forces 'I< at

Randrup, J.

2011-01-01T23:59:59.000Z

154

Global Nuclear Security  

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

Global Nuclear Security Both DOE and the National Nuclear Security Administration are working to reduce the risk of nuclear proliferation and provide technologies to improve...

155

Simulation of neutron displacement damage in bipolar junction transistors using high-energy heavy ion beams.  

SciTech Connect (OSTI)

Electronic components such as bipolar junction transistors (BJTs) are damaged when they are exposed to radiation and, as a result, their performance can significantly degrade. In certain environments the radiation consists of short, high flux pulses of neutrons. Electronics components have traditionally been tested against short neutron pulses in pulsed nuclear reactors. These reactors are becoming less and less available; many of them were shut down permanently in the past few years. Therefore, new methods using radiation sources other than pulsed nuclear reactors needed to be developed. Neutrons affect semiconductors such as Si by causing atomic displacements of Si atoms. The recoiled Si atom creates a collision cascade which leads to displacements in Si. Since heavy ions create similar cascades in Si we can use them to create similar damage to what neutrons create. This LDRD successfully developed a new technique using easily available particle accelerators to provide an alternative to pulsed nuclear reactors to study the displacement damage and subsequent transient annealing that occurs in various transistor devices and potentially qualify them against radiation effects caused by pulsed neutrons.

Doyle, Barney Lee; Buller, Daniel L.; Hjalmarson, Harold Paul; Fleming, Robert M; Bielejec, Edward Salvador; Vizkelethy, Gyorgy

2006-12-01T23:59:59.000Z

156

Virtual environments for nuclear power plant design  

SciTech Connect (OSTI)

In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP).

Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W. [and others

1996-03-01T23:59:59.000Z

157

Nuclear Science/Nuclear Chemistry  

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 Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchivesNuclear Science/Nuclear Chemistry

158

ANALYSIS OF DAMAGE TO WASTE PACKAGES CAUSED BY SEISMIC EVENTS DURING POST-CLOSURE  

SciTech Connect (OSTI)

This paper presents methodology and results of an analysis of damage due to seismic ground motion for waste packages emplaced in a nuclear waste repository at Yucca Mountain, Nevada. A series of three-dimensional rigid body kinematic simulations of waste packages, pallets, and drip shields subjected to seismic ground motions was performed. The simulations included strings of several waste packages and were used to characterize the number, location, and velocity of impacts that occur during seismic ground motion. Impacts were categorized as either waste package-to-waste package (WP-WP) or waste package-to-pallet (WP-P). In addition, a series of simulations was performed for WP-WP and WP-P impacts using a detailed representation of a single waste package. The detailed simulations were used to determine the amount of damage from individual impacts, and to form a damage catalog, indexed according to the type, angle, location and force/velocity of the impact. Finally, the results from the two analyses were combined to estimate the total damage to a waste package that may occur during an episode of seismic ground motion. This study addressed two waste package types, four levels of peak ground velocity (PGV), and 17 ground motions at each PGV. Selected aspects of waste package degradation, such as effective wall thickness and condition of the internals, were also considered. As expected, increasing the PGV level of the vibratory ground motion increases the damage to the waste packages. Results show that most of the damage is caused by WP-P impacts. TAD-bearing waste packages with intact internals are highly resistant to damage, even at a PGV of 4.07 m/s, which is the highest level analyzed.

Alves, S W; Blair, S C; Carlson, S R; Gerhard, M; Buscheck, T A

2008-05-27T23:59:59.000Z

159

Nuclear Incident Team | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Incident Team | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear...

160

Nuclear Medicine CT Angiography  

E-Print Network [OSTI]

Nuclear Medicine CT Angiography Stress Testing Rotation The Nuclear Medicine/CT angiography. Understand the indications for exercise treadmill testing and specific nuclear cardiology tests, safe use Level 2 proficiency in performing and interpreting cardiac nuclear imaging tests. Progression

Ford, James

Note: This page contains sample records for the topic "nuclear damage contingent" from the National Library of EnergyBeta (NLEBeta).
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161

National Nuclear Security Administration  

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

FROM: SUBJECT: USIUK Memorandum of Understanding between National Nuclear Security Administration's (NNSA) Associate Administrator for Defense Nuclear Security (AADNS)...

162

Fretting Corrosion Damage of Total Hip Prosthesis: Friction Coefficient and Damage Rate Constant Approach  

E-Print Network [OSTI]

1 Fretting Corrosion Damage of Total Hip Prosthesis: Friction Coefficient and Damage Rate Constant Building, University Park 16802 PA USA 4 Chair Professor Center for Research Excellence in Corrosion hip prosthesis. Fretting corrosion tests were conducted with stainless steel and poly (methyl

Boyer, Edmond

163

Nuclear photonics  

SciTech Connect (OSTI)

With the planned new {gamma}-beam facilities like MEGa-ray at LLNL (USA) or ELI-NP at Bucharest (Romania) with 10{sup 13}{gamma}/s and a band width of {Delta}E{gamma}/E{gamma} Almost-Equal-To 10{sup -3}, a new era of {gamma} beams with energies up to 20MeV comes into operation, compared to the present world-leading HI{gamma}S facility at Duke University (USA) with 10{sup 8}{gamma}/s and {Delta}E{gamma}/E{gamma} Almost-Equal-To 3 Dot-Operator 10{sup -2}. In the long run even a seeded quantum FEL for {gamma} beams may become possible, with much higher brilliance and spectral flux. At the same time new exciting possibilities open up for focused {gamma} beams. Here we describe a new experiment at the {gamma} beam of the ILL reactor (Grenoble, France), where we observed for the first time that the index of refraction for {gamma} beams is determined by virtual pair creation. Using a combination of refractive and reflective optics, efficient monochromators for {gamma} beams are being developed. Thus, we have to optimize the total system: the {gamma}-beam facility, the {gamma}-beam optics and {gamma} detectors. We can trade {gamma} intensity for band width, going down to {Delta}E{gamma}/E{gamma} Almost-Equal-To 10{sup -6} and address individual nuclear levels. The term 'nuclear photonics' stresses the importance of nuclear applications. We can address with {gamma}-beams individual nuclear isotopes and not just elements like with X-ray beams. Compared to X rays, {gamma} beams can penetrate much deeper into big samples like radioactive waste barrels, motors or batteries. We can perform tomography and microscopy studies by focusing down to {mu}m resolution using Nuclear Resonance Fluorescence (NRF) for detection with eV resolution and high spatial resolution at the same time. We discuss the dominating M1 and E1 excitations like the scissors mode, two-phonon quadrupole octupole excitations, pygmy dipole excitations or giant dipole excitations under the new facet of applications. We find many new applications in biomedicine, green energy, radioactive waste management or homeland security. Also more brilliant secondary beams of neutrons and positrons can be produced.

Habs, D.; Guenther, M. M.; Jentschel, M.; Thirolf, P. G. [Ludwig-Maximilians-Universitaet Muenchen, D-85748 Garching (Germany); Max Planck Institut fuer Quantenoptik, D-85748 Garching (Germany); Institut Laue-Langevin, F-38042 Grenoble (Germany); Ludwig-Maximilians-Universitaet Muenchen, D-85748 Garching (Germany)

2012-07-09T23:59:59.000Z

164

To be submitted to Continuum Mechanics and Thermodynamics From the onset of damage to rupture: construction of responses with damage  

E-Print Network [OSTI]

To be submitted to Continuum Mechanics and Thermodynamics From the onset of damage to rupture: construction of responses with damage localization for a general class of gradient damage models Kim Pham solutions for the traction problem of an elastic damaging bar. This bar has a softening behavior which obeys

Boyer, Edmond

165

Journal of Nuclear Materials 199 (1993) 221-230 North-Holland  

E-Print Network [OSTI]

Journal of Nuclear Materials 199 (1993) 221-230 North-Holland Neutron displacement damage cross sections foi- Sic * Hanchen Huang and Nasr Ghoniem Mechanical, Aerospace and Nuclear Engineering Department materials is computed on the basis of Bragg's Additivity Rule. A continuous form of the inverse power law

Ghoniem, Nasr M.

166

Coupon Surveillance For Corrosion Monitoring In Nuclear Fuel Basin  

SciTech Connect (OSTI)

Aluminum and stainless steel coupons were put into a nuclear fuel basin to monitor the effect of water chemistry on the corrosion of fuel cladding. These coupons have been monitored for over ten years. The corrosion and pitting data is being used to model the kinetics and estimate the damage that is occurring to the fuel cladding.

Mickalonis, J. I.; Murphy, T. R.; Deible, R.

2012-10-01T23:59:59.000Z

167

Nuclear Waffles  

E-Print Network [OSTI]

The dense neutron-rich matter found in supernovae and neutron stars is expected to form complex nonuniform phases referred to as nuclear pasta. The pasta shapes depend on density, temperature and proton fraction and determine many transport properties in supernovae and neutron star crusts. We use two recently developed hybrid CPU/GPU codes to perform large scale molecular dynamics (MD) simulations with $51200$ and $409600$ nucleons of nuclear pasta. From the output of the MD simulations we characterize the topology and compute two observables, the radial distribution function $g(r)$ and the structure factor $S(q)$, for systems with proton fractions $Y_p=0.10, 0.20, 0.30$ and $0.40$ at about one third of nuclear saturation density and temperatures near $1.0$ MeV. We observe that the two lowest proton fraction systems simulated, $Y_p=0.10$ and $0.20$, equilibrate quickly and form liquid-like structures. Meanwhile, the two higher proton fraction systems, $Y_p=0.30$ and $0.40$, take a longer time to equilibrate and organize themselves in solid-like periodic structures. Furthermore, the $Y_p=0.40$ system is made up of slabs, lasagna phase, interconnected by defects while the $Y_p=0.30$ systems consist of a stack of perforated plates, the nuclear waffle phase. The periodic configurations observed in our MD simulations for proton fractions $Y_p\\ge0.30$ have important consequences for the structure factors $S(q)$ of protons and neutrons, which relate to many transport properties of supernovae and neutron star crust. A detailed study of the waffle phase and how its structure depends on temperature, size of the simulation and the screening length showed that finite-size effects appear to be under control and, also, that the plates in the waffle phase merge at temperatures slightly above $1.0$ MeV and the holes in the plates form an hexagonal lattice at temperatures slightly lower than $1.0$ MeV.

A. S. Schneider; D. K. Berry; C. M. Briggs; M. E. Caplan; C. J. Horowitz

2014-09-08T23:59:59.000Z

168

Nuclear Forensics  

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 of7379583Forensics

169

Nuclear Science  

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 Nuclear

170

Nuclear Nonproliferation,  

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 Nuclear Navy Posted:Sensor

171

Nuclear Astrophysics  

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 Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchives Events/NewsYouNuclear Astrophysics One

172

Density Functional Theory Models for Radiation Damage  

E-Print Network [OSTI]

Density Functional Theory Models for Radiation Damage S.L. Dudarev EURATOM/CCFE Fusion Association, DFT Abstract Density functional theory models developed over the past decade provide unique phenomena. Density functional theory models have effectively created a new paradigm for the scientific

173

Gas condensate damage in hydraulically fractured wells  

E-Print Network [OSTI]

of this research are a step forward in helping to improve the management of gas condensate reservoirs by understanding the mechanics of liquid build-up. It also provides methodology for quantifying the condensate damage that impairs linear flow of gas...

Reza, Rostami Ravari

2004-11-15T23:59:59.000Z

174

The Status of Radiation Damage Experiments  

SciTech Connect (OSTI)

Experiments have been on-going for about two years to determine the effects that radiation damage have on the physical and chemical properties of candidate titanate ceramics for the immobilization of plutonium. We summarize the results of these experiments in this document.

Strachan, Denis M.; Scheele, Randall D.; Icenhower, Jonathan P.; Kozelisky, Anne E.; Sell, Richard L.; Legore, Virginia L.; Schaef, Herbert T.; O'Hara, Matthew J.; Brown, Christopher F.; Buchmiller, William C.

2001-11-20T23:59:59.000Z

175

Nondestructive Damage Detection in General Beams  

E-Print Network [OSTI]

is to provide NDE methodologies that simultaneously identify the location, the extent, and the severity of damage in general beams. By general beams, we mean beyond Euler-Bernoulli beams (i.e. slender beams) to deep beams and stubby beams whose response may...

Dincal, Selcuk

2010-12-08T23:59:59.000Z

176

Security and Use Control of Nuclear Explosives and Nuclear Weapons...  

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

4C, Security and Use Control of Nuclear Explosives and Nuclear Weapons by LtCol Karl Basham Functional areas: Nuclear Explosives, Nuclear Weapons, Security The Order establishes...

177

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

178

Nuclear reactor engineering  

SciTech Connect (OSTI)

Chapters are presented concerning energy from nuclear fission; nuclear reactions and radiations; diffusion and slowing-down of neutrons; principles of reactor analysis; nuclear reactor kinetics and control; energy removal; non-fuel reactor materials; the reactor fuel system; radiation protection and environmental effects; nuclear reactor shielding; nuclear reactor safety; and power reactor systems.

Glasstone, S.; Sesonske, A.

1981-01-01T23:59:59.000Z

179

Accelerated alpha radiation damage in a ceramic waste form, interim results  

SciTech Connect (OSTI)

Interim results are presented on the alpha-decay damage study of a {sup 238}Pu-loaded ceramic waste form (CWF). The waste form was developed to immobilize fission products and transuranic species accumulated from the electrometallurgical treatment of spent nuclear fuel. To evaluate the effects of {alpha}-decay damage on the waste form the {sup 238}Pu-loaded material was analyzed by (1) x-ray diffraction (XRD), (2) microstructure characterization by scanning electron microscopy (SEM) and transmission electron microscopy (TEM) with energy and wavelength dispersive spectroscopy (EDS/WDS) and electron diffraction, (3) bulk density measurements and (4) waste form durability, performed by the product consistency test (PCT). While the predominate phase of plutonium in the CWF, PuO{sub 2}, shows the expected unit cell expansion due to {alpha}-decay damage, currently no significant change has occurred to the macro- or microstructure of the material. The major phase of the waste form is sodalite and contains very little Pu, although the exact amount is unknown. Interestingly, measurement of the sodalite phase unit cell is also showing very slight expansion; again, presumably from {alpha}-decay damage.

Frank, S. M.; Johnson, S. G.; Moschetti, T. L.; O'Holleran, T. P.; Sinkler, W.; Esh, D.; Goff, K. M.

1999-11-11T23:59:59.000Z

180

Continuum-based Multiscale Computational Damage Modeling of Cementitous Composites  

E-Print Network [OSTI]

of ? , and its comparison with experimental results by Kupfer et al. (1969) ...... 32 5.1 Evolution of the damage due to the change of the compressive hardening modulus Q ? for: (a) Exponential damage evolution law in Eq. (2.48) and (b) power damage... evolution law in Eq. (2.52) ............... 71 5.2 Evolution of the damage due to the change of the compressive hardening rate constant b? for: (a) Exponential damage evolution law in Eq. (2.48) and (b) power damage evolution law in Eq. (2...

Kim, Sun-Myung

2011-08-08T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Reactor & Nuclear Systems Publications | ORNL  

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

Nuclear Science Home | Science & Discovery | Nuclear Science | Publications and Reports | Reactor and Nuclear Systems Publications SHARE Reactor and Nuclear Systems Publications...

182

Nuclear Explosive Safety  

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

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, or successor directive, for routine and planned nuclear explosive operations (NEOs).

2015-01-26T23:59:59.000Z

183

Nuclear Explosive Safety  

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

The Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs).

2014-07-10T23:59:59.000Z

184

RELATIVISTIC NUCLEAR COLLISIONS: THEORY  

E-Print Network [OSTI]

Effects in Relativistic Nuclear Collisions", Preprint LBL-Pion Interferometry of Nuclear Collisions. 18.1 M.Gyulassy,was supported by the Office of Nuclear Physics of the U.S.

Gyulassy, M.

2010-01-01T23:59:59.000Z

185

NUCLEAR STRUCTURE DATABASE  

E-Print Network [OSTI]

CALIFORNIA NUCLEAR STRUCTURE DATABASE R. B. Firestone and E.11089 NUCLEAR STRUCTURE DATABASE by R.B. Firestone and E.iii- NUCLEAR STRUCTURE DATABASE R.B Firestone and E. Browne

Firestone, R.B.

2010-01-01T23:59:59.000Z

186

Nuclear Safety (Pennsylvania)  

Broader source: Energy.gov [DOE]

The Nuclear Safety Division conducts a comprehensive nuclear power plant oversight review program of the nine reactors at the five nuclear power sites in Pennsylvania. It also monitors the...

187

Nuclear Fuel Cycle & Vulnerabilities  

SciTech Connect (OSTI)

The objective of safeguards is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection. The safeguards system should be designed to provide credible assurances that there has been no diversion of declared nuclear material and no undeclared nuclear material and activities.

Boyer, Brian D. [Los Alamos National Laboratory

2012-06-18T23:59:59.000Z

188

Nonuniform radiation damage in permanent magnet quadrupoles  

SciTech Connect (OSTI)

We present data that indicate nonuniform magnetization loss due to radiation damage in neodymium-iron-boron Halbach-style permanent magnet quadrupoles. The proton radiography (pRad) facility at Los Alamos uses permanent-magnet quadrupoles for magnifying lenses, and a system recently commissioned at GSI-Darmsdadt uses permanent magnets for its primary lenses. Large fluences of spallation neutrons can be produced in close proximity to these magnets when the proton beam is, intentionally or unintentionally, directed into the tungsten beam collimators; imaging experiments at LANLs pRad have shown image degradation with these magnetic lenses at proton beam doses lower than those expected to cause damage through radiation-induced reduction of the quadrupole strength alone. We have observed preferential degradation in portions of the permanent magnet quadrupole where the field intensity is highest, resulting in increased high-order multipole components.

Danly, C. R.; Merrill, F. E.; Barlow, D.; Mariam, F. G. [Los Alamos National Laboratory, Los Alamos, New Mexico 87544 (United States)

2014-08-15T23:59:59.000Z

189

Evaluation of radiation damage using nonlinear ultrasound  

SciTech Connect (OSTI)

Nonlinear ultrasound was used to monitor radiation damage in two reactor pressure vessel (RPV) steels. The microstructural changes associated with radiation damage include changes in dislocation density and the formation of precipitates, and nonlinear ultrasonic waves are known to be sensitive to such changes. Six samples each of two different RPV steels were previously irradiated in the Rheinsberg power reactor to two fluence levels, up to 10{sup 20} n/cm{sup 2} (E > 1 MeV). Longitudinal waves were used to measure the acoustic nonlinearity in these samples, and the results show a clear increase in the measured acoustic nonlinearity from the unirradiated state to the medium dose, and then a decrease from medium dose to high dose.

Matlack, K. H. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States); Wall, J. J. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States); Electric Power Research Institute, Charlotte, North Carolina 28262 (United States); Kim, J.-Y. [School of Civil and Environmental Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States); Qu, J. [Department of Civil and Environmental Engineering, Northwestern University, Evanston, Illinois 60208 (United States); Jacobs, L. J. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States); School of Civil and Environmental Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States); Viehrig, H.-W. [Department of Structural Materials, Helmholtz Zentrum Dresden-Rossendorf, Institute of Ion-Beam Physics and Materials Research, P.O. Box 510119, 01314 Dresden (Germany)

2012-03-01T23:59:59.000Z

190

Carbon Fiber Damage in Particle Beam  

E-Print Network [OSTI]

Carbon fibers are commonly used as moving targets in beam wire scanners. The heating of the fiber due to energy loss of the particles travelling through is simulated with Geant4. The heating induced by the beam electromagnetic field is estimated with ANSYS. The heat transfer and sublimation processes are modelled. Due to the model nonlinearity, a numerical approach based on discretization of the wire movement is used to solve it for particular beams. Radiation damage to the fiber is estimated with SRIM. The model is tested with available SPS and LEP data and a dedicated damage test on the SPS beam is performed followed by a post-mortem analysis of the wire remnants. Predictions for the LHC beams are made.

Dehning, B; Kroyer, T; Meyer, M; Sapinski, M

2011-01-01T23:59:59.000Z

191

Nuclear Safeguards | 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...

192

Nuclear Forensics | 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...

193

Cellular responses to environmental DNA damage  

SciTech Connect (OSTI)

This volume contains the proceedings of the conference entitled Cellular Responses to Environmental DNA Damage held in Banff,Alberta December 1--6, 1991. The conference addresses various aspects of DNA repair in sessions titled DNA repair; Basic Mechanisms; Lesions; Systems; Inducible Responses; Mutagenesis; Human Population Response Heterogeneity; Intragenomic DNA Repair Heterogeneity; DNA Repair Gene Cloning; Aging; Human Genetic Disease; and Carcinogenesis. Individual papers are represented as abstracts of about one page in length.

Not Available

1994-08-01T23:59:59.000Z

194

Damage analysis in asphalt concrete mixtures based on parameter relationships  

E-Print Network [OSTI]

Asphalt pavements experience damage due to traffic loading under various environmental conditions. Damage can be caused by viscopl microcracks, fracture due to fatigue cracking, or fracture due to thermal cracking. Asphalt pavements have...

Song, Injun

2004-11-15T23:59:59.000Z

195

The biological and metabolic fates of endogenous DNA damage products  

E-Print Network [OSTI]

DNA and other biomolecules are subjected to damaging chemical reactions during normal physiological processes and in states of pathophysiology caused by endogenous and exogenous mechanisms. In DNA, this damage affects ...

Chan, Wan Simon

196

Single cell trapping and DNA damage analysis using microwell arrays  

E-Print Network [OSTI]

With a direct link to cancer, aging, and heritable diseases as well as a critical role in cancer treatment, the importance of DNA damage is well-established. The intense interest in DNA damage in applications ranging from ...

Wood, David

197

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...

198

Nuclear weapons modernizations  

SciTech Connect (OSTI)

This article reviews the nuclear weapons modernization programs underway in the world's nine nuclear weapons states. It concludes that despite significant reductions in overall weapons inventories since the end of the Cold War, the pace of reductions is slowing - four of the nuclear weapons states are even increasing their arsenals, and all the nuclear weapons states are busy modernizing their remaining arsenals in what appears to be a dynamic and counterproductive nuclear competition. The author questions whether perpetual modernization combined with no specific plan for the elimination of nuclear weapons is consistent with the nuclear Non-Proliferation Treaty and concludes that new limits on nuclear modernizations are needed.

Kristensen, Hans M. [Federation of American Scientists, Washington, DC (United States)

2014-05-09T23:59:59.000Z

199

Nuclear Energy Advisory Committee  

Broader source: Energy.gov [DOE]

The Nuclear Energy Advisory Committee (NEAC), formerly the Nuclear Energy Research Advisory Committee (NERAC), was established on October 1, 1998, to provide independent advice to the Office of...

200

National Nuclear Security Administration  

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

the safety, security and effectiveness of the nuclear deterrent without underground nuclear testing, consistent with the principles of the Stockpile Management Program...

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Nuclear Waste Reduction  

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

Nuclear Waste Reduction Pyroprocessing is a promising technology for recycling used nuclear fuel and improving the associated waste management options. The process...

202

Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay  

E-Print Network [OSTI]

Security of the National Nuclear Security Administration, USof Energys National Nuclear Security Administration (NNSA)

Quiter, Brian

2012-01-01T23:59:59.000Z

203

Measurement of Radiation Damage on Silica Aerogel Cerenkov Radiator  

E-Print Network [OSTI]

We measured the radiation damage on silica aerogel Cerenkov radiators originally developed for the B-factory experiment at KEK. Refractive index of the aerogel samples ranged from 1.012 to 1.028. The samples were irradiated up to 9.8 MRad of equivalent dose. Measurements of transmittance and refractive index were carried out and these samples were found to be radiation hard. Deteriorations in transparency and changes of refractive index were observed to be less than 1.3% and 0.001 at 90% confidence level, respectively. Prospects of using aerogels under high-radiation environment are discussed. 1 Introduction Silica aerogels(aerogels) are a colloidal form of glass, in which globules of silica are connected in three dimensional networks with siloxan bonds. They are solid, very light, transparent and their refractive index can be controlled in the production process. Many high energy and nuclear physics experiments have used aerogels instead of pressurized gas for their Cerenkov coun...

Belle Preprint; Sahu Wang; M. Z. Wang; R. Suda; R. Enomoto; K. C. Peng; C. H. Wang; I. Adachi; M. Amami

204

Nuclear reactor  

DOE Patents [OSTI]

A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

Thomson, Wallace B. (Severna Park, MD)

2004-03-16T23:59:59.000Z

205

A BAYESIAN PROBABILISTIC APPROACH TO DAMAGE DETECTION FOR CIVIL  

E-Print Network [OSTI]

damage or other environmental e ects. Results based on the eld vibration test of a bridge indicate on the vibration parameters can be di erentiated from other environmental e ects or potential structural damage. vA BAYESIAN PROBABILISTIC APPROACH TO DAMAGE DETECTION FOR CIVIL STRUCTURES a dissertation submitted

Stanford University

206

A damage mechanics approach to life prediction for a salt structure  

SciTech Connect (OSTI)

Excavated rooms in natural bedded salt formations are being considered for use as repositories for nuclear waste. It is presumed that deformation of the rooms by creep will lead to loss of structural integrity and affect room life history and seal efficiency. At projected repository temperatures, two possible fracture mechanisms in salt are creep-induced microcracking in triaxial compression and cleavage in tension. Thus, an accurate prediction of room life and seal degradation requires a reliable description of the creep and damage processes. While several constitutive models that treat either creep or fracture in salt are available in the literature, very few models have considered creep and damage in a coupled manner. Previously, Munson and Dawson formulated a set of creep equations for salt based on the consideration of dislocation mechanisms in the creep process. This set of creep equations has been generalized to include continuum, isotropic damage as a fully coupled variable in the response equation. The extended model has been referred to as the Multimechanism Deformation Coupled Fracture (MDCF) model. A set of material constants for the creep and damage terms was deduced based on test data for both clean and argillaceous salt. In this paper, the use of the MDCF model for establishing the failure criteria and for analyzing the creep response of a salt structure is demonstrated. The paper is divided into three parts. A summary of the MDCF model is presented first, which is followed by an evaluation of the MDCF model against laboratory data. Finally, finite-element calculations of the creep and damage response of a salt structure are presented and compared against in-situ field measurements.

Chan, K.S.; Bodner, S.R. [Southwest Research Inst., San Antonio, TX (United States); DeVries, K.L.; Fossum, A.F. [RE/SPEC, Inc., Rapid City, SD (United States); Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States)

1995-03-01T23:59:59.000Z

207

The Joys of Nuclear Engineering  

SciTech Connect (OSTI)

Nuclear fuels researcher Jon Carmack talks about the satisfactions of a career in nuclear engineering.

Jon Carmack

2009-10-02T23:59:59.000Z

208

The Joys of Nuclear Engineering  

ScienceCinema (OSTI)

Nuclear fuels researcher Jon Carmack talks about the satisfactions of a career in nuclear engineering.

Jon Carmack

2010-01-08T23:59:59.000Z

209

Cytogenetic status and oxidative DNA-damage induced by atorvastatin in human peripheral blood lymphocytes: Standard and Fpg-modified comet assay  

SciTech Connect (OSTI)

To investigate the genotoxic potential of atorvastatin on human lymphocytes in vitro standard comet assay was used in the evaluation of basal DNA damage and to investigate possible oxidative DNA damage produced by reactive oxygen species (ROS) Fpg-modified version of comet assay was also conducted. In addition to these techniques the new criteria for scoring micronucleus test were applied for more complete detection of baseline damage in binuclear lymphocytes exposed to atorvastatin 80 mg/day in different time periods by virtue of measuring the frequency of micronuclei, nucleoplasmic bridges and nuclear buds. All parameters obtained with the standard comet assay and Fpg-modified comet assay were significantly higher in the treated than in control lymphocytes. The Fpg-modified comet assay showed a significantly greater tail length, tail intensity, and tail moment in all treated lymphocytes than did the standard comet assay, which suggests that oxidative stress is likely to be responsible for DNA damage. DNA damage detected by the standard comet assay indicates that some other mechanism is also involved. In addition to the comet assay, a total number of micronuclei, nucleoplasmic bridges and nuclear buds were significantly higher in the exposed than in controlled lymphocytes. Regression analyses showed a positive correlation between the results obtained by the comet (Fpg-modified and standard) and micronucleus assay. Overall, the study demonstrated that atorvastatin in its highest dose is capable of producing damage on the level of DNA molecule and cell.

Gajski, Goran [Institute for Medical Research and Occupational Health, Mutagenesis Unit, 10000 Zagreb (Croatia)], E-mail: ggajski@imi.hr; Garaj-Vrhovac, Vera [Institute for Medical Research and Occupational Health, Mutagenesis Unit, 10000 Zagreb (Croatia); Orescanin, Visnja [Ruder Boskovic Institute, 10000 Zagreb (Croatia)

2008-08-15T23:59:59.000Z

210

Mechanical Damage from Cavitation in High Intensity Focused Ultrasound Accelerated Thrombolysis  

E-Print Network [OSTI]

for Mechanical Damage . . . . . . . . . . . . . . . .3.3.3 Connection to Mechanical Damage . . . . . . 3.41.2.5 Assessing mechanical damage . . 1.3 Bubble

Weiss, Hope

2012-01-01T23:59:59.000Z

211

Delay-active damage versus non-local enhancement for anisotropic damage dynamics computations with alternated loading  

E-Print Network [OSTI]

of anisotropic visco-damage, by introducing a material strain rate effect in the cases of positive hydro- static: anisotropic damage, concrete, non-local, visco-damage, micro-cracks closure Email address: desmorat such as concrete are mainly governed by the nucleation and the propagation of micro-cracks. Present within

212

Advanced nuclear fuel  

ScienceCinema (OSTI)

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-15T23:59:59.000Z

213

Advanced nuclear fuel  

SciTech Connect (OSTI)

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-14T23:59:59.000Z

214

Focus Article Nuclear winter  

E-Print Network [OSTI]

the climatic effects of nuclear war. Smoke from the fires started by nuclear weapons, especially the black in recorded human history. Although the number of nuclear weapons in the world has fallen from 70,000 at its and Russia could still produce nuclear winter. This theory cannot be tested in the real world. However

Robock, Alan

215

INSTRUCTIONS FOR SUBMITTING NUCLEAR  

E-Print Network [OSTI]

. Decommissioning 13 I. Performance 13 J. Nuclear Fuel 14 K. Nuclear Insurance 14 L. Relicensing or Plant RetirementCALIFORNIA ENERGY COMMISSION INSTRUCTIONS FOR SUBMITTING NUCLEAR POWER PLANT-RELATED DATA of Submitted Data 3 NUCLEAR POWER PLANT DATA REQUESTS 6 A. Environmental Impacts 6 B. Spent Fuel Generation 8 C

216

Nuclear Science & Engineering  

E-Print Network [OSTI]

. 1 Nuclear Science & Engineering Nuclear Energy Present and Future Ian H. Hutchinson Head, Department of Nuclear Science and Engineering CoPrincipal, Alcator Tokamak Project, Plasma Science and Fusion Science & Engineering Nuclear Power Plants Worldwide · US: 103 plants in operation, none under

217

Ion-induced nuclear radiotherapy  

DOE Patents [OSTI]

Ion-induced Nuclear Radiotherapy (INRT) is a technique for conducting radiosurgery and radiotherapy with a very high degree of control over the spatial extent of the irradiated volume and the delivered dose. Based upon the concept that low energy, ion induced atomic and nuclear reactions can be used to produce highly energetic reaction products at the site of a tumor, the INRT technique is implemented through the use of a conduit-needle or tube which conducts a low energy ion beam to a position above or within the intended treatment area. At the end of the conduit-needle or tube is a specially fabricated target which, only when struck by the ion beam, acts as a source of energetic radiation products. The inherent limitations in the energy, and therefore range, of the resulting reaction products limits the spatial extent of irradiation to a pre-defined volume about the point of reaction. Furthermore, since no damage is done to tissue outside this irradiated volume, the delivered dose may be made arbitrarily large. INRT may be used both as a point-source of radiation at the site of a small tumor, or as a topical bath of radiation to broad areas of diseased tissue.

Horn, Kevin M. (Albuquerque, NM); Doyle, Barney L. (Albuquerque, NM)

1996-01-01T23:59:59.000Z

218

Ion-induced nuclear radiotherapy  

DOE Patents [OSTI]

Ion-induced Nuclear Radiotherapy (INRT) is a technique for conducting radiosurgery and radiotherapy with a very high degree of control over the spatial extent of the irradiated volume and the delivered dose. Based upon the concept that low energy, ion induced atomic and nuclear reactions can be used to produce highly energetic reaction products at the site of a tumor, the INRT technique is implemented through the use of a conduit-needle or tube which conducts a low energy ion beam to a position above or within the intended treatment area. At the end of the conduit-needle or tube is a specially fabricated target which, only when struck by the ion beam, acts as a source of energetic radiation products. The inherent limitations in the energy, and therefore range, of the resulting reaction products limits the spatial extent of irradiation to a pre-defined volume about the point of reaction. Furthermore, since no damage is done to tissue outside this irradiated volume, the delivered dose may be made arbitrarily large. INRT may be used both as a point-source of radiation at the site of a small tumor, or as a topical bath of radiation to broad areas of diseased tissue. 25 figs.

Horn, K.M.; Doyle, B.L.

1996-08-20T23:59:59.000Z

219

Damage of MEMS thermal actuators heated by laser irradiation.  

SciTech Connect (OSTI)

Optical actuation of microelectromechanical systems (MEMS) is advantageous for applications for which electrical isolation is desired. Thirty-two polycrystalline silicon opto-thermal actuators, optically-powered MEMS thermal actuators, were designed, fabricated, and tested. The design of the opto-thermal actuators consists of a target for laser illumination suspended between angled legs that expand when heated, providing the displacement and force output. While the amount of displacement observed for the opto-thermal actuators was fairly uniform for the actuators, the amount of damage resulting from the laser heating ranged from essentially no damage to significant amounts of damage on the target. The likelihood of damage depended on the target design with two of the four target designs being more susceptible to damage. Failure analysis of damaged targets revealed the extent and depth of the damage.

Walraven, Jeremy Allen; Klody, Kelly Anne; Sackos, John T.; Phinney, Leslie Mary

2004-11-01T23:59:59.000Z

220

Damage of MEMS thermal actuators heated by laser irradiation.  

SciTech Connect (OSTI)

Optical actuation of microelectromechanical systems (MEMS) is advantageous for applications for which electrical isolation is desired. Thirty-two polycrystalline silicon opto-thermal actuators, optically-powered MEMS thermal actuators, were designed, fabricated, and tested. The design of the opto-thermal actuators consists of a target for laser illumination suspended between angled legs that expand when heated, providing the displacement and force output. While the amount of displacement observed for the opto-thermal actuators was fairly uniform for the actuators, the amount of damage resulting from the laser heating ranged from essentially no damage to significant amounts of damage on the target. The likelihood of damage depended on the target design with two of the four target designs being more susceptible to damage. Failure analysis of damaged targets revealed the extent and depth of the damage.

Walraven, Jeremy Allen; Klody, Kelly Anne; Sackos, John T.; Phinney, Leslie Mary

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Survey of four damage models for concrete.  

SciTech Connect (OSTI)

Four conventional damage plasticity models for concrete, the Karagozian and Case model (K&C), the Riedel-Hiermaier-Thoma model (RHT), the Brannon-Fossum model (BF1), and the Continuous Surface Cap Model (CSCM) are compared. The K&C and RHT models have been used in commercial finite element programs many years, whereas the BF1 and CSCM models are relatively new. All four models are essentially isotropic plasticity models for which 'plasticity' is regarded as any form of inelasticity. All of the models support nonlinear elasticity, but with different formulations. All four models employ three shear strength surfaces. The 'yield surface' bounds an evolving set of elastically obtainable stress states. The 'limit surface' bounds stress states that can be reached by any means (elastic or plastic). To model softening, it is recognized that some stress states might be reached once, but, because of irreversible damage, might not be achievable again. In other words, softening is the process of collapse of the limit surface, ultimately down to a final 'residual surface' for fully failed material. The four models being compared differ in their softening evolution equations, as well as in their equations used to degrade the elastic stiffness. For all four models, the strength surfaces are cast in stress space. For all four models, it is recognized that scale effects are important for softening, but the models differ significantly in their approaches. The K&C documentation, for example, mentions that a particular material parameter affecting the damage evolution rate must be set by the user according to the mesh size to preserve energy to failure. Similarly, the BF1 model presumes that all material parameters are set to values appropriate to the scale of the element, and automated assignment of scale-appropriate values is available only through an enhanced implementation of BF1 (called BFS) that regards scale effects to be coupled to statistical variability of material properties. The RHT model appears to similarly support optional uncertainty and automated settings for scale-dependent material parameters. The K&C, RHT, and CSCM models support rate dependence by allowing the strength to be a function of strain rate, whereas the BF1 model uses Duvaut-Lion viscoplasticity theory to give a smoother prediction of transient effects. During softening, all four models require a certain amount of strain to develop before allowing significant damage accumulation. For the K&C, RHT, and CSCM models, the strain-to-failure is tied to fracture energy release, whereas a similar effect is achieved indirectly in the BF1 model by a time-based criterion that is tied to crack propagation speed.

Leelavanichkul, Seubpong (University of Utah, Salt Lake City, UT); Brannon, Rebecca Moss (University of Utah, Salt Lake City, UT)

2009-08-01T23:59:59.000Z

222

Minimizing radiation damage in nonlinear optical crystals  

DOE Patents [OSTI]

Methods are disclosed for minimizing laser induced damage to nonlinear crystals, such as KTP crystals, involving various means for electrically grounding the crystals in order to diffuse electrical discharges within the crystals caused by the incident laser beam. In certain embodiments, electrically conductive material is deposited onto or into surfaces of the nonlinear crystals and the electrically conductive surfaces are connected to an electrical ground. To minimize electrical discharges on crystal surfaces that are not covered by the grounded electrically conductive material, a vacuum may be created around the nonlinear crystal.

Cooke, D. Wayne (Santa Fe, NM); Bennett, Bryan L. (Los Alamos, NM); Cockroft, Nigel J. (Santa Fe, NM)

1998-01-01T23:59:59.000Z

223

Minimizing radiation damage in nonlinear optical crystals  

DOE Patents [OSTI]

Methods are disclosed for minimizing laser induced damage to nonlinear crystals, such as KTP crystals, involving various means for electrically grounding the crystals in order to diffuse electrical discharges within the crystals caused by the incident laser beam. In certain embodiments, electrically conductive material is deposited onto or into surfaces of the nonlinear crystals and the electrically conductive surfaces are connected to an electrical ground. To minimize electrical discharges on crystal surfaces that are not covered by the grounded electrically conductive material, a vacuum may be created around the nonlinear crystal. 5 figs.

Cooke, D.W.; Bennett, B.L.; Cockroft, N.J.

1998-09-08T23:59:59.000Z

224

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

225

Isotope Development & Production | Nuclear Science | ORNL  

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

Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery |...

226

Nuclear Structure Aspects in Nuclear Astrophysics  

SciTech Connect (OSTI)

Nuclear Astrophysics as a broad and diverse field of study can be viewed as a magnifier of the impact of microscopic processes on the evolution of macroscopic events. One of the primary goals in Nuclear Astrophysics is the understanding of the nucleosynthesis processes that take place in the cosmos and the simulation of the correlated stellar and explosive burning scenarios. These simulations are strongly dependent on the input from Nuclear Physics which sets the time scale for all stellar dynamic processes--from giga-years of stellar evolution to milliseconds of stellar explosions--and provides the basis for most of the signatures that we have for the interpretation of these events--from stellar luminosities, elemental and isotopic abundances to neutrino flux from distant supernovae. The Nuclear Physics input comes through nuclear structure, low energy reaction rates, nuclear masses, and decay rates. There is a common perception that low energy reaction rates are the most important component of the required nuclear physics input; however, in this article we take a broader approach and present an overview of the close correlation between various nuclear structure aspects and their impact on nuclear astrophysics. We discuss the interplay between the weak and the strong forces on stellar time scales due to the limitations they provide for the evolution of slow and rapid burning processes. The effects of shell structure in nuclei on stellar burning processes as well as the impact of clustering in nuclei is outlined. Furthermore we illustrate the effects of the various nuclear structure aspects on the major nucleosynthesis processes that have been identified in the last few decades. We summarize and provide a coherent overview of the impact of all aspects of nuclear structure on nuclear astrophysics.

Smith, Michael Scott [ORNL

2006-12-01T23:59:59.000Z

227

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

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

Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

228

Tennessee Nuclear Profile - Watts Bar Nuclear Plant  

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

Watts Bar Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

229

Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station  

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

Pilgrim Nuclear Power Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer cpacity factor (percent)","Type","Commercial operation date","License...

230

Arkansas Nuclear Profile - Arkansas Nuclear One  

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

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

231

Of Disasters and Dragon Kings: A Statistical Analysis of Nuclear Power Incidents & Accidents  

E-Print Network [OSTI]

We provide, and perform a risk theoretic statistical analysis of, a dataset that is 75 percent larger than the previous best dataset on nuclear incidents and accidents, comparing three measures of severity: INES (International Nuclear Event Scale), radiation released, and damage dollar losses. The annual rate of nuclear accidents, with size above 20 Million US$, per plant, decreased from the 1950s until dropping significantly after Chernobyl (April, 1986). The rate is now roughly stable at 0.002 to 0.003, i.e., around 1 event per year across the current fleet. The distribution of damage values changed after Three Mile Island (TMI; March, 1979), where moderate damages were suppressed but the tail became very heavy, being described by a Pareto distribution with tail index 0.55. Further, there is a runaway disaster regime, associated with the "dragon-king" phenomenon, amplifying the risk of extreme damage. In fact, the damage of the largest event (Fukushima; March, 2011) is equal to 60 percent of the total damag...

Wheatley, Spencer; Sornette, Didier

2015-01-01T23:59:59.000Z

232

A damage mechanics based approach to structural deterioration and reliability  

SciTech Connect (OSTI)

Structural deterioration often occurs without perceptible manifestation. Continuum damage mechanics defines structural damage in terms of the material microstructure, and relates the damage variable to the macroscopic strength or stiffness of the structure. This enables one to predict the state of damage prior to the initiation of a macroscopic flaw, and allows one to estimate residual strength/service life of an existing structure. The accumulation of damage is a dissipative process that is governed by the laws of thermodynamics. Partial differential equations for damage growth in terms of the Helmholtz free energy are derived from fundamental thermodynamical conditions. Closed-form solutions to the equations are obtained under uniaxial loading for ductile deformation damage as a function of plastic strain, for creep damage as a function of time, and for fatigue damage as function of number of cycles. The proposed damage growth model is extended into the stochastic domain by considering fluctuations in the free energy, and closed-form solutions of the resulting stochastic differential equation are obtained in each of the three cases mentioned above. A reliability analysis of a ring-stiffened cylindrical steel shell subjected to corrosion, accidental pressure, and temperature is performed.

Bhattcharya, B.; Ellingwood, B. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

1998-02-01T23:59:59.000Z

233

Dynamics of nuclear envelope and nuclear pore complex formation  

E-Print Network [OSTI]

Limited expression of nuclear pore membrane glycoprotein 210suggests cell-type specific nuclear pores in metazoans. Expand Dultz, E. (2008). Nuclear pore complex assembly through

Anderson, Daniel J.

2008-01-01T23:59:59.000Z

234

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network [OSTI]

Organizations, accidents, and nuclear weapons. Princeton,the likelihood of a nuclear accident (Sagan 1993, 1995). potential for a nuclear accident. Yet it seems implausible

Kroenig, Matthew

2006-01-01T23:59:59.000Z

235

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network [OSTI]

nature of the nuclear recipients security environment. ThisKeywords: Nuclear weapons proliferation; security; securitynature of the nuclear recipients security environment. This

Kroenig, Matthew

2006-01-01T23:59:59.000Z

236

Precursors to potential severe core damage accidents: 1994, a status report. Volume 22: Appendix I  

SciTech Connect (OSTI)

Nine operational events that affected eleven commercial light-water reactors (LWRs) during 1994 and that are considered to be precursors to potential severe core damage are described. All these events had conditional probabilities of subsequent severe core damage greater than or equal to 1.0 {times} 10{sup {minus}6}. These events were identified by computer-screening the 1994 licensee event reports from commercial LWRs to identify those that could be potential precursors. Candidate precursors were then selected and evaluated in a process similar to that used in previous assessments. Selected events underwent engineering evaluation that identified, analyzed, and documented the precursors. Other events designated by the Nuclear Regulatory Commission (NRC) also underwent a similar evaluation. Finally, documented precursors were submitted for review by licensees and NRC headquarters and regional offices to ensure that the plant design and its response to the precursor were correctly characterized. This study is a continuation of earlier work, which evaluated 1969--1981 and 1984--1993 events. The report discusses the general rationale for this study, the selection and documentation of events as precursors, and the estimation of conditional probabilities of subsequent severe core damage for events. This document is bound in two volumes: Vol. 21 contains the main report and Appendices A--H; Vol. 22 contains Appendix 1.

Belles, R.J.; Cletcher, J.W.; Copinger, D.A.; Vanden Heuvel, L.N. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States); Dolan, B.W.; Minarick, J.W. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States); [Science Applications International Corp., Oak Ridge, TN (United States)

1995-12-01T23:59:59.000Z

237

Radiation damage characterization in reactor pressure vessel steels with nonlinear ultrasound  

SciTech Connect (OSTI)

Nuclear generation currently accounts for roughly 20% of the US baseload power generation. Yet, many US nuclear plants are entering their first period of life extension and older plants are currently undergoing assessment of technical basis to operate beyond 60 years. This means that critical components, such as the reactor pressure vessel (RPV), will be exposed to higher levels of radiation than they were originally intended to withstand. Radiation damage in reactor pressure vessel steels causes microstructural changes such as vacancy clusters, precipitates, dislocations, and interstitial loops that leave the material in an embrittled state. The development of a nondestructive evaluation technique to characterize the effect of radiation exposure on the properties of the RPV would allow estimation of the remaining integrity of the RPV with time. Recent research has shown that nonlinear ultrasound is sensitive to radiation damage. The physical effect monitored by nonlinear ultrasonic techniques is the generation of higher harmonic frequencies in an initially monochromatic ultrasonic wave, arising from the interaction of the ultrasonic wave with microstructural features such as dislocations, precipitates, and their combinations. Current findings relating the measured acoustic nonlinearity parameter to increasing levels of neutron fluence for different representative RPV materials are presented.

Matlack, K. H. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 (United States); Kim, J.-Y. [School of Civil and Environmental Engineering, Georgia Institute of Technology, Atlanta, GA 30332 (United States); Wall, J. J. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 and Nuclear Sector, The Electric Power Research Institute, Charlotte, NC 28262 (United States); Qu, J. [Department of Civil and Environmental Engineering, Northwestern University, Evanston, IL 60208 (United States); Jacobs, L. J. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 and School of Civil and Environmental Engineering, Georgia Institute of Technology, Atlanta, GA 30332 (United States)

2014-02-18T23:59:59.000Z

238

Sandia National Laboratories: mitigate turbine damage  

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 the1developmentturbine bladelifetime is themicrodesignmicrosystems-enabledloss ofturbine

239

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

240

Nuclear Safety Research and Development...  

Energy Savers [EERE]

Nuclear Safety Research and Development Proposal Review and Prioritization Process and Criteria Nuclear Safety Research and Development Program Office of Nuclear Safety Office of...

Note: This page contains sample records for the topic "nuclear damage contingent" 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

What is spent nuclear fuel?  

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

What is Spent Nuclear Fuel? Spent nuclear fuel (SNF) is irradiated fuel or targets containing uranium, plutonium, or thorium that is permanently withdrawn from a nuclear reactor or...

242

Is Nuclear Energy the Solution?  

E-Print Network [OSTI]

009-0270-y Is Nuclear Energy the Solution? Milton H. Saier &in the last 50 years, nuclear energy subsidies have totaledadministration, the Global Nuclear Energy Partnership (GNEP)

Saier, Milton H.; Trevors, Jack T.

2010-01-01T23:59:59.000Z

243

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

244

Nuclear & Radiological Activity Center (NRAC)  

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

Nuclear & Radiological Activity Center (NRAC) Where nuclear research and deployment capabilities come together to solve nuclear nonproliferation challenges. Skip Navigation Links...

245

Damage-induced nonassociated inelastic flow in rock salt  

SciTech Connect (OSTI)

The multi-mechanism deformation coupled fracture model recently developed by CHAN, et al. (1992), for describing time-dependent, pressure-sensitive inelastic flow and damage evolution in crystalline solids was evaluated against triaxial creep experiments on rock salt. Guided by experimental observations, the kinetic equation and the flow law for damage-induced inelastic flow in the model were modified to account for the development of damage and inelastic dilatation in the transient creep regime. The revised model was then utilized to obtain the creep response and damage evolution in rock salt as a function of confining pressure and stress difference. Comparison between model calculation and experiment revealed that damage-induced inelastic flow is nonassociated, dilatational, and contributes significantly to the macroscopic strain rate observed in rock salt deformed at low confining pressures. The inelastic strain rate and volumetric strain due to damage decrease with increasing confining pressures, and all are suppressed at sufficiently high confining pressures.

Chan, K.S.; Bodner, S.R. [Southwest Research Inst., San Antonio, TX (United States); Brodsky, N.S.; Fossum, A.F. [RE/SPEC, Inc., Rapid City, SD (United States); Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States)

1993-06-01T23:59:59.000Z

246

Climate Change, Nuclear Power and Nuclear  

E-Print Network [OSTI]

Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters Rob Goldston MIT IAP plays a large role in replacing coal red plants. al hydro electricity options penetrate in the climate way across scenarios, showing a slight severe climate targets. In Industry, the climate target has

247

Damage detection in initially nonlinear systems  

SciTech Connect (OSTI)

The primary goal of Structural Health Monitoring (SHM) is to detect structural anomalies before they reach a critical level. Because of the potential life-safety and economic benefits, SHM has been widely studied over the past decade. In recent years there has been an effort to provide solid mathematical and physical underpinnings for these methods; however, most focus on systems that behave linearly in their undamaged state - a condition that often does not hold in complex 'real world' systems and systems for which monitoring begins mid-lifecycle. In this work, we highlight the inadequacy of linear-based methodology in handling initially nonlinear systems. We then show how the recently developed autoregressive support vector machine (AR-SVM) approach to time series modeling can be used for detecting damage in a system that exhibits initially nonlinear response. This process is applied to data acquired from a structure with induced nonlinearity tested in a laboratory environment.

Bornn, Luke [Los Alamos National Laboratory; Farrar, Charles [Los Alamos National Laboratory; Park, Gyuhae [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

248

Radiation Damage in Polarized Ammonia Solids  

E-Print Network [OSTI]

Solid NH3 and ND3 provide a highly polarizable, radiation resistant source of polarized protons and deuterons and have been used extensively in high luminosity experiments investigating the spin structure of the nucleon. Over the past twenty years, the UVA polarized target group has been instrumental in producing and polarizing much of the material used in these studies, and many practical considerations have been learned in this time. In this discussion, we analyze the polarization performance of the solid ammonia targets used during the recent JLab Eg4 run. Topics include the rate of polarization decay with accumulated charge, the annealing procedure for radiation damaged targets to recover polarization, and the radiation induced change in optimum microwave frequency used to polarize the sample. We also discuss the success we have had in implementing frequency modulation of the polarizing microwave frequency.

K. Slifer

2007-11-28T23:59:59.000Z

249

Beryllium - A Unique Material in Nuclear Applications  

SciTech Connect (OSTI)

Beryllium, due to its unique combination of structural, chemical, atomic number, and neutron absorption cross section characteristics, has been used successfully as a neutron reflector for three generations of nuclear test reactors at the Idaho National Engineering and Environmental Laboratory (INEEL). The Advanced Test Reactor (ATR), the largest test reactor in the world, has utilized five successive beryllium neutron reflectors and is scheduled for continued operation with a sixth beryllium reflector. A high radiation environment in a test reactor produces radiation damage and other changes in beryllium. These changes necessitate safety analysis of the beryllium, methods to predict performance, and appropriate surveillances. Other nuclear applications also utilize beryllium. Beryllium, given its unique atomic, physical, and chemical characteristics, is widely used as a window for x-rays and gamma rays. Beryllium, intimately mixed with high-energy alpha radiation emitters has been successfully used to produce neutron sources. This paper addresses operational experience and methodologies associated with the use of beryllium in nuclear test reactors and in windows for x-rays and gamma rays. Other nuclear applications utilizing beryllium are also discussed.

T., A. Tomberlin

2004-11-01T23:59:59.000Z

250

Triangle Universities Nuclear Laboratory  

SciTech Connect (OSTI)

This report contains brief papers that discusses the following topics: Fundamental Symmetries in the Nucleus; Internucleon Interactions; Dynamics of Very Light Nuclei; Facets of the Nuclear Many-Body Problem; and Nuclear Instruments and Methods.

Not Available

1991-01-01T23:59:59.000Z

251

Hegemony and nuclear proliferation  

E-Print Network [OSTI]

Contrary to longstanding of predictions of nuclear tipping points, the number of states interested in nuclear weapons has sharply declined in recent decades. In contrast to existing explanations, this dissertation argues ...

Miller, Nicholas L. (Nicholas LeSuer)

2014-01-01T23:59:59.000Z

252

Promulgating Nuclear Safety Requirements  

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

Applies to all Nuclear Safety Requirements Adopted by the Department to Govern the Conduct of its Nuclear Activities. Cancels DOE P 410.1. Canceled by DOE N 251.85.

1996-05-15T23:59:59.000Z

253

Nuclear disarmament verification  

SciTech Connect (OSTI)

Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification.

DeVolpi, A.

1993-12-31T23:59:59.000Z

254

Nuclear Engineer (Criticality Safety)  

Broader source: Energy.gov [DOE]

This position is located in the Nuclear Safety Division (NSD) which has specific responsibility for managing the development, analysis, review, and approval of non-reactor nuclear facility safety...

255

Nuclear radiation actuated valve  

DOE Patents [OSTI]

A nuclear radiation actuated valve for a nuclear reactor. The valve has a valve first part (such as a valve rod with piston) and a valve second part (such as a valve tube surrounding the valve rod, with the valve tube having side slots surrounding the piston). Both valve parts have known nuclear radiation swelling characteristics. The valve's first part is positioned to receive nuclear radiation from the nuclear reactor's fuel region. The valve's second part is positioned so that its nuclear radiation induced swelling is different from that of the valve's first part. The valve's second part also is positioned so that the valve's first and second parts create a valve orifice which changes in size due to the different nuclear radiation caused swelling of the valve's first part compared to the valve's second part. The valve may be used in a nuclear reactor's core coolant system.

Christiansen, David W. (Kennewick, WA); Schively, Dixon P. (Richland, WA)

1985-01-01T23:59:59.000Z

256

General Engineer (Nuclear Safety)  

Broader source: Energy.gov [DOE]

The Chief of Nuclear Safety (CNS) reports the US/M&P; in serving as the Central Technical Authority (CTA) for M&P; activities, ensuring the Departments nuclear safety policies and...

257

Damage Detection and Characterization in Smart Material Structures \\Lambda y  

E-Print Network [OSTI]

­maps'' as done in the thermal based tomography techniques of [BK1, BK2, BKW] wherein the damaged physical domain

258

attack damage due: Topics by E-print Network  

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

Cell damage extent due to irradiation with nanosecond laser pulses under cell culturing medium and dry environment Engineering Websites Summary: Autnoma de Mxico; Av....

259

A matrix damage accumulation model for laminated composites  

E-Print Network [OSTI]

of the evolutionary relationship with respect to either time or the number of loa, d cycles. The damage histories f' or cross-ply laminates subjected to constant maximum stress fatigue were generated by the dart. age evolutionary relationship. These predictions... with respect to the measured damage state. . 5 Structure of FORTRAN code for the integration of the damage evolution- ary rela. tionship. 6 Matrix ' rack damage variable in the 90' plies for a. [Os/90s], AS4/3501 ? 6 laminate loaded at a maximum fatigue...

Lo, David Chi Shing

1990-01-01T23:59:59.000Z

260

Hail Ice Damage of Stringer-Stiffened Curved Composite Panels /  

E-Print Network [OSTI]

Stiffener Impact Damage. Composite Structures 2003;62:213FTE Values of Carbon/Epoxy Composite Tape Laminate Plates [Sarh B, Kismarton MU. Composite Structures: The First 100

Le, Jacqueline Linh

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

assessing dna damage: Topics by E-print Network  

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

damage may not only reduce the number of amplifiable template molecules, but may also lead to the generation of erroneous sequence information. A qualitative and quantitative...

262

affects dna damage: Topics by E-print Network  

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

damage may not only reduce the number of amplifiable template molecules, but may also lead to the generation of erroneous sequence information. A qualitative and quantitative...

263

assessing tubal damage: Topics by E-print Network  

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

State University, Deborah French, Applied Sciences Associates, Bruce Wright 5 Natural Resource Damage Assessment for the Deepwater BP Oil Spill Environmental Sciences and...

264

Nuclear Multifragmentation Critical Exponents  

E-Print Network [OSTI]

We show that the critical exponents of nuclear multi-fragmentation have not been determined conclusively yet.

Wolfgang Bauer; William Friedman

1994-11-14T23:59:59.000Z

265

Nuclear Explosive Safety Manual  

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

This Manual provides supplemental details to support the requirements of DOE O 452.2D, Nuclear Explosive Safety.

2009-04-14T23:59:59.000Z

266

3D NUCLEAR SEGMENTAT  

Energy Science and Technology Software Center (OSTI)

003029WKSTN00 Delineation of nuclear structures in 3D multicellular systems https://vision.lbl.gov/Software/3DMorphometry/

267

Nuclear power browning out  

SciTech Connect (OSTI)

When the sad history of nuclear power is written, April 26, 1986, will be recorded as the day the dream died. The explosion at the Chernobyl plant was a terrible human tragedy- and it delivered a stark verdict on the hope that nuclear power will one day replace fossil fuel-based energy systems. Nuclear advocates may soldier on, but a decade after Chernobyl it is clear that nuclear power is no longer a viable energy option for the twenty-first century.

Flavin, C.; Lenssen, N.

1996-05-01T23:59:59.000Z

268

WILD PIGS: BIOLOGY, DAMAGE, CONTROL TECHINQUES AND MANAGEMENT  

SciTech Connect (OSTI)

The existence of problems with wild pigs (Sus scrofa) is nothing new to the Western Hemisphere. Damage by these introduced animals was reported as far back as 1505 by the early Spanish colonies in the Caribbean, where wild pigs were killing the colonists cattle. Droves of these animals also ravaged cultivated crops of maize and sugarcane on islands in the West Indies during this same time period. These wild pigs reportedly were very aggressive and often attacked Spanish soldiers hunting rebellious Indians or escaped slaves on these islands, especially when these animals were cornered. The documentation of such impacts by introduced populations of this species in the United States has subsequently increased in recent years, and continued up through the present (Towne and Wentworth. 1950, Wood and Barrett 1979, Mayer and Brisbin 1991, Dickson et al. 2001). In spite of a fairly constant history in this country since the early 1900s, wild pigs have had a dramatic recent increase in both distribution and numbers in the United States. Between 1989 and 2009, the number of states reporting the presence of introduced wild pigs went from 19 up to as many as 44. This increase, in part natural, but largely manmade, has caused an increased workload and cost for land and resource managers in areas where these new populations are found. This is the direct result of the damage that these introduced animals do. The cost of both these impacts and control efforts has been estimated to exceed a billion dollars annually (Pimentel 2007). The complexity of this problem has been further complicated by the widespread appeal and economic potential of these animals as a big game species (Tisdell 1982, Degner 1989). Wild pigs are a controversial problem that is not going away and will likely only get worse with time. Not only do they cause damage, but wild pigs are also survivors. They reproduce at a rate faster than any other mammal of comparable size, native or introduced; they can eat just about anything; and, they can live just about anywhere. On top of that, wild pigs are both very difficult to control and, with the possible exception of island ecosystems, almost impossible to eradicate (Dickson et al. 2001, Sweeney et al. 2003). The solution to the wild pig problem has not been readily apparent. The ultimate answer as to how to control these animals has not been found to date. In many ways, wild pigs are America's most successful large invasive species. All of which means that wild pigs are a veritable nightmare for land and resource managers trying to keep the numbers of these animals and the damage that they do under control. Since the more that one knows about an invasive species, the easier it is to deal with and hopefully control. For wild pigs then, it is better to 'know thy enemy' than to not, especially if one expects to be able to successfully control them. In an effort to better 'know thy enemy,' a two-day symposium was held in Augusta, Georgia, on April 21-22, 2004. This symposium was organized and sponsored by U.S.D.A. Forest Service-Savannah River (USFS-SR), U. S. Department of Energy-Savannah River Operations Office (DOE-SR), the Westinghouse Savannah River Company (WSRC), the South Carolina Chapter of the Soil & Water Conservation Society, and the Savannah River Ecology Laboratory (SREL). The goal of this symposium was to assemble researchers and land managers to first address various aspects of the biology and damage of wild pigs, and then review the control techniques and management of this invasive species. The result would then be a collected synopsis of what is known about wild pigs in the United States. Although the focus of the symposium was primarily directed toward federal agencies, presenters also included professionals from academic institutions, and private-sector control contractors and land managers. Most of the organizations associated with implementing this symposium were affiliated with the Savannah River Site (SRS), a 803 km{sup 2} federal nuclear facility, located in western South Carolina along the Savannah

Mayer, John; Brisbin, I. Lehr

2009-12-31T23:59:59.000Z

269

United States and Italy Sign Nuclear Energy Agreements | Department of  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of EnergyofProject is on Track| DepartmentPinakin2Nuclear Damage |

270

Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay  

E-Print Network [OSTI]

of the Institute of Nuclear Material Management, Tucson, AZ,Assay, Institute of Nuclear Materials Management 51st Annual

Quiter, Brian

2012-01-01T23:59:59.000Z

271

Nuclear Explosive Safety  

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

This Order establishes requirements to implement the nuclear explosive safety elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations. Cancels DOE O 452.2C. Admin Chg 1, 7-10-13

2009-04-14T23:59:59.000Z

272

Nuclear Explosive Safety  

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

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs). Cancels DOE O 452.2C. Admin Chg 1, dated 7-10-13, cancels DOE O 452.2D.

2009-04-14T23:59:59.000Z

273

NUCLEAR POWER in CALIFORNIA  

E-Print Network [OSTI]

NUCLEAR POWER in CALIFORNIA: 2007 STATUS REPORT CALIFORNIA ENERGY COMMISSION October 2007 CEC-100, California Contract No. 700-05-002 Prepared For: California Energy Commission Barbara Byron, Senior Nuclear public workshops on nuclear power. The Integrated Energy Policy Report Committee, led by Commissioners

274

NUCLEAR PLANT OPERATIONS AND  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed absorption cross-section behavior. Consequently, if NUCLEAR TECHNOLOGY VOL. 140 NOV. 2002 147 #12;Demazire

Demazire, Christophe

275

NUCLEAR PLANT OPERATIONS AND  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper- ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed. Consequently, if*E-mail: demaz@nephy.chalmers.se NUCLEAR TECHNOLOGY VOL. 140 NOV. 2002 147 #12;high-burnup fuel

Pzsit, Imre

276

NUCLEAR PLANT AND CONTROL  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: software require- ments, safety analysis, formal for the digital protection systems of a nuclear power plant. When spec- ifying requirements for software and CRSA processes are described using shutdown system 2 of the Wolsong nuclear power plants as the digital

277

DETERMINING THE EFFECTS OF RADIATION ON AGING CONCRETE STRUCTURES OF NUCLEAR REACTORS  

SciTech Connect (OSTI)

The U.S. Department of Energy Office of Environmental Management (DOE-EM) is responsible for the Decontamination and Decommissioning (D&D) of nuclear facilities throughout the DOE Complex. Some of these facilities will be completely dismantled, while others will be partially dismantled and the remaining structure will be stabilized with cementitious fill materials. The latter is a process known as In-Situ Decommissioning (ISD). The ISD decision process requires a detailed understanding of the existing facility conditions, and operational history. System information and material properties are need for aged nuclear facilities. This literature review investigated the properties of aged concrete structures affected by radiation. In particular, this review addresses the Savannah River Site (SRS) isotope production nuclear reactors. The concrete in the reactors at SRS was not seriously damaged by the levels of radiation exposure. Loss of composite compressive strength was the most common effect of radiation induced damage documented at nuclear power plants.

Serrato, M.

2010-01-29T23:59:59.000Z

278

Preparing Non-nuclear Engineers for the Nuclear Field  

E-Print Network [OSTI]

Preparing Non-nuclear Engineers for the Nuclear Field Elizabeth K. Ervin The University. An understanding of power generation is important for all modern-day engineers, and nuclear energy serves as a good-four universities have nuclear- related programs, including Nuclear or Radiological Engineering, Nuclear Science

Ervin, Elizabeth K.

279

ANNOUNCEMENT NUCLEAR ENGINEERING FACULTY POSITION  

E-Print Network [OSTI]

ANNOUNCEMENT NUCLEAR ENGINEERING FACULTY POSITION The Department of Nuclear Engineering undergraduate and graduate courses in general nuclear engineering. The Knoxville campus of the University, Associate Professor of Nuclear Engineering; The University of Tennessee; 312 Pasqua Engineering Bldg

Tennessee, University of

280

Unlimited Damage Accumulation in Metallic Materials Under Cascade-Damage Conditions  

SciTech Connect (OSTI)

Most experiments on neutron or heavy-ion cascade-produced irradiation of pure metals and metallic alloys demonstrate unlimited void growth as well as development of the dislocation structure. In contrast, the theory of radiation damage predicts saturation of void swelling at sufficiently high irradiation doses and, accordingly, termination of accumulation of interstitial-type defects. It is shown in the present paper that, under conditions of steady production of one-dimensionally (1-D) mobile clusters of self-interstitial atoms (SIAs) in displacement cascades, any one of the following three conditions can result in indefinite damage accumulation. First, if the fraction of SIAs generated in the clustered form is smaller than some finite value of the order of the dislocation bias factor. Second, if solute, impurity or transmuted atoms form atmospheres around voids and repel the SIA clusters. Third, if spatial correlations between voids and other defects, such as second-phase precipitates and dislocations, exist that provide shadowing of voids from the SIA clusters. The driving force for the development of such correlations is the same as for void lattice formation and is argued to be always present under cascade-damage conditions. It is emphasised that the mean-free path of 1-D migrating SIA clusters is typically at least an order of magnitude longer than the average distance between microstructural defects; hence spatial correlations on the same scale should be taken into consideration. A way of developing a predictive theory is discussed. An interpretation

Barashev, Aleksandr [University of Liverpool; Golubov, Stanislav I [ORNL

2008-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Neurton Damage and MAX Phase Ternary Compounds  

SciTech Connect (OSTI)

The Demands of Gen IV nuclear power plants for long service life under neutron radiation at high temperature are severe. Advanced materials that would withstand high temperatures (up to 1000+ C) to high doses in a neutron field would be ideal for reactor internal structures and would add to the long service life and reliability of the reactors. The objective of this work is to investigate the resonse of a new class of machinable, conductive, layered, ternary transition metal carbides and nitrides - the so-called MAX phases - to low and moderate neutron dose levels.

Barsoum, Michael; Hoffman, Elizabeth; Sindelar, Robert; Garcua-Duaz, Brenda; Kohse, Gordon

2014-06-17T23:59:59.000Z

282

Is Nuclear Energy the Solution?  

E-Print Network [OSTI]

the potential of nuclear power to combat global warming havecompetitive today, and for nuclear power to succeed, it must

Saier, Milton H.; Trevors, Jack T.

2010-01-01T23:59:59.000Z

283

Reorganization bolsters nuclear nonproliferation capability  

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

Reorganization bolsters nuclear nonproliferation capability Reorganization bolsters nuclear nonproliferation capability LANL has strengthened its capability in a key aspect of...

284

SuppCompensationNuclearDamage_ExtensionComments.PDF | 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 RankCombustion |Energy Usage »of Energy Strain Rate4Superhard Coating

285

Nuclear Systems Technology | Nuclear Science | 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 ConsortiumNuclearSafeguardsResearch AreasNuclear

286

Nuclear spirals in galaxies  

E-Print Network [OSTI]

Recent high-resolution observations indicate that nuclear spirals are often present in the innermost few hundred parsecs of disc galaxies. My models show that nuclear spirals form naturally as a gas response to non-axisymmetry in the gravitational potential. Some nuclear spirals take the form of spiral shocks, resulting in streaming motions in the gas, and in inflow comparable to the accretion rates needed to power local Active Galactic Nuclei. Recently streaming motions of amplitude expected from the models have been observed in nuclear spirals, confirming the role of nuclear spirals in feeding of the central massive black holes.

Witold Maciejewski

2006-11-08T23:59:59.000Z

287

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

288

Multi-source contingency clustering  

E-Print Network [OSTI]

This thesis examines the problem of clustering multiple, related sets of data simultaneously. Given datasets which are in some way connected (e.g. temporally) but which do not necessarily share label compatibility, we ...

Bouvrie, Jacob V

2004-01-01T23:59:59.000Z

289

An enhanced Lemaitre model formulation for materials processing damage computation  

E-Print Network [OSTI]

are presented and discussed to deal with complex multiaxial configurations ­ such as multi-stages bulk forming loading, involving crack closure effects. - Simple parameters identification: whatever the damage model used, the identification of damage parameters is an important issue. Most of the time

Boyer, Edmond

290

Evaluation of moisture damage within asphalt concrete mixes  

E-Print Network [OSTI]

Pavements are a major part of the infrastructure in the United States. Moisture damage of these pavements is a significant problem. To predict and prevent this kind of moisture damage a great deal of research has been performed on this issue in past...

Shah, Brij D.

2004-09-30T23:59:59.000Z

291

AFM CHARACTERIZATION OF LASER INDUCED DAMAGE ON CDZNTE CRYSTAL SURFACES  

SciTech Connect (OSTI)

Semi-conducting CdZnTe (or CZT) crystals can be used in a variety of detector-type applications. CZT shows great promise for use as a gamma radiation spectrometer. However, its performance is adversely affected by point defects, structural and compositional heterogeneities within the crystals, such as twinning, pipes, grain boundaries (polycrystallinity), secondary phases and in some cases, damage caused by external forces. One example is damage that occurs during characterization of the surface by a laser during Raman spectroscopy. Even minimal laser power can cause Te enriched areas on the surface to appear. The Raman spectra resulting from measurements at moderate intensity laser power show large increases in peak intensity that is attributed to Te. Atomic Force Microscopy (AFM) was used to characterize the extent of damage to the CZT crystal surface following exposure to the Raman laser. AFM data reveal localized surface damage in the areas exposed to the Raman laser beam. The degree of surface damage to the crystal is dependent on the laser power, with the most observable damage occurring at high laser power. Moreover, intensity increases in the Te peaks of the Raman spectra are observed even at low laser power with little to no visible damage observed by AFM. AFM results also suggest that exposure to the same amount of laser power yields different amounts of surface damage depending on whether the exposed surface is the Te terminating face or the Cd terminating face of CZT.

Hawkins, S; Lucile Teague, L; Martine Duff, M; Eliel Villa-Aleman, E

2008-06-10T23:59:59.000Z

292

Atomic processes during damage production and defect Nasr M. Ghoniem *  

E-Print Network [OSTI]

- sitivity to the deleterious eects of neutron irradiation. Electro-optical properties of semi uncertainties exposed. Damage production under neutron and ion irradiation proceeds through the elementary step-cascade interaction events. Under fusion neutron irradiation, single cascade damage production occurs within 10 ps

Ghoniem, Nasr M.

293

LASER ULTRASONIC IMAGING FOR IMPACT DAMAGE VISUALIZATION IN COMPOSITE STRUCTURE  

E-Print Network [OSTI]

LASER ULTRASONIC IMAGING FOR IMPACT DAMAGE VISUALIZATION IN COMPOSITE STRUCTURE Chao Zhang1 , Jinhao Qiu1* , Hongli Ji1 1 State Key Laboratory of Mechanics and Control of Mechanical Structures ultrasonic scanning technique has great potential for damage evaluation in various applications. In order

Boyer, Edmond

294

Damage detection in mechanical structures using extreme value statistic.  

SciTech Connect (OSTI)

The first and most important objective of any damage identification algorithms is to ascertain with confidence if damage is present or not. Many methods have been proposed for damage detection based on ideas of novelty detection founded in pattern recognition and multivariate statistics. The philosophy of novelty detection is simple. Features are first extracted from a baseline system to be monitored, and subsequent data are then compared to see if the new features are outliers, which significantly depart from the rest of population. In damage diagnosis problems, the assumption is that outliers are generated from a damaged condition of the monitored system. This damage classification necessitates the establishment of a decision boundary. Choosing this threshold value is often based on the assumption that the parent distribution of data is Gaussian in nature. While the problem of novelty detection focuses attention on the outlier or extreme values of the data i.e. those points in the tails of the distribution, the threshold selection using the normality assumption weighs the central population of data. Therefore, this normality assumption might impose potentially misleading behavior on damage classification, and is likely to lead the damage diagnosis astray. In this paper, extreme value statistics is integrated with the novelty detection to specifically model the tails of the distribution of interest. Finally, the proposed technique is demonstrated on simulated numerical data and time series data measured from an eight degree-of-freedom spring-mass system.

Worden, K.; Allen, D. W. (David W.); Sohn, H. (Hoon); Farrar, C. R. (Charles R.)

2002-01-01T23:59:59.000Z

295

Permeability of WIPP Salt During Damage Evolution and Healing  

SciTech Connect (OSTI)

The presence of damage in the form of microcracks can increase the permeability of salt. In this paper, an analytical formulation of the permeability of damaged rock salt is presented for both initially intact and porous conditions. The analysis shows that permeability is related to the connected (i.e., gas accessible) volumetric strain and porosity according to two different power-laws, which may be summed to give the overall behavior of a porous salt with damage. This relationship was incorporated into a constitutive model, known as the Multimechanism Deformation Coupled Fracture (MDCF) model, which has been formulated to describe the inelastic flow behavior of rock salt due to coupled creep, damage, and healing. The extended model was used to calculate the permeability of rock salt from the Waste Isolation Pilot Plant (WIPP) site under conditions where damage evolved with stress over a time period. Permeability changes resulting from both damage development under deviatoric stresses and damage healing under hydrostatic pressures were considered. The calculated results were compared against experimental data from the literature, which indicated that permeability in damaged intact WIPP salt depends on the magnitude of the gas accessible volumetric strain and not on the total volumetric strain. Consequently, the permeability of WIPP salt is significantly affected by the kinetics of crack closure, but shows little dependence on the kinetics of crack removal by sintering.

BODNER,SOL R.; CHAN,KWAI S.; MUNSON,DARRELL E.

1999-12-03T23:59:59.000Z

296

Ris-R-1334(EN) Identification of Damage to Wind  

E-Print Network [OSTI]

Ris-R-1334(EN) Identification of Damage to Wind Turbine Blades by Modal Parameter Estimation April 2002 #12;Ris-R-1334(EN) Identification of Damage to Wind Turbine Blades by Modal Parameter condition monitoring of wind turbine blades (Phase I)". The goal of Phase I is to make a pre

297

THE IMPACT OF THE GLOBAL NUCLEAR SAFETY REGIME IN BRAZIL  

SciTech Connect (OSTI)

A turning point of the world nuclear industry with respect to safety occurred due to the accident at Chernobyl, in 1986. A side from the tragic personal losses and the enormous financial damage, the Chernobyl accident has literally demonstrated that ''a nuclear accident anywhere is an accident everywhere''. The impact was felt immediately by the nuclear industry, with plant cancellations (e.g. Austria), elimination of national programs (e.g. Italy) and general construction delays. However, the reaction of the nuclear industry was equally immediate, which led to the proposal and establishment of a Global Nuclear Safety Regime. This regime is composed of biding international safety conventions, globally accepted safety standard, and a voluntary peer review system. In a previous work, the author has presented in detail the components of this Regime, and briefly discussed its impact in the Brazilian nuclear power organizations, including the Regulatory Body. This work, on the opposite, briefly reviews the Global Nuclear Safety Regime, and concentrates in detail in the discussion of its impact in Brazil, showing how it has produced some changes, and where the peer pressure regime has failed to produce real results.

Almeida, C.

2004-10-06T23:59:59.000Z

298

Application of Damage Detection Techniques Using Wind Turbine Modal Data  

SciTech Connect (OSTI)

As any structure ages, its structural characteristics will also change. The goal of this work was to determine if modal response data fkom a wind turbine could be used in the detection of damage. The input stimuli to the wind turbine were from traditional modal hammer input and natural wind excitation. The structural response data was acquired using accelerometers mounted on the rotor of a parked and undamaged horizontal-axis wind turbine. The bolts at the root of one of the three blades were then loosened to simulate a damaged blade. The structural response data of the rotor was again recorded. The undamaged and damage-simulated datasets were compared using existing darnage detection algorithms. Also, a novel algorithm for combining the results of different damage detection algorithms was utilized in the assessment of the data. This paper summarizes the code development and discusses some preliminary damage detection results.

Gross, E.; Rumsey, M.; Simmermacher, T.; Zadoks, R.I.

1998-12-17T23:59:59.000Z

299

How Damage Diversification Can Reduce Systemic Risk  

E-Print Network [OSTI]

We consider the problem of risk diversification in complex networks. Nodes represent e.g. financial actors, whereas weighted links represent e.g. financial obligations (credits/debts). Each node has a risk to fail because of losses resulting from defaulting neighbors, which may lead to large failure cascades. Classical risk diversification strategies usually neglect network effects and therefore suggest that risk can be reduced if possible losses (i.e., exposures) are split among many neighbors (exposure diversification, ED). But from a complex networks perspective diversification implies higher connectivity of the system as a whole which can also lead to increasing failure risk of a node. To cope with this, we propose a different strategy (damage diversification, DD), i.e. the diversification of losses that are imposed on neighboring nodes as opposed to losses incurred by the node itself. Here, we quantify the potential of DD to reduce systemic risk in comparison to ED. For this, we develop a branching proce...

Burkholz, Rebekka; Schweitzer, Frank

2015-01-01T23:59:59.000Z

300

Nuclear and Non-Ionizing Energy-Loss for Coulomb Scattered Particles from Low Energy up to Relativistic Regime in Space Radiation Environment  

E-Print Network [OSTI]

In the space environment, instruments onboard of spacecrafts can be affected by displacement damage due to radiation. The differential scattering cross section for screened nucleus--nucleus interactions - i.e., including the effects due to screened Coulomb nuclear fields -, nuclear stopping powers and non-ionization energy losses are treated from about 50\\,keV/nucleon up to relativistic energies.

Boschini, M J; Gervasi, M; Giani, S; Grandi, D; Ivantchenko, V; Pensotti, S; Rancoita, P G; Tacconi, M

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Journal of Nuclear Materials 72 (1978) 147-167 0 North-Holland Publishing Company  

E-Print Network [OSTI]

Journal of Nuclear Materials 72 (1978) 147-167 0 North-Holland Publishing Company RADIATION damage and energy deposition. In this paper, radiation environment for the magnets is characterized into radiation effects using available experimental data. The impact of the tradeoffs in radiation shielding

Abdou, Mohamed

302

Nuclear Science References Database  

E-Print Network [OSTI]

The Nuclear Science References (NSR) database together with its associated Web interface, is the world's only comprehensive source of easily accessible low- and intermediate-energy nuclear physics bibliographic information for more than 210,000 articles since the beginning of nuclear science. The weekly-updated NSR database provides essential support for nuclear data evaluation, compilation and research activities. The principles of the database and Web application development and maintenance are described. Examples of nuclear structure, reaction and decay applications are specifically included. The complete NSR database is freely available at the websites of the National Nuclear Data Center http://www.nndc.bnl.gov/nsr and the International Atomic Energy Agency http://www-nds.iaea.org/nsr.

B. Pritychenko; E. B?tk; B. Singh; J. Totans

2014-07-08T23:59:59.000Z

303

Absolute nuclear material assay  

DOE Patents [OSTI]

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-05-15T23:59:59.000Z

304

Nuclear Fabrication Consortium  

SciTech Connect (OSTI)

This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) â?? Office of Nuclear Energy (NE) for the management and operation of the Nuclear Fabrication Consortium (NFC). The NFC was established by EWI to independently develop, evaluate, and deploy fabrication approaches and data that support the re-establishment of the U.S. nuclear industry: ensuring that the supply chain will be competitive on a global stage, enabling more cost-effective and reliable nuclear power in a carbon constrained environment. The NFC provided a forum for member original equipment manufactures (OEM), fabricators, manufacturers, and materials suppliers to effectively engage with each other and rebuild the capacity of this supply chain by : â?¢ Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. â?¢ Providing and facilitating detailed scientific-based studies on new approaches and technologies that will have positive impacts on the cost of building of nuclear plants. â?¢ Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. â?¢ Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. â?¢ Supporting industry in helping to create a larger qualified nuclear supplier network. â?¢ Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. â?¢ Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. â?¢ Serving as a focal point for technology, policy, and politically interested parties to share ideas and concepts associated with fabrication across the nuclear industry. The report the objectives and summaries of the Nuclear Fabrication Consortium projects. Full technical reports for each of the projects have been submitted as well.

Levesque, Stephen

2013-04-05T23:59:59.000Z

305

Inhibition of Oxidation in Nuclear Graphite  

SciTech Connect (OSTI)

Graphite is a fundamental material of high temperature gas cooled nuclear reactors, providing both structure and neutron moderation. Its high thermal conductivity, chemical inertness, thermal heat capacity, and high thermal structural stability under normal and off normal conditions contribute to the inherent safety of these reactor designs. One of the primary safety issues for a high temperature graphite reactor core is the possibility of rapid oxidation of the carbon structure during an off normal design basis event where an oxidizing atmosphere (air ingress) can be introduced to the hot core. Although the current Generation IV high temperature reactor designs attempt to mitigate any damage caused by a postualed air ingress event, the use of graphite components that inhibit oxidation is a logical step to increase the safety of these reactors. Recent experimental studies of graphite containing between 5.5 and 7 wt% boron carbide (B4C) indicate that oxidation is dramatically reduced even at prolonged exposures at temperatures up to 900C. The proposed addition of B4C to graphite components in the nuclear core would necessarily be enriched in B-11 isotope in order to minimize B-10 neutron absorption and graphite swelling. The enriched boron can be added to the graphite during billet fabrication. Experimental oxidation rate results and potential applications for borated graphite in nuclear reactor components will be discussed.

Phil Winston; James W. Sterbentz; William E. Windes

2013-10-01T23:59:59.000Z

306

Radiation effects in nuclear materials: Role of nuclear and electronic energy losses and their synergy  

SciTech Connect (OSTI)

Ceramic oxides and carbides are promising matrices for the immobilization and/or transmutation of nuclear wastes, cladding materials for gas-cooled fission reactors and structural components for fusion reactors. For these applications there is a need of fundamental data concerning the behavior of nuclear ceramics upon irradiation. This article is focused on the presentation of a few remarkable examples regarding ion-beam modifications of nuclear ceramics with an emphasis on the mechanisms leading to damage creation and phase transformations. Results obtained by combining advanced techniques (Rutherford backscattering spectrometry and channeling, X-ray diffraction, transmission electron microscopy, Raman spectroscopy) concern irradiations in a broad energy range (from keV to GeV) with the aim of exploring both nuclear collision (Sn) and electronic excitation (Se) regimes. Finally, the daunting challenge of the demonstration of the existence of synergistic effects between Sn and Se is tackled by discussing the healing due to intense electronic energy deposition (SHIBIEC) and by reporting results recently obtained in dual-beam irradiation (DBI) experiments.

Thom, Lionel [Centre de Spectromtrie Nuclaire et de Spectromtrie de Masse, CNRS-IN2P3-Universit Paris-Sud; Debelle, Aurelien [Universite Paris Sud, Orsay, France; Garrido, Frederico [Universite Paris Sud, Orsay, France; Mylonas, Stamatis [Universite Paris Sud, Orsay, France; Dcamps, B. [Universite Paris Sud, Orsay, France; Bachelet, C. [Universite Paris Sud, Orsay, France; Sattonnay, G. [LEMHE/ICMMO, Universit Paris-Sud, Bt. Orsay, France; Moll, Sandra [French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette; Pellegrino, S. [French Atomic Energy Commission (CEA); Miro, S. [French Atomic Energy Commission (CEA); Trocellier, P. [French Atomic Energy Commission (CEA); Serruys, Y. [French Atomic Energy Commission (CEA); Velisa, G. [French Atomic Energy Commission (CEA); Grygiel, C. [CNRS, France; Monnet, I. [CIMAP, CEA-CNRS-Universit de Caen, France; Toulemonde, Marcel [French Atomic Energy Commission (CEA), French National Centre for Scientific Research (CNRS)-ENSICAE; Simon, P. [CEMHTI, CNRS, France; Jagielski, Jacek [Institute for Electronic Materials Technology; Jozwik-Biala, Iwona [Institute for Electronic Materials Technology; Nowicki, Lech [Soltan Institute for Nuclear Studies, Swierk, Poland; Behar, M. [Instituto de Fisica, Universidade Federal do Rio Grande do Sul, Porto Alegre,; Weber, William J [ORNL; Zhang, Yanwen [ORNL; Backman, Marie [University of Tennessee, Knoxville (UTK); Nordlund, Kai [University of Helsinki; Djurabekova, Flyura [University of Helsinki

2013-01-01T23:59:59.000Z

307

Nuclear criticality safety guide  

SciTech Connect (OSTI)

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

Pruvost, N.L.; Paxton, H.C. [eds.] [eds.

1996-09-01T23:59:59.000Z

308

Nuclear Safety Regulatory Framework  

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

overall Nuclear Safety Policy & ESH Goals Safety Basis Review and Approval In the DOE governance model, contractors responsible for the facility develop the safety basis and...

309

Nuclear Physics from QCD  

E-Print Network [OSTI]

Effective field theories provide a bridge between QCD and nuclear physics. I discuss light nuclei from this perspective, emphasizing the role of fine-tuning.

U. van Kolck

2008-12-20T23:59:59.000Z

310

Unclassified Controlled Nuclear Information  

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

To prevent unauthorized dissemination of Unclassified Controlled Nuclear Information (UCNI). Cancels DOE 5635.4 and DOE 5650.3A

1995-09-25T23:59:59.000Z

311

Nuclear Spectra from Skyrmions  

SciTech Connect (OSTI)

The structures of Skyrmions, especially for baryon numbers 4, 8 and 12, are reviewed. The quantized Skyrmion states are compared with nuclear spectra.

Manton, N. S. [DAMTP, University of Cambridge, Wilberforce Road, Cambridge CB3 0WA (United Kingdom)

2009-08-26T23:59:59.000Z

312

2013 Nuclear Workforce Development ...  

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

Patient Care Medical Imaging & Computers Moderator: Deborah M. Gibbs, MEd, PET, CNMT Lead Nuclear Medicine PET Facility Administrator Georgia Regents University...

313

National Nuclear Security Administration  

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

Project Reviews, etc., except those specifically reserved for the Administrator for the National Nuclear Security Administration and the Deputy Secretary. cc: Mike Hickman. NA-Stl...

314

Management of Nuclear Materials  

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

To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Cancels DOE O 5660.1B.

2009-08-17T23:59:59.000Z

315

Reference handbook: Nuclear criticality  

SciTech Connect (OSTI)

The purpose for this handbook is to provide Rocky Flats personnel with the information necessary to understand the basic principles underlying a nuclear criticality.

Not Available

1991-12-06T23:59:59.000Z

316

Nuclear | Department of Energy  

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 Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchivesNuclear Science/NuclearNuclear Nuclear

317

National Nuclear Security Administration  

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

and Related Structures within TA-3 at Los Alamos National Laboratory, Los Alamos, New Mexico U. S. Department of Energy National Nuclear Security Administration Los Alamos Area...

318

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

319

Thermoacoustic Thermometry for Nuclear Reactor Monitoring  

SciTech Connect (OSTI)

On Friday, March 11, 2011, at 2:46pm (Japan Standard Trme), the Tohoku region on the east coast of northern Japan experienced what would become known as the largest earthquake in the country's history at magnitude 9.0 on the Richter scale. The Fukushima Daiichi nuclear power plant suffered extensive and irreversible damage. Six operating units were at the site, each with a boiling water reactor. When the earthquake struck, three of the six reactors were operating and the others were in a periodic inspection outage phase. In one reactor, all of the fuel had been relocated to a spent fuel pool in the reactor building. The seismic acceleration caused by the earthquake brought the three operating units to an automatic shutdown. Since there was damage to the power transmission lines, the emergency diesel generators (EDG) were automatically started to ensure continued cooling of the reactors and spent fuel pools. The situation was under control until the tsunami hit about forty-five minutes later with a maximum wave height of approximately 15 meters, which was three times taller than the sea wall of 5m. The influx of water submerged the EDGs, the electrical switchgear, and dc batteries, resulting in the total loss of power to five of the six reactors. The flooding also resulted in the loss of instrumentation that would have other wise been used to monitor and control the emergency. The ugly aftermath included high radiation exposure to operators at the nuclear power plants and early contamination of food supplies and water within several restricted areas in Japan, where high radiation levels have rendered them unsafe for human habitation. While the rest of the story will remain a tragic history, it is this part of the series of unfortunate events that has inspired our research. It has indubitably highlighted the need for a novel sensor and instrumentation system that can withstand similar or worse conditions to avoid future catastrophe and assume damage prevention as quickly as possible. This is the question which we are attempting to answer: Is it possible to implement a self-powered sensor that could transmit data independently of electronic networks while taking advantage of the harsh operating environment of the nuclear reactor?

James A. Smith; Dale K. Kotter; Steven L. Garrett; Randall A. Ali

2013-06-01T23:59:59.000Z

320

Development and Application of a Strength and Damage Model for Rock under Dynamic Loading  

SciTech Connect (OSTI)

Simulating the behavior of geologic materials under impact loading conditions requires the use of a constitutive model that includes the effects of bulking, yielding, damage, porous compaction and loading rate on the material response. This paper describes the development, implementation and calibration of a thermodynamically consistent constitutive model that incorporates these features. The paper also describes a computational study in which the model was used to perform numerical simulations of PILE DRIVER, a deeply-buried underground nuclear explosion detonated in granite at the Nevada Test Site. Particle velocity histories, peak velocity and peak displacement as a function of slant range obtained from the code simulations compare favorably with PILE DRIVER data. The simulated attenuation of peak velocity and peak displacement also agrees with the results from several other spherical wave experiments in granite.

Antoun, T H; Lomov, I N; Glenn, L A

2001-03-12T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Prioritization of reactor control components susceptible to fire damage as a consequence of aging  

SciTech Connect (OSTI)

The Fire Vulnerability of Aged Electrical Components Test Program is to identify and assess issues of plant aging that could lead to an increase in nuclear power plant risk because of fires. Historical component data and prior analyses are used to prioritize a list of components with respect to aging and fire vulnerability and the consequences of their failure on plant safety systems. The component list emphasizes safety system control components, but excludes cables, large equipment, and devices encompassed in the Equipment Qualification (EQ) program. The test program selected components identified in a utility survey and developed test and fire conditions necessary to maximize the effectiveness of the test program. Fire damage considerations were limited to purely thermal effects.

Lowry, W.; Vigil, R. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Nowlen, S. [Sandia National Labs., Albuquerque, NM (United States)

1994-01-01T23:59:59.000Z

322

Draft Advanced Nuclear Energy Projects Solicitation | Department...  

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

Draft Advanced Nuclear Energy Projects Solicitation Draft Advanced Nuclear Energy Projects Solicitation INFORMATIONAL MATERIALS DRAFT ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION...

323

SUBSPACE-BASED DETECTION OF FATIGUE DAMAGE ON JACKET SUPPORT STRUCTURES OF OFFSHORE WIND TURBINES  

E-Print Network [OSTI]

SUBSPACE-BASED DETECTION OF FATIGUE DAMAGE ON JACKET SUPPORT STRUCTURES OF OFFSHORE WIND TURBINES damage in real size structural components of offshore wind turbines. KEYWORDS : Damage detection, Offshore wind turbines, Numerical response simulation. INTRODUCTION Offshore wind turbines are exposed

Paris-Sud XI, Université de

324

Strain localization and cyclic damage of polyurethane foam cylinders: experimental tests and theoretical model  

E-Print Network [OSTI]

Strain localization and cyclic damage of polyurethane foam cylinders: experimental tests subject to progressive damage. The chain of springs models the strain localization, and the second series qualitative agreement with the experiments. Keywords: polyurethane foams; strain localization; cyclic damage

Boyer, Edmond

325

ENVIRONMENTAL DAMAGE AS NEGATIVE EXTERNALITY: UNCERTAINTY, MORAL COMPLEXITY AND THE LIMITS OF THE MARKET  

E-Print Network [OSTI]

21 ENVIRONMENTAL DAMAGE AS NEGATIVE EXTERNALITY: UNCERTAINTY, MORAL COMPLEXITY AND THE LIMITS environmental damage with a sociological approach, I show how the process of externalities definition inclusive and democratic public deliberation on environmental damage and its reparation. Key Words

Boyer, Edmond

326

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

327

Nuclear Security 101 | National Nuclear Security Administration  

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

328

Nuclear Security Enterprise | National Nuclear Security Administration  

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

329

Failure Predictions for VHTR Core Components using a Probabilistic Contiuum Damage Mechanics Model  

SciTech Connect (OSTI)

The proposed work addresses the key research need for the development of constitutive models and overall failure models for graphite and high temperature structural materials, with the long-term goal being to maximize the design life of the Next Generation Nuclear Plant (NGNP). To this end, the capability of a Continuum Damage Mechanics (CDM) model, which has been used successfully for modeling fracture of virgin graphite, will be extended as a predictive and design tool for the core components of the very high- temperature reactor (VHTR). Specifically, irradiation and environmental effects pertinent to the VHTR will be incorporated into the model to allow fracture of graphite and ceramic components under in-reactor conditions to be modeled explicitly using the finite element method. The model uses a combined stress-based and fracture mechanics-based failure criterion, so it can simulate both the initiation and propagation of cracks. Modern imaging techniques, such as x-ray computed tomography and digital image correlation, will be used during material testing to help define the baseline material damage parameters. Monte Carlo analysis will be performed to address inherent variations in material properties, the aim being to reduce the arbitrariness and uncertainties associated with the current statistical approach. The results can potentially contribute to the current development of American Society of Mechanical Engineers (ASME) codes for the design and construction of VHTR core components.

Fok, Alex

2013-10-30T23:59:59.000Z

330

NUCLEAR ENERGY PERGAMON Annals of Nuclear Energy 27 (2000) 138551398  

E-Print Network [OSTI]

annafs of NUCLEAR ENERGY PERGAMON Annals of Nuclear Energy 27 (2000) 138551398 www-4549(00)00033-5 #12;1386 I. Phi!, V. Arzhanov. /Annals qf Nuclear Energy 27 (2000) 1385-1398 subcritical systems (ADS

Pázsit, Imre

331

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network [OSTI]

204. Bhatia, Shyam. 1988. Nuclear rivals in the Middle East.of the merits of selective nuclear proliferation. Journal ofThe Case for a Ukranian nuclear deterrent. Foreign Affairs.

Kroenig, Matthew

2006-01-01T23:59:59.000Z

332

Automated structural damage detection using one class machine learning  

E-Print Network [OSTI]

Measuring and analysing the vibration of structures using sensors can help identify and detect damage, potentially prolonging the life of structures and preventing disasters. Wireless sensor systems promise to make this ...

Long, James, S.M. Massachusetts Institute of Technology

2014-01-01T23:59:59.000Z

333

Neutron and gamma irradiation damage to organic materials.  

SciTech Connect (OSTI)

This document discusses open literature reports which investigate the damage effects of neutron and gamma irradiation on polymers and/or epoxies - damage refers to reduced physical chemical, and electrical properties. Based on the literature, correlations are made for an SNL developed epoxy (Epon 828-1031/DDS) with an expected total fast-neutron fluence of {approx}10{sup 12} n/cm{sup 2} and a {gamma} dosage of {approx}500 Gy received over {approx}30 years at < 200 C. In short, there are no gamma and neutron irradiation concerns for Epon 828-1031/DDS. To enhance the fidelity of our hypotheses, in regards to radiation damage, we propose future work consisting of simultaneous thermal/irradiation (neutron and gamma) experiments that will help elucidate any damage concerns at these specified environmental conditions.

White, Gregory Von, II; Bernstein, Robert

2012-04-01T23:59:59.000Z

334

RADIATION DAMAGE TO BSCCO-2223 FROM 50 MEV PROTONS  

E-Print Network [OSTI]

B. and Gupta, R. , Radiation Resistant Magnets for the RIARADIATION DAMAGE TO BSCCO-2223 FROM 50 MEV PROTONS A. F.HTS materials in high radiation environments requires that

Zeller, A.F.; Ronningen, R.M.; Godeke, A.; Heilbronn, L.H.; McMahan-Norris, P.; Gupta, R.

2007-01-01T23:59:59.000Z

335

Review of Dynamic Recovery Effects on Ion Irradiation Damage...  

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

6HSiC, ionization processes are less dominant. Citation: Weber WJ, Y Zhang, and LM Wang.2012."Review of Dynamic Recovery Effects on Ion Irradiation Damage in...

336

Obstacles to Determining Punitive Damages in Class Actions  

E-Print Network [OSTI]

Courts and commentators have often embraced the class action device as an ideal means of assessing punitive damages fairly in mass tort cases. In this Article, Professor Hines sounds a cautionary note by identifying a number of procedural...

Hines, Laura J.

2001-01-01T23:59:59.000Z

337

Assessing blackbird damage to ripening rice in Matagorda County, Texas  

E-Print Network [OSTI]

of pyrotechnic and auditory scare devices, but with only limited success. However, in order to develop new control techniques, as well as to test the efficacy of current techniques, damage must be accurately assessed. Large scale estimates (over entire fields...

Wright, Robert Glen

1987-01-01T23:59:59.000Z

338

Hail Ice Damage of Stringer-Stiffened Curved Composite Panels /  

E-Print Network [OSTI]

Damage. Composite Structures 2003;62:21321. Ice Drop.How to make clear ice. 28 February 2011. Victoria, BC,2011/02/how-to- make-clear-ice-that-actually-works/ Graham,

Le, Jacqueline Linh

2013-01-01T23:59:59.000Z

339

Drag amplification and fatigue damage in vortex-induced vibrations  

E-Print Network [OSTI]

Fatigue damage and drag force amplification due to Vortex-Induced-Vibrations (VIV) continue to cause significant problems in the design of structures which operate in ocean current environments. These problems are magnified ...

Jhingran, Vikas Gopal

2008-01-01T23:59:59.000Z

340

Visual Indication of Mechanical Damage Using Core-Shell Microcapsules  

E-Print Network [OSTI]

-7 Changes in pH have been used to detect compression in polymer brushes,8 and microcapsules containing a p have been incorporated into filled hollow fibers to enhance damage visibility in the structure

Sottos, Nancy R.

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Atomistic simulations of radiation damage in amorphous metal alloys  

E-Print Network [OSTI]

While numerous fundamental studies have characterized the atomic-level radiation response mechanisms in irradiated crystalline alloys, comparatively little is known regarding the mechanisms of radiation damage in amorphous ...

Baumer, Richard E. (Richard Edward)

2013-01-01T23:59:59.000Z

342

Spatially localized generation of nucleotide sequence-specific DNA damage  

E-Print Network [OSTI]

Spatially localized generation of nucleotide sequence-specific DNA damage Dennis H. Oh* , Brett A- neously manipulated at the nucleotide level and in three dimen- sions. This approach for targeting

Boxer, Steven G.

343

Economic Damages from Climate Change: An Assessment of Market Impacts  

E-Print Network [OSTI]

damage induced by sea level rise in the United States. InImpacts on Water Sea Level Rise Temperature-Related Extremewater supply and sea level rise and the costs of adjustment

Hanemann, W Michael; Dale, Larry

2006-01-01T23:59:59.000Z

344

Graded Materials for Resistance to Contact Deformation and Damage  

E-Print Network [OSTI]

Graded Materials for Resistance to Contact Deformation and Damage S. Suresh The mechanical response as diverse as tribology, geology, optoelectronics, biomechanics, fracture mechanics, and nanotechnology changes in the elastic properties of sands, soils, and rocks beneath Earth's surface in- fluence

Suresh, Subra

345

Effects of ballistic damage on the dynamics of composite driveshafts  

E-Print Network [OSTI]

The objective of this research program is to study the dynamics of a composite driveshaft before and after ballistic damage is incurred. Driveshafts are tested under static and dynamic loads to obtain material, mechanical, and vibrational...

Ayers, Thomas Ray

1993-01-01T23:59:59.000Z

346

Linking Cell Cycle Reentry and DNA Damage in Neurodegeneration  

E-Print Network [OSTI]

Aberrant cell cycle activity and DNA damage have been observed in neurons in association with various neurodegenerative conditions. While there is strong evidence for a causative role for these events in neurotoxicity, it ...

Kim, Dohoon

347

Existence and Regularity for Dynamic Viscoelastic Adhesive Contact with Damage  

SciTech Connect (OSTI)

A model for the dynamic process of frictionless adhesive contact between a viscoelastic body and a reactive foundation, which takes into account the damage of the material resulting from tension or compression, is presented. Contact is described by the normal compliance condition. Material damage is modelled by the damage field, which measures the pointwise fractional decrease in the load-carrying capacity of the material, and its evolution is described by a differential inclusion. The model allows for different damage rates caused by tension or compression. The adhesion is modelled by the bonding field, which measures the fraction of active bonds on the contact surface. The existence of the unique weak solution is established using the theory of set-valued pseudomonotone operators introduced by Kuttler and Shillor (1999). Additional regularity of the solution is obtained when the problem data is more regular and satisfies appropriate compatibility conditions.

Kuttler, Kenneth L. [Department of Mathematics, Brigham Young University, Provo, UT 84602 (United States)], E-mail: klkuttler@math.byu.edu; Shillor, Meir [Department of Mathematics and Statistics, Oakland University, Rochester, MI 48309 (United States)], E-mail: shillor@oakland.edu; Fernandez, Jose R. [Departamento de Matematica Aplicada, Facultade de Matematicas, University of Santiago de Compostela, 15706 Santiago de Compostela (Spain)], E-mail: jramon@usc.es

2006-01-15T23:59:59.000Z

348

National Nuclear Science Week 2012 - SRSCRO  

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

to Know Nuclear National Nuclear Science Week January 23 - 27, 2012 Fostering a deeper public understanding Logos for: National Nuclear Science Week, Nuclear Workforce Initiative,...

349

Whither Nuclear Physics ?  

E-Print Network [OSTI]

Nuclear Physics has had its ups and downs. However in recent years, bucked up by some new and often puzzling data, it has become a potentially very rich field. We review some of these exciting developments in a few important sectors of nuclear physics. Emphasis shall be on the study of exotic nuclei and the new physics that these nuclei are teaching us.

Syed Afsar Abbas

2008-01-07T23:59:59.000Z

350

Nuclear Explosive Safety  

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

The directive establishes specific nuclear explosive safety (NES) program requirements to implement the DOE NES standards and other NES criteria for routine and planned nuclear explosive operations. Cancels DOE O 452.2B. Canceled by DOE O 452.2D.

2006-06-12T23:59:59.000Z

351

[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

352

(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

353

Nuclear physics and cosmology  

SciTech Connect (OSTI)

There are important aspects of Cosmology, the scientific study of the large scale properties of the universe as a whole, for which nuclear physics can provide insights. Here, we will focus on Standard Big-Bang Nucleosynthesis and we refer to the previous edition of the School [1] for the aspects concerning the variations of constants in nuclear cosmo-physics.

Coc, Alain [Centre de Sciences Nuclaires et de Sciences de la Matire (CSNSM), CNRS/IN2P3, Universit Paris Sud 11, UMR 8609, Btiment 104, F-91405 Orsay Campus (France)

2014-05-09T23:59:59.000Z

354

Quantitative studies of severe fuel damage using delayed neutron data  

SciTech Connect (OSTI)

A technique to quantify fuel damage in an LMR through analysis of delayed neutron data is presented, which is suitable for analysis of both small-scale in-pile experiments and full-scale plants. Validating analyses are described for five in-pile severe accident simulations performed within the SLSF and Mol 7C test programs. Comparison is made of measured and calculated amounts of fuel damage. 8 refs., 5 figs., 2 tabs.

Bauer, T.H.; Braid, T.H. (Argonne National Lab., IL (USA)); Schleisiek, K. (Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.))

1990-01-01T23:59:59.000Z

355

Quantitative studies of severe fuel damage using delayed neutron data  

SciTech Connect (OSTI)

In this paper, a technique is presented to quantify fuel damage in a liquid-metal reactor through fast-running computer analysis of delayed neutron data, suitable for analysis of both small-scale in-pile experiments and full-scale plants. Validating analyses are described for five in-pile severe accident simulations performed within the Sodium Loop Safety Facility and Mol-7C test programs. Comparison is made of measured and calculated amounts of fuel damage.

Bauer, T.H.; Braiel, T.H. (Argonne National Lab., IL (United States)); Schleisiek, K. (Kernforschungszentrum Karlsruhe GmbH (Germany))

1992-09-01T23:59:59.000Z

356

The application of ultrasonics to assess damage in composite materials  

E-Print Network [OSTI]

THE APPLICATION OF ULTRASONICS TO ASSESS DAMAGE IN COMPOSITE MATERIALS A Thesis by JOHN GREGORY EDEN Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE... December 1985 Major Subjectr Aerospace Engineering THE APPLICATION OF ULTRASONICS TO ASSESS DAMAGE IN COMPOSITE MATERIALS A Thesis by JOHN GREGORY EDEN Approved as to style and content by: (V. . Kinra, Chairman) (D. H. Allen, Member) (R. A...

Eden, John Gregory

2012-06-07T23:59:59.000Z

357

Viscoelastic{Viscoplastic Damage Model for Asphalt Concrete  

E-Print Network [OSTI]

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 2.2.1 Yield surface . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 2.2.2 Viscoplastic potential energy function . . . . . . . . . . . . . . 23 2.2.3 Hardening function . . . . . . . . . . . . . . . . . . . . . . . . 23 2.3 Numerical... viii LIST OF FIGURES FIGURE Page 1.1 Moisture-induced damage in pavements results in raveling and potholing 4 1.2 Adhesive and cohesive failure . . . . . . . . . . . . . . . . . . . . . . . 5 1.3 Damaged and e ective undamaged con gurations...

Graham, Michael A.

2010-10-12T23:59:59.000Z

358

Grey Squirrel bark stripping damage A Case Study  

E-Print Network [OSTI]

Height & DBH each tree Stems per ha Basal area Thinned Nov 1998 43% removed Growth Rate 1998 & 2003 with no damage 223 81.1 51 39 7 13/04/2010 #12;Case study DBH Tree size (DBH) v year of damage for `new.4 9.4 11.4 10 9 12 11 Basal area Post thinning 25.4 18.0 20.0 18 20 18 19 Total Basal area 27.2 28

359

Predicting threshold and location of laser damage on optical surfaces  

DOE Patents [OSTI]

An apparatus useful in the prediction of the damage threshold of various optical devices, the location of weak spots on such devices and the location, identification, and elimination of optical surface impurities comprising, a focused and pulsed laser, an photo electric detector/imaging means, and a timer. The weak spots emit photoelectrons when subjected to laser intensities that are less than the intensity actually required to produce the damage. The weak spots may be eliminated by sustained exposure to the laser beam.

Siekhaus, Wigbert (Berkeley, CA)

1987-01-01T23:59:59.000Z

360

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

Note: This page contains sample records for the topic "nuclear damage contingent" 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

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

362

NuclearNuclear ""BurningBurning"" of Nuclearof Nuclear ""WasteWaste"" Constantine P. Tzanos  

E-Print Network [OSTI]

as a geologic repository for disposal of spent nuclear fuel and high level radioactive waste. #12;The YuccaNuclearNuclear ""BurningBurning"" of Nuclearof Nuclear ""WasteWaste"" Constantine P. Tzanos Argonne-level radioactive waste that has accumulated at 72 commercial and 4 DOE sites. s U.S. Congress adopted the Nuclear

363

Laser-induced Damage in Optical Materials: 2004  

SciTech Connect (OSTI)

This volume contains papers presented at the 35th Annual Symposium on Optical Materials for High-Power Lasers, held at the National Institute of Standards and Technology in Boulder, Colorado, 22-24 September 2003. The symposium was attended by 125 participants from China, India, Russia, France, Germany, Japan, the United States, and the United Kingdom. A meeting summary and some 75 reviewed papers appear. The book is divided into sections devoted to the following topics: thin films, surfaces and mirrors, fundamental mechanisms, materials and measurements, and finally, understanding optical damage with ultrashort laser pulses. Topics of interest to the high-peak-power and high-average-power laser communities in addition to damage issues related to various research efforts and commercial laser applications are discussed. Also discussed are improved scaling relations as a function of pulse duration in the femtosecond range, beam footprint size, and irradiation of optical materials with wavelengths down to the x-ray region. New sources at shorter wavelengths continue to be developed, and a corresponding shift in emphasis to short-wavelength and repetitively pulsed damage problems can be seen in some of these papers. Fabrication and test procedures are discussed particularly in the area of thin films. New materials and the implication of defects on the damage process are emphasized in addition to new reports of conditioning effects and damage repair or damage mitigation.

Exarhos, Gregory J.; Guenther, Arthur H.; Kaiser, Norbert; Lewis, Keith L.; Soileau, M. J.; Stolz, Christopher J.

2005-03-01T23:59:59.000Z

364

Femtosecond pulse damage thresholds of dielectric coatings in vacuum  

SciTech Connect (OSTI)

At 10-7 Torr, the multiple femtosecond pulse damage threshold, F(?), is about 10% of the single pulse damage fluence F(1) for hafnia and silica films compared to about 65% and 50%, respectively, at 630 Torr. In contrast, the single-pulse damage threshold is pressure independent. The decrease of F(?) with decreasing air pressure correlates with the water vapor and oxygen content of the ambient gas with the former having the greater effect. The decrease in F(?) is likely associated with an accumulation of defects derived from oxygen deficiency, for example vacancies. From atmospheric air pressure to pressures of {approx}3 x 10{sup -6} Torr, the damage 'crater' starts deterministically at the center of the beam and grows in diameter as the fluence increases. At pressure below 3x10-6 Torr, damage is initiated at random 'sites' within the exposed area in hafnia films, while the damage morphology remains deterministic in silica films. A possible explanation is that absorbing centers are created at predisposed sample sites in hafnia, for example at boundaries between crystallites, or crystalline and amorphous phases.

Michelle D. Shinn, Duy N. Nguyen, Luke A. Emmert ,Paul Schwoebel, Dinesh Patel, Carmen S. Menoni, Wolfgang Rudolph

2011-03-01T23:59:59.000Z

365

Quercitrin protects skin from UVB-induced oxidative damage  

SciTech Connect (OSTI)

Exposure of the skin to ultraviolet B (UVB) radiation causes oxidative damage to skin, resulting in sunburn, photoaging, and skin cancer. It is generally believed that the skin damage induced by UV irradiation is a consequence of generation of reactive oxygen species (ROS). Recently, there is an increased interest in the use of natural products as chemopreventive agents for non-melanoma skin cancer (NMSC) due to their antioxidants and anti-inflammatory properties. Quercitrin, glycosylated form of quercetin, is the most common flavonoid in nature with antioxidant properties. The present study investigated the possible beneficial effects of quercitrin to inhibit UVB irradiation-induced oxidative damage in vitro and in vivo. Our results showed that quercitrin decreased ROS generation induced by UVB irradiation in JB6 cells. Quercitrin restored catalase expression and GSH/GSSG ratio reduced by UVB exposure, two major antioxidant enzymes, leading to reductions of oxidative DNA damage and apoptosis and protection of the skin from inflammation caused by UVB exposure. The present study demonstrated that quercitrin functions as an antioxidant against UVB irradiation-induced oxidative damage to skin. - Highlights: Oxidative stress plays a key role in UV-induced cell and tissue injuries. Quercitrin decreases ROS generation and restores antioxidants irradiated by UVB. Quercitrin reduces UVB-irradiated oxidative DNA damage, apoptosis, and inflammation. Quercitrin functions as an antioxidant against UVB-induced skin injuries.

Yin, Yuanqin [Cancer Institute, The First Affiliated Hospital, China Medical University, Shenyang (China); Graduate Center for Toxicology, University of Kentucky, 1095 VA Drive, Lexington, KY (United States); Li, Wenqi; Son, Young-Ok; Sun, Lijuan; Lu, Jian; Kim, Donghern; Wang, Xin [Graduate Center for Toxicology, University of Kentucky, 1095 VA Drive, Lexington, KY (United States); Yao, Hua [Department of Stomatology, The First Affiliated Hospital, College of Medicine, Zhejiang University, Hangzhou, Zhejiang (China); Wang, Lei; Pratheeshkumar, Poyil; Hitron, Andrew J. [Graduate Center for Toxicology, University of Kentucky, 1095 VA Drive, Lexington, KY (United States); Luo, Jia [Department of Internal Medicine, University of Kentucky, 800 Rose Street, Lexington, KY (United States); Gao, Ning [Department of Pharmacognos, College of Pharmacy, 3rd Military Medical University, Chongqing (China); Shi, Xianglin [Graduate Center for Toxicology, University of Kentucky, 1095 VA Drive, Lexington, KY (United States); Zhang, Zhuo, E-mail: zhuo.zhang@uky.edu [Graduate Center for Toxicology, University of Kentucky, 1095 VA Drive, Lexington, KY (United States)

2013-06-01T23:59:59.000Z

366

acetaminophen-induced oxidative damage: Topics by E-print Network  

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

and damage detection...21 3.5 Damage identification using a 3DOFs reduced order system Yang, Jann 105 Numerical aperture...

367

E-Print Network 3.0 - adapted damage control Sample Search Results  

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

Carlo simulation Summary: : Monte Carlo simulation; Masked irradiation damage; Josephson junction 1. Introduction Controlled... controlled damaged barrier layers, due to the long...

368

Reliability-based framework for fatigue damage prognosis of bonded structural elements in aerospace composite structures  

E-Print Network [OSTI]

situ damage detection of composite materials for structuralmaterials, Journal of Composite Materials , 10, 342-354,effects in damaged composite aerospace structures ,

Gobbato, Maurizio

2011-01-01T23:59:59.000Z

369

Western Interstate Nuclear Compact State Nuclear Policy (Multiple States)  

Broader source: Energy.gov [DOE]

Legislation authorizes states' entrance into the Western Interstate Nuclear Compact, which aims to undertake the cooperation of participating states in deriving the optimum benefit from nuclear and...

370

China's Nuclear Industry After Fukushima  

E-Print Network [OSTI]

2013-9 January 2013 Chinas Nuclear Industry After FukushimaMarch 2011 Fukushima nuclear accident has had a significanton the future of Chinas nuclear power. First, it highlights

YUAN, Jingdong

2013-01-01T23:59:59.000Z

371

THz Dynamic Nuclear Polarization NMR  

E-Print Network [OSTI]

Dynamic nuclear polarization (DNP) increases the sensitivity of nuclear magnetic resonance (NMR) spectroscopy by using high frequency microwaves to transfer the polarization of the electrons to the nuclear spins. The ...

Nanni, Emilio Alessandro

372

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

373

Is Nuclear Energy the Solution?  

E-Print Network [OSTI]

10.1007/s11270-009-0270-y Is Nuclear Energy the Solution?MHS) attended a lecture on Nuclear Responsibility on theof the Alliance for Nuclear Responsibility. The information

Saier, Milton H.; Trevors, Jack T.

2010-01-01T23:59:59.000Z

374

Supporting Our Nation's Nuclear Industry  

ScienceCinema (OSTI)

On the 60th anniversary of the world's first nuclear power plant to produce electricity, Assistant Secretary for Nuclear Energy Peter Lyons discusses the Energy Department's and the Administration's commitment to promoting a nuclear renaissance in the United States.

Lyons, Peter

2013-05-29T23:59:59.000Z

375

China's Nuclear Industry After Fukushima  

E-Print Network [OSTI]

Brief 2013-9 January 2013 Chinas Nuclear Industry Aftera significant impact on the future of Chinas nuclear power.the importance of safety as China builds more nuclear power

YUAN, Jingdong

2013-01-01T23:59:59.000Z

376

On Damage Propagation in a Soft Low-Permeability Formation  

SciTech Connect (OSTI)

In this presentation, we develop a mathematical model of fluid flow with changing formation properties. The modification of formation permeability is caused by development of a connected system of fractures. As the fluids are injected or withdrawn from the reservoir, the balance between the pore pressure and the geostatic formation stresses is destroyed. If the strength of the rock is not sufficient to accommodate such an imbalance, the cementing bonds between the rock grains become broken. Such a process is called damage propagation. The micromechanics and the basic mathematical model of damage propagation have been studied in [7]. The theory was further developed in [3], where new nonlocal damage propagation model has been studied. In [2] this theory has been enhanced by incorporation of the coupling between damage propagation and fluid flow. As it has been described above, the forced fluid flow causes changes in the rock properties including formation permeability. At the same time, changing permeability facilitates fluid flow and, therefore, enhances damage propagation. One of the principle concepts introduced in [3] and [2] is the characterization of damage by a dimensionless ratio of the number of broken bonds to the number of bonds in pristine rock per unit volume. It turns out, that the resulting mathematical model consist of a system of two nonlinear parabolic equations. As it has been shown in [6] using modeling of micromechanical properties of sedimentary rocks, at increasing stress the broken bonds coalesce into a system of cracks surrounding practically intact matrix blocks. These blocks have some characteristic size and a regular geometry. The initial microcracks expand, interact with each other, coalesce and form bigger fractures, etc. Therefore, as the damage is accumulated, the growing system of connected fractures determines the permeability of the reservoir rock. Significant oil deposits are stored in low-permeability soft rock reservoirs such as shales, chalks and diatomites [9, 10]. The permeability of the pristine formation matrix in such reservoirs is so low that oil production was impossible until hydraulic fracturing was applied. For development of correct production policy, it is very significant to adequately understand and predict how fast and to what extend the initial damage induced by drilling and hydrofracturing will propagate into the reservoir. The importance of fractures for rock flow properties is a well-established and recognized fact [4, 9, 5]. Different conceptual models have been developed [8]. In this study, we propose a damage propagation model based on a combination of the model of double-porosity and double-permeability medium [4] and a modification of the model of damage propagation developed in [2].

Silin, D.; Patzek, T.; Barenblatt, G.I.

2003-11-18T23:59:59.000Z

377

Virginia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

378

Ohio Nuclear Profile - Power Plants  

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

Ohio nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

379

Arkansas Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

380

Michigan Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Alabama Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

382

Texas Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

383

Tennessee Nuclear Profile - Power Plants  

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

Tennessee nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

384

Georgia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

385

Nebraska Nuclear Profile - Power Plants  

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

Nebraska nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

386

Arizona Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

387

Maryland Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

388

Illinois Nuclear Profile - Power Plants  

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

Illinois nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

389

Florida Nuclear Profile - Power Plants  

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

Florida nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

390

Wisconsin Nuclear Profile - Power Plants  

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

Wisconsin nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

391

Minnesota Nuclear Profile - Power Plants  

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

Minnesota nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

392

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...

393

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....

394

China's Nuclear Industry After Fukushima  

E-Print Network [OSTI]

s Nuclear Industry After Fukushima Jingdong YUAN SummaryT he March 2011 Fukushima nuclear accident has had aand speedy responses to Fukushima-like and other unexpected

YUAN, Jingdong

2013-01-01T23:59:59.000Z

395

Nuclear & Particle Physics, Astrophysics, Cosmology  

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

production, nuclear weapons, and nuclear threat reduction Proton radiography, muon tomography, proton active interrogation, wide-angle, fast-response optical telescopes, and...

396

Nuclear Forensics | ornl.gov  

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

nuclear facilities, and inorganic mass spectrometry as applied to traditional nuclear forensic science applications. The application of classical forensic science tools (mass...

397

Inspection of Nuclear Power Plant Containment Structures  

SciTech Connect (OSTI)

Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.

Graves, H.L.; Naus, D.J.; Norris, W.E.

1998-12-01T23:59:59.000Z

398

Evaluated Nuclear Data  

SciTech Connect (OSTI)

This chapter describes the current status of evaluated nuclear data for nuclear technology applications. We start with evaluation procedures for neutron-induced reactions focusing on incident energies from the thermal energy up to 20 MeV, though higher energies are also mentioned. This is followed by examining the status of evaluated neutron data for actinides that play dominant role in most of the applications, followed by coolants/moderators, structural materials and fission products. We then discuss neutron covariance data that characterize uncertainties and correlations. We explain how modern nuclear evaluated data libraries are validated against an extensive set of integral benchmark experiments. Afterwards, we briefly examine other data of importance for nuclear technology, including fission yields, thermal neutron scattering and decay data. A description of three major evaluated nuclear data libraries is provided, including the latest version of the US library ENDF/B-VII.0, European JEFF-3.1 and Japanese JENDL-3.3. A brief introduction is made to current web retrieval systems that allow easy access to a vast amount of up-to-date evaluated nuclear data for nuclear technology applications.

Oblozinsky, P.; Oblozinsky,P.; Herman,M.; Mughabghab,S.F.

2010-10-01T23:59:59.000Z

399

Structural Health Monitoring for Impact Damage in Composite Structures.  

SciTech Connect (OSTI)

Composite structures are increasing in prevalence throughout the aerospace, wind, defense, and transportation industries, but the many advantages of these materials come with unique challenges, particularly in inspecting and repairing these structures. Because composites of- ten undergo sub-surface damage mechanisms which compromise the structure without a clear visual indication, inspection of these components is critical to safely deploying composite re- placements to traditionally metallic structures. Impact damage to composites presents one of the most signi fi cant challenges because the area which is vulnerable to impact damage is generally large and sometimes very dif fi cult to access. This work seeks to further evolve iden- ti fi cation technology by developing a system which can detect the impact load location and magnitude in real time, while giving an assessment of the con fi dence in that estimate. Fur- thermore, we identify ways by which impact damage could be more effectively identi fi ed by leveraging impact load identi fi cation information to better characterize damage. The impact load identi fi cation algorithm was applied to a commercial scale wind turbine blade, and results show the capability to detect impact magnitude and location using a single accelerometer, re- gardless of sensor location. A technique for better evaluating the uncertainty of the impact estimates was developed by quantifying how well the impact force estimate meets the assump- tions underlying the force estimation technique. This uncertainty quanti fi cation technique was found to reduce the 95% con fi dence interval by more than a factor of two for impact force estimates showing the least uncertainty, and widening the 95% con fi dence interval by a fac- tor of two for the most uncertain force estimates, avoiding the possibility of understating the uncertainty associated with these estimates. Linear vibration based damage detection tech- niques were investigated in the context of structural stiffness reductions and impact damage. A method by which the sensitivity to damage could be increased for simple structures was presented, and the challenges of applying that technique to a more complex structure were identi fi ed. The structural dynamic changes in a weak adhesive bond were investigated, and the results showed promise for identifying weak bonds that show little or no static reduction in stiffness. To address these challenges in identifying highly localized impact damage, the possi- bility of detecting damage through nonlinear dynamic characteristics was also identi fi ed, with a proposed technique which would leverage impact location estimates to enable the detection of impact damage. This nonlinear damage identi fi cation concept was evaluated on a composite panel with a substructure disbond, and the results showed that the nonlinear dynamics at the damage site could be observed without a baseline healthy reference. By further developing impact load identi fi cation technology and combining load and damage estimation techniques into an integrated solution, the challenges associated with impact detection in composite struc- tures can be effectively solved, thereby reducing costs, improving safety, and enhancing the operational readiness and availability of high value assets.

Roach, Dennis P.; Raymond Bond (Purdue); Doug Adams (Purdue)

2014-08-01T23:59:59.000Z

400

Nuclear Regulatory Commission issuances  

SciTech Connect (OSTI)

This document is the March 1996 listing of NRC issuances. Included are: (1) NRC orders granting Cleveland Electric Illuminating Company`s petition for review of the ASLB order LBP-95-17, (2) NRC orders relating to the potential disqualification of two commissioners in the matter of the decommissioning of Yankee Nuclear Power Station, (3) ASLB orders pertaining to the Oncology Services Corporation, (4) ASLB orders pertaining to the Radiation Oncology Center, (5) ASLB orders pertaining to the Yankee Nuclear Power Station, and (6) Director`s decision pertaining to the Yankee Nuclear Power Station.

NONE

1996-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

Monitoring international nuclear activity  

SciTech Connect (OSTI)

The LBNL Table of Isotopes website provides primary nuclearinformation to>150,000 different users annually. We have developedthe covert technology to identify users by IP address and country todetermine the kinds of nuclear information they are retrieving. Wepropose to develop pattern recognition software to provide an earlywarning system to identify Unusual nuclear activity by country or regionSpecific nuclear/radioactive material interests We have monitored nuclearinformation for over two years and provide this information to the FBIand LLNL. Intelligence is gleaned from the website log files. Thisproposal would expand our reporting capabilities.

Firestone, R.B.

2006-05-19T23:59:59.000Z

402

Nuclear Physics: Experiment Research  

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 ConsortiumNuclear PairsNuclear Physicsfrom

403

Nuclear Science & Technology  

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

404

Nuclear Weapons Journal  

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 ConsortiumNuclearSafeguardsResearchNuclear Weapons

405

Procedures for the external event core damage frequency analyses for NUREG-1150  

SciTech Connect (OSTI)

This report presents methods which can be used to perform the assessment of risk due to external events at nuclear power plants. These methods were used to perform the external events risk assessments for the Surry and Peach Bottom nuclear power plants as part of the NRC-sponsored NUREG-1150 risk assessments. These methods apply to the full range of hazards such as earthquakes, fires, floods, etc. which are collectively known as external events. The methods described in this report have been developed under NRC sponsorship and represent, in many cases, both advancements and simplifications over techniques that have been used in past years. They also include the most up-to-date data bases on equipment seismic fragilities, fire occurrence frequencies and fire damageability thresholds. The methods described here are based on making full utilization of the power plant systems logic models developed in the internal events analyses. By making full use of the internal events models one obtains an external event analysis that is consistent both in nomenclature and in level of detail with the internal events analyses, and in addition, automatically includes all the appropriate random and tests/maintenance unavailabilities as appropriate. 50 refs., 9 figs., 11 tabs.

Bohn, M.P.; Lambright, J.A. (Sandia National Labs., Albuquerque, NM (USA))

1990-11-01T23:59:59.000Z

406

Synergistic Smart Fuel For In-pile Nuclear Reactor Measurements  

SciTech Connect (OSTI)

In March 2011, an earthquake of magnitude 9.0 on the Richter scale struck Japan with its epicenter on the northeast coast, near the Tohoku region. In addition to the immense physical destruction and casualties across the country, several nuclear power plants (NPP) were affected. It was the Fukushima Daiichi NPP that experienced the most severe and irreversible damage. The earthquake brought the reactors at Fukushima to an automatic shutdown and because the power transmission lines were damaged, emergency diesel generators (EDGs) were activated to ensure that there was continued cooling of the reactors and spent fuel pools. The situation was being successfully managed until the tsunami hit about forty-five minutes later with a maximum wave height of approximately 15 m. The influx of water submerged the EDGs, the electrical switchgear, and dc batteries, resulting in the total loss of power to the reactors.2 At this point, the situation became critical. There was a loss of the sensors and instrumentation within the reactor that could have provided valuable information to guide the operators to make informed decisions and avoid the unfortunate events that followed. In the light of these events, we have developed and tested a potential self-powered thermoacoustic system, which will have the ability to serve as a temperature sensor and can transmit data independently of electronic networks. Such a device is synergistic with the harsh environment of the nuclear reactor as it utilizes the heat from the nuclear fuel to provide the input power.

James A. Smith; Dale K. Kotter; Randall A. Ali; Steven L . Garrett

2013-10-01T23:59:59.000Z

407

NUCLEAR ENERGY Annals of Nuclear Energy 32 (2005) 812842  

E-Print Network [OSTI]

annals of NUCLEAR ENERGY Annals of Nuclear Energy 32 (2005) 812­842 www of Nuclear Energy 32 (2005) 812­842 background noise is present, this technique is useful to indicate.elsevier.com/locate/anucene Identification and localization of absorbers of variable strength in nuclear reactors C. Demazie`re a,*, G

Demazière, Christophe

408

Precursors to potential severe core damage accidents: 1994, a status report. Volume 21: Main report and appendices A--H  

SciTech Connect (OSTI)

Nine operational events that affected eleven commercial light-water reactors (LWRs) during 1994 and that are considered to be precursors to potential severe core damage are described. All these events had conditional probabilities of subsequent severe core damage greater than or equal to 1.0 {times} 10{sup {minus}6}. These events were identified by computer-screening the 1994 licensee event reports from commercial LWRs to identify those that could be potential precursors. Candidate precursors were then selected and evaluated in a process similar to that used in previous assessments. Selected events underwent engineering evaluation that identified, analyzed, and documented the precursors. Other events designated by the Nuclear Regulatory Commission (NRC) also underwent a similar evaluation. Finally, documented precursors were submitted for review by licensees and NRC headquarters and regional offices to ensure that the plant design and its response to the precursor were correctly characterized. This study is a continuation of earlier work, which evaluated 1969--1981 and 1984--1993 events. The report discusses the general rationale for this study, the selection and documentation of events as precursors, and the estimation of conditional probabilities of subsequent severe core damage for events. This document is bound in two volumes: Vol. 21 contains the main report and Appendices A--H; Vol. 22 contains Appendix 1.

Belles, R.J.; Cletcher, J.W.; Copinger, D.A.; Vanden Heuvel, L.N. [Oak Ridge National Lab., TN (United States); Dolan, B.W.; Minarick, J.W. [Oak Ridge National Lab., TN (United States)]|[Science Applications International Corp., Oak Ridge, TN (United States)

1995-12-01T23:59:59.000Z

409

Nuclear Controls | National Nuclear Security Administration  

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 | National Nuclear Security

410

Nuclear Operations | National Nuclear Security Administration  

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 Nuclear Navy

411

Nuclear Verification | National Nuclear Security Administration  

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 |NavyNuclear

412

Monthly/Annual Energy Review - nuclear section  

Reports and Publications (EIA)

Monthly and latest annual statistics on nuclear electricity capacity, generation, and number of operable nuclear reactors.

2015-01-01T23:59:59.000Z

413

Nuclear Material Packaging Manual  

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

The manual provides detailed packaging requirements for protecting workers from exposure to nuclear materials stored outside of an approved engineered contamination barrier. No cancellation. Certified 11-18-10.

2008-03-07T23:59:59.000Z

414

Nuclear Emergency Search Team  

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

To establish Department of Energy (DOE) policy for Nuclear Emergency Search Team (NEST) operations to malevolent radiological incidents. This directive does not cancel another directive. Canceled by DOE O 153.1.

1991-09-20T23:59:59.000Z

415

PDFs for nuclear targets  

E-Print Network [OSTI]

Understanding nuclear effects in parton distribution functions (PDF) is an essential component needed to determine the strange and anti-strange quark contributions in the proton. In addition Nuclear Parton Distribution Functions (NPDF) are critically important for any collider experiment with nuclei (e.g. RHIC, ALICE). Here two next-to-leading order chi^2-analyses of NPDF are presented. The first uses neutral current charged-lepton Deeply Inelastic Scattering (DIS) and Drell-Yan data for several nuclear targets and the second uses neutrino-nucleon DIS data. We compare the nuclear corrections factors (F_2^Fe/F_2^D) for the charged-lepton data with other results from the literature. In particular, we compare and contrast fits based upon the charged-lepton DIS data with those using neutrino-nucleon DIS data.

Karol Kovarik

2010-06-25T23:59:59.000Z

416

INL '@work' Nuclear Engineer  

ScienceCinema (OSTI)

Heather MacLean talks about her job as a Nuclear Engineer for Idaho National Laboratory. For more information about INL careers, visit http://www.facebook.com/idahonationallaboratory.

McLean, Heather

2013-05-28T23:59:59.000Z

417

Relativistic Nuclear Collisions  

E-Print Network [OSTI]

A comprehensive introduction is given to the field of relativistic nuclear collisions, and the phase diagram of strongly interacting matter. The content of this complex of reviews is shown.

Reinhard Stock

2009-07-29T23:59:59.000Z

418

Management of Nuclear Materials  

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

To establish requirements and procedures for the management of nuclear materials within the Department of Energy (DOE). Cancels DOE 5660.1A. Canceled by DOE O 410.2.

1994-05-26T23:59:59.000Z

419

Western Nuclear Science Alliance  

SciTech Connect (OSTI)

The primary objective of the INIE program is to strengthen nuclear science and engineering programs at the member institutions and to address the long term goal of the University Reactor Infrastructure and Education Assistance Program.

Steve Reese; George Miller; Stephen Frantz; Denis Beller; Denis Beller; Ed Morse; Melinda Krahenbuhl; Bob Flocchini; Jim Elliston

2010-12-07T23:59:59.000Z

420

Management of Nuclear Materials  

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

To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Cancels DOE O 410.2. Admin Chg 1 dated 4-10-2014, cancels DOE O 410.2.

2009-08-17T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear damage contingent" 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

State Nuclear Profiles 2010  

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

60 Vermont Vermont total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 620 55.0 4,782 72.2 Hydro and Pumped Storage 324 28.7 1,347...

422

Pioneering the nuclear age  

SciTech Connect (OSTI)

This paper reviews the historical aspects of nuclear physics. The scientific aspects of the early transuranium elements are discussed and arms control measures are reviewed. 11 refs., 14 figs. (LSP)

Seaborg, G.T.

1988-09-01T23:59:59.000Z

423

International Nuclear Security  

SciTech Connect (OSTI)

This presentation discusses: (1) Definitions of international nuclear security; (2) What degree of security do we have now; (3) Limitations of a nuclear security strategy focused on national lock-downs of fissile materials and weapons; (4) What do current trends say about the future; and (5) How can nuclear security be strengthened? Nuclear security can be strengthened by: (1) More accurate baseline inventories; (2) Better physical protection, control and accounting; (3) Effective personnel reliability programs; (4) Minimize weapons-usable materials and consolidate to fewer locations; (5) Consider local threat environment when siting facilities; (6) Implement pledges made in the NSS process; and (7) More robust interdiction, emergency response and special operations capabilities. International cooperation is desirable, but not always possible.

Doyle, James E. [Los Alamos National Laboratory

2012-08-14T23:59:59.000Z

424

Nuclear material operations manual  

SciTech Connect (OSTI)

This manual provides a concise and comprehensive documentation of the operating procedures currently practiced at Sandia National Laboratories with regard to the management, control, and accountability of nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion.

Tyler, R.P.

1981-02-01T23:59:59.000Z

425

Nuclear Explosive Safety  

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

The directive provides supplemental details to support the requirements of DOE O 452.2C, Nuclear Explosive Safety, dated 6-12-06. Canceled by DOE M 452.2-1A.

2006-06-12T23:59:59.000Z

426

Mechanisms for microvascular damage induced by ultrasound-activated microbubbles  

SciTech Connect (OSTI)

To provide insight into the mechanisms of microvascular damage induced by ultrasound-activated microbubbles, experimental studies were performed to correlate microvascular damage to the dynamics of bubble-vessel interactions. High-speed photomicrography was used to record single microbubbles interacting with microvessels in ex vivo tissue, under the exposure of short ultrasound pulses with a center frequency of 1 MHz and peak negative pressures (PNP) ranging from 0.8-4 MPa. Vascular damage associated with observed bubble-vessel interactions was either indicated directly by microbubble extravasation or examined by transmission electron microscopy (TEM) analyses. As observed previously, the high-speed images revealed that ultrasound-activated microbubbles could cause distention and invagination of adjacent vessel walls, and could form liquid jets in microvessels. Vessel distention, invagination, and liquid jets were associated with the damage of microvessels whose diameters were smaller than those of maximally expanded microbubbles. However, vessel invagination appeared to be the dominant mechanism for the damage of relative large microvessels.

Chen Hong; Brayman, Andrew A.; Evan, Andrew P.; Matula, Thomas J. [Center for Industrial and Medical Ultrasound, Applied Physics Laboratory, University of Washington, Seattle, WA (United States); Department of Anatomy and Cell Biology and Medicine, Indiana University School of Medicine, Indianapolis (United States); Center for Industrial and Medical Ultrasound, Applied Physics Laboratory, University of Washington, Seattle, WA (United States)

2012-10-03T23:59:59.000Z

427

Geologic Assessment of the Damage Zone from the Second Test at Source Physics Experiment-Nevada (SPE-N)  

SciTech Connect (OSTI)

The National Center for Nuclear Security, established by the U.S. Department of Energy, National Nuclear Security Administration (NNSA), is conducting a series of explosive tests at the Nevada National Security Site that are designed to increase the understanding of certain basic physical phenomena associated with underground explosions. These tests will aid in developing technologies that might be used to detect underground nuclear explosions in support of verification activities for the Comprehensive Nuclear-Test-Ban Treaty. The initial project is a series of explosive tests, known collectively as the Source Physics Experiment-Nevada (SPE-N), being conducted in granitic rocks. The SPE-N test series is designed to study the generation and propagation of seismic waves. The results will help advance the seismic monitoring capability of the United States by improving the predictive capability of physics-based modeling of explosive phenomena. The first SPE N (SPE-N-1) test was conducted in May 2011, using 100 kg of explosives at the depth of 54.9 m in the U 15n source hole. SPE-N-2 was conducted in October 2011, using 1,000 kg of explosives at the depth of 45.7 m in the same source hole. The SPE-N-3 test was conducted in the same source hole in July 2012, using the same amount and type of explosive as for SPE-N-2, and at the same depth as SPE-N-2, within the damage zone created by the SPE-N-2 explosion to investigate damage effects on seismic wave propagation. Following the SPE-N-2 shot and prior to the SPE-N-3 shot, the core hole U-15n#10 was drilled at an angle from the surface to intercept the SPE-N-2 shot point location to obtain information necessary to characterize the damage zone. The objective was to determine the position of the damage zone near the shot point, at least on the northeast, where the core hole penetrated it, and obtain information on the properties of the damaged medium. Geologic characterization of the post-SPE-N-2 core hole included geophysical logging, a directional survey, and geologic description of the core to document visual evidence of damage. Selected core samples were provided to Sandia National Laboratories (SNL) for measurement of physical and mechanical properties. A video was also run in the source hole after it was cleaned out. A significant natural fault zone was encountered in the angle core hole between 5.7 and 7.5 m from the shot point. However, several of the fractures observed in the core hole are interpreted as having been caused by the explosion. The fractures are characterized by a fresh, mechanically broken look, with uncoated and very irregular surfaces. They tend to terminate against natural fractures and have orientations that differ from the previously defined natural fracture sets; they are common starting at about 5.4 m from the shot point. Within about 3.3 m of the shot point to the end of the recovered core at 1.6 m from the shot point, some of the core samples are softer and lighter in color, but do not appear to be weathered. It is thought this could be indicative of the presence of distributed microfracturing.

Townsend, M. J.; Huckins-Gang, H. E.; Prothro, L. B.; Reed, D. N.

2012-12-01T23:59:59.000Z

428

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...

429

b) Economic i) Total damage estimates: From Pimentel et al. (2000)  

E-Print Network [OSTI]

4) Impacts b) Economic i) Total damage estimates: From Pimentel et al. (2000) · United States #12;4) Impacts b) Economic i) Total damage estimates: From Pimentel et al. (2000) · United States Economic impacts from losses/damage #12;4) Impacts b) Economic i) Total damage estimates: From Pimentel et al

Nowak, Robert S.

430

Nuclear Energy Research Brookhaven National  

E-Print Network [OSTI]

Nuclear Energy Research Brookhaven National Laboratory William C. Horak, Chair Nuclear Science and Technology Department #12;BNL Nuclear Energy Research Brookhaven Graphite Research Reactor - 1948 National&T Department #12;Nuclear Energy Today 435 Operable Power Reactors, 12% electrical generation (100 in US, 19

Ohta, Shigemi

431

CONSTRUCTION OF NUCLEAR POWER PLANTS  

E-Print Network [OSTI]

CONSTRUCTION OF NUCLEAR POWER PLANTS A Workshop on "NUCLEAR ENERGY RENAISSANCE" Addressing WAS DEEPLY INVOLVED IN ALMOST EVERY ASPECT OF BUILDING THE PLANTS THROUGH Quality Assurance Nuclear IN CONSTRUCTION OF ST. LUCIE-2 #12;LESSONS LEARNED FROM St. Lucie-2 NUCLEAR POWER PLANTS CAN BE BUILT

432

NUCLEAR ENGINEERING Four Year Plan  

E-Print Network [OSTI]

NUCLEAR ENGINEERING Four Year Plan Fall 2009 Nuclear Engineering (67 hrs) CH Grade Perspectives (15;Nuclear Engineering Four Year Plan Starting Fall 2009 FALL Year 1 Credits WINTER Year 1 Credits SPRING I NE 452 3 Neutronic Analysis II NE 457 2 Nuclear Reactor Lab Western Culture (3): NE 467 4 Nucl

Tullos, Desiree

433

The dynamic interplay between DNA damage and metabolism : the metabolic fate and transport of DNA lesions and novel DNA damage derived from intermediary metabolism  

E-Print Network [OSTI]

The work presented in this thesis explores two novel and complementary facets of endogenous DNA damage: the development of biomarkers of inflammation based on metabolites of DNA damage products and the formation of DNA ...

Jumpathong, Watthanachai

2014-01-01T23:59:59.000Z

434

Application Of Shakedown Analysis To Cyclic Creep Damage Limits  

SciTech Connect (OSTI)

Shakedown analysis may be used to provide a conservative estimate of local rupture and hence cyclic creep damage for use in a creep-fatigue assessment. The shakedown analysis is based on an elastic-perfectly plastic material with a temperature-dependent pseudo yield stress defined to guarantee that a shakedown solution exists which does not exceed rupture stress and temperature for a defined life. The ratio of design life to the estimated maximum cyclic life is the shakedown creep damage. The methodology does not require stress classification and is also applicable to cycles over the full range of temperature above and below the creep regime. Full cyclic creep and damage analysis is the alternative when shakedown analysis appears to be excessively conservative.

Carter, Peter [Stress Engineering Services Inc.] [Stress Engineering Services Inc.; Jetter, Robert I [Consultant] [Consultant; Sham, Sam [ORNL] [ORNL

2012-01-01T23:59:59.000Z

435

Oxidative stress and oxidative damage in chemical carcinogenesis  

SciTech Connect (OSTI)

Reactive oxygen species (ROS) are induced through a variety of endogenous and exogenous sources. Overwhelming of antioxidant and DNA repair mechanisms in the cell by ROS may result in oxidative stress and oxidative damage to the cell. This resulting oxidative stress can damage critical cellular macromolecules and/or modulate gene expression pathways. Cancer induction by chemical and physical agents involves a multi-step process. This process includes multiple molecular and cellular events to transform a normal cell to a malignant neoplastic cell. Oxidative damage resulting from ROS generation can participate in all stages of the cancer process. An association of ROS generation and human cancer induction has been shown. It appears that oxidative stress may both cause as well as modify the cancer process. Recently association between polymorphisms in oxidative DNA repair genes and antioxidant genes (single nucleotide polymorphisms) and human cancer susceptibility has been shown.

Klaunig, James E., E-mail: jklauni@indiana.edu; Wang Zemin; Pu Xinzhu; Zhou Shaoyu

2011-07-15T23:59:59.000Z

436

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

437

Thermal annealing of laser damage precursors on fused silica surfaces  

SciTech Connect (OSTI)

Previous studies have identified two significant precursors of laser damage on fused silica surfaces at fluenes below {approx} 35 J/cm{sup 2}, photoactive impurities in the polishing layer and surface fractures. In the present work, isothermal heating is studied as a means of remediating the highly absorptive, defect structure associated with surface fractures. A series of Vickers indentations were applied to silica surfaces at loads between 0.5N and 10N creating fracture networks between {approx} 10{micro}m and {approx} 50{micro}m in diameter. The indentations were characterized prior to and following thermal annealing under various times and temperature conditions using confocal time-resolved photo-luminescence (CTP) imaging, and R/1 optical damage testing with 3ns, 355nm laser pulses. Significant improvements in the damage thresholds, together with corresponding reductions in CTP intensity, were observed at temperatures well below the glass transition temperature (T{sub g}). For example, the damage threshold on 05.N indentations which typically initiates at fluences <8 J/cm{sup 2} could be improved >35 J/cm{sup 2} through the use of a {approx} 750 C thermal treatment. Larger fracture networks required longer or higher temperature treatment to achieve similar results. At an annealing temperature > 1100 C, optical microscopy indicates morphological changes in some of the fracture structure of indentations, although remnants of the original fracture and significant deformation was still observed after thermal annealing. This study demonstrates the potential of using isothermal annealing as a means of improving the laser damage resistance of fused silica optical components. Similarly, it provides a means of further understanding the physics associated with optical damage and related mitigation processes.

Shen, N; Miller, P E; Bude, J D; Laurence, T A; Suratwala, T I; Steele, W A; Feit, M D; Wang, L L

2012-03-19T23:59:59.000Z

438

Focused ion beam damage to MOS integrated circuits  

SciTech Connect (OSTI)

Commercial focused ion beam (FIB) systems are commonly used to image integrated circuits (ICS) after device processing, especially in failure analysis applications. FIB systems are also often employed to repair faults in metal lines for otherwise functioning ICS, and are being evaluated for applications in film deposition and nanofabrication. A problem that is often seen in FIB imaging and repair is that ICS can be damaged during the exposure process. This can result in degraded response or out-right circuit failure. Because FIB processes typically require the surface of an IC to be exposed to an intense beam of 30--50 keV Ga{sup +} ions, both charging and secondary radiation damage are potential concerns. In previous studies, both types of effects have been suggested as possible causes of device degradation, depending on the type of device examined and/or the bias conditions. Understanding the causes of this damage is important for ICS that are imaged or repaired by a FIB between manufacture and operation, since the performance and reliability of a given IC is otherwise at risk in subsequent system application. In this summary, the authors discuss the relative roles of radiation damage and charging effects during FIB imaging. Data from exposures of packaged parts under controlled bias indicate the possibility for secondary radiation damage during FIB exposure. On the other hand, FIB exposure of unbiased wafers (a more common application) typically results in damage caused by high-voltage stress or electrostatic discharge. Implications for FIB exposure and subsequent IC use are discussed.

FLEETWOOD,D.M.; CAMPBELL,ANN N.; HEMBREE,CHARLES E.; TANGYUNYONG,PAIBOON; JESSING,JEFFREY R.; SODEN,JERRY M.

2000-05-10T23:59:59.000Z

439

Analysis of tank damage during the 1994 Northridge earthquake  

SciTech Connect (OSTI)

The damage sustained by cylindrical liquid storage tanks during the 1994 Northridge earthquake is summarized. It included elephant foot buckling, anchor failure and roof-shell connection separation. A few of the important lessons learned, in particular, as related to the accuracy of code computations in predicting the actual behavior of these structures are outlined. A detailed case study is presented to illustrate the application of current seismic design standards to a damaged unanchored tank and to demonstrate the use of a state-of-the-art finite element analysis in assessing the seismic safety of the same tank.

Haroun, M.A.; Bhatia, H. [Univ. of California, Irvine, CA (United States). Dept. of Civil and Environmental Engineering

1995-12-31T23:59:59.000Z

440

Optical Damage Threshold of Silicon for Ultrafast Infrared Pulses  

SciTech Connect (OSTI)

While silicon has several properties making it an attractive material for structure-based laser-driven acceleration, its optical damage threshold, a key parameter for high-gradient acceleration, has been unknown. Here we present measurements of the optical damage threshold of crystalline silicon for ultrafast pulses in the mid-infrared. The wavelengths tested span a range from the telecommunications band at 1550 nm extending longer toward the two-photon absorption threshold at around 2200 nm. We discuss the prevailing theories of ultrafast optical breakdown, describe the experimental setup and preliminary results, and propose a relevant performance parameter for candidate accelerator structures.

Cowan, B.; /SLAC

2006-09-07T23:59:59.000Z

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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
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441

Predicting threshold and location of laser damage on optical surfaces  

DOE Patents [OSTI]

Disclosed is an apparatus useful in the prediction of the damage threshold of various optical devices, the location of weak spots on such devices and the location, identification, and elimination of optical surface impurities. The apparatus comprises a focused and pulsed laser, a photo electric detector/imaging means, and a timer. The weak spots emit photoelectrons when subjected to laser intensities that are less than the intensity actually required to produce the damage. The weak spots may be eliminated by sustained exposure to the laser beam.

Siekhaus, W.

1985-02-04T23:59:59.000Z

442

BDS Thin Film UV Antireflection Laser Damage Competition  

SciTech Connect (OSTI)

UV antireflection coatings are a challenging coating for high power laser applications as exemplified by the use of uncoated Brewster's windows in laser cavities. In order to understand the current laser resistance of UV AR coatings in the industrial and university sectors, a double blind laser damage competition was performed. The coatings have a maximum reflectance of 0.5% at 355 nm at normal incidence. Damage testing will be performed using the raster scan method with a 7.5 ns pulse length on a single testing facility to facilitate direct comparisons. In addition to the laser resistance results, details of deposition processes and coating materials will also be shared.

Stolz, C J

2010-10-26T23:59:59.000Z

443

Measuring Radiation Damage from Heavy Energetic Ions in Aluminum  

SciTech Connect (OSTI)

An intense beam of 122 MeV/u (9.3 GeV) 76Ge ions was stopped in aluminum samples at the Coupled Cyclotron Facility at NSCL, MSU. Attempts were made at ORNL to measure changes in material properties by measuring changes in electrical resistivity and microhardness, and by transmission electron microscopy characterization, for defect density caused by radiation damage, as a function of depth and integrated ion flux. These measurements are relevant for estimating damage to components at a rare isotope beam facility.

Kostin, M., PI-MSU; Ronningen, R., PI-MSU; Ahle, L., PI-LLNL; Gabriel, T., Scientific Investigation and Development; Mansur, L., PI-ORNL; Leonard, K., ORNL; Mokhov, N., FNAL; Niita, K., RIST, Japan

2009-02-21T23:59:59.000Z

444

The elements of nuclear power  

SciTech Connect (OSTI)

An introduction to the principles of nuclear fission power generation. Describes the physical processes which occur in a nuclear reactor and discusses the theory behind the calculations. Also covers heat transfer in reactors, thermodynamic power cycles, reactor operators, and radiation shielding. Material covered includes topics on the effects of nuclear radiation on humans, the safety of nuclear reactors and of those parts of the nuclear fuel cycle which deal with fuel element manufacture and the reprocessing of irradiated fuel.

Bennet, D.J.; Thomson, J.R.

1989-01-01T23:59:59.000Z

445

TEPS/BPA Information | National Nuclear Security Administration  

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 | E nergyTEPS/BPA

446

Nuclear Safeguards | 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) "ofEarlyEnergyDepartmentNationalRestart of the Review ofElectronic InputNuclearNature

447

Nuclear Detonation Detection | National Nuclear Security Administration  

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 | National NuclearDetonation

448

Defense Nuclear Security | National Nuclear Security Administration  

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 JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to UserProduct: CrudeOffice ofINLNuclear Security | National Nuclear

449

Report to the Nuclear Regulatory Commission from the staff panel on the Commission's determination of an Extraordinary Nuclear Occurrence (ENO)  

SciTech Connect (OSTI)

The Panel finds that the first criterion, pertaining to whether the accident caused a discharge of radioactive material or levels of radiation offsite as defined in 10 CFR 140.84, has not been met. It further finds that there is presently insufficient information to support any definitive finding as to whether or not the second criterion, relating to damage to persons or property offsite as defined in 10 CFR 140.85, has been met. Since the Panel has not found that both criteria have been met, it recommends that the Commission determine that the accident at Three Mile Island did not constitute an extraordinary nuclear occurrence.

none,

1980-01-01T23:59:59.000Z

450

Modelling of fatigue damage in aluminum cylinder heads. R. Salapeteb  

E-Print Network [OSTI]

. 1. INTRODUCTION Increase in the specific power of Diesel engines leads to severe operating fatigue damage that may cause Diesel engine to fail after a few thousand cycles on the test bench and under severe operating conditions. The alternative heating and cooling of the operative Diesel engine

Paris-Sud XI, Université de

451

Topeka, Kansas, Flood Damage Reduction Project 30 January 2009  

E-Print Network [OSTI]

with and approved by the necessary resource agencies. The long-term environmental and cultural consequences of planTopeka, Kansas, Flood Damage Reduction Project 30 January 2009 Abstract: The recommended plan provides for flood risk management and restores the reliability of the Topeka, Kansas, Levee System located

US Army Corps of Engineers

452

NONLINEAR ACOUSTIC IMAGING OF STRUCTURAL DAMAGES IN LAMINATED COMPOSITES  

E-Print Network [OSTI]

are performed on a carbon fiber/epoxy laminated composite plate with barely visible impact damage and requires an ever increasing accuracy of detection. A good example is the inspection of composite materials been applied to a variety of materials including rocks [4], metals [5-10] and composites [11

Boyer, Edmond

453

Fungal endophytes limit pathogen damage in a tropical tree  

E-Print Network [OSTI]

Fungal endophytes limit pathogen damage in a tropical tree A. Elizabeth Arnold* , Luis Carlos Meji species examined to date harbors endophytic fungi within its asymptomatic aerial tissues, such that endophytes rep- resent a ubiquitous, yet cryptic, component of terrestrial plant communities. Fungal

Bermingham, Eldredge

454

Temporary patching of damaged UF{sub 6} cylinders  

SciTech Connect (OSTI)

Patching techniques based on application of epoxy resins have been developed for temporarily repairing UF{sub 6} cylinders which have sustained relatively minor damage and must be safely emptied. The method is considerably faster and simpler than metallurgical weld repairs. Laboratory tests, detailed operational procedures, and case histories of experience at the Portsmouth Gaseous Diffusion Plant are described.

Cardenas, A.L. [Martin Marietta Energy Systems, Inc., OH (United States)

1991-12-31T23:59:59.000Z

455

Automated Damage Diagnosis and Recovery for Remote Robotics  

E-Print Network [OSTI]

; damage may require rapid compensation (eg., power drain due to coverage of solar panels); and repeated that are qualitatively different from the original controller. A number of algorithms based on repeated testing have been only handles pre­ specified error types. The algorithm proposed here is demon­ strated to automatically

Bongard, Josh

456

Automated Damage Diagnosis and Recovery for Remote Robotics  

E-Print Network [OSTI]

; damage may require rapid compensation (eg., power drain due to coverage of solar panels); and repeated that are qualitatively different from the original controller. A number of algorithms based on repeated testing have been only handles pre- specified error types. The algorithm proposed here is demon- strated to automatically

Bongard, Josh

457

Electric heating units in pollination bags avoid damage  

E-Print Network [OSTI]

Electric heating units in pollination bags avoid damage to flowers by spring frost J. CH. FERRAND n'Orlgans Ardon, F 45160 Olivet Summary An effective, cheap and simple heating device was designed by INRA heating, Larix. Controlled crosses are essential for forest tree breeding, but spring frost can destroy

Paris-Sud XI, Université de

458

Specific grinding energy causing thermal damage in precision gear steels  

E-Print Network [OSTI]

of thermal damage for surface grinding of AISI 9310 gear steel using two different grinding wheels and two different coolants. The grinding wheels used for this research are plain alumina wheel-32A80-JVBE and Seeded Gel alumina abrasive-5SG80-JVS...

Hatathodi, Srinivas

2002-01-01T23:59:59.000Z

459

A micromechanics based ductile damage model for anisotropic titanium alloys  

E-Print Network [OSTI]

of internal cavitation. The model is developed from a rigorous micromechanical basis, following well-known previous works in the field. The model incorporates the porosity and void aspect ratio as internal damage variables, and seeks to provide a more accurate...

Keralavarma, Shyam Mohan

2009-05-15T23:59:59.000Z

460

Methods for globally treating silica optics to reduce optical damage  

DOE Patents [OSTI]

A method for preventing damage caused by high intensity light sources to optical components includes annealing the optical component for a predetermined period. Another method includes etching the optical component in an etchant including fluoride and bi-fluoride ions. The method also includes ultrasonically agitating the etching solution during the process followed by rinsing of the optical component in a rinse bath.

Miller, Philip Edward; Suratwala, Tayyab Ishaq; Bude, Jeffrey Devin; Shen, Nan; Steele, William Augustus; Laurence, Ted Alfred; Feit, Michael Dennis; Wong, Lana Louie

2012-11-20T23:59:59.000Z

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


461

Scaling of fracture length and distributed damage Vladimir Lyakhovsky  

E-Print Network [OSTI]

Scaling of fracture length and distributed damage Vladimir Lyakhovsky The Institute of Earth space scaling except linear relations between fracture length and displacements and thus the determination theoretically of the strength of a body or structure directly. Self-similarity of a fracture

Lyakhovsky, Vladimir

462

Dynamics and Fatigue Damage of Wind Turbine Rotors  

E-Print Network [OSTI]

6 3 RiS0-Rr512 Dynamics and Fatigue Damage of Wind Turbine Rotors during Steady Operation Peter OF WIND TURBINE ROTORS DURING STEADY OPERATION Peter Hauge Madsen, Sten Frandsen, William E. Holley-carrying capacity of a wind turbine rotor with respect to short-term strength and material fatigue are presented

463

Non-Destructive Damage Evaluation Based on Element Strain Energies  

E-Print Network [OSTI]

should apply to 1-D as well as 2-D and 3-D structures with single or multiple damage locations. To achieve the objectives listed above, the following four tasks are addressed: (1) the development of the theoretical foundations of the nondestructive...

Li, Ran

2013-05-01T23:59:59.000Z

464

Proton Irradiation Damage Assessment of Carbon Reinforced Composites  

E-Print Network [OSTI]

Proton Irradiation Damage Assessment of Carbon Reinforced Composites: 2-D & 3-D Weaved Structures carbon-carbon composite ATJ Graphite 3D CC composite AGS Beam-on-Target tests show clearly that carbon composites are better absorbers of thermo- mechanical shock. This is attributed to the very low coeff

McDonald, Kirk

465

IDENTIFICATION OF MATERIAL DAMAGE IN TWO DIMENSIONAL DOMAINS  

E-Print Network [OSTI]

IDENTIFICATION OF MATERIAL DAMAGE IN TWO DIMENSIONAL DOMAINS USING SQUID BASED NDE SYSTEM H on such problems entails quantitative nondestructive evaluation methods in SQUID-based NDE system [1]. It is well, SQUID based nondestructive evaluation (NDE) systems using injection current methods have been recently

466

IDENTIFICATION OF MATERIAL DAMAGE IN TWO DIMENSIONAL DOMAINS  

E-Print Network [OSTI]

IDENTIFICATION OF MATERIAL DAMAGE IN TWO DIMENSIONAL DOMAINS USING SQUID BASED NDE SYSTEM H#ort on such problems entails quantitative nondestructive evaluation methods in SQUID­based NDE system [1]. It is well nondestructive evaluation (NDE) systems using injection current methods have been recently developed [3, 4

467

Collaborative Post-Disaster Damage Mapping via Geo Web Services  

E-Print Network [OSTI]

with geospatial services that can interact in a loosely coupled envir- onment and be used to create more suitable architecture for a collaborative post-disaster damage mapping system. We focus particularly on satellite image-based post-disaster support situations, and present our ideas for a prototype based on this architecture

Köbben, Barend

468

Monitoring Forest Damage Methods and Development in Sweden  

E-Print Network [OSTI]

, fieldwork in the target-tailored inventory of resin top disease, damage by Spruce bark beetle. (photo: S is the most important information that can be obtained from these kinds of inventories. Short variability. Large-scale monitoring, such as that performed in national forest inventories, has good potential

469

TMI-2 core damage: a summary of present knowledge  

SciTech Connect (OSTI)

Extensive fuel damage (oxidation and fragmentation) has occurred and the top approx. 1.5 m of the center portion of the TMI-2 core has relocated. The fuel fragmentation extends outward to slightly beyond one-half the core radius in the direction examined by the CCTV camera. While the radial extent of core fragmentation in other directions was not directly observed, control and spider drop data and in-core instrument data suggest that the core void is roughly symmetrical, although there are a few indications of severe fuel damage extending to the core periphery. The core material fragmented into a broad range of particle sizes, extending down to a few microns. APSR movement data, the observation of damaged fuel assemblies hanging unsupported from the bottom of the reactor upper plenum structure, and the observation of once-molten stainless steel immediately above the active core indicate high temperatures (up to at least 1720 K) extended to the very top of the core. The relative lack of damage to the underside of the plenum structure implies a sharp temperature demarcation at the core/plenum interface. Filter debris and leadscrew deposit analyses indicate extensive high temperature core materials interaction, melting of the Ag-In-Cd control material, and transport of particulate control material to the plenum and out of the vessel.

Owen, D.E.; Mason, R.E.; Meininger, R.D.; Franz, W.A.

1983-01-01T23:59:59.000Z

470

DAMAGE DETECTION IN COMPOSITES BY NONCONTACT LASER Byeongjin Park  

E-Print Network [OSTI]

, Composite structures, Wind blade. INTRODUCTION Composite materials are widely used for various industries. The feasibility of the proposed technique is examined by localizing a delamination in a real 10 kW wind turbine blade. KEYWORDS : Laser ultrasonics, Damage detection and localization, Time-of-flight triangulation

Paris-Sud XI, Universit de

471

Pediatric nuclear medicine  

SciTech Connect (OSTI)

This symposium presented the latest techniques and approaches to the proper medical application of radionuclides in pediatrics. An expert faculty, comprised of specialists in the field of pediatric nuclear medicine, discussed the major indications as well as the advantages and potential hazards of nuclear medicine procedures compared to other diagnostic modalities. In recent years, newer radiopharmaceuticals labeled with technetium-99m and other short-lived radionuclides with relatively favorable radiation characteristics have permitted a variety of diagnostic studies that are very useful clinically and carry a substantially lower radiation burden then many comparable X-ray studies. This new battery of nuclear medicine procedures is now widely available for diagnosis and management of pediatric patients. Many recent research studies in children have yielded data concerning the effacacy of these procedures, and current recommendations will be presented by those involved in conducting such studies. Individual papers are processed separately for the Energy Data Base.

Not Available

1986-01-01T23:59:59.000Z

472

Fission product behavior during the PBF (Power Burst Facility) Severe Fuel Damage Test 1-1  

SciTech Connect (OSTI)

In response to the accident at Three Mile Island Unit 2 (TMI-2), the United States Nuclear Regulatory Commission (USNRC) initiated a series of Severe Fuel Damage tests that were performed in the Power Burst Facility at the Idaho National Engineering Laboratory to obtain data necessary to understand (a) fission product release, transport, and deposition; (b) hydrogen generation; and (c) fuel/cladding material behavior during degraded core accidents. Data are presented about fission product behavior noted during the second experiment of this series, the Severe Fuel Damage Test 1-1, with an in-depth analysis of the fission product release, transport, and deposition phenomena that were observed. Real-time release and transport data of certain fission products were obtained from on-line gamma spectroscopy measurements. Liquid and gas effluent grab samples were collected at selected periods during the test transient. Additional information was obtained from steamline deposition analysis. From these and other data, fission product release rates and total release fractions are estimated and compared with predicted release behavior using current models. Fission product distributions and a mass balance are also summarized, and certain probable chemical forms are predicted for iodine, cesium, and tellurium. An in-depth evaluation of phenomena affecting the behavior of the high-volatility fission products - xenon, krypton, iodine, cesium, and tellurium - is presented. Analysis indicates that volatile release from fuel is strongly influenced by parameters other than fuel temperature. Fission product behavior during transport through the Power Burst Facility effluent line to the fission product monitoring system is assessed. Tellurium release behavior is also examined relatve to the extent of Zircaloy cladding oxidation. 81 fig., 53 tabs.

Hartwell, J K; Petti, D A; Hagrman, D L; Jensen, S M; Cronenberg, A W

1987-05-01T23:59:59.000Z

473

Swedish nuclear waste efforts  

SciTech Connect (OSTI)

After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981.

Rydberg, J.

1981-09-01T23:59:59.000Z

474

Neutrinos in Nuclear Physics  

E-Print Network [OSTI]

Since the discovery of nuclear beta decay, nuclear physicists have studied the weak interaction and the nature of neutrinos. Many recent and current experiments have been focused on the elucidation of neutrino oscillations and neutrino mass. The quest for the absolute value of neutrino mass continues with higher precision studies of the tritium beta decay spectrum near the endpoint. Neutrino oscillations are studied through measurements of reactor neutrinos as a function of baseline and energy. And experiments searching for neutrinoless double beta decay seek to discover violation of lepton number and establish the Majorana nature of neutrino masses.

R. D. McKeown

2014-12-03T23:59:59.000Z

475

Clustering in nuclear environment  

E-Print Network [OSTI]

The properties of few-body clusters (mass number $A \\le 4$) are modified if they are immersed in a nuclear medium. In particular, Pauli blocking that reflects the antisymmetrization of the many-body wave function is responsible for the medium modification of light clusters and the dissolution with increasing density. A more consistent description is given with takes also the contribution of correlations in the continuum into account. The relation between cluster formation in warm dense matter and in nuclear structure is discussed.

G. Rpke

2014-08-12T23:59:59.000Z

476

Nuclear Masses in Astrophysics  

E-Print Network [OSTI]

Among all nuclear ground-state properties, atomic masses are highly specific for each particular combination of N and Z and the data obtained apply to a variety of physics topics. One of the most crucial questions to be addressed in mass spectrometry of unstable radionuclides is the one of understanding the processes of element formation in the Universe. To this end, accurate atomic mass values of a large number of exotic nuclei participating in nucleosynthesis are among the key input data in large-scale reaction network calculations. In this paper, a review on the latest achievements in mass spectrometry for nuclear astrophysics is given.

Christine Weber; Klaus Blaum; Hendrik Schatz

2008-12-09T23:59:59.000Z

477

Nuclear medicine imaging system  

DOE Patents [OSTI]

It is an object of this invention to provide a nuclear imaging system having the versatility to do positron annihilation studies, rotating single or opposed camera gamma emission studies, and orthogonal gamma emission studies. It is a further object of this invention to provide an imaging system having the capability for orthogonal dual multipinhole tomography. It is another object of this invention to provide a nuclear imaging system in which all available energy data, as well as patient physiological data, are acquired simultaneously in list mode.

Bennett, G.W.; Brill, A.B.; Bizais, Y.J.C.; Rowe, R.W.; Zubal, I.G.

1983-03-11T23:59:59.000Z

478

Neutrinos in Nuclear Physics  

E-Print Network [OSTI]

Since the discovery of nuclear beta decay, nuclear physicists have studied the weak interaction and the nature of neutrinos. Many recent and current experiments have been focused on the elucidation of neutrino oscillations and neutrino mass. The quest for the absolute value of neutrino mass continues with higher precision studies of the tritium beta decay spectrum near the endpoint. Neutrino oscillations are studied through measurements of reactor neutrinos as a function of baseline and energy. And experiments searching for neutrinoless double beta decay seek to discover violation of lepton number and establish the Majorana nature of neutrino masses.

McKeown, R D

2014-01-01T23:59:59.000Z

479

EIA - State Nuclear Profiles  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed NewcatalystNeutron scatteringDelawareTexasMissouri Nuclear ProfileYork Nuclear

480

EIA - State Nuclear Profiles  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed NewcatalystNeutron scatteringDelawareTexasMissouri Nuclear ProfileYork NuclearNorth

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


481

Nuclear Pairs | Jefferson Lab  

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 ConsortiumNuclear Pairs High-Resolution

482

Nuclear Physics Program  

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 ConsortiumNuclear Pairs

483

Nuclear Science Series: Radiochemistry  

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

484

Safer nuclear power  

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

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

485

Nuclear Imaging | Jefferson Lab  

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 Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchives Events/NewsYouNuclearNuclear

486

Nuclear Physics | Jefferson Lab  

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 Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchives Events/NewsYouNuclearNuclearNP

487

Nuclear Science at NERSC  

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 Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchives Events/NewsYouNuclearNuclearNP

488

Nuclear Workforce Initiative - SRSCRO  

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 Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchivesNuclear Science/Nuclear

489

Geologic Assessment of the Damage Zone from the Second Test at Source Physics Experiment-Nevada (SPE-N)  

SciTech Connect (OSTI)

The National Center for Nuclear Security (NCNS), established by the U.S. Department of Energy, National Nuclear Security Administration, is conducting a series of explosive tests at the Nevada National Security Site (NNSS; formerly the Nevada Test Site) that are designed to increase the understanding of certain basic physical phenomena associated with underground explosions. These tests will aid in developing technologies that might be used to detect underground nuclear explosions in support of verification activities for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The initial NCNS project is a series of explosive tests, known collectively as the Source Physics Experiment at the NNSS (SPE-N), being conducted in granitic rocks at the Climax stock in northern Yucca Flat. The SPE-N test series is designed to study the generation and propagation of seismic waves. The data will be used to improve the predictive capability of calculational models for detecting and characterizing underground explosions. The first SPE-N test (SPE-N-1) was a calibration shot conducted in May 2011, using 100 kilograms (kg) of explosives at the depth of 54.9 meters (m) (180 feet [ft]) in the U-15n source hole. SPE-N-2 was conducted in October 2011, using 1,000 kg of explosives at the depth of 45.7 m (150 ft) in the same source hole. Following the SPE-N-2 test, the core hole U-15n#10 was drilled at an angle from the surface to intercept the SPE-N-2 shot point location to obtain information necessary to characterize the damage zone. The desire was to determine the position of the damage zone near the shot point, at least on the northeast side, where the core hole penetrated it. The three-dimensional shape and symmetry of the damage zone are unknown at this time. Rather than spherical in shape, the dimensions of the damage zone could be influenced by the natural fracture sets in the vicinity. Geologic characterization of the borehole included geophysical logging, a directional survey, and geologic description of the core to document visual evidence of damage. Selected core samples were provided to Sandia National Laboratories (SNL) for laboratory tests (to be reported by SNL). A significant natural fault zone was encountered in the U-15n#10 angle core hole between the drilled depths of 149 and 155 ft (straight-line distance or range station [RS] from the shot point of 7.5 to 5.7 m). However, several of the fractures observed in the U-15n#10 hole are interpreted as having been caused by the explosion. These fractures are characterized by a fresh, mechanically broken look, with uncoated and very irregular surfaces. They tend to terminate against natural fractures and have orientations that differ from the previously defined natural fracture sets. The most distant fracture from the shot point that could be interpreted as having been caused by the explosion was seen at approximately RS 10.0 m. No other possibly explosion-induced fractures are apparent above the fault, but are common starting at RS 5.4 m, which is below the fault. It is unknown how the fault zone might have affected the propagation of seismic waves or how the materials in the fault zone (altered granite, breccia, gouge) were affected by the explosion. From RS 3.3 m to the end of the recovered core at RS 1.6 m, some of the core samples are softer and lighter in color, but do not appear to be weathered. It is thought this could be indicative of the presence of distributed microfracturing.

,

2012-09-18T23:59:59.000Z

490

Strategic petroleum reserve caverns casing damage update 1997  

SciTech Connect (OSTI)

Hanging casing strings are used for oil and brine transfer in the domal salt storage caverns of the Strategic Petroleum Reserve (SPR). Damage to these casings is of concern because hanging string replacement is costly and because of implications on cavern stability. Although the causes of casing damage are not always well defined, many events leading to damage are assumed to be the result of salt falls impacting the hanging strings. However, in some cases, operational aspects may be suspected. The history of damage to hanging strings is updated in this study to include the most recent events. Potential general domal and local operational and material factors that could influence the tendency for caverns to have salt falls are examined in detail. As a result of this examination, general factors, such as salt dome anomalies and crude type, and most of the operational factors, such as geometry, location and depressurizations, are not believed to be primary causes of casing damage. Further analysis is presented of the accumulation of insolubles during cavern solutioning and accumulation of salt fall material on the cavern floor. Inaccuracies in sump geometry probably make relative cavern insolubles contents uncertain. However, determination of the salt fall accumulations, which are more accurate, suggest that the caverns with the largest salt fall accumulations show the greatest number of hanging string events. There is good correlation between the accumulation rate and the number of events when the event numbers are corrected to an equivalent number for a single hanging string in a quiescent, operating cavern. The principal factor that determines the propensity for a cavern to exhibit this behavior is thought to be the effect of impurity content on the fracture behavior of salt.

Munson, D.E.; Molecke, M.A.; Neal, J.T. [and others

1998-01-01T23:59:59.000Z

491

Security and Control of Nuclear Explosives and Nuclear Weapons  

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

This directive establishes requirements and responsibilities to prevent the deliberate unauthorized use of U.S. nuclear explosives and U.S. nuclear weapons. Cancels DOE O 452.4.

2001-12-17T23:59:59.000Z

492

NUCLEAR INCIDENT CAPABILITIES, KNOWLEDGE & ENABLER LEVERAGING  

SciTech Connect (OSTI)

The detonation of a 10 Kiloton Improvised Nuclear Device (IND) is a serious scenario that the United States must be prepared to address. The likelihood of a single nuclear bomb exploding in a single city is greater today than at the height of the Cold War. Layered defenses against domestic nuclear terrorism indicate that our government continues to view the threat as credible. The risk of such an event is further evidenced by terrorists desire to acquire nuclear weapons. The act of nuclear terrorism, particularly an act directed against a large population center in the United States, will overwhelm the capabilities of many local and state governments to respond, and will seriously challenge existing federal response capabilities. A 10 Kiloton IND detonation would cause total infrastructure damage in a 3-mile radius and levels of radiation spanning out 3,000 square miles. In a densely populated urban area, the anticipated casualties would be in excess of several hundred thousand. Although there would be enormous loss of life, housing and infrastructure, an IND detonation is a recoverable event. We can reduce the risk of these high-consequence, nontraditional threats by enhancing our nuclear detection architecture and establishing well planned and rehearsed plans for coordinated response. It is also important for us to identify new and improved ways to foster collaboration regarding the response to the IND threat to ensure the demand and density of expertise required for such an event is postured and prepared to mobilize, integrate, and support a myriad of anticipated challenges. We must be prepared to manage the consequences of such an event in a deliberate manner and get beyond notions of total devastation by adopting planning assumptions around survivability and resiliency. Planning for such a scenario needs to be decisive in determining a response based on competencies and desired outcomes. It is time to synthesize known threats and plausible consequences into action. Much work needs to be accomplished to enhance nuclear preparedness and to substantially bolster and clarify the capacity to deploy competent resources. Until detailed plans are scripted, and personnel and other resources are postured, and exercised, IND specific planning remains an urgent need requiring attention and action. Although strategic guidance, policies, concepts of operations, roles, responsibilities, and plans governing the response and consequence management for the IND scenario exist, an ongoing integration challenge prevails regarding how best to get capable and competent surge capacity personnel (disaster reservists) and other resources engaged and readied in an up-front manner with pre-scripted assignments to augment the magnitude of anticipated demands of expertise. With the above in mind, Savannah River National Laboratory (SRNL) puts science to work to create and deploy practical, high-value, cost-effective nuclear solutions. As the Department of Energy's (DOE) applied research and development laboratory, SRNL supports Savannah River Site (SRS) operations, DOE, national initiatives, and other federal agencies, across the country and around the world. SRNL's parent at SRS also employs more than 8,000 personnel. The team is a great asset that seeks to continue their service in the interest of national security and stands ready to accomplish new missions. Overall, an integral part of the vision for SRNL's National and Homeland Security Directorate is the establishment of a National Security Center at SRNL, and development of state of the science capabilities (technologies and trained technical personnel) for responding to emergency events on local, regional, or national scales. This entails leveraging and posturing the skills, knowledge and experience base of SRS personnel to deliver an integrated capability to support local, state, and federal authorities through the development of pre-scripted requests for assistance, agreements, and plans. It also includes developing plans, training, exercises, recruitment strategies, and processes to e

Kinney, J.; Newman, J.; Goodwyn, A.; Dewes, J.

2011-04-18T23:59:59.000Z

493

Nuclear Science and Engineering | ornl.gov  

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

Nuclear Science Engineering SHARE Nuclear Science and Engineering The Nuclear Science and Engineering Directorate (NSED) at Oak Ridge National Laboratory (ORNL) is committed to...

494

Office of Nuclear Facility Safety Programs  

Broader source: Energy.gov [DOE]

The Office of Nuclear Facility Safety Programs establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities.

495

Nuclear Explosive Safety Manual - DOE Directives, Delegations...  

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

1A Admin Chg 1, Nuclear Explosive Safety Manual by Carl Sykes Functional areas: Administrative Change, Defense Nuclear Facility Safety and Health Requirement, Nuclear Safety,...

496

Nuclear Safety Information Dashboard | Department of Energy  

Office of Environmental Management (EM)

Nuclear Safety Information Dashboard Nuclear Safety Information Dashboard The Nuclear Safety Information (NSI) Dashboard provides a new user interface to the Occurrence Reporting...

497

International Nuclear Energy Policy and Cooperation | Department...  

Office of Environmental Management (EM)

International Nuclear Energy Policy and Cooperation International Nuclear Energy Policy and Cooperation Recent Events 6th US-India Civil Nuclear Energy Working Group Meeting 6th...

498

Nuclear Safety News | Department of Energy  

Office of Environmental Management (EM)

Nuclear Safety News Nuclear Safety News October 4, 2012 Department of Energy Cites Battelle Energy Alliance, LLC for Nuclear Safety and Radiation Protection Violations The U.S....

499

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network [OSTI]

et al. Investigation of Nuclear Structure by Resonance1996, pp. G. Warren et al. Nuclear Resonance Fluorescenceof 235U IEEE Nuclear Science Symposium 2006, pp. 914. W.

Quiter, Brian J.

2010-01-01T23:59:59.000Z

500

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network [OSTI]

clandestine material with nuclear resonance fluorescence.E. Norman, UC Berkeley Dept. of Nuclear Engineering, privatepp. 349. G. Warren et al. Nuclear Resonance Fluorescence of

Quiter, Brian

2010-01-01T23:59:59.000Z