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1

SRS FTF Section 3116 Basis for Determination | Department of Energy  

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

FTF Section 3116 Basis for Determination FTF Section 3116 Basis for Determination SRS FTF Section 3116 Basis for Determination Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site. In accordance with NDAA Section 3116, certain waste from reprocessing of spent nuclear fuel is not high-level waste if the Secretary of Energy, in consultation with the NRC, determines that the criteria in NDAA Section 3116(a) are met. This FTF 3116 Basis Document shows that those criteria are satisfied, to support a determination that the Secretary may make pursuant to NDAA Section 3116. This FTF 3116 Basis Document concerns the stabilized residuals in waste tanks and ancillary structures, those waste tanks, and the ancillary structures (including integral equipment) at the SRS FTF at the time of closure.

2

Basis for Section 3116 Determination for Salt Waste Disposal at the  

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

Basis for Section 3116 Determination for Salt Waste Disposal at the Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site The Secretary of Energy is making this 3116 Determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) [1]. This 3116 Determination concerns the disposal of separated, solidified low-activity radioactive salt waste at the Savannah River Site (SRS) near Aiken, South Carolina. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site More Documents & Publications EIS-0082-S2: Amended Record of Decision Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

3

Basis for Section 3116 Determination for Salt Waste Disposal at the  

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

Basis for Section 3116 Determination for Salt Waste Disposal at the Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site The Secretary of Energy is making this 3116 Determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) [1]. This 3116 Determination concerns the disposal of separated, solidified low-activity radioactive salt waste at the Savannah River Site (SRS) near Aiken, South Carolina. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site More Documents & Publications EIS-0082-S2: Amended Record of Decision Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

4

Basis for Section 3116 Determination for the Idaho Nuclear Technology and  

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

Basis for Section 3116 Determination for the Idaho Nuclear Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory This 3116 Basis Document addresses the disposal of stabilized residuals in the TFF, and the TFF tank system, and disposal of the tanks, vaults, and associated piping and ancillary equipment at INTEC. The TFF tank system comprises the eleven 300,000-gal tanks, four 30,000-gal tanks, and the vaults, piping, structures, and ancillary equipment associated with these tanks. Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory

5

A criterion for determining exceedance of the operating basis earthquake: Final report  

Science Conference Proceedings (OSTI)

A criterion is recommended for determining whether the Operating Basis Earthquake (OBE) has been exceeded after the occurrence of a seismic event at a nuclear power plant. The technical procedure provides a fast and effective means for assessing the damage potential of any ''felt'' earthquake in the first few hours after occurrence. For OBE exceedance to occur, the recommended criterion requires exceedance of both a response spectrum parameter and a second damage parameter, referred to as the Cumulative Absolute Velocity (CAV). The detailed operational requirements for implementing the criterion are provided. The criterion was developed, based on a study of earthquake damage to conventional buildings, review of past damage to power plants and heavy industrial facilities, blast damage, fragility data and equipment vibration performance, to ensure that ground motions greater than Modified Mercalli Intensity VI are conservatively identified as exceeding the OBE. Based on direct correlations of the criterion parameters with damage data, ground motions which cause damage to buildings of good design and construction (which in general are not as seismically strong as nuclear facilities) are a factor of at least 1.5 larger than the recommended criterion threshold values. This ensures adequate conservatism in the criterion. Issues related to OBE exceedance, including the history of the OBE, regulatory and operational issues, plant operation concerns, current industry activities related to OBE exceedance and recent earthquake experience are discussed in the report.

Reed, J.W.; Anderson, N.; Chokshi, N.C.; Kennedy, R.P.; Metevia, W.J.; Ostrom, D.K.; Stevenson, J.D.

1988-07-01T23:59:59.000Z

6

Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site  

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

SRS-WD-2012-001 SRS-WD-2012-001 Revision 0 Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site March 2012 Basis for Section 3116 Determination DOE/SRS-WD-2012-001 for Closure of F-Tank Farm Revision 0 at the Savannah River Site March 2012 Page ii REVISION SUMMARY REV. # DESCRIPTION DATE OF ISSUE 0 Initial Issue March 2012 Basis for Section 3116 Determination DOE/SRS-WD-2012-001 for Closure of F-Tank Farm Revision 0 at the Savannah River Site March 2012 Page iii TABLE OF CONTENTS Page REVISION SUMMARY ................................................................................................................................. ii LIST OF TABLES ........................................................................................................................................ vi

7

Draft Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site.  

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

SRS-WD-2010-001 SRS-WD-2010-001 Revision 0 Draft Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site September 30, 2010 Draft Basis for Section 3116 Determination DOE/SRS-WD-2010-001 for Closure of F-Tank Farm Revision 0 at the Savannah River Site September 30, 2010 Page ii REVISION SUMMARY REV. # DESCRIPTION DATE OF ISSUE 0 Initial Issue 09/30/2010 Draft Basis for Section 3116 Determination DOE/SRS-WD-2010-001 for Closure of F-Tank Farm Revision 0 at the Savannah River Site September 30, 2010 Page iii TABLE OF CONTENTS Page REVISION SUMMARY ................................................................................................................................. ii LIST OF TABLES .........................................................................................................................................

8

Fast static available transfer capability determination using radial basis function neural network  

Science Conference Proceedings (OSTI)

In a competitive electricity market, available transfer capability information is required by market participants as well as the system operator for secure operation of the power system. The on-line updating of available transfer capability information ... Keywords: Available transfer capability, Euclidean distance based clustering technique, Radial basis function neural network, Random forest technique

T. Jain; S. N. Singh; S. C. Srivastava

2011-03-01T23:59:59.000Z

9

Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal  

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

The Department of Energy (DOE) published in the Federal Register (January 24, 2006), a Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site.

10

Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory  

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

NE-ID-11226 NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 DOE/NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 ii CONTENTS ACRONYMS.............................................................................................................................................. vii 1. INTRODUCTION AND PURPOSE.................................................................................................. 1 2. BACKGROUND................................................................................................................................ 5 2.1 Tank Farm Facility Description.............................................................................................

11

Safety Basis Report  

SciTech Connect

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

R.J. Garrett

2002-01-14T23:59:59.000Z

12

Dual generalized Bernstein basis  

Science Conference Proceedings (OSTI)

The generalized Bernstein basis in the space @P"n of polynomials of degree at most n, being an extension of the q-Bernstein basis introduced by Philips [Bernstein polynomials based on the q-integers, Ann. Numer. Math. 4 (1997) 511-518], is given by the ... Keywords: Bernstein basis, Big q-Jacobi polynomials, Discrete Bernstein basis, Dual basis, Generalized Bernstein basis, Little q-Jacobi polynomials, Shifted Jacobi polynomials, q -Bernstein basis

Stanis?aw Lewanowicz; Pawe? Wo?ny

2006-02-01T23:59:59.000Z

13

lattice basis - CECM  

E-Print Network (OSTI)

Discover an identity using lattice basis reduction. Find integers a and b such that a*Zeta(50)+b*Pi^50 = 0 using lattice basis reduction . First try using quadruple...

14

Beyond Design Basis Events  

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

Beyond Design Basis Events Beyond Design Basis Events Following the March 2011 Fukushima Daiichi nuclear plant accident in Japan, DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to beyond design basis events (BDBEs). These initiatives included issuing Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis, and conducting two DOE nuclear safety workshops. DOE also issued two reports documenting the results of these initiatives: Review of Requirements and Capabilities for Analyzing and Responding to BDBEs, August 2011, and Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities, January 2013.

15

(DOE/EIS-0128-SA-02): Supplement Analysis: Los Banos-Gates (Path 15) Transmission line project changes to alignment, access road stream crossing, and basis for Supplemental EIS Determination  

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

Los Banos-Gates (Path 15) Transmission Line Project DOE/EIS-0128-SA02 Western Area Power Administration Sierra Nevada Customer Service Region U.S. Department of Energy Changes to Alignment, Access Road Stream Crossing, and Basis for Supplemental Environmental Impact Statement Determination Background The Los Banos-Gates 500-kilovolt Transmission Line project was originally proposed as part of the California-Oregon Transmission Project in the 1980s. These two projects were the subject of a single set of documents prepared in 1986 (draft) and 1988 (final) that served as the Environmental Impact Statement (EIS) under the National Environmental Policy Act and the Environmental Impact Report (EIR) under the California Environmental Quality Act. The EIS is entitled "Final Environmental Impact

16

Nuclear Facility Safety Basis  

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

Safety Basis Safety Basis FUNCTIONAL AREA GOAL: A fully compliant Nuclear Facility Safety Basis. Program is implemented and maintained across the site. REQUIREMENTS:  10 CFR 830 Subpart B Guidance:  DOE STD 3009  DOE STD 1104  DOE STD  DOE G 421.1-2 Implementation Guide For Use in Developing Documented Safety Analyses To Meet Subpart B Of 10 CFR 830  DOE G 423.1-1 Implementation Guide For Use In Developing Technical Safety Requirements  DOE G 424.1-1 Implementation Guide For Use In Addressing Unreviewed Safety Question Requirements Performance Objective 1: Contractor Program Documentation The site contractor has developed an up-to-date, comprehensive, compliant, documented nuclear facility safety basis and associated implementing mechanisms and procedures for all required nuclear facilities and activities (10 CFR

17

SNS backscattering spectrometer, BASIS  

Science Conference Proceedings (OSTI)

We describe the design and current performance of the backscattering silicon spectrometer (BASIS), a time-of-flight backscattering spectrometer built at the spallation neutron source (SNS) of the Oak Ridge National Laboratory (ORNL). BASIS is the first silicon-based backscattering spectrometer installed at a spallation neutron source. In addition to high intensity, it offers a high-energy resolution of about 3.5 {mu}eV and a large and variable energy transfer range. These ensure an excellent overlap with the dynamic ranges accessible at other inelastic spectrometers at the SNS.

Mamontov, Eugene [ORNL; Herwig, Kenneth W [ORNL

2011-01-01T23:59:59.000Z

18

Radioactive Waste Management Basis  

SciTech Connect

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2009-06-03T23:59:59.000Z

19

Basis for UCNI | Department of Energy  

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

Basis for UCNI Basis for UCNI Basis for UCNI What documents contain the legal and policy foundations for the UCNI program? Section 148 of the Atomic Energy Act of 1954, as amended (42 U.S.C. 2011 et seq.), is the statutory basis for the UCNI program. 10 CFR Part 1017, Identification and Protection of Unclassified Controlled Nuclear Information specifies many detailed policies and requirements concerning the UCNI program. DOE O 471.1B, Identification and Protection of Unclassified Controlled Nuclear Information, specifies additional policies and requirements concerning the Department of Energy (DOE) UCNI program. UCNI General Guideline, GG-5, is a record of decisions made by the Director, OC, as to what general subject areas are UCNI. Note: GG-5 may only be used by the Director, OC, to make determinations as to whether

20

Virginia Regional Middle School Science Bowl | U.S. DOE Office...  

Office of Science (SC) Website

1 Registration Fee: NA Regional Geographic Information: Virginia Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

Note: This page contains sample records for the topic "first-served basis determined" 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

Colorado Regional High School Science Bowl | U.S. DOE Office...  

Office of Science (SC) Website

2 Registration Fee: NA Regional Geographic Information: Colorado Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

22

Virginia Regional High School Science Bowl | U.S. DOE Office...  

Office of Science (SC) Website

1 Registration Fee: NA Regional Geographic Information: Virginia Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

23

Hawaii Science Bowl | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

School: 2 Registration Fee: NA Regional Geographic Information: Hawaii Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

24

Arkansas Regional High Science Bowl | U.S. DOE Office of Science...  

Office of Science (SC) Website

3 Registration Fee: NA Regional Geographic Information: Arkansas Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

25

Missouri Regional Middle School Science Bowl | U.S. DOE Office...  

Office of Science (SC) Website

3 Registration Fee: TBD Regional Geographic Information: Missouri Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

26

Iowa Regional High School Science Bowl | U.S. DOE Office of Science...  

Office of Science (SC) Website

School: 3 Registration Fee: NA Regional Geographic Information: Iowa Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

27

Montana Regional High School Science Bowl | U.S. DOE Office of...  

Office of Science (SC) Website

School: 2 Registration Fee: NA Regional Geographic Information: Montana Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

28

Mississippi Regional Middle School Science Bowl | U.S. DOE Office...  

Office of Science (SC) Website

Fee: 40 per team Regional Geographic Information: Mississippi Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

29

Arkansas Regional Middle School Science Bowl | U.S. DOE Office...  

Office of Science (SC) Website

3 Registration Fee: NA Regional Geographic Information: Arkansas Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

30

Arizona Regional High Science Bowl | U.S. DOE Office of Science...  

Office of Science (SC) Website

School: 3 Registration Fee: NA Regional Geographic Information: Arizona Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

31

Existing reactor expansion study basis  

SciTech Connect

The latest HAPO Five Year Program review, HW-59633, forecasts substantial increases in Pu production from the eight existing Hanford reactors over the next several years. These production increases would be attained by a combination of several methods which include increased reactor power levels resulting from higher process water flow rates and coolant bulk outlet temperatures, improved time operated efficiency, higher conversion ratios, and reduced transient reactivity losses. In order to provide a realistic basis for budgeting to meet these or other increased production goals, it is necessary that a study program be undertaken to determine in general terms the plant changes required to support these forecasted levels, to evaluate the economic and technical feasibility of achieving the process conditions, and to present an integrated program for achieving these objectives. This study program will necessarily consider the interrelated effects of a number of various facets of reactor and water plant process conditions, operational requirements, and proposed development programs. The purpose of this document is to present a plan for the execution of the proposed study. Included in this outline are a review of the basic study considerations, problem assignments and schedules, and manpower and cost estimates for the performance of the study.

Heacock, H.W.

1959-06-24T23:59:59.000Z

32

Basis for OUO | Department of Energy  

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

Services » Classification » Official Use Only Information » Services » Classification » Official Use Only Information » Basis for OUO Basis for OUO What documents contain the policy foundation for the OUO program? DOE O 471.3 Admin Chg 1, Identifying and Protecting Official Use Only Information. DOE M 471.3-1 Admin Chg 1, Manual for Identifying and Protecting Official Use Only Information. Training & Reference Materials Basis for OUO OUO Review Requirement Access to OUO Protection of OUO Questions about Making OUO Determinations - OUO and the FOIA Exemptions How is a Document Containing OUO Marked? Controlled Unclassified Information and E.O. 13556 Resources for OUO Enforcement Guidance Oversight Reporting Security Classification Classification Training Institute Official Use Only Information Unclassified Controlled Nuclear Information (UCNI)

33

Mixtures of truncated basis functions  

Science Conference Proceedings (OSTI)

In this paper we propose a framework, called mixtures of truncated basis functions (MoTBFs), for representing general hybrid Bayesian networks. The proposed framework generalizes both the mixture of truncated exponentials (MTEs) framework and the Mixture ... Keywords: Approximations, Hybrid Bayesian networks, Inference, Mixtures of truncated basis functions, Mixtures of truncated exponentials

Helge Langseth; Thomas D. Nielsen; Rafael Rum?; Antonio Salmern

2012-02-01T23:59:59.000Z

34

Microsoft Word - Final_SRS_FTF_WD_Basis_March_2012  

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

2-001 2-001 Revision 0 Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site March 2012 Basis for Section 3116 Determination DOE/SRS-WD-2012-001 for Closure of F-Tank Farm Revision 0 at the Savannah River Site March 2012 Page ii REVISION SUMMARY REV. # DESCRIPTION DATE OF ISSUE 0 Initial Issue March 2012 Basis for Section 3116 Determination DOE/SRS-WD-2012-001 for Closure of F-Tank Farm Revision 0 at the Savannah River Site March 2012 Page iii TABLE OF CONTENTS Page REVISION SUMMARY ................................................................................................................................. ii LIST OF TABLES ........................................................................................................................................ vi

35

Optimal ratio between phase basis and bit basis in QKD  

E-Print Network (OSTI)

In the original BB84 protocol, we use the bit basis and the phase basis with the equal probability. Lo et al (J. of Cryptology, 18, 133-165 (2005)) proposed to modify the ratio between two bases for increasing the final key generation rate in the asymptotic setting. In the present letter, in order to treat this problem the non-asymptotic setting, we optimize the ratio between the two bases with exponential constraints for Eve's information distinguishability and the final error probability.

Hayashi, Masahito

2008-01-01T23:59:59.000Z

36

Facility worker technical basis document  

SciTech Connect

This report documents the technical basis for facility worker safety to support the Tank Farms Documented Safety Analysis and described the criteria and methodology for allocating controls to hazardous conditions with significant facility worker consequences and presents the results of the allocation.

EVANS, C.B.

2003-03-21T23:59:59.000Z

37

FACILITY WORKER TECHNICAL BASIS DOCUMENT  

Science Conference Proceedings (OSTI)

This technical basis document was developed to support RPP-13033, ''Tank Farms Documented Safety Analysis (DSA). It describes the criteria and methodology for allocating controls to hazardous conditions with significant facility worker (FW) consequence and presents the results of the allocation. The criteria and methodology for identifying controls that address FW safety are in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''.

SHULTZ, M.V.

2005-03-31T23:59:59.000Z

38

Hanford Generic Interim Safety Basis  

SciTech Connect

The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

Lavender, J.C.

1994-09-09T23:59:59.000Z

39

TCAP Aluminium Dissolution Flowsheet Basis  

Science Conference Proceedings (OSTI)

The Actinide Technology Section has proposed the use of an nitric acid HNO3 and potassium fluoride KF flowsheet for stripping palladium Pd from palladium-coated kieselguhr Pd/K and removing aluminum (Al) metal foam from the TCAP coils. The basis for the HNO3-KF flowsheet is drawn from many sources. A brief review of the sources will be presented. The basic flowsheet involves three process steps, each with its own chemistry.

PIERCE, ROBERTA.

2004-03-01T23:59:59.000Z

40

Basis for Section 3116 Determination for Salt Waste Disposal...  

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

concentrate the insoluble solids and the MST solids loaded with Sr and actinides, if MST treatment of the waste was performed. The cross-flow filtration process will yield a...

Note: This page contains sample records for the topic "first-served basis determined" 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

BASIS Equipment | ORNL Neutron Sciences  

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

Equipment Equipment BASIS Schematic Schematic of the SNS Backscattering Spectrometer. Helium dewer cooling a sample Helium dewer cooling a sample (bird's eye view). The heart of the work in a typical experiment is setting up the sample in the desired environment. A typical neutron sample ranging from a millimeter to a few centimeters is placed in a specialized cylindrical can and sealed. For liquids, the backscattering instrument often uses an annular can, created by placing a smaller can within a larger can and inserting the liquid sample between the two cans. This picture shows a helium dewer cooling the environment encompassing the sample can, which has been lowered into the beam from the top of the scattering tank. Crystals Crystals. The backscattering spectrometer is defined by the reflection of specific

42

Internal dosimetry technical basis manual  

Science Conference Proceedings (OSTI)

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

Not Available

1990-12-20T23:59:59.000Z

43

BASIS Set Exchange (BSE): Chemistry Basis Sets from the William R. Wiley Environmental Molecular Sciences Laboratory (EMSL) Basis Set Library  

DOE Data Explorer (OSTI)

The Basis Set Exchange (BSE) provides a web-based user interface for downloading and uploading Gaussian-type (GTO) basis sets, including effective core potentials (ECPs), from the EMSL Basis Set Library. It provides an improved user interface and capabilities over its predecessor, the EMSL Basis Set Order Form, for exploring the contents of the EMSL Basis Set Library. The popular Basis Set Order Form and underlying Basis Set Library were originally developed by Dr. David Feller and have been available from the EMSL webpages since 1994. BSE not only allows downloading of the more than 200 Basis sets in various formats; it allows users to annotate existing sets and to upload new sets. (Specialized Interface)

Feller, D; Schuchardt, Karen L.; Didier, Brett T.; Elsethagen, Todd; Sun, Lisong; Gurumoorthi, Vidhya; Chase, Jared; Li, Jun

44

Advanced Fuel Cycle Cost Basis  

SciTech Connect

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

2008-03-01T23:59:59.000Z

45

Advanced Fuel Cycle Cost Basis  

SciTech Connect

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

2007-04-01T23:59:59.000Z

46

Advanced Fuel Cycle Cost Basis  

SciTech Connect

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

2009-12-01T23:59:59.000Z

47

Office of Nuclear Facility Basis & Facility Design  

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

Office of Nuclear Safety Basis & Facility Design(HS-31) Reports to the Office of Nuclear Safety About Us The Office of Nuclear Safety Basis & Facility Design establishes safety...

48

Basis of conversion factors for energy equivalents  

Science Conference Proceedings (OSTI)

... Basis of conversion factors for energy equivalents Conversion factors for energy equivalents are derived from the following relations: ...

49

Generalized multiscale radial basis function networks  

Science Conference Proceedings (OSTI)

A novel modelling framework is proposed for constructing parsimonious and flexible multiscale radial basis function networks (RBF). Unlike a conventional standard single scale RBF network, where all the basis functions have a common kernel width, the ... Keywords: Model term selection, Neural networks, Nonlinear system identification, Orthogonal least squares, Radial basis functions

Stephen A. Billings; Hua-Liang Wei; Michael A. Balikhin

2007-12-01T23:59:59.000Z

50

Beyond Design Basis Events | Department of Energy  

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

Beyond Design Basis Events Beyond Design Basis Events Beyond Design Basis Events Beyond Design Basis Events Following the March 2011 Fukushima Daiichi nuclear plant accident in Japan, DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to beyond design basis events (BDBEs). These initiatives included issuing Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis, and conducting two DOE nuclear safety workshops. DOE also issued two reports documenting the results of these initiatives: Review of Requirements and Capabilities for Analyzing and Responding to BDBEs, August 2011, and Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities,

51

INL FCF Basis Review Follow-up  

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

2: Evaluation Basis Earthquake Event The second Significant Issue related to the EBE event and included several elements, including input parameters to the analysis,...

52

Lawrence Livermore National Laborotory Safety Basis Assessment...  

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

and implementation of safety basis documentation and execution of the unreviewed safety question (USQ) process. SCOPE The scope of this assessment includes the plans,...

53

Lawrence Livermore National Laborotory Safety Basis Assessment...  

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

of the safety basis for LLNL nuclear facilities. It describes the method for categorizing nuclear facilities and summarizes the resulting requirements for the contents of the DSA....

54

Facility Representative Program: Nuclear Safety Basis Fundamentals...  

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

Qualification Information Qualification Standards DOE Order Self-Study Modules DOE Fundamentals Handbooks Nuclear Safety Basis Self-Study Guide Energy Online Courses Available...

55

Grey-box radial basis function modelling  

Science Conference Proceedings (OSTI)

A fundamental principle in data modelling is to incorporate available a priori information regarding the underlying data generating mechanism into the modelling process. We adopt this principle and consider grey-box radial basis function (RBF) modelling ... Keywords: Black-box model, Boundary value constraint, Data modelling, Grey-box model, Orthogonal least squares algorithm, Radial basis function network, Symmetry

Sheng Chen; Xia Hong; Chris J. Harris

2011-05-01T23:59:59.000Z

56

Property:ExplorationBasis | Open Energy Information  

Open Energy Info (EERE)

ExplorationBasis ExplorationBasis Jump to: navigation, search Property Name ExplorationBasis Property Type Text Description Exploration Basis Why was exploration work conducted in this area (e.g., USGS report of a geothermal resource, hot springs with geothemmetry indicating electrical generation capacity, etc.) Subproperties This property has the following 1 subproperty: M Mercury Vapor At Salt Wells Area (Henkle, Et Al., 2005) Pages using the property "ExplorationBasis" Showing 25 pages using this property. (previous 25) (next 25) 2 2-M Probe Survey At Coso Geothermal Area (1977) + Compare directly shallow temperature results with standard geothermal exploration techniques. 2-M Probe Survey At Coso Geothermal Area (1979) + Correct previously analyzed 2-m probe data

57

Design Basis Threat | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Design Basis Threat | National Nuclear Security Administration Design Basis Threat | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Design Basis Threat Home > About Us > Our Programs > Nuclear Security > Design Basis Threat Design Basis Threat NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or SNM)

58

Basis for UCNI | Department of Energy  

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

and policy foundations for the UCNI program? Section 148 of the Atomic Energy Act of 1954, as amended (42 U.S.C. 2011 et seq.), is the statutory basis for the UCNI program. 10...

59

Fossil Maintenance Basis Optimization: Challenges and Strategies  

Science Conference Proceedings (OSTI)

This report covers many of the process challenges and strategies that were encountered and deployed during the implementation and execution of a preventive maintenance basis optimization (MBO) process at fossil generating stations. This MBO process was executed by several Electric Power Research Institutemember (EPRI-member) companies on a fleetwide basis as part of the members' plant reliability optimization (PRO) efforts. The PRO process covers many of the preventive maintenance (PM) programs at multip...

2010-05-27T23:59:59.000Z

60

Kansas Regional High School Science Bowl | U.S. DOE Office of...  

Office of Science (SC) Website

3 Registration Fee: 25 per team Regional Geographic Information: Kansas Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

Note: This page contains sample records for the topic "first-served basis determined" 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

Wyoming Regional Science Bowl | U.S. DOE Office of Science (SC...  

Office of Science (SC) Website

Information: Wyoming Regional Website: www.wyrsb.org External link Team Approval Process Teams are approved on a first-come, first-served basis determined by the datetime...

62

Safety Basis Criteria & Review Approach Documents | Department of Energy  

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

Safety Basis Criteria & Review Approach Documents Safety Basis Criteria & Review Approach Documents Safety Basis Criteria & Review Approach Documents Documents Available for Download CRAD, Safety Basis - Idaho MF-628 Drum Treatment Facility CRAD, Safety Basis - Idaho Accelerated Retrieval Project Phase II CRAD, Safety Basis - Los Alamos National Laboratory TA 55 SST Facility CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Safety Basis - Y-12 Enriched Uranium Operations Oxide Conversion Facility

63

Solar Power Tower Design Basis Document, Revision 0  

DOE Green Energy (OSTI)

This report contains the design basis for a generic molten-salt solar power tower. A solar power tower uses a field of tracking mirrors (heliostats) that redirect sunlight on to a centrally located receiver mounted on top a tower, which absorbs the concentrated sunlight. Molten nitrate salt, pumped from a tank at ground level, absorbs the sunlight, heating it up to 565 C. The heated salt flows back to ground level into another tank where it is stored, then pumped through a steam generator to produce steam and make electricity. This report establishes a set of criteria upon which the next generation of solar power towers will be designed. The report contains detailed criteria for each of the major systems: Collector System, Receiver System, Thermal Storage System, Steam Generator System, Master Control System, and Electric Heat Tracing System. The Electric Power Generation System and Balance of Plant discussions are limited to interface requirements. This design basis builds on the extensive experience gained from the Solar Two project and includes potential design innovations that will improve reliability and lower technical risk. This design basis document is a living document and contains several areas that require trade-studies and design analysis to fully complete the design basis. Project- and site-specific conditions and requirements will also resolve open To Be Determined issues.

ZAVOICO,ALEXIS B.

2001-07-01T23:59:59.000Z

64

INL FCF Basis Review Follow-up  

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

, 2011 , 2011 Independent Review Report Idaho National Laboratory Fuel Conditioning Facility Safety Basis Review Follow-up PURPOSE The purpose of this follow-up review was to verify how and to what extent Idaho National Laboratory (INL) addressed the Significant Issues that were identified in the April 2010 Independent Oversight report on the INL Fuel Conditioning Facility (FCF) safety basis review, as well as the consideration given to the recommendations that were made. Significant Issues were defined in that report as problems or concerns that affected the validity of the FCF safety basis documentation. The Office of Health, Safety and Security (HSS) fulfilled this objective by reviewing the draft Safety Analysis Report (SAR) for the FCF,

65

Technical Basis for DOE Policy 420.1  

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

HS-0006 HS-0006 TECHNICAL BASIS FOR U.S. DEPARTMENT OF ENERGY NUCLEAR SAFETY POLICY, DOE POLICY 420.1 U.S. DEPARTMENT OF ENERGY OFFICE OF HEALTH, SAFETY AND SECURITY OFFICE OF NUCLEAR SAFETY JULY 2011 i Executive Summary This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOE's operation of nuclear facilities. In developing the revised Policy and performing this analysis, DOE reviewed the current Nuclear

66

Coupled-channel continuum eigenchannel basis  

E-Print Network (OSTI)

The goal of this paper is to calculate bound, resonant and scattering states in the coupled-channel formalism without relying on the boundary conditions at large distances. The coupled-channel solution is expanded in eigenchannel bases i.e. in eigenfunctions of diagonal Hamiltonians. Each eigenchannel basis may includes discrete and discretized continuum (real or complex energy) single particle states. The coupled-channel solutions are computed through diagonalization in these bases. The method is applied to a few two-channel problems. The exact bound spectrum of the Poeschl-Teller potential is well described by a basis of real energy continuum states. For the deuteron with the Reid potential the experimental energy and the $S$ and $D$ wave functions content are reproduced in the asymptotic limit of the energy cutoff. For the Noro-Taylor potential, beside the exact bound state energies the resonant state energy is also well reproduced by using the complex energy Berggren basis. It is found that the expansion of the coupled-channel wave functions in these eigenchannel bases require less computational effort than the use of any other basis. The solutions are stable and converge as the energy cutoff increases.

R. M. Id Betan

2013-11-18T23:59:59.000Z

67

Cold Vacuum Drying facility design basis accident analysis documentation  

SciTech Connect

This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

CROWE, R.D.

2000-08-08T23:59:59.000Z

68

Radioactive Waste Management BasisApril 2006  

Science Conference Proceedings (OSTI)

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2011-08-31T23:59:59.000Z

69

Bessel-Zernike Discrete Variable Representation Basis  

SciTech Connect

The connection between the Bessel discrete variable basis expansion and a specific form of an orthogonal set of Jacobi polynomials is demonstrated. These so-called Zernike polynomials provide alternative series expansions of suitable functions over the unit interval. Expressing a Bessel function in a Zernike expansion provides a straightforward method of generating series identities. Furthermore, the Zernike polynomials may also be used to efficiently evaluate the Hankel transform for rapidly decaying functions or functions with finite support.

Cerjan, C J

2005-10-24T23:59:59.000Z

70

Structural Basis for Activation of Cholera Toxin  

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

Structural Basis for Activation Structural Basis for Activation of Cholera Toxin Structural Basis for Activation of Cholera Toxin Print Wednesday, 30 November 2005 00:00 Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of electrolytes and water into the intestinal cavity, causing the watery diarrhea characteristic of cholera that can lead to severe dehydration and death. Crystal structures of the CTA1 subunit in complex with its activator molecule (ARF6) reveal that binding of the ARF6 "switch" elicits dramatic changes in CTA1 loop regions, exposing the toxin's active site. The extensive CTA1-ARF6 interface mimics recognition of ARF6's normal cellular protein partners, which suggests that the toxin has evolved to exploit the molecular switch's promiscuous binding properties.

71

Business Case Slide 16: High-Volume: Casks - Basis  

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

Basis Previous Slide Next Slide Table of Contents High-Volume: Casks - Basis Basis Storage casks with high-density shielding can be directly loaded in reactor pools Eliminates a...

72

ORISE: The Medical Basis for Radiation-Accident Preparedness...  

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

The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REACTS Symposium on the Medical Basis for Radiation-Accident...

73

The Molecular Basis for Water Taste in Drosophila  

E-Print Network (OSTI)

odorant receptors: a molecular basis for odor recognition.J. , Weissman, J. , Julius, D. Molecular basis of infraredDarnell, J. (2000). Molecular Cell Biology, 4th edition.

Cameron, Peter

2010-01-01T23:59:59.000Z

74

Online Monitoring Technical Basis and Analysis Framework for...  

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

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

75

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT  

Science Conference Proceedings (OSTI)

This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.

KOZLOWSKI, S.D.

2007-05-30T23:59:59.000Z

76

Central waste complex interim safety basis  

Science Conference Proceedings (OSTI)

This interim safety basis provides the necessary information to conclude that hazards at the Central Waste Complex are controlled and that current and planned activities at the CWC can be conducted safely. CWC is a multi-facility complex within the Solid Waste Management Complex that receives and stores most of the solid wastes generated and received at the Hanford Site. The solid wastes that will be handled at CWC include both currently stored and newly generated low-level waste, low-level mixed waste, contact-handled transuranic, and contact-handled TRU mixed waste.

Cain, F.G.

1995-05-15T23:59:59.000Z

77

Technical basis for internal dosimetry at Hanford  

SciTech Connect

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01T23:59:59.000Z

78

Technical basis for internal dosimetry at Hanford  

SciTech Connect

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01T23:59:59.000Z

79

Structural Basis for Activation of Cholera Toxin  

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

Structural Basis for Activation of Cholera Toxin Print Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of electrolytes and water into the intestinal cavity, causing the watery diarrhea characteristic of cholera that can lead to severe dehydration and death. Crystal structures of the CTA1 subunit in complex with its activator molecule (ARF6) reveal that binding of the ARF6 "switch" elicits dramatic changes in CTA1 loop regions, exposing the toxin's active site. The extensive CTA1-ARF6 interface mimics recognition of ARF6's normal cellular protein partners, which suggests that the toxin has evolved to exploit the molecular switch's promiscuous binding properties.

80

Structural Basis for Activation of Cholera Toxin  

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

Structural Basis for Activation of Cholera Toxin Print Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of electrolytes and water into the intestinal cavity, causing the watery diarrhea characteristic of cholera that can lead to severe dehydration and death. Crystal structures of the CTA1 subunit in complex with its activator molecule (ARF6) reveal that binding of the ARF6 "switch" elicits dramatic changes in CTA1 loop regions, exposing the toxin's active site. The extensive CTA1-ARF6 interface mimics recognition of ARF6's normal cellular protein partners, which suggests that the toxin has evolved to exploit the molecular switch's promiscuous binding properties.

Note: This page contains sample records for the topic "first-served basis determined" 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

Structural Basis for Activation of Cholera Toxin  

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

Structural Basis for Activation of Cholera Toxin Print Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of electrolytes and water into the intestinal cavity, causing the watery diarrhea characteristic of cholera that can lead to severe dehydration and death. Crystal structures of the CTA1 subunit in complex with its activator molecule (ARF6) reveal that binding of the ARF6 "switch" elicits dramatic changes in CTA1 loop regions, exposing the toxin's active site. The extensive CTA1-ARF6 interface mimics recognition of ARF6's normal cellular protein partners, which suggests that the toxin has evolved to exploit the molecular switch's promiscuous binding properties.

82

Environmentally Assisted Fatigue (EAF) Screening: Process and Technical Basis for Identifying EAF Limiting Locations  

Science Conference Proceedings (OSTI)

This report provides the technical basis and process for a screening evaluation of a nuclear power plant. This screening will identify appropriate limiting locations for systematic monitoring of the environmentally assisted fatigue (EAF) effects in a Class 1 reactor on the reactor coolant pressure boundary components that are wetted with primary coolant. Use of this process will ensure that the most limiting locations for EAF are determined on a consistent basis.The process developed in ...

2012-09-06T23:59:59.000Z

83

Assessing Beyond Design Basis Seismic Events and Implications on Seismic  

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

Assessing Beyond Design Basis Seismic Events and Implications on Assessing Beyond Design Basis Seismic Events and Implications on Seismic Risk Assessing Beyond Design Basis Seismic Events and Implications on Seismic Risk September 19, 2012 Presenter: Jeffrey Kimball, Technical Specialist (Seismologist) Defense Nuclear Facilities Safety Board Topics Covered: Department of Energy Approach to Natural Phenomena Hazards Analysis and Design (Seismic) Design Basis and Beyond Design Basis Seismic Events Seismic Risk Implications - Key Parameters and Insights Conclusions Assessing Beyond Design Basis Seismic Events and Implications on Seismic Risk More Documents & Publications DOE's Approach to Nuclear Facility Safety Analysis and Management Results from Beyond Design Basis Event Pilots Idaho National Laboratory Advanced Test Reactor Probabilistic Risk

84

Radioactive Waste Management BasisSept 2001  

SciTech Connect

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Goodwin, S S

2011-08-31T23:59:59.000Z

85

Los Alamos National Laboratory Fission Basis  

Science Conference Proceedings (OSTI)

This report is an overview of two main publications that provide a comprehensive review of the Los Alamos National Laboratory (LANL) Fission Basis. The first is the experimental paper, {sup F}ission Product Data Measured at Los Alamos for Fission Spectrum and Thermal Neutrons on {sup 239}Pu, {sup 235}U, {sup 238}U, [Selby, H. D., et al., Nucl. Data Sheets, Vol. 111 2010, pp. 2891-2922] and the second is the theoretical paper, Fission Product Yields from Fission Spectrum n+ {sup 239}Pu for ENDF/B-VII.1, [Chadwick, M. B., et al., Nucl. Data Sheets, Vol. 111, 2010, pp. 2923-2964]. One important note is that none of this work would have been possible without the great documentation of the experimental details and results by G.W. Knobeloch, G. Butler, C.I. Browne, B. Erdal, B. Bayhurst, R. Prestwood, V. Armijo, J. Hasty and many others. (authors)

Keksis, A.L.; Chadwick, M.B.; Selby, H.D.; Mac Innes, M.R.; Barr, D.W.; Meade, R.A.; Burns, C.J.; Wallstrom, T.C. [Los Alamos National Laboratory, NM 87545 (United States)

2011-07-01T23:59:59.000Z

86

Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents  

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

SENSITIVE DOE-STD-1104-2009 May 2009 Superseding DOE-STD-1104-96 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2009 ii Available on the Department of Energy Technical Standards web page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1104-2009 iii CONTENTS FOREWORD .................................................................................................................................. v INTRODUCTION ..........................................................................................................................

87

Climate Change 2001: The Scientific Basis  

Office of Scientific and Technical Information (OSTI)

Climate Change 2001: Climate Change 2001: Working Group I: The Scientific Basis Get Javascript Other reports in this collection 4. Atmospheric Chemistry and Greenhouse Gases Contents Executive Summary 4.1 Introduction 4.1.1 Sources of Greenhouse Gases 4.1.2 Atmospheric Chemistry and Feedbacks 4.1.3 Trace Gas Budgets and Trends 4.1.4 Atmospheric Lifetimes and Time-Scales 4.2 Trace Gases: Current Observations, Trends and Budgets 4.2.1 Non-CO2 Kyoto Gases 4.2.1.1 Methane (CH4) 4.2.1.2 Nitrous oxide (N2O) 4.2.1.3 Hydrofluorocarbons (HFCs) 4.2.1.4 Perfluorocarbons (PFCs) and sulphur hexafluoride (SF6) 4.2.2 Montreal Protocol Gases and Stratospheric Ozone (O3) 4.2.3 Reactive Gases 4.2.3.1 Carbon monoxide (CO) and hydrogen (H2) 4.2.3.2 Volatile organic compounds (VOC) 4.2.3.3 Nitrogen oxides (NOx)

88

Technical Basis for U. S. Department of Energy Nuclear Safety...  

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

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1, 711 Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1,...

89

Business Case Slide 27: High-Value: Semiconductors - Basis for...  

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

Semiconductors - Basis for Use Basis for use DUO2 has good electronic properties for semi-conductor applications Have made and tested a diode and transistor which appear superior...

90

Authorization basis status report (miscellaneous TWRS facilities, tanks and components)  

SciTech Connect

This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.

Stickney, R.G.

1998-04-29T23:59:59.000Z

91

Project Hanford nuclear facilities list and authorization basis information  

SciTech Connect

Rev. 4 documents and updates the Nuclear Facilities list and associated Authorization Basis (AB) information for applicable Project Hanford facilities.

EVANS, C.B.

1999-03-03T23:59:59.000Z

92

A Cautionary Tale of Two Basis Sets and Graphene  

Science Conference Proceedings (OSTI)

Density functional theory is a leading approach for simulating materials. However, the basis set used in calculations can directly affect our understanding of a material. By comparing two basis sets for graphene, this highlights an important subtle point ... Keywords: Density functional theory, basis set, graphene, electronic structure, computational materials science, scientific computing

Derek Stewart

2012-03-01T23:59:59.000Z

93

Skew-Radial Basis Function Expansions for Empirical Modeling  

Science Conference Proceedings (OSTI)

We propose a skew-radial basis function (sRBF) expansion for the empirical model fitting problem. sRBFs employ a standard radial term, which is now made asymmetric by modulating, or skewing it with another function. The additional parameters in the skewing ... Keywords: data fitting, data interpolation, function approximation, manifold learning, radial basis function, skew-radial basis function

Arta A. Jamshidi; Michael J. Kirby

2009-11-01T23:59:59.000Z

94

Minimal Realizations of Linear Systems: The "Shortest Basis" Approach  

E-Print Network (OSTI)

Given a discrete-time linear system C, a shortest basis for C is a set of linearly independent generators for C with the least possible lengths. A basis B is a shortest basis if and only if it has the predictable span ...

Forney, G. David, Jr.

95

Beyond Design Basis Events Analysis and Response Information | Department  

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

Beyond Design Basis Events Analysis Beyond Design Basis Events Analysis and Response Information Beyond Design Basis Events Analysis and Response Information September 19-20, 2012 Beyond Design Basis Events Analysis and Response Information DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011 DOE's Nuclear Safety Workshop Newsletter, June 2011 2011 Nuclear Safety Workshop Presentations, June 2011 Transmittal Memorandum, Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events, September 2011 Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events, August 2011 NRC Report - Recommendations for Enhancing Reactor Safety in the 21st Century; The Near-Term Task Force Review of Insights from the

96

CRAD, Engineering Design and Safety Basis - December 22, 2009 | Department  

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

Engineering Design and Safety Basis - December 22, 2009 Engineering Design and Safety Basis - December 22, 2009 CRAD, Engineering Design and Safety Basis - December 22, 2009 December 22, 2009 Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0) The engineering design and safety basis inspection will evaluate the effectiveness of programs and processes for the design and safety basis of selected safety structures, systems, and components (SSCs) of a nuclear facility. The nuclear facility may be an existing facility, a major modification to an existing facility, or a new facility under construction. Accordingly, the safety basis for the facility, for example, a documented safety analysis (DSA) or a preliminary documented safety analysis (PDSA),

97

CRAD, Engineering Design and Safety Basis - December 22, 2009 | Department  

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

Engineering Design and Safety Basis - December 22, 2009 Engineering Design and Safety Basis - December 22, 2009 CRAD, Engineering Design and Safety Basis - December 22, 2009 December 22, 2009 Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0) The engineering design and safety basis inspection will evaluate the effectiveness of programs and processes for the design and safety basis of selected safety structures, systems, and components (SSCs) of a nuclear facility. The nuclear facility may be an existing facility, a major modification to an existing facility, or a new facility under construction. Accordingly, the safety basis for the facility, for example, a documented safety analysis (DSA) or a preliminary documented safety analysis (PDSA),

98

Design basis for the NRC Operations Center  

SciTech Connect

This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project.

Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

1983-05-01T23:59:59.000Z

99

Results from Beyond Design Basis Event Pilots | Department of Energy  

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

Results from Beyond Design Basis Event Pilots Results from Beyond Design Basis Event Pilots Results from Beyond Design Basis Event Pilots September 19, 2012 Presenter: Mike Hillman, Program Manager, Office of Health, Safety and Security, US Department of Energy Topics covered: Update DOE safety analysis and emergency management requirements/guidance and perform pilot applications Perform system walkdowns and evaluations at several Cat 1 and 2 DOE nuclear facilities to assess potential susceptibilities to natural phenomena hazards and external BDBEs Conduct emergency drills and exercises at DOE sites with nuclear facilities, focusing on BDBEs Results from Beyond Design Basis Event Pilots More Documents & Publications Development of Guidance for Analysis of Beyond Design Basis Events Report to the Secretary of Energy on Beyond Design Basis Event Pilot

100

Groebner Basis Conversion with FGLM - CECM - Simon Fraser ...  

E-Print Network (OSTI)

Groebner Basis Conversion with FGLM. Roman Pearce, MITACS project. Simon Fraser University. The FGLM algorithm of Faugere, Gianni, Lazard and Mora,...

Note: This page contains sample records for the topic "first-served basis determined" 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

Evaluation of Authorization Basis Management Systems and Processes...  

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

related to authorization basis was identified in the 1996 Office of Oversight safety management evaluation of the Pantex Plant. The Defense Nuclear Facilities Safety Board (DNFSB)...

102

CRAD, Safety Basis - Y-12 Enriched Uranium Operations Oxide Conversion...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Safety Basis - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to...

103

Review of Safety Basis Development for the Savannah River Site...  

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

Department of Energy Subject: Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility - Inspection Criteria, Approach, and Line: HS: Rev:...

104

Microsoft Word - Final_SRS_FTF_WD_Basis_March_2012  

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

TED Total Effective Dose TEDE Total Effective Dose Equivalent TER Technical Evaluation Report TNX Training and Experimental Test Facility U.S. United States Basis for Section...

105

CRAD, Review of Safety Basis Development- May 6, 2013  

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

Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility (HSS CRAD 45-59, Rev. 0)

106

Independent Oversight Review of Hanford Tank Farms Safety Basis...  

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

Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades November 2011 Office of Safety and Emergency Management Evaluations Office of...

107

Structural basis of substrate discrimination and integrin binding by autotaxin  

SciTech Connect

Autotaxin (ATX, also known as ectonucleotide pyrophosphatase/phosphodiesterase-2, ENPP2) is a secreted lysophospholipase D that generates the lipid mediator lysophosphatidic acid (LPA), a mitogen and chemoattractant for many cell types. ATX-LPA signaling is involved in various pathologies including tumor progression and inflammation. However, the molecular basis of substrate recognition and catalysis by ATX and the mechanism by which it interacts with target cells are unclear. Here, we present the crystal structure of ATX, alone and in complex with a small-molecule inhibitor. We have identified a hydrophobic lipid-binding pocket and mapped key residues for catalysis and selection between nucleotide and phospholipid substrates. We have shown that ATX interacts with cell-surface integrins through its N-terminal somatomedin B-like domains, using an atypical mechanism. Our results define determinants of substrate discrimination by the ENPP family, suggest how ATX promotes localized LPA signaling and suggest new approaches for targeting ATX with small-molecule therapeutic agents.

Hausmann, Jens; Kamtekar, Satwik; Christodoulou, Evangelos; Day, Jacqueline E.; Wu, Tao; Fulkerson, Zachary; Albers, Harald M.H.G.; van Meeteren, Laurens A.; Houben, Anna J.S.; van Zeijl, Leonie; Jansen, Silvia; Andries, Maria; Hall, Troii; Pegg, Lyle E.; Benson, Timothy E.; Kasiem, Mobien; Harlos, Karl; Vander Kooi, Craig W.; Smyth, Susan S.; Ovaa, Huib; Bollen, Mathieu; Morris, Andrew J.; Moolenaar, Wouter H.; Perrakis, Anastassis (Pfizer); (Leuven); (Oxford); (NCI-Netherlands); (Kentucky)

2013-09-25T23:59:59.000Z

108

Canonical-basis time-dependent Hartree-Fock-Bogoliubov theory and linear-response calculations  

E-Print Network (OSTI)

We present simple equations for a canonical-basis formulation of the time-dependent Hartree-Fock-Bogoliubov (TDHFB) theory. The equations are obtained from the TDHFB theory with an approximation that the pair potential is assumed to be diagonal in the canonical basis. The canonical-basis formulation significantly reduces the computational cost. We apply the method to linear-response calculations for even-even light nuclei and demonstrate its capability and accuracy by comparing our results with recent calculations of the quasi-particle random-phase approximation with Skyrme functionals. We show systematic studies of E1 strength distributions for Ne and Mg isotopes. The evolution of the low-lying pygmy strength seems to be determined by the interplay of several factors, including the neutron excess, separation energy, neutron shell effects, deformation, and pairing.

Shuichiro Ebata; Takashi Nakatsukasa; Tsunenori Inakura; Kenichi Yoshida; Yukio Hashimoto; Kazuhiro Yabana

2010-07-05T23:59:59.000Z

109

Prediction of Critical Desalination Parameters Using Radial Basis Functions Networks  

Science Conference Proceedings (OSTI)

Prediction of critical desalination parameters (recovery and salt rejection) of two distinct processes based on real operational data is presented. The proposed method utilizes the radial basis function network using data clustering and histogram equalization. ... Keywords: neural network, radial basis, reverse osmosis

Mutaz M. Jafar; Ali Zilouchian

2002-06-01T23:59:59.000Z

110

DETERMINATION OF BASIS VALUES FROM EXPERIMENTAL DATA FOR FABRICS AND COMPOSITES  

E-Print Network (OSTI)

, Germany, 2010 Edition. 16. U. S. Department of Defense. Military Handbook - MIL-HDBK-17-1F: Composite

Barbero, Ever J.

111

Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 2, Appendices  

SciTech Connect

This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical & Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties.

Not Available

1993-03-18T23:59:59.000Z

112

Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 1  

SciTech Connect

This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz.

Not Available

1993-03-18T23:59:59.000Z

113

Guidelines for Determining Design Basis Ground Motions: Volumes 1-5  

Science Conference Proceedings (OSTI)

Procedures currently used to assess the nature of earthquake ground motion in Eastern North America introduce considerable uncertainty to the design parameters of nuclear power plants and other critical facilities. This report examines that issue in-depth and provides an engineering model and guideline for selecting a site and assessing its seismic suitability.

1993-12-23T23:59:59.000Z

114

Guidelines for Determining Design Basis Ground Motions: Volumes 1-5  

Science Conference Proceedings (OSTI)

Procedures currently used to assess the nature of earthquake ground motion in Eastern North America introduce considerable uncertainty to the design parameters of nuclear power plants and other critical facilities. This report examines that issue in-depth and provides an engineering model and guideline for selecting a site and assessing its seismic suitability.

1993-12-01T23:59:59.000Z

115

CRAD, Facility Safety - Nuclear Facility Safety Basis | Department of  

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

CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Facility Safety - Nuclear Facility Safety Basis More Documents & Publications CRAD, Facility Safety - Unreviewed Safety Question Requirements Site Visit Report, Livermore Site Office - February 2011 FAQS Job Task Analyses - Nuclear Safety Specialist

116

Exploring continuum structures with a pseudo-state basis  

SciTech Connect

The ability of a recently developed square-integrable discrete basis to represent the properties of the continuum of a two-body system is investigated. The basis is obtained performing a simple analytic local scale transformation to the harmonic oscillator basis. Scattering phase-shifts and the electric transition probabilities B(E1) and B(E2) have been evaluated for several potentials using the proposed basis. Both quantities are found to be in excellent agreement with the exact values calculated from the true scattering states. The basis has been applied to describe the projectile continuum in the {sup 6}He scattering by {sup 12}C and {sup 208}Pb targets at 240 MeV/nucleon and the {sup 11}Be scattering by {sup 12}C at 67 MeV/nucleon. The calculated breakup differential cross sections are found to be in very good agreement with the available experimental data for these reactions.

Lay, J. A.; Moro, A. M.; Arias, J. M.; Gomez-Camacho, J. [Departamento de FAMN, Facultad de Fisica, Universidad de Sevilla, Apdo. 1065, E-41080 Sevilla (Spain); Departamento de FAMN, Facultad de Fisica, Universidad de Sevilla, Apdo. 1065, E-41080 Sevilla, Spain and Centro Nacional de Aceleradores, Avda. Thomas A. Edison, E-41092, Sevilla (Spain)

2010-08-15T23:59:59.000Z

117

CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization,  

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

Basis - Los Alamos National Laboratory Waste Basis - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Safety Basis portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization,

118

Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy  

Science Conference Proceedings (OSTI)

The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system.

TRAWINSKI, B.J.

2000-02-08T23:59:59.000Z

119

Perspective on Beyond Design Basis Event Analysis and Response | Department  

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

Perspective on Beyond Design Basis Event Analysis and Response Perspective on Beyond Design Basis Event Analysis and Response Perspective on Beyond Design Basis Event Analysis and Response September 20, 2012 Presenter: John Schwenker, Nuclear Safety Manager for Liquid Operations, Savannah River Remediation, LLC, Savannah River Site Topics Covered: Waste Tanks can contain up to 1.3 Millions Gallons of highly radioactive waste (sludge, salt, supernate). Type III/IIIA Waste Tank Structures and berms are PC-3 Qualified. Tanks may fail in a Beyond Design Basis Seismic Event. Waste could flow above ground to streams and rivers. Unmitigated Tank Explosion exceeds offsite Evaluation Guidelines Hydrogen gas can be trapped in the sludge and saltcake structure. Seismic Event can cause a prompt release of trapped hydrogen. It is not physically practical to install a ventilation system that

120

Development of Guidance for Analysis of Beyond Design Basis Events |  

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

Development of Guidance for Analysis of Beyond Design Basis Events Development of Guidance for Analysis of Beyond Design Basis Events Development of Guidance for Analysis of Beyond Design Basis Events Wednesday, September 19 Presenter: Dr. James O'Brien, Director, Office of Nuclear Safety, Office of Health, Safety and Security, US Department of Energy Topics covered: Types of DOE Facilities ◦ Research Reactors; ◦ Weapons disassembly, maintenance, and testing facilities; ◦ Nuclear material storage facilities; ◦ Processing facilities; and waste disposal facilities. Safety Analysis Framework ◦ DOE Nuclear Safety Policy ◦ Nuclear Safety Rule ◦ Nuclear Safety Analysis Standards ◦ Documented Safety Analysis Guide Development of Guidance for Analysis of Beyond Design Basis Events More Documents & Publications DOE's Approach to Nuclear Facility Safety Analysis and Management

Note: This page contains sample records for the topic "first-served basis determined" 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

CRAD, Safety Basis - Idaho Accelerated Retrieval Project Phase...  

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

Idaho Accelerated Retrieval Project Phase II CRAD, Safety Basis - Idaho Accelerated Retrieval Project Phase II February 2006 A section of Appendix C to DOE G 226.1-2 "Federal Line...

122

CRAD, Review of Safety Basis Development- October 11, 2012  

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

Review of Safety Basis Development for the Y-12 National Security Complex Uranium Processing Facility Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 45-55, Rev. 0)

123

A Theoretical Basis for Household Energy Conservation UsingProduct...  

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

A Theoretical Basis for Household Energy Conservation Using Product-Integrated Feedback Speaker(s): Teddy McCalley Date: October 11, 2002 - 12:00pm Location: Bldg. 90 Seminar Host...

124

Efficient Software Implementation for Finite Field Multiplication in Normal Basis  

E-Print Network (OSTI)

Abstract. Finite field arithmetic is becoming increasingly important in today's computer systems, particularly for implementing cryptographic operations. Among various arithmetic operations, finite field multiplication is of particular interest since it is a major building block for elliptic curve cryptosystems. In this paper, we present new techniques for efficient software implementation of binary field multiplication in normal basis. Our techniques are more efficient in terms of both speed and memory compared with alternative approaches. 1 Introduction Finite field arithmetic is becoming increasingly important in today's computer systems, particularly for implementing cryptographic operations. Among the more common finite fields in cryptography are odd-characteristic finite fields of degree 1 and even-characteristic finite fields of degree greater than 1. The latter is conventionally known as GF (2m) arithmetic or binary field arithmetic. GF (2m) arithmetic is further classified according to the choice of basis for representing elements of the finite field; two common choices are polynomial basis and normal basis. Fast implementation techniques for GF (2m) arithmetic have been studied intensively in the past twenty years. Among various arithmetic operations, GF (2m) multiplication has attracted most of the attention since it is a major building block for implementing elliptic curve cryptosystems. Depending on the choice of basis, the mathematical formula for a GF (2m) multiplication can be quite different, thus making major differences in practical implementation. Currently, it seems that normal basis representation (especially optimal normal basis) offers the best performance in hardware [9-11], while in software polynomial basis representation is more efficient [2, 3, 8].

Peng Ning; Yiqun Lisa Yin

2001-01-01T23:59:59.000Z

125

Technical Basis Document for PFP Area Monitoring Dosimetry Program  

Science Conference Proceedings (OSTI)

This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

COOPER, J.R.

2000-04-17T23:59:59.000Z

126

Authorization basis supporting documentation for plutonium finishing plant  

Science Conference Proceedings (OSTI)

The identification and definition of the authorization basis for the Plutonium Finishing Plant (PFP) facility and operations are essential for compliance to DOE Order 5480.21, Unreviewed Safety Questions. The authorization basis, as defined in the Order, consists of those aspects of the facility design basis, i.e., the structures, systems and components (SSCS) and the operational requirements that are considered to be important to the safety of operations and are relied upon by DOE to authorize operation of the facility. These facility design features and their function in various accident scenarios are described in WHC-SD-CP-SAR-021, Plutonium Finishing Plant Final Safety Analysis Report (FSAR), Chapter 9, `Accident Analysis.` Figure 1 depicts the relationship of the Authorization Basis to its components and other information contained in safety documentation supporting the Authorization Basis. The PFP SSCs that are important to safety, collectively referred to as the `Safety Envelope` are discussed in various chapters of the FSAR and in WHC-SD-CP-OSR-010, Plutonium Finishing Plant Operational Safety Requirements. Other documents such as Criticality Safety Evaluation Reports (CSERS) address and support some portions of the Authorization Basis and Safety Envelope.

King, J.P., Fluor Daniel Hanford

1997-03-05T23:59:59.000Z

127

CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

128

BASIS: Backscattering Spectrometer at SNS | ORNL Neutron Sciences  

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

Backscattering Spectrometer Backscattering Spectrometer View inside the BAIS tank View inside the BASIS tank. BASIS is a near-backscattering, crystal-analyzer spectrometer that provides very fine energy resolution, as low as 3.0 to 3.5 µeV at the elastic peak (depending on sample size). This requires a long initial guide section of 84 m from moderator to sample in order to achieve the timing resolution necessary for obtaining the desired energy resolution. BASIS provides an excellent dynamic range near the elastic peak of about plus and minus 100 µeV in the standard high-intensity operation regime, which, if needed, could be extended to plus and minus 200 µeV and beyond. The spectrometer is optimized for quasielastic scattering but provides about 0.1% resolution in energy transfers up to ~40 meV; the inelastic excitations need to be

129

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747  

SciTech Connect

'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

RYAN GW

2007-09-24T23:59:59.000Z

130

The Functional Requirements and Design Basis for Information Barriers  

SciTech Connect

This report summarizes the results of the Information Barrier Working Group workshop held at Sandia National Laboratory in Albuquerque, NM, February 2-4, 1999. This workshop was convened to establish the functional requirements associated with warhead radiation signature information barriers, to identify the major design elements of any such system or approach, and to identify a design basis for each of these major elements. Such information forms the general design basis to be used in designing, fabricating, and evaluating the complete integrated systems developed for specific purposes.

Fuller, James L.

2012-05-01T23:59:59.000Z

131

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE  

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

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1 This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOE's operation of nuclear facilities. In developing the revised Policy and performing this analysis, DOE reviewed the current Nuclear Safety Policy (Secretary of Energy Notice [SEN] 35-91, Nuclear Safety Policy) and safety policies established by other safety

132

A Radial Basis Function Method for Global Optimization  

Science Conference Proceedings (OSTI)

We introduce a method that aims to find the global minimum of a continuous nonconvex function on a compact subset of \\dRd. It is assumed that function evaluations are expensive and that no additional information is available. ... Keywords: Global optimization, P-algorithm, interpolation, radial basis functions

H.-M. Gutmann

2001-03-01T23:59:59.000Z

133

Hierarchical Structure for function approximation using radial basis function  

Science Conference Proceedings (OSTI)

The hierarchial network proposed (Multi-RBFNN), is composed of complete Radial Basis Function Neural Networks (RBFNNs) that are in charge of a reduced set of input variables with the property of which every Sub-RBFNN can take charge of a set of input ... Keywords: function approximation, hierarchical architectures, input variable selection, radial bases functions

A. Awad; H. Pomares; I. Rojas; L. J. Herrera; A. Guillen; O. Valenzuela

2005-12-01T23:59:59.000Z

134

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation  

Science Conference Proceedings (OSTI)

This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

CROWE, R.D.; PIEPHO, M.G.

2000-03-23T23:59:59.000Z

135

Technical basis for classification of low-activity waste fraction from Hanford site tanks  

SciTech Connect

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Petersen, C.A.

1996-09-20T23:59:59.000Z

136

Basis for NGNP Reactor Design Down-Selection  

Science Conference Proceedings (OSTI)

The purpose of this paper is to identify the extent of technology development, design and licensing maturity anticipated to be required to credibly identify differences that could make a technical choice practical between the prismatic and pebble bed reactor designs. This paper does not address a business decision based on the economics, business model and resulting business case since these will vary based on the reactor application. The selection of the type of reactor, the module ratings, the number of modules, the configuration of the balance of plant and other design selections will be made on the basis of optimizing the Business Case for the application. These are not decisions that can be made on a generic basis.

L.E. Demick

2010-08-01T23:59:59.000Z

137

The reduced basis method for the electric field integral equation  

Science Conference Proceedings (OSTI)

We introduce the reduced basis method (RBM) as an efficient tool for parametrized scattering problems in computational electromagnetics for problems where field solutions are computed using a standard Boundary Element Method (BEM) for the parametrized electric field integral equation (EFIE). This combination enables an algorithmic cooperation which results in a two step procedure. The first step consists of a computationally intense assembling of the reduced basis, that needs to be effected only once. In the second step, we compute output functionals of the solution, such as the Radar Cross Section (RCS), independently of the dimension of the discretization space, for many different parameter values in a many-query context at very little cost. Parameters include the wavenumber, the angle of the incident plane wave and its polarization.

Fares, M., E-mail: fares@cerfacs.f [2 Avenue Gaspard Coriolis, 31057 Toulouse Cedex 01 (France); Hesthaven, J.S., E-mail: Jan_Hesthaven@Brown.ed [Division of Applied Mathematics, Brown University, Box F, Providence, RI 02912 (United States); Maday, Y., E-mail: maday@ann.jussieu.f [Laboratoire Jacques-Louis Lions, Universite Pierre et Marie Curie, Boite courrier 18, 75252 Paris Cedex 05 (France); Stamm, B., E-mail: stamm@math.berkeley.ed [Department of Mathematics, University of California, Berkeley, CA 94720 (United States)

2011-06-20T23:59:59.000Z

138

Basis for NGNP Reactor Design Down-Selection  

SciTech Connect

The purpose of this paper is to identify the extent of technology development, design and licensing maturity anticipated to be required to credibly identify differences that could make a technical choice practical between the prismatic and pebble bed reactor designs. This paper does not address a business decision based on the economics, business model and resulting business case since these will vary based on the reactor application. The selection of the type of reactor, the module ratings, the number of modules, the configuration of the balance of plant and other design selections will be made on the basis of optimizing the Business Case for the application. These are not decisions that can be made on a generic basis.

L.E. Demick

2011-11-01T23:59:59.000Z

139

Biological Basis for Radiation Adaptive Responses that Protect Against  

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

Basis for Radiation Adaptive Responses that Protect Against Basis for Radiation Adaptive Responses that Protect Against Bronchial Epithelial Cell Transformation Wenshu Chen Lovelace Respiratory Research Institute Abstract The major hypothesis in this project is that low-dose, low linear-energy-transfer (LET) radiation stimulates an adaptive response that protects cells from neoplastic transformation involving modulation of paracrine factors (e.g., cytokines), cell survival/death signaling pathways, and reprogramming of the epigenome. To test this hypothesis, a validated, sensitive in vitro transformation model and a media transfer method were used to study the mechanisms of low-LET gamma radiation activated natural protection (ANP) against chemical carcinogen-induced bronchial cell transformation. Immortalized human bronchial epithelial cell

140

Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities  

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

5506-2007 5506-2007 April 2007 DOE STANDARD Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities U.S. Department of Energy Washington, D.C. 20585 AREA-SAFT DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-5506-2007 ii Available on the Department of Energy Technical Standards Program Web Site at Http://tis.eh.doe.gov/techstds/ DOE-STD-5506-2007 iii Foreword This Standard provides analytical assumptions and methods, as well as hazard controls to be used when developing Safety Basis (SB) documents for transuranic (TRU) waste facilities in the U.S. Department of Energy (DOE) Complex. It also provides supplemental technical

Note: This page contains sample records for the topic "first-served basis determined" 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

First-Generation Monitoring System for ADA: Design Basis  

Science Conference Proceedings (OSTI)

The vision of the EPRI ADA Program (Program 124) is to create the technology basis for the distribution system of the future by transforming traditional single-function distribution systems into multifunctional power and information exchange systems with increased reliability, improved performance (lower system losses), better economics, better power quality, and more customer service options. Achieving this vision will require capturing the benefits of new capabilities in power electronics, information ...

2006-12-18T23:59:59.000Z

142

Engineering basis for selection of positron source material  

Science Conference Proceedings (OSTI)

This note describes the engineering basis for the selection of the positron source material. It assumes the approximate physics parameters have already been chosen (i.e. a high Z material of 6 radiation lengths thickness). As part of this study a basic heat transfer analysis of the target was performed and is discussed. It is concluded that Ta-10W is the most likely material to meet required physics parameters and not fail structurally.

Feerick, B.

1983-10-10T23:59:59.000Z

143

Burnup Credit Technical Basis for Spent-Fuel Burnup Verification  

Science Conference Proceedings (OSTI)

Present regulatory practices provide as much burnup credit flexibility as can be currently expected. Further progress is achievable by incorporating the negative reactivity effects of a subset of neutron-absorbing fission-product isotopes, and by optimizing the procedural approach for establishing the burnup characteristics of the spent fuel to be loaded in burnup-credit-designed storage and transportation systems. This report describes progress toward developing a technical basis for a cost-effective bu...

2003-12-02T23:59:59.000Z

144

Evolution of Safety Basis Documentation for the Fernald Site  

SciTech Connect

The objective of the Department of Energy's (DOE) Fernald Closure Project (FCP), in suburban Cincinnati, Ohio, is to safely complete the environmental restoration of the Fernald site by 2006. Over 200 out of 220 total structures, at this DOE plant site which processed uranium ore concentrates into high-purity uranium metal products, have been safely demolished, including eight of the nine major production plants. Documented Safety Analyses (DSAs) for these facilities have gone through a process of simplification, from individual operating Safety Analysis Reports (SARs) to a single site-wide Authorization Basis containing nuclear facility Bases for Interim Operations (BIOs) to individual project Auditable Safety Records (ASRs). The final stage in DSA simplification consists of project-specific Integrated Health and Safety Plans (I-HASPs) and Nuclear Health and Safety Plans (N-HASPs) that address all aspects of safety, from the worker in the field to the safety basis requirements preserving the facility/activity hazard categorization. This paper addresses the evolution of Safety Basis Documentation (SBD), as DSAs, from production through site closure.

Brown, T.; Kohler, S.; Fisk, P.; Krach, F.; Klein, B.

2004-03-01T23:59:59.000Z

145

Gender determination in populus  

DOE Green Energy (OSTI)

Gender, the expression of maleness or femaleness, in dioecious plants has been associated with changes in morphology, physiology, ecological position, and commercial importance of several species, including members of the Salicaceae family. Various mechanisms have been proposed to explain the expression of gender in Salicaceae, including sex chromosomes, simple Mendelian genes, quantitative genes, environment, and genotype-by-environment interactions. Published reports would favor a genetic basis for gender. The objective of this study was to identify molecular markers associated with gender in a segregating family of hybrid poplars. Bulked segregant analysis and chi-squared analysis were used to test for the occurrence of sex chromosomes, individual loci, and chromosome ratios (i.e., ploidy levels) as the mechanisms for gender determination. Examination of 2488 PCR based RAPD markers from 1219 primers revealed nine polymorphic bands between male and female bulked samples. However, linkage analysis indicated that none of these markers were significantly associated with gender. Chisquared results for difference in male-to-female ratios between diploid and triploid genotypes also revealed no significant differences. These findings suggest gender is not controlled via sex chromosomes, simple Mendelian loci or ratios of autosome to gender-determining loci. It is possible that gender is determined genetically by regions of the genome not sampled by the tested markers or by a complex of loci operating in an additive threshold manner or in an epistatic manner. It is also possible that gender is determined environmentally at an early zygote stage, canalizing gender expression.

McLetchie, D.N. [Univ. of Kentucky, Lexington, KY (United States). Dept. of Biological Sciences; Tuskan, G.A. [Oak Ridge National Lab., TN (United States)

1994-12-31T23:59:59.000Z

146

Business Case Slide 8: High-Volume: Repository - Basis for Use  

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

Volume: Repository - Basis for Use Basis for use DUO2 in or near cask should be a geochemical barrier Establish reducing conditions Inhibit spent fuel dissolution Keep...

147

Interim safety basis for fuel supply shutdown facility  

SciTech Connect

This ISB in conjunction with the new TSRs, will provide the required basis for interim operation or restrictions on interim operations and administrative controls for the Facility until a SAR is prepared in accordance with the new requirements. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings.

Brehm, J.R.; Deobald, T.L.; Benecke, M.W.; Remaize, J.A.

1995-05-23T23:59:59.000Z

148

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNLs Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNLs Electronic Records & Information Capture Architecture (ERICA) database.

Rathbone, Bruce A.

2005-02-25T23:59:59.000Z

149

A New Basis of Geoscience: Whole-Earth Decompression Dynamics  

E-Print Network (OSTI)

Neither plate tectonics nor Earth expansion theory is sufficient to provide a basis for understanding geoscience. Each theory is incomplete and possesses problematic elements, but both have served as stepping stones to a more fundamental and inclusive geoscience theory that I call Whole-Earth Decompression Dynamics (WEDD). WEDD begins with and is the consequence of our planet's early formation as a Jupiter-like gas giant and permits deduction of:(1) Earth's internal composition, structure, and highly-reduced oxidation state; (2) Core formation without whole-planet melting; (3) Powerful new internal energy sources - proto-planetary energy of compression and georeactor nuclear fission energy; (4) Georeactor geomagnetic field generation; (5) Mechanism for heat emplacement at the base of the crust resulting in the crustal geothermal gradient; (6) Decompression driven geodynamics that accounts for the myriad of observations attributed to plate tectonics without requiring physically-impossible mantle convection, and; (7) A mechanism for fold-mountain formation that does not necessarily require plate collision. The latter obviates the necessity to assume supercontinent cycles. Here, I review the principles of Whole-Earth Decompression Dynamics and describe a new underlying basis for geoscience and geology.

J. Marvin Herndon

2013-07-04T23:59:59.000Z

150

Electric Utility Rate Design Study: embedded generation costs on a time-of-day basis for Iowa Southern Utilities Company  

SciTech Connect

This report develops a method for determining average embedded generation costs on a time-of-day basis and describes the application of the method to Iowa Southern Utilities. These costs are not allocated to customer classes. Since average embedded costs are composed of the running (or variable) costs and the capital costs, the analysis examines each of these separately. Running costs on a time-of-day basis are determined through the use of a generation dispatch model that reports the loadings by generating unit and the running costs of meeting the load. These costs are reported on an hour-by-hour basis. The dispatch model takes into account the operating characteristics of each unit and the major engineering constraints on a system; e.g., must-run units, minimum up and down time, startup cost. After reviewing several suggested capital-cost allocation procedures, a method is developed that allocates capital costs on a time-of-day basis by using a recontracting-for-capacity procedure that allows capacity to vary by hour for each month. The method results in allocations to customers who benefit from its use. An important and distinguishing feature of this method is that it allows calculation of the costs before rating periods are chosen.

1980-01-01T23:59:59.000Z

151

Guidance For Preparatioon of Basis For Interim Operation (BIO) Documents  

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

3011-2002 3011-2002 December 2002 Superceding DOE-STD-3011-94 November 1994 DOE STANDARD GUIDANCE FOR PREPARATION OF BASIS FOR INTERIM OPERATION (BIO) DOCUMENTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-3011-2002 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161;

152

Online Monitoring Technical Basis and Analysis Framework for Large Power  

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

for Large for Large Power Transformers; Interim Report for FY 2012 Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012 The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the U.S. Department of Energy Office of Nuclear Energy. The program is operated in collaboration with the Electric Power Research Institute's (EPRI's) research and development efforts in the Long-Term Operations (LTO) Program. The LTO Program is managed as a separate technical program operating in the Plant Technology Department of the EPRI Nuclear Power Sector with the guidance of an industry advisory Integration Committee. Because both the Department of Energy Office of Nuclear Energy and EPRI conduct research and development in technologies

153

Online Monitoring Technical Basis and Analysis Framework for Emergency  

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

for for Emergency Diesel Generators-Interim Report for FY 2013 Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators-Interim Report for FY 2013 The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the U.S. Department of Energy Office of Nuclear Energy. The program is operated in collaboration with the Electric Power Research Institute's (EPRI's) research and development efforts in the Long-Term Operations Program. The Long-Term Operations Program is managed as a separate technical program operating in the Plant Technology Department of the EPRI Nuclear Power Sector with the guidance of an industry advisory Integration Committee. Because both the Department of Energy Office of Nuclear Energy and EPRI conduct research and development

154

Experimental Progress Report--Modernizing the Fission Basis  

Science Conference Proceedings (OSTI)

In 2010 a proposal (Modernizing the Fission Basis) was prepared to 'resolve long standing differences between LANL and LLNL associated with the correct fission basis for analysis of nuclear test data'. Collaboration between LANL/LLNL/TUNL has been formed to implement this program by performing high precision measurements of neutron induced fission product yields as a function of incident neutron energy. This new program benefits from successful previous efforts utilizing mono-energetic neutrons undertaken by this collaboration. The first preliminary experiment in this new program was performed between July 24-31, 2011 at TUNL and had 2 main objectives: (1) demonstrating the capability to measure characteristic {gamma}-rays from specific fission products; (2) studying background effects from room scattered neutrons. In addition, a new dual fission ionization chamber has been designed and manufactured. The production design of the chamber is shown in the picture below. The first feasibility experiment to test this chamber is scheduled at the TUNL Tandem Laboratory from September 19-25, 2011. The dual fission chamber design will allow simultaneous exposure of absolute fission fragment emission rate detectors and the thick fission activation foils, positioned between the two chambers. This document formalizes the earlier experimental report demonstrating the experimental capability to make accurate (fission product yields of the 239Pu(n,f) reaction (induced by quasimonoenergetic neutrons). A second experiment (9/2011) introduced an compact double-sided fission chamber into the experimental arrangement, and so the relative number of incident neutrons striking the sample foil at each bombarding energy is limited only by statistics. (The number of incident neutrons often limits the experimental accuracy.) Fission chamber operation was so exceptional that 2 more chambers have been fabricated; thus fission foils of different isotopes may be left in place with sample changes. The scope of the measurements is both greatly expanded and the results become vetted. Experiment 2 is not reported here. A continuing experiment has been proposed for February 2012.

Macri, R A

2012-02-17T23:59:59.000Z

155

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNLs Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNLs Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document.

Rathbone, Bruce A.

2009-08-28T23:59:59.000Z

156

A Basis for the Prediction of Performance of Deaf Aids  

Science Conference Proceedings (OSTI)

A relation can be established whereby the performance of a deaf aid can be rated in a manner comparable with other scientific apparatus. By using normal hearing observers determinations were made for representative types and makes of hearing aids

Charles M. R. Balbi

1942-01-01T23:59:59.000Z

157

Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 2, Technical basis  

Science Conference Proceedings (OSTI)

Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume, Volume 2, contains the technical basis for the 1992 PA. Specifically, it describes the conceptual basis for consequence modeling and the PA methodology, including the selection of scenarios for analysis, the determination of scenario probabilities, and the estimation of scenario consequences using a Monte Carlo technique and a linked system of computational models. Additional information about the 1992 PA is provided in other volumes. Volume I contains an overview of WIPP PA and results of a preliminary comparison with the long-term requirements of the EPA`s Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses related to the preliminary comparison with 40 CFR 191B. Volume 5 contains uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance. Finally, guidance derived from the entire 1992 PA is presented in Volume 6.

Not Available

1992-12-01T23:59:59.000Z

158

Engineering Basis Document Review Supporting the Double Shell Tank (DST) System Specification Development  

Science Conference Proceedings (OSTI)

The Double-Shell Tank (DST) System is required to transition from its current storage mission to a storage and retrieval mission supporting the River Protection Project Phase 1 privatization, defined in HNF-SD-WM-MAR-008, Tank Waste Remediation System Mission Analysis Report. Requirements for the DST subsystems are being developed using the top-down systems engineering process outlined in HNF-SD-WM-SEMP-002, Tank Waste Remediation System Systems Engineering Management Plan. This top-down process considers existing designs to the extent that these designs impose unavoidable constraints on the Phase 1 mission. Existing engineering-basis documents were screened, and the unavoidable constraints were identified. The constraints identified herein will be added to the DST System specification (HNF-SD-WM-TRD-007, System Specification for the Double-Shell Tank System). While the letter revisions of the DST System specification were constructed with a less rigorous review of the existing engineering-basis documents, the Revision 0 release of the specification must incorporate the results of the review documented herein. The purpose of this document is to describe the screening process and criteria used to determine which constraints are unavoidable and to document the screening results.

LEONARD, M.W.

2000-03-14T23:59:59.000Z

159

Current plans to characterize the design basis ground motion at the Yucca Mountain, Nevada Site  

SciTech Connect

A site at Yucca Mountain Nevada is currently being studied to assess its suitability as a potential host site for the nation`s first commercial high level waste repository. The DOE has proposed a new methodology for determining design-basis ground motions that uses both deterministic and probabilistic methods. The role of the deterministic approach is primary. It provides the level of detail needed by design engineers in the characterization of ground motions. The probabilistic approach provides a logical structured procedure for integrating the range of possible earthquakes that contribute to the ground motion hazard at the site. In addition, probabilistic methods will be used as needed to provide input for the assessment of long-term repository performance. This paper discusses the local tectonic environment, potential seismic sources and their associated displacements and ground motions. It also discusses the approach to assessing the design basis earthquake for the surface and underground facilities, as well as selected examples of the use of this type of information in design activities.

Simecka, W.B. [USDOE Nevada Field Office, Las Vegas, NV (United States); Grant, T.A.; Voegele, M.D. [Science Applications International Corp., Las Vegas, NV (United States); Cline, K.M. [Woodward-Clyde Federal Services, Washington, DC (United States)

1992-12-31T23:59:59.000Z

160

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanfords DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNLs Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2.

Rathbone, Bruce A.

2010-04-01T23:59:59.000Z

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


161

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanfords DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNLs Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2.

Rathbone, Bruce A.

2011-04-04T23:59:59.000Z

162

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNLs Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNLs Electronic Records & Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor revision. Updated Chapters 5, 6 and 9 to reflect change in default ring calibration factor used in HEDP dose calculation software. Factor changed from 1.5 to 2.0 beginning January 1, 2007. Pages on which changes were made are as follows: 5.23, 5.69, 5.78, 5.80, 5.82, 6.3, 6.5, 6.29, 9.2.

Rathbone, Bruce A.

2007-03-12T23:59:59.000Z

163

Experimental Progress Report--Modernizing the Fission Basis  

SciTech Connect

In 2010 a proposal (Modernizing the Fission Basis) was prepared to 'resolve long standing differences between LANL and LLNL associated with the correct fission basis for analysis of nuclear test data'. Collaboration between LANL/LLNL/TUNL has been formed to implement this program by performing high precision measurements of neutron induced fission product yields as a function of incident neutron energy. This new program benefits from successful previous efforts utilizing mono-energetic neutrons undertaken by this collaboration. The first preliminary experiment in this new program was performed between July 24-31, 2011 at TUNL and had 2 main objectives: (1) demonstrating the capability to measure characteristic {gamma}-rays from specific fission products; (2) studying background effects from room scattered neutrons. In addition, a new dual fission ionization chamber has been designed and manufactured. The production design of the chamber is shown in the picture below. The first feasibility experiment to test this chamber is scheduled at the TUNL Tandem Laboratory from September 19-25, 2011. The dual fission chamber design will allow simultaneous exposure of absolute fission fragment emission rate detectors and the thick fission activation foils, positioned between the two chambers. This document formalizes the earlier experimental report demonstrating the experimental capability to make accurate (< 2 %) precision gamma-ray spectroscopic measurements of the excitation function of high fission product yields of the 239Pu(n,f) reaction (induced by quasimonoenergetic neutrons). A second experiment (9/2011) introduced an compact double-sided fission chamber into the experimental arrangement, and so the relative number of incident neutrons striking the sample foil at each bombarding energy is limited only by statistics. (The number of incident neutrons often limits the experimental accuracy.) Fission chamber operation was so exceptional that 2 more chambers have been fabricated; thus fission foils of different isotopes may be left in place with sample changes. The scope of the measurements is both greatly expanded and the results become vetted. Experiment 2 is not reported here. A continuing experiment has been proposed for February 2012.

Macri, R A

2012-02-17T23:59:59.000Z

164

Hanford Technical Basis for Multiple Dosimetry Effective Dose Methodology  

SciTech Connect

The current method at Hanford for dealing with the results from multiple dosimeters worn during non-uniform irradiation is to use a compartmentalization method to calculate the effective dose (E). The method, as documented in the current version of Section 6.9.3 in the 'Hanford External Dosimetry Technical Basis Manual, PNL-MA-842,' is based on the compartmentalization method presented in the 1997 ANSI/HPS N13.41 standard, 'Criteria for Performing Multiple Dosimetry.' With the adoption of the ICRP 60 methodology in the 2007 revision to 10 CFR 835 came changes that have a direct affect on the compartmentalization method described in the 1997 ANSI/HPS N13.41 standard, and, thus, to the method used at Hanford. The ANSI/HPS N13.41 standard committee is in the process of updating the standard, but the changes to the standard have not yet been approved. And, the drafts of the revision of the standard tend to align more with ICRP 60 than with the changes specified in the 2007 revision to 10 CFR 835. Therefore, a revised method for calculating effective dose from non-uniform external irradiation using a compartmental method was developed using the tissue weighting factors and remainder organs specified in 10 CFR 835 (2007).

Hill, Robin L.; Rathbone, Bruce A.

2010-08-01T23:59:59.000Z

165

Probing the Pareto frontier for basis pursuit solutions  

E-Print Network (OSTI)

and a single parameter determines a curve that traces the optimal trade-off between the least-squares ... In the presence of noisy or imperfect data, however, it is undesirable to exactly fit the ...... Algorithm 2 is a distillation of this procedure.

166

Business Case Slide 23: High-Value: Catalysts - Basis for Use  

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

Catalysts - Basis for Use Basis for use DUO2 has previously been used as a catalyst Dissociation of volatile organic compounds and nitrogen oxides in off-gas streams Oxidation of...

167

Business Case Slide 30: High-Value: Energy Uses - Basis for Use  

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

Energy Uses - Basis for Use DUO2 battery test cell at U. Kentucky DUO2 battery test cell at U. Kentucky Basis for use Capable of sustaining high temperatures Electronic properties...

168

Optimizing Radial Basis Functions by D.C. Programming and its use ...  

E-Print Network (OSTI)

Oct 6, 2009 ... the use of derivative-free models based on radial basis functions .... known, one can use a radial basis functions (RBF) model of the form m(x) =.

169

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNLs Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNLs Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Updated Chapters 5, 6 and 9 to reflect change in default ring calibration factor used in HEDP dose calculation software. Factor changed from 1.5 to 2.0 beginning January 1, 2007. Pages on which changes were made are as follows: 5.23, 5.69, 5.78, 5.80, 5.82, 6.3, 6.5, 6.29, and 9.2. Rev 0.2 (8/28/2009) Updated Chapters 3, 5, 6, 8 and 9. Chapters 6 and 8 were significantly expanded. References in the Preface and Chapters 1, 2, 4, and 7 were updated to reflect updates to DOE documents. Approved by HPDAC on 6/2/2009. Rev 1.0 (1/1/2010) Major revision. Updated all chapters to reflect the Hanford site wide implementation on January 1, 2010 of new DOE requirements for occupational radiation protection. The new requirements are given in the June 8, 2007 amendment to 10 CFR 835 Occupational Radiation Protection (Federal Register, June 8, 2007. Title 10 Part 835. U.S., Code of Federal Regulations, Vol. 72, No. 110, 31904-31941). Revision 1.0 to the manual replaces ICRP 26 dosimetry concepts and terminology with ICRP 60 dosimetry concepts and terminology and replaces external dose conversion factors from ICRP 51 with those from ICRP 74 for use in measurement of operational quantities with dosimeters. Descriptions of dose algorithms and dosimeter response characteristics, and field performance were updated to reflect changes in the neutron quality factors used in the measurement of operational quantities.

Rathbone, Bruce A.

2010-01-01T23:59:59.000Z

170

Safety evaluation of MHTGR licensing basis accident scenarios  

SciTech Connect

The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant reactor safety codes were extended for this purpose and applied to this new reactor concept, searching primarily for potential accident scenarios that might lead to fuel failures due to excessive core temperatures and/or to vessel damage, due to excessive vessel temperatures. The design basis accident scenario leading to the highest vessel temperatures is the depressurized core heatup scenario without any forced cooling and with decay heat rejection to the passive Reactor Cavity Cooling System (RCCS). This scenario was evaluated, including numerous parametric variations of input parameters, like material properties and decay heat. It was found that significant safety margins exist, but that high confidence levels in the core effective thermal conductivity, the reactor vessel and RCCS thermal emissivities and the decay heat function are required to maintain this safety margin. Severe accident extensions of this depressurized core heatup scenario included the cases of complete RCCS failure, cases of massive air ingress, core heatup without scram and cases of degraded RCCS performance due to absorbing gases in the reactor cavity. Except for no-scram scenarios extending beyond 100 hr, the fuel never reached the limiting temperature of 1600/degree/C, below which measurable fuel failures are not expected. In some of the scenarios, excessive vessel and concrete temperatures could lead to investment losses but are not expected to lead to any source term beyond that from the circulating inventory. 19 refs., 56 figs., 11 tabs.

Kroeger, P.G.

1989-04-01T23:59:59.000Z

171

Nuclear Facility Safety Basis Fundamentals Self-Study Guide - November 2002  

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

Oak Ridge Operations Office Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)] November 2002 Nuclear Facility Safety Basis Fundamentals Self-Study Guide TABLE OF CONTENTS Acronyms and Abbreviations ......................................................................................... iii List of Figures ....................................................................................................................iv List of Tables......................................................................................................................iv INTRODUCTION..............................................................................................................1

172

Efficient basis for the Dicke Model I: theory and convergence in energy  

E-Print Network (OSTI)

An extended bosonic coherent basis has been shown by Chen to provide numerically exact solutions of the finite-size Dicke model. The advantages in employing this basis, as compared with the photon number (Fock) basis, are exhibited to be valid for a large region of the Hamiltonian parameter space by analyzing the converged values of the ground state energy.

Miguel Angel Bastarrachea-Magnani; Jorge G. Hirsch

2013-12-06T23:59:59.000Z

173

Molecular basis for activation of G protein-coupled receptor kinases  

E-Print Network (OSTI)

Molecular basis for activation of G protein-coupled receptor kinases Cassandra A Boguth1,3 , Puja regulated by acti- vated GPCRs, but the molecular basis for this interaction is not understood. Herein, we to discriminate between active and inactive GPCRs. The molecular basis for how these protein families can identify

Rosenberg, Noah

174

Optimized local basis set for Kohn-Sham density functional theory  

Science Conference Proceedings (OSTI)

We develop a technique for generating a set of optimized local basis functions to solve models in the Kohn-Sham density functional theory for both insulating and metallic systems. The optimized local basis functions are obtained by solving a minimization ... Keywords: Discontinuous Galerkin, Electronic structure, GMRES, Kohn-Sham density functional theory, Molecular dynamics, Optimized local basis set, Preconditioning, Pulay force, Trace minimization

Lin Lin; Jianfeng Lu; Lexing Ying; Weinan E

2012-05-01T23:59:59.000Z

175

The basis for the determination that the abandoned cold recovery system is a non-fissle operation  

E-Print Network (OSTI)

Application of strict NRC regulation to older nuclear facilities raises safety concerns that would otherwise have been overlooked. This paper looks at a specific operation that has been abandoned for thirty years. The method of evaluation, while applying the basic fundamentals of nuclear criticality safety, is different in approach from the industry standard nuclear criticality evaluation due to the circumstances. Unknown quantities and enrichments of fissile material were left in the process equipment. The evaluation provides guidance to bring closure and provides nuclear criticality safety for this legacy equipment issue.

Burdick, Paul Alan

1999-01-01T23:59:59.000Z

176

NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 |  

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

NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 The objective of this surveillance is for the Facility Representative to verify that the facility's configuration and operations remain consistent with the authorization basis. As defined in DOE Notice 411.1-1B, the authorization basis consists of those aspects of the facility design basis and operational requirements relied upon by DOE to authorize operation. These aspects are considered to be important to the safety of the facility operations. The authorization basis is described in documents such as the facility safety analysis report and other documented safety analyses; hazard classification documents, and the Technical Safety Requirements,

177

Safety-Basis Thermal Analysis for KE Basin Sludge Transport and Storage  

DOE Green Energy (OSTI)

A series of safety-basis thermal and gas generation analyses were completed and independently reviewed to assess the thermal performance of a large diameter container (LDC) containing KE Basin sludge. The results demonstrate: (1) the sludge transport system (STS) containing a LDC can safely transport a KE basin sludge payload up to 2.0 m{sup 3} and, (2) large diameter containers with sludge payloads up to 2.0 m{sup 3} can be safely stored in a process cell at T Plant. The transport and storage analyses are based on a conservative set of assumptions, including limiting environmental conditions. Conclusions drawn from the transport and storage results were not impacted by changes in the radial gap between the cask and LDC, purge gas (i.e., either helium or nitrogen), sludge porosity, or thermal conductivity. The design of the transport cask and large diameter container can accommodate reasonable changes in these values. Both transport from KE Basin and long-term storage at T Plant are addressed for sludge payloads up to 2.0 m{sup 3}. Additional analyses determined the expected range of T Plant environmental temperatures, the hydrogen and oxygen generation rate due to the radiolysis of water, and the maximum hydrogen concentration within a process cell due to chemical reactions and the radiolysis of water. All sludge temperature and hydrogen concentration criteria for transport and storage are met. The analyses assumed a safety-basis sludge mixture defined as 60% by volume floor and 40% by volume canister sludge with 35% retained gas, and a conservative segregated (axial) distribution of metallic uranium (resulting from particulate settling) with associated safety-basis properties. The analyses recognized that the retrieval process would produce non-uniform sludge distributions. Four batch process loadings of 0.5m{sup 3} each are assumed. Each process batch loading will settle and segregate (separate) into two layers: an active layer containing all the metallic uranium which is chemically active, and a non-active layer containing uranium oxide, non-uranium material, and no metallic uranium. This is a conservative representation of operational controls designed to limit the metallic uranium concentration. The sludge layers are assumed to remain intact during transport and storage.

HEARD, F.J.; SATHYANARAYANA, J.J.

2002-09-30T23:59:59.000Z

178

CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP  

SciTech Connect

With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5, Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified i

Kessler, S

2009-04-21T23:59:59.000Z

179

Structural Basis of Cell Wall Cleavage by a Staphylococcal  

E-Print Network (OSTI)

The major autolysins (Atl) of Staphylococcus epidermidis and S. aureus play an important role in cell separation, and their mutants are also attenuated in virulence. Therefore, autolysins represent a promising target for the development of new types of antibiotics. Here, we report the high-resolution structure of the catalytically active amidase domain AmiE (amidase S. epidermidis) from the major autolysin of S. epidermidis. This is the first protein structure with an amidase-like fold from a bacterium with a gram-positive cell wall architecture. AmiE adopts a globular fold, with several a-helices surrounding a central b-sheet. Sequence comparison reveals a cluster of conserved amino acids that define a putative binding site with a buried zinc ion. Mutations of key residues in the putative active site result in loss of activity, enabling us to propose a catalytic mechanism. We also identified and synthesized muramyltripeptide, the minimal peptidoglycan fragment that can be used as a substrate by the enzyme. Molecular docking and digestion assays with muramyltripeptide derivatives allow us to identify key determinants of ligand binding. This results in a plausible model of interaction of this ligand not only for AmiE, but also for other PGN-hydrolases that share the same fold. As AmiE active-site mutations also show a severe growth defect, our findings provide an excellent platform for the design of specific inhibitors that target staphylococcal cell

Sebastian Zoll; Bernhard Ptzold; Martin Schlag; Friedrich Gtz; Hubert Kalbacher

2010-01-01T23:59:59.000Z

180

Surveillance Guide - NSS 18.3 Verification of Authorization Basis Documentation  

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

VERIFICATION OF AUTHORIZATION BASIS DOCUMENTATION VERIFICATION OF AUTHORIZATION BASIS DOCUMENTATION 1.0 Objective The objective of this surveillance is for the Facility Representative to verify that the facility's configuration and operations remain consistent with the authorization basis. As defined in DOE Notice 411.1-1B, the authorization basis consists of those aspects of the facility design basis and operational requirements relied upon by DOE to authorize operation. These aspects are considered to be important to the safety of the facility operations. The authorization basis is described in documents such as the facility safety analysis report and other documented safety analyses; hazard classification documents, and the Technical Safety Requirements, DOE- issued safety evaluation reports, and facility-specific commitments made in

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181

Establishing the Technical Basis for Disposal of Heat-generating Waste in  

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

Establishing the Technical Basis for Disposal of Heat-generating Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis. Though the basis for a salt safety case is strong and has been made by the German repository program, RD&D programs continue in order to help reduce uncertainty, to improve understanding of certain complex processes, to demonstrate operational concepts, to confirm performance expectations, and to improve modeling capabilities utilizing the latest software platforms.

182

The Molecular Basis for Metabolic and Energetic Diversity  

DOE Green Energy (OSTI)

We have used experimental and computational analysis of R. sphaeroides photosynthesis and other gene expression networks (Kaplan, Gomelsky, Donohue) (3-9, 12, 13, 15-18, 20). We have identified many new candidate photosynthesis genes with expression patterns that varied as a function of light intensity. Results from these experiments suggest there are many more light-regulated aspects of the photosynthetic lifestyle of this bacterium than previously appreciated. Ongoing genetic analysis confirms that mutations in some of these newly-identified photosynthesis block the ability of cells to use solar energy in the laboratory. We also carried out transcriptome and computational analysis of individual R. sphaeroides regulons. This identified additional genes that are directly regulated by individual transcription factors and refined the consensus sequence for master regulators of photosystem development. We also showed that PpsR indirectly regulates genes that do not contain the PpsR-binding sites, e.g. puf and puhA operons. This suggests that PpsR plays a more global role as a regulator of photosystem development than what was assumed before. A similar computational and microarray analysis of PrrA target genes has identified many new candidate promoters that are controlled by this master regulator of photosynthesis. We have begun bioinformatic, genetic and biochemical experiments aimed at elucidating the interactions of transcriptional pathways controlling photosystem development (PrrBA and AppA-PpsR). We carried out computational analysis designed to cluster oxygen-dependent genes in R. sphaeroides based on the transcriptome data for cells grown between 30% and 0% oxygen. As a result, new statistical tools for clustering expression profiles from DNA microarrays have been developed. We have analyzed the assembly, bioenergetic role and regulatory functions of the aerobic respiratory chain (Donohue, Edwards, Hosler, Kaplan)(10, 11, 14)(Hiser, 2000-4612). We have used computational, genetic and biochemical approaches to map the flow of electrons through the major bioenergetic pathways of this bacterium. From this, we have formulated and tested predictions for the major and minor routes of electron transport to the 5 predicted terminal oxidases; these are now being tested by genetic and physiological experiments. We have demonstrated a direct role for the R. sphaeroides cyt cbb{sub 3} terminal oxidase of the aerobic respiratory chain in controlling the activity of a master energy homeostasis pathway, PrrBA. This presents an opportunity for analyzing the ability of a cytochrome oxidase to act as a direct modulator of a second bioenergetic machine like the photosynthetic apparatus. Given the important bioenergetic and regulatory role of the aerobic respiratory chain, we have analyzed assembly of this machine. One of these proteins, Cox11p is a copper protein that plays a critical, yet poorly-understood, role cytochrome oxidase assembly in many bacteria and organelles. We have (for the first time) succeeded in expressing the soluble domain of Cox11p as a fusion protein with thioredoxin in E. coli and shown that the protein binds copper. This and a series of mutant Cox11p proteins are being used to analyze the role of copper in this protein and determine the role of Cox11p homologs in assembly of Cu-dependent bioenergetic machines. In collaboration with GTL researchers at Pacific Northwest National Laboratory, we analyzed and localized the R. sphaeroides proteome (Kaplan, Donohue, Smith)(1, 2, 19). We have determined the entire proteome of cells grown under different energy states and localizes what fraction of the proteome is contained in the major subcellular fractions of the cell, including the photosynthetic apparatus. This has identified many new and unknown proteins within this specialized solar energy harvesting machine that we would like to analyze with future DOE support.

Timothy Donohue, PI

2007-03-19T23:59:59.000Z

183

Gel'fand-Zetlin Basis and Clebsch-Gordan Coefficients for Covariant Representations of the Lie superalgebra gl(m|n)  

E-Print Network (OSTI)

A Gel'fand-Zetlin basis is introduced for the irreducible covariant tensor representations of the Lie superalgebra gl(m|n). Explicit expressions for the generators of the Lie superalgebra acting on this basis are determined. Furthermore, Clebsch-Gordan coefficients corresponding to the tensor product of any covariant tensor representation of gl(m|n) with the natural representation V ([1,0,...,0]) of gl(m|n) with highest weight (1,0,. . . ,0) are computed. Both results are steps for the explicit construction of the parastatistics Fock space.

N. I. Stoilova; J. Van der Jeugt

2010-04-14T23:59:59.000Z

184

A Report to the Secretary of Energy, Beyond Design Basis Event...  

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

Basis Event Pilot Evaluations Results and Recommendations for Improvements to Enhance Nuclear Safety at Department of Energy Nuclear Facilities Office of Nuclear Safety Office...

185

Guideline for the Treatment of Uncertainty in Risk-Informed Applications: Technical Basis Document  

Science Conference Proceedings (OSTI)

This report provides the technical basis for a process to characterize the uncertainty distribution for risk metrics derived from probabilistic risk assessments (PRAs).

2004-12-21T23:59:59.000Z

186

Structural Basis for NADH/NAD+ Redox Sensing by a Rex Family Repressor  

SciTech Connect

Nicotinamide adenine dinucleotides have emerged as key signals of the cellular redox state. Yet the structural basis for allosteric gene regulation by the ratio of reduced NADH to oxidized NAD{sup +} is poorly understood. A key sensor among Gram-positive bacteria, Rex represses alternative respiratory gene expression until a limited oxygen supply elevates the intracellular NADH:NAD{sup +} ratio. Here we investigate the molecular mechanism for NADH/NAD{sup +} sensing among Rex family members by determining structures of Thermus aquaticus Rex bound to (1) NAD{sup +}, (2) DNA operator, and (3) without ligand. Comparison with the Rex/NADH complex reveals that NADH releases Rex from the DNA site following a 40{sup o} closure between the dimeric subunits. Complementary site-directed mutagenesis experiments implicate highly conserved residues in NAD-responsive DNA-binding activity. These rare views of a redox sensor in action establish a means for slight differences in the nicotinamide charge, pucker, and orientation to signal the redox state of the cell.

McLaughlin, K.J.; Soares, A.; Strain-Damerell, C. M.; Xie, K.; Brekasis, D.; Pagent, M. S. B.; Kielkopf, C. L.

2010-05-28T23:59:59.000Z

187

Accurate correlation consistent basis sets for molecular core-valence correlation effects: The second row atoms Al-Ar and the first row atoms B-Ne revisited  

Science Conference Proceedings (OSTI)

Correlation consistent basis sets for accurately describing core-core and core-valence correlation effects in atoms and molecules have been developed for the second row atoms Al - Ar. Two different optimization strategies were investigated, which led to two families of core-valence basis sets when the optimized functions were added to the standard correlation consistent basis sets (cc-pVnZ). In the first case, the exponents of the augmenting primitive Gaussian functions were optimized with respect to the difference between all-electron and valence-electron correlated calculations, i.e., for the core-core plus core-valence correlation energy. This yielded the cc-pCVnZ family of basis sets, which are analogous to the sets developed previously for the first row atoms[D.E. Woon and T.H. Dunning, Jr., J. Chem. Phys. 103, 4572 (1995)]. Although the cc-pCVnZ sets exhibit systematic convergence to the all-electron correlation energy at the complete basis set limit, the intershell (core-valence ) correlation energy converges more slowly than the intrashell (core-core) correlation energy. Since the effect of including the core electrons on the calculation of molecular properties tends to be dominated by core-valence correlation effects, a second scheme for determining the augmenting functions was investigated. In this approach, the exponents of the functions to be added to the cc-pVnZ sets were optimized with respect to just the core-valence (intershell) correlation energy, except that a small amount of core-core correlation energy was included in order to ensure systematic convergence to the complete basis set limit. These new sets, denoted weighted core-valence basis sets (cc-pwCVnZ), significantly improve the convergence of many molecular properties with n. Optimum cc-pwCVnZ sets for the first-row atoms were also developed and show similar advantages.

Peterson, Kirk A. (WASHINGTON STATE UNIV TC); Dunning, Thom H. (BATTELLE (PACIFIC NW LAB))

2002-12-15T23:59:59.000Z

188

Fully complex-valued radial basis function networks: Orthogonal least squares regression and classification  

Science Conference Proceedings (OSTI)

We consider a fully complex-valued radial basis function (RBF) network for regression and classification applications. For regression problems, the locally regularised orthogonal least squares (LROLS) algorithm aided with the D-optimality experimental ... Keywords: Classification, Complex-valued radial basis function network, D-optimality experimental design, Fisher ratio of class separability measure, Orthogonal least squares algorithm, Regression

S. Chen; X. Hong; C. J. Harris; L. Hanzo

2008-10-01T23:59:59.000Z

189

Independent Oversight Review of the Idaho National Laboratory Fuel Conditioning Facility Safety Basis  

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

INDEPENDENT OVERSIGHT INDEPENDENT OVERSIGHT REVIEW OF THE IDAHO NATIONAL LABORATORY FUEL CONDITIONING FACILITY SAFETY BASIS April 2010 U.S. Department of Energy Office of Health, Safety and Security Office of Independent Oversight i INDEPENDENT OVERSIGHT REVIEW OF THE IDAHO NATIONAL LABORATORY FUEL CONDITIONING FACILITY SAFETY BASIS Table of Contents Acronyms ............................................................................................................................ ii Executive Summary ........................................................................................................... iii 1.0 Introduction ..................................................................................................................1

190

Multiscale finite element methods for high-contrast problems using local spectral basis functions  

Science Conference Proceedings (OSTI)

In this paper we study multiscale finite element methods (MsFEMs) using spectral multiscale basis functions that are designed for high-contrast problems. Multiscale basis functions are constructed using eigenvectors of a carefully selected local spectral ... Keywords: High contrast, Multiscale finite element, Porous media, Spectral

Yalchin Efendiev; Juan Galvis; Xiao-Hui Wu

2011-02-01T23:59:59.000Z

191

Fusion Engineering and Design 80 (2006) 2562 Physics basis for the advanced tokamak fusion  

E-Print Network (OSTI)

2005 Abstract The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power.V. All rights reserved. Keywords: Reactor studies; Fusion power plant; Advanced tokamak; Physics basis 1

192

A generalization of the Wiener rational basis functions on infinite intervals, Part II - Numerical investigation  

Science Conference Proceedings (OSTI)

In Part I we introduced the generalized Wiener rational basis functions, and here in Part II we continue our investigation with numerical experiments. Wiener's generalized basis can utilize the fast Fourier transform for integer values of the decay parameter ... Keywords: Fast Fourier transform, Infinite intervals, Spectral methods

Akil C. Narayan; Jan S. Hesthaven

2013-01-01T23:59:59.000Z

193

A forecasting system for car fuel consumption using a radial basis function neural network  

Science Conference Proceedings (OSTI)

A predictive system for car fuel consumption using a radial basis function (RBF) neural network is proposed in this paper. The proposed work consists of three parts: information acquisition, fuel consumption forecasting algorithm and performance evaluation. ... Keywords: Artificial neural network, Car fuel consumption, Radial basis function algorithm

Jian-Da Wu; Jun-Ching Liu

2012-02-01T23:59:59.000Z

194

Parallel algorithms for identifying convex and non-convex basis polygons in an image  

Science Conference Proceedings (OSTI)

In this paper, we propose two novel parallel algorithms for identifying all the basis polygons in an image formed by n straight line segments each of which is represented by its two end points. The first algorithm is designed to tackle the simple situation ... Keywords: Basis polygon, Edge traversal, Parallel algorithm

Arijit Laha; Amitava Sen; Bhabani P. Sinha

2005-03-01T23:59:59.000Z

195

To see the property of , we take a basis set of energy eigenstates  

E-Print Network (OSTI)

MECHANISM To see the property of , we take a basis set of energy eigenstates (although we never employ such a basis in practical calculations) #12;Energy per site u Increases exponentially density of states MECHANISM Energy distribution of Energy distribution of becomes #12;Energy per site u ( ) #12

Shimizu, Akira

196

An application of radial basis function networks in operation of home appliances  

Science Conference Proceedings (OSTI)

Neural networks (NN) have made a great impact in modeling and synthesizing non-linear mapping of input-output space. In this paper, we describe the design and testing of a particular class of NN, radial basis function networks, for dryness prediction ... Keywords: appliance engineering, dryness prediction, radial basis function networks

Yu-To Chen

2000-12-01T23:59:59.000Z

197

An 'optimal' spawning algorithm for adaptive basis set expansion in nonadiabatic dynamics  

Science Conference Proceedings (OSTI)

The full multiple spawning (FMS) method has been developed to simulate quantum dynamics in the multistate electronic problem. In FMS, the nuclear wave function is represented in a basis of coupled, frozen Gaussians, and a 'spawning' procedure prescribes a means of adaptively increasing the size of this basis in order to capture population transfer between electronic states. Herein we detail a new algorithm for specifying the initial conditions of newly spawned basis functions that minimizes the number of spawned basis functions needed for convergence. 'Optimally' spawned basis functions are placed to maximize the coupling between parent and child trajectories at the point of spawning. The method is tested with a two-state, one-mode avoided crossing model and a two-state, two-mode conical intersection model.

Yang, Sandy; Coe, Joshua D.; Kaduk, Benjamin; Martinez, Todd J. [Department of Chemistry and Beckman Institute, University of Illinois at Urbana-Champaign, 600 S. Mathews Ave., Urbana, Illinois 61801 (United States)

2009-04-07T23:59:59.000Z

198

SPECIAL REREVIEW FINAL DETERMINATION UNCLASSIFIED  

Office of Legacy Management (LM)

SPECIAL REREVIEW SPECIAL REREVIEW FINAL DETERMINATION UNCLASSIFIED , ?4~0180N SctuAnr P. 0. 00x *a STATION F New YORK, N. Y. IN RLPLY RCFSRTO EID?f A- 43 MS ~-7405 eng-8 ". Subject: Contract No.H-7405 eng-8 with Metal Hydrides Incorporated. MEMORAhDUM to the Files. 1. Reference is made to basi.c communication dated 27 September 1945, Symbol No. EIDM 1%-30-b, requesting certain information with respect to the subject contract. 2. Reference pars,?-raph a. The Government committed to restore Contractor's plant 70 its original conditfon because of the fact that In furtherance of the Government work great expansion of facility ?.natallation in the Con- tractor's plant was required and the Contractor was un- W illing, in the event of termination or early cessation of

199

Data:4e494399-0515-4efe-a9c1-626930d4b98e | Open Energy Information  

Open Energy Info (EERE)

of the Company. Fixed Monthly Charge Includes Renewable Energy Surcharge The Company's Net Metering Program is available on a first come, first served basis until the nameplate...

200

Safety basis academy summary of project implementation from 2007-2009  

Science Conference Proceedings (OSTI)

During fiscal years 2007 through 2009, in accordance with Performance Based Incentives with DOE/NNSA Los Alamos Site Office, Los Alamos National Security (LANS) implemented and operated a Safety Basis Academy (SBA) to facilitate uniformity in technical qualifications of safety basis professionals across the nuclear weapons complex. The implementation phase of the Safety Basis Academy required development, delivery, and finalizing a set of 23 courses. The courses developed are capable of supporting qualification efforts for both federal and contractor personnel throughout the DOE/NNSA Complex. The LANS Associate Director for Nuclear and High Hazard Operations (AD-NHHO) delegated project responsibillity to the Safety Basis Division. The project was assigned to the Safety Basis Technical Services (SB-TS) Group at Los Alamos National Laboratory (LANL). The main tasks were project needs analysis, design, development, implementation of instructional delivery, and evaluation of SBA courses. DOE/NNSA responsibility for oversight of the SBA project was assigned to the Chief of Defense for Nuclear Safety, and delegated to the Authorization Basis Senior Advisor, Continuous Learning Chair (CDNS-ABSA/CLC). NNSA developed a memorandum of agreement with LANS AD-NHHO. Through a memorandum of agreement initiated by NNSA, the DOE National Training Center (NTC) will maintain the set of Safety Basis Academy courses and is able to facilitate course delivery throughout the DOE Complex.

Johnston, Julie A [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

CRAD, Review of Safety Basis Development - January 31, 2013 | Department of  

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

January 31, 2013 January 31, 2013 CRAD, Review of Safety Basis Development - January 31, 2013 January 31, 2013 Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility - Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 45-57, Rev. 0) The review will consider selected aspects of the development of safety basis for the Salt Waste Processing Facility (SWPF) to assess the extent to which safety is integrated into the design of the SWPF in accordance with DOE directives; in particular, DOE Order 420.1 B, DOE-STD-1189, and DOE-STD3009. The review will focus on a few selected safety systems, such as the Process Vessel Ventilation System (PVVS) and the Air Dilution System (ADS), and associated supporting/interfacing systems. CRAD, Review of Safety Basis Development - January 31, 2013

202

Order Module--NNSA Orders Self-Study Program Safety Basis Documentation |  

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

NNSA Orders Self-Study Program Safety Basis NNSA Orders Self-Study Program Safety Basis Documentation Order Module--NNSA Orders Self-Study Program Safety Basis Documentation The familiar level of this module is divided into five sections. In the first section, we will discuss the regulation. In the second, third, and fourth sections, we will discuss the U. Department of Energy (DOE) guides for documented safety analyses (DSAs), technical safety requirements (TSRs), and unreviewed safety questions (USQs). Section 5 discusses the DOE standard related to DSAs and TSRs. We have provided several examples and practices throughout the module to help familiarize you with the material. The practices will also help prepare you for the criterion test. DOE Order Self Study Modules - 10 CFR 830 Safety Basis Documentation

203

A Report to the Secretary of Energy, Beyond Design Basis Event Pilot Evaluations  

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

Beyond Design Basis Event Beyond Design Basis Event Pilot Evaluations Results and Recommendations for Improvements to Enhance Nuclear Safety at Department of Energy Nuclear Facilities Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy January 2013 Beyond Design Basis Event Pilot Evaluations TABLE OF CONTENTS Executive Summary i Acronyms iv 1.0 Introduction and Purpose 1 2.0 Background 2 3.0 Pilot Evaluations of Safety Analysis, NPH, and Emergency Management Guidance 2 4.0 Insights Gained from NRC and the Nuclear Community 11 5.0 Summary of Results and Recommendations 12 6.0 Conclusions 14 Appendix A - Pilot Evaluation Team Members 15 Beyond Design Basis Event Pilot Evaluations * i

204

DOE M&O Contractor Perspectives on Beyond Design Basis Event Analysis and  

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

DOE M&O Contractor Perspectives on Beyond Design Basis Event DOE M&O Contractor Perspectives on Beyond Design Basis Event Analysis and Response DOE M&O Contractor Perspectives on Beyond Design Basis Event Analysis and Response September 20, 2013 Presenter: Ron Crone, Director Research Reactors Division UT-Battelle, LLC Oak Ridge National Laboratory HFIR serves a broad range of science and technology communities and will need to operate to at least 2040 until replacement capabiltiies are available DOE M&O Contractor Perspectives on Beyond Design Basis Event Analysis and Response More Documents & Publications Independent Oversight Review, Oak Ridge National Laboratory - January 2013 Preliminary Notice of Violation, Lockheed Martin Energy Research Corporation - EA-98-13 EIS-0373: Draft Environmental Impact Statement, Summary

205

DOE Order Self Study Modules - 10 CFR 830 Safety Basis Documentation  

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

Orders Orders Self-Study Program Safety Basis Documentation 10 CFR 830, NUCLEAR SAFETY MANAGEMENT DOE G 421.1-2, IMPLEMENTATION GUIDE FOR USE IN DEVELOPING DOCUMENTED SAFETY ANALYSES TO MEET SUBPART B OF 10 CFR 830 DOE G 423.1.1, IMPLEMENTATION GUIDE FOR USE IN DEVELOPING TECHNICAL SAFETY REQUIREMENTS DOE G 424.1-1, IMPLEMENTATION GUIDE FOR USE IN ADDRESSING UNREVIEWED SAFETY QUESTION REQUIREMENTS DOE-STD-1104-96, REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS DOCUMENTS (DOCUMENTED SAFETY ANALYSES AND TECHNICAL SAFETY REQUIREMENTS) NNSA SERVICE CENTER Change No: 0 Safety Basis Documents Level: Familiar Date: 10/15/03 1 SAFETY BASIS DOCUMENTS FAMILIAR LEVEL OBJECTIVES Given the familiar level of this module and the resources listed below, you will be able to:

206

2010 DOE National Science Bowl® Photos - Basis Charter School | U.S. DOE  

Office of Science (SC) Website

Basis Charter School Basis Charter School National Science Bowl® (NSB) NSB Home About National Science Bowl Contacts Regional Science Bowl Coordinators National Science Bowl FAQ's Alumni Past National Science Bowl Winners Past National Science Bowl Photos National Science Bowl Logos High School Middle School Attending National Event Volunteers 2013 Competition Results News Media WDTS Home Contact Information National Science Bowl® U.S. Department of Energy SC-27/ Forrestal Building 1000 Independence Ave., SW Washington, DC 20585 P: 202-586-6702 E: National.Science.Bowl@science.doe.gov 2010 National Science Bowl Photos 2010 DOE National Science Bowl® Photos - Basis Charter School Print Text Size: A A A RSS Feeds FeedbackShare Page The BASIS Charter School Science Bowl team from Scottsdale, AZ explores the

207

Nuclear Maintenance Applications Center: The Physical Basis of Abnormal Seal Leakoff Mitigation  

Science Conference Proceedings (OSTI)

This technical update provides insights into the physical basis for the effectiveness of actions taken to address Westinghouse #1 seal leakoff anomalies (that is, when #1 seal leakoff exceeds manufacturer's maximum value or is less than manufacturer's minimum value).

2012-08-16T23:59:59.000Z

208

A priori convergence of the Greedy algorithm for the parametrized reduced basis method  

E-Print Network (OSTI)

The convergence and efficiency of the reduced basis method used for the approximation of the solutions to a class of problems written as a parametrized PDE depends heavily on the choice of the elements that constitute the ...

Buffa, Annalisa

209

Basis for Interim Operation for the K-Reactor in Cold Standby  

SciTech Connect

The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993).

Shedrow, B.

1998-10-19T23:59:59.000Z

210

Optimizing radial basis functions by DC programming and its use in ...  

E-Print Network (OSTI)

Oct 12, 2009 ... Optimizing radial basis functions by D.C. programming and its use in direct search for global derivative-free optimization. An Le Thi Hoai(lethi...

211

On a euro basis, Brent crude oil spot price surpasses prior ...  

U.S. Energy Information Administration (EIA)

On a euro basis, the spot price for Brent crude oil, a global benchmark, has surpassed its prior record high and set a new record high of 96.53 euros per barrel on ...

212

Basis-Spline Interpolation on the Sphere: Applications to Semi-Lagrangian Advection  

Science Conference Proceedings (OSTI)

An algorithm for the interpolation of data on a colatitudelongitude grid is presented. The method employs periodic tensor product cubic basis splines (B splines) and requires no special assumptions about function derivatives at the poles. The ...

P. A. Makar; S. R. Karpik

1996-01-01T23:59:59.000Z

213

Reduced-basis output bound methods for parametrized partial differential equations  

E-Print Network (OSTI)

An efficient and reliable method for the prediction of outputs of interest of partial differential equations with affine parameter dependence is presented. To achieve efficiency we employ the reduced-basis method: a weighted ...

Rovas, Dimitrios V. (Dimitrios Vasileios), 1975-

2003-01-01T23:59:59.000Z

214

The parabolic Sturmian-function basis representation of the six-dimensional Coulomb Green's function  

E-Print Network (OSTI)

The square integrable basis set representation of the resolvent of the asymptotic three-body Coulomb wave operator in parabolic coordinates is obtained. The resulting six-dimensional Green's function matrix is expressed as a convolution integral over separation constants.

S. A. Zaytsev

2008-06-03T23:59:59.000Z

215

Generic Letter 96-06 Waterhammer Issues Resolution: Technical Basis Report - Proprietary  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 96-06 identified potential issues for waterhammer effects during postulated events that can cause potential damage to service water systems. The User's Manual (Volume 1) provides methods recommended for evaluating the impact of potential waterhammer loads on plant service water system components. This Technical Basis Report (Volume 2) provides detailed background information and the technical basis for the methods defined in the User's Manual.

2002-04-30T23:59:59.000Z

216

Generic Letter 96-06 Waterhammer Issues Resolution: Technical Basis Report - Non Proprietary  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 96-06 identified potential issues for waterhammer effects during postulated events that can cause potential damage to service water systems. The User's Manual (Volume 1) provides methods recommended for evaluating the impact of potential waterhammer loads on plant service water system components. This Technical Basis Report (Volume 2) provides detailed background information and the technical basis for the methods defined in the User's Manual.

2002-04-30T23:59:59.000Z

217

Structural basis of error-prone replication and stalling at a thymine base by human DNA polymerase  

Science Conference Proceedings (OSTI)

Human DNA polymerase iota (pol iota) is a unique member of Y-family polymerases, which preferentially misincorporates nucleotides opposite thymines (T) and halts replication at T bases. The structural basis of the high error rates remains elusive. We present three crystal structures of pol complexed with DNA containing a thymine base, paired with correct or incorrect incoming nucleotides. A narrowed active site supports a pyrimidine to pyrimidine mismatch and excludes Watson-Crick base pairing by pol. The template thymine remains in an anti conformation irrespective of incoming nucleotides. Incoming ddATP adopts a syn conformation with reduced base stacking, whereas incorrect dGTP and dTTP maintain anti conformations with normal base stacking. Further stabilization of dGTP by H-bonding with Gln59 of the finger domain explains the preferential T to G mismatch. A template 'U-turn' is stabilized by pol and the methyl group of the thymine template, revealing the structural basis of T stalling. Our structural and domain-swapping experiments indicate that the finger domain is responsible for pol's high error rates on pyrimidines and determines the incorporation specificity.

Kirouac, Kevin N.; Ling, Hong; (UWO)

2009-06-30T23:59:59.000Z

218

On the Optimality of Basis Transformations to Secure Entanglement Swapping Based QKD Protocols  

E-Print Network (OSTI)

In this article, we discuss the optimality of basis transformations as a security measure for quantum key distribution protocols based on entanglement swapping. To estimate the security, we focus on the information an adversary obtains on the raw key bits from a generic version of a collective attack strategy. In the scenario described in this article, the application of general basis transformations serving as a counter measure by one or both legitimate parties is analyzed. In this context, we show that the angles, which describe these basis transformations can be optimized compared to the application of a Hadamard operation, which is the standard basis transformation recurrently found in literature. As a main result, we show that the adversary's information can be reduced to an amount of approximately 0.20752 when using a single basis transformation and to an amount of approximately 0.0548 when combining two different basis transformations. This is less than half the information compared to other protocols using a Hadamard operation and thus represents an advantage regarding the security of entanglement swapping based protocols.

Stefan Schauer; Martin Suda

2013-07-22T23:59:59.000Z

219

Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management  

SciTech Connect

The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk as a function of different configurations in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.

Curtis Smith; James Knudsen; Bentley Harwood

2013-08-01T23:59:59.000Z

220

TECHNICAL BASIS FOR EVALUATING SURFACE BARRIERS TO PROTECT GROUNDWATER FROM DEEP VADOSE ZONE CONTAMINATION  

Science Conference Proceedings (OSTI)

The U.S. DOE and its predecessors released nearly 2 trillion liters (450 billion gallons) of contaminated liquid into the vadose zone at the Hanford Site. Some of the contaminants currently reside in the deeper parts of the vadose zone where they are much less accessible to characterization, monitoring, and typical remediation activities. The DOE Richland Operations Office (DOE-RL) prepared a treatability test plan in 2008 to examine remediation options for addressing contaminants in the deep vadose zone; one of the technologies identified was surface barriers (also known as engineered barriers, covers, and caps). In the typical configuration, the contaminants are located relatively close to the surface, generally within 15 m, and thus they are close to the base of the surface barrier. The proximity of the surface barrier under these conditions yielded few concerns about the effectiveness of the barrier at depth, particularly for cases in which the contaminants were in a lined facility. At Hanford, however, some unlined sites have contaminants located well below depths of 15 m. The issue raised about these sites is the degree of effectiveness of a surface barrier in isolating contaminants in the deep vadose zone. Previous studies by Hanford Site and PNNL researchers suggest that surface barriers have the potential to provide a significant degree of isolation of deep vadose zone contaminants. The studies show that the actual degree of isolation is site-specific and depends on many factors, including recharge rates, barrier size, depth of contaminants, geohydrologic properties ofthe sediments, and the geochemical interactions between the contaminants and the sediments. After the DOE-RL treatability test plan was published, Pacific Northwest National Laboratory was contracted to review the information available to support surface barrier evaluation for the deep vadose zone, identify gaps in the information and outcomes necessary to fill the data gaps, and outline tasks to achieve those outcomes. Full understanding of contaminant behavior in the deep vadose zone is constrained by four key data gaps: limited access; limited data; limited time; and the lack of an accepted predictive capability for determining whether surface barriers can effectively isolate deep vadose zone contaminants. Activities designed to fill these data gaps need to have these outcomes: (1) common evaluation methodology that provides a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination; (2) deep vadose zone data that characterize the lithology, the spatial distribution of moisture and contaminants, the physical, chemical, and biological process that affect the mobility of each contaminant, and the impacts to the contaminants following placement of a surface barrier; (3) subsurface monitoring to provide subsurface characterization of initial conditions and changes that occur during and following remediation activities; and (4) field observations that span years to decades to validate the evaluation methodology. A set of six proposed tasks was identified to provide information needed to address the above outcomes. The proposed tasks are: (1) Evaluation Methodology - Develop common evaluation methodology that will provide a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination. (2) Case Studies - Conduct case studies to demonstrate the applicability ofthe common evaluation methodology and provide templates for subsequent use elsewhere. Three sites expected to have conditions that would yield valuable information and experience pertinent to deep vadose zone contamination were chosen to cover a range of conditions. The sites are BC Cribs and Trenches, U Plant Cribs, and the T Farm Interim Cover. (3) Subsurface Monitoring Technologies - Evaluate minimally invasive geophysical approaches for delineating subsurface plumes and monitoring their migration in the deep

FAYER JM; FREEDMAN VL; WARD AL; CHRONISTER GB

2010-02-24T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

TECHNICAL BASIS FOR EVALUATING SURFACE BARRIERS TO PROTECT GROUNDWATER FROM DEEP VADOSE ZONE CONTAMINATION  

SciTech Connect

The U.S. DOE and its predecessors released nearly 2 trillion liters (450 billion gallons) of contaminated liquid into the vadose zone at the Hanford Site. Some of the contaminants currently reside in the deeper parts of the vadose zone where they are much less accessible to characterization, monitoring, and typical remediation activities. The DOE Richland Operations Office (DOE-RL) prepared a treatability test plan in 2008 to examine remediation options for addressing contaminants in the deep vadose zone; one of the technologies identified was surface barriers (also known as engineered barriers, covers, and caps). In the typical configuration, the contaminants are located relatively close to the surface, generally within 15 m, and thus they are close to the base of the surface barrier. The proximity of the surface barrier under these conditions yielded few concerns about the effectiveness of the barrier at depth, particularly for cases in which the contaminants were in a lined facility. At Hanford, however, some unlined sites have contaminants located well below depths of 15 m. The issue raised about these sites is the degree of effectiveness of a surface barrier in isolating contaminants in the deep vadose zone. Previous studies by Hanford Site and PNNL researchers suggest that surface barriers have the potential to provide a significant degree of isolation of deep vadose zone contaminants. The studies show that the actual degree of isolation is site-specific and depends on many factors, including recharge rates, barrier size, depth of contaminants, geohydrologic properties ofthe sediments, and the geochemical interactions between the contaminants and the sediments. After the DOE-RL treatability test plan was published, Pacific Northwest National Laboratory was contracted to review the information available to support surface barrier evaluation for the deep vadose zone, identify gaps in the information and outcomes necessary to fill the data gaps, and outline tasks to achieve those outcomes. Full understanding of contaminant behavior in the deep vadose zone is constrained by four key data gaps: limited access; limited data; limited time; and the lack of an accepted predictive capability for determining whether surface barriers can effectively isolate deep vadose zone contaminants. Activities designed to fill these data gaps need to have these outcomes: (1) common evaluation methodology that provides a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination; (2) deep vadose zone data that characterize the lithology, the spatial distribution of moisture and contaminants, the physical, chemical, and biological process that affect the mobility of each contaminant, and the impacts to the contaminants following placement of a surface barrier; (3) subsurface monitoring to provide subsurface characterization of initial conditions and changes that occur during and following remediation activities; and (4) field observations that span years to decades to validate the evaluation methodology. A set of six proposed tasks was identified to provide information needed to address the above outcomes. The proposed tasks are: (1) Evaluation Methodology - Develop common evaluation methodology that will provide a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination. (2) Case Studies - Conduct case studies to demonstrate the applicability ofthe common evaluation methodology and provide templates for subsequent use elsewhere. Three sites expected to have conditions that would yield valuable information and experience pertinent to deep vadose zone contamination were chosen to cover a range of conditions. The sites are BC Cribs and Trenches, U Plant Cribs, and the T Farm Interim Cover. (3) Subsurface Monitoring Technologies - Evaluate minimally invasive geophysical approaches for delineating subsurface plumes and monitoring their migration in the deep

FAYER JM; FREEDMAN VL; WARD AL; CHRONISTER GB

2010-02-24T23:59:59.000Z

222

Determination of the Shortwave Anisotropic Function for Clear-Sky Desert Scenes from Meteosat Data  

Science Conference Proceedings (OSTI)

Determination of planetary albedo on the basis of satellite observations of reflected shortwave (SW) radiances requires taking into account the anisotropic (non-Lambertian) reflectance properties of the earth?atmosphere system, depending both on ...

Michel Capderou; Robert Kandel

1995-06-01T23:59:59.000Z

223

Convergent Partially Augmented Basis Sets for Post-Hartree-Fock Calculations of Molecular Properties and Reaction Barrier Heights  

Science Conference Proceedings (OSTI)

We present sets of convergent, partially augmented basis set levels corresponding to subsets of the augmented aug-cc-pV(n+d)Z basis sets of Dunning and co-workers. We show that for many molecular properties a basis set fully augmented with diffuse functions is computationally expensive and almost always unnecessary. On the other hand, unaugmented cc-pV(n+d)Z basis sets are insufficient for many properties that require diffuse functions. Therefore, we propose using intermediate basis sets. We developed an efficient strategy for partial augmentation, and in this article, we test it and validate it. Sequentially deleting diffuse basis functions from the aug basis sets yields the jul, jun, may, apr, etc. basis sets. Tests of these basis sets for Mller-Plesset second-order perturbation theory (MP2) show the advantages of using these partially augmented basis sets and allow us to recommend which basis sets offer the best accuracy for a given number of basis functions for calculations on large systems. Similar truncations in the diffuse space can be performed for the aug-cc-pVxZ, aug-cc-pCVxZ, etc. basis sets.

Papajak, Ewa; Truhlar, Donald G.

2011-01-11T23:59:59.000Z

224

Energy absorption by laser fusion targets determined by ion calorimetry  

SciTech Connect

The absorbed energy determined by the ion calorimeters was used as a basis for computations of the target behavior. Both neutron yield and x-ray spectra thus obtained were in agreement with the measured values within the precision of both calculations and experiments. Some results are described. (MOW)

Rupert, V.C.; Gunn, S.R.; Holzrichter, J.F.

1976-10-01T23:59:59.000Z

225

Basis Functions for Estimating Intravoxel Structure Alonso Ramirez-Manzanares, Mariano Rivera, Baba C. Vemuri and Thomas Mareci  

E-Print Network (OSTI)

Basis Functions for Estimating Intra­voxel Structure in DW­MRI Alonso Ram´irez-Manzanares, Mariano

Rivera, Mariano

226

Basis for Identification of Disposal Options for R and D for Spent Nuclear  

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

Basis for Identification of Disposal Options for R and D for Spent Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered barrier, and the waste. Salt, clay/shale, and granitic rocks represent a reasonable cross-section of behavior. Granitic rocks are also the primary basement rock to consider for deep borehole disposal. UFD is developing generic system analysis capability and general experimental data related to mined geologic disposal in the three

227

Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis |  

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

Bulletin 2011-01, Events Beyond Design Safety Basis Analysis Bulletin 2011-01, Events Beyond Design Safety Basis Analysis Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and the subsequent tsunami. While there is still a lot to be learned from the accident · about the adequacy of design specifications and the equipment failure modes, reports from the Nuclear Regulatory Commission (NRC) have identified some key aspects of the operational emergency at the Fukushima Daiichi nuclear power station.

228

Operating Experience Level 1 - Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events  

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

OE-1: 2013-01 April 2013 OE-1: 2013-01 April 2013 Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events PURPOSE: The purpose of this Operating Experience (OE) document is to (1) provide results from U.S. Department of Energy (DOE), including the National Nuclear Security Administration , initiatives related to beyond design basis events (BDBEs) , and (2) provide direction for enhancing capabilities for mitigating BDBEs at DOE sites . BACKGROUND: After the March 2011 Fukushima Daiich i nuclear plant accident in Japan , DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to BDBEs. These initiatives included issuing Safety Bulletin 2011-01 , Events Beyond Design Safety Basis Analysis, conducting pilots to refine possible

229

CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project |  

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

TRU ALPHA LLWT TRU ALPHA LLWT Project CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a November 2003 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project More Documents & Publications CRAD, Conduct of Operations - Oak Ridge National Laboratory TRU ALPHA LLWT

230

Report to the Secretary of Energy on Beyond Design Basis Event Pilot  

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

Facilities, January 2013 Facilities, January 2013 Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities, January 2013 In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made. These actions and recommendations were addressed in an August 2011 report to the Secretary of Energy, Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events. BDBE_Report_final.pdf More Documents & Publications Report to the Secretary of Energy on Beyond Design Basis Event Pilot

231

Technical basis and evaluation criteria for an air sampling/monitoring program  

Science Conference Proceedings (OSTI)

Air sampling and monitoring programs at DOE facilities need to be reviewed in light of revised requirements and guidance found in, for example, DOE Order 5480.6 (RadCon Manual). Accordingly, the Oak Ridge National Laboratory (ORNL) air monitoring program is being revised and placed on a sound technical basis. A draft technical basis document has been written to establish placement criteria for instruments and to guide the ``retrospective sampling or real-time monitoring`` decision. Facility evaluations are being used to document air sampling/monitoring needs, and instruments are being evaluated in light of these needs. The steps used to develop this program and the technical basis for instrument placement are described.

Gregory, D.C.; Bryan, W.L.; Falter, K.G.

1993-06-01T23:59:59.000Z

232

A New Multilevel Method for Electrostatic Problems through Hierarchical Loop Basis  

E-Print Network (OSTI)

We present a new multilevel method for calculating Poisson's equation, which often arises form electrostatic problems, by using hierarchical loop bases. This method, termed hierarchical Loop basis Poisson Solver (hieLPS), extends previous Poisson solver through loop-tree basis to a multilevel mesh. In this method, Poisson's equation is solved by a two-step procedure: First, the electric flux is found by using loop-tree basis based on Helmholtz decomposition of field; Second, the potential distribution is solved rapidly with a fast solution of O(N) complexity. Among the solution procedures, finding the loop part of electric flux is the most critical part and dominates the computational effort. To expedite this part's convergent speed, we propose to use hierarchical loop bases to construct a multilevel system. As a result, the whole solution time has been noticeably reduced. Numerical examples are presented to demonstrate the efficiency of the proposed method.

Z. -H. Ma; W. C. Chew; Y. M. Wu; L. J. Jiang

2013-05-14T23:59:59.000Z

233

Report to the Secretary of Energy on Beyond Design Basis Event Pilot  

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

Facilities, January 2013 Facilities, January 2013 Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities, January 2013 In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made. These actions and recommendations were addressed in an August 2011 report to the Secretary of Energy, Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events. BDBE_Report_final.pdf More Documents & Publications Report to the Secretary of Energy on Beyond Design Basis Event Pilot

234

Safety basis for selected activities in single-shell tanks with flammable gas concerns. Revision 1  

DOE Green Energy (OSTI)

This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade.

Schlosser, R.L.

1996-02-05T23:59:59.000Z

235

A time-of-flight backscattering spectrometer at the Spallation Neutron Source, BASIS  

Science Conference Proceedings (OSTI)

We describe the design and current performance of the backscattering silicon spectrometer (BASIS), a time-of-flight backscattering spectrometer built at the spallation neutron source (SNS) of the Oak Ridge National Laboratory (ORNL). BASIS is the first silicon-based backscattering spectrometer installed at a spallation neutron source. In addition to high intensity, it offers a high-energy resolution of about 3.5 {mu}eV and a large and variable energy transfer range. These ensure an excellent overlap with the dynamic ranges accessible at other inelastic spectrometers at the SNS.

Mamontov, E.; Herwig, K. W. [Neutron Scattering Science Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

2011-08-15T23:59:59.000Z

236

Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America  

SciTech Connect

The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

2011-11-01T23:59:59.000Z

237

A genetic fuzzy radial basis function neural network for structural health monitoring of composite laminated beams  

Science Conference Proceedings (OSTI)

In this paper, a new neural network learning procedure, called genetic fuzzy hybrid learning algorithm (GFHLA) is proposed for training the radial basis function neural network (RBFNN). The method combines the genetic algorithm and fuzzy logic to optimize ... Keywords: Fuzzy logic, Genetic algorithm, RBF neural network, Structural health monitoring

Shi-jie Zheng; Zheng-qiang Li; Hong-tao Wang

2011-09-01T23:59:59.000Z

238

Basis Reduction for the Shakedown Problem for Bounded Kinematic Hardening Material  

Science Conference Proceedings (OSTI)

Limit and shakedown analysis are effective methods for assessing the load carrying capacity of a given structure. The elastoplastic behavior of the structure subjected to loads varying in a given load domain is characterized by the shakedown load ... Keywords: Basis reduction, Convex optimization, FEM, Shakedown analysis

Michael Heitzer; Gabriela Pop; Manfred Staat

2000-09-01T23:59:59.000Z

239

Reducing the Plagiarism Detection Search Space on the Basis of the Kullback-Leibler Distance  

E-Print Network (OSTI)

Reducing the Plagiarism Detection Search Space on the Basis of the Kullback-Leibler Distance, jbenedi}@dsic.upv.es http://www.dsic.upv.es/grupos/nle/ Abstract. Automatic plagiarism detection the plagiarised fragments to their potential source. Publications on this task often assume that the search space

Rosso, Paolo

240

Severe Accident Management Guidance Technical Basis Report: Volumes 1 and 2  

Science Conference Proceedings (OSTI)

Severe accident management guidance encompasses actions that would be taken to recover from a damaged core condition and to prevent or mitigate the release of fission products. This report provides the technical basis for developing such guidance by the nuclear steam supply system owners groups.

1993-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

Preliminary tank characterization report for single-shell tank 241-BY-109: best-basis inventory  

Science Conference Proceedings (OSTI)

An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-BY-109 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.

Kupfer, M.J.

1997-09-02T23:59:59.000Z

242

A PHYSICAL BASIS FOR MULTI-FIBER RECONSTRUCTION FROM DW-MRI DATA Ritwik Kumar1  

E-Print Network (OSTI)

A PHYSICAL BASIS FOR MULTI-FIBER RECONSTRUCTION FROM DW-MRI DATA Ritwik Kumar1 , Angelos Barmpoutis to model the signal attenuation obtained from Diffusion Weighted Magnetic Resonance Imaging (DW-value, gradient pulse duration, pulse separation etc.) involved in the DW-MRI acquisition pro- cess. To address

Kumar, Ritwik

243

BASIS FUNCTIONS FOR ESTIMATING INTRA-VOXEL STRUCTURE IN DW-MRI  

E-Print Network (OSTI)

BASIS FUNCTIONS FOR ESTIMATING INTRA-VOXEL STRUCTURE IN DW-MRI Alonso Ramírez-Manzanares, Mariano Functions for Estimating Intra­voxel Structure in DW­MRI Alonso Ram´irez-Manzanares, Mariano Rivera, Baba C­voxel fiber paths, using Diffusion Weighted Magnetic Resonance Images (DW-MRI). The method recovers the intra

Rivera, Mariano

244

Technical Basis Document for Internal Dosimetry at the Plutonium Finishing Plant (PFP)  

SciTech Connect

The document identifies the source term for PFP and documents the requirements providing the basis for the internal bioassay monitoring for routine work within the facility. It is also intended to identify the need for specific planning for internal dosimetry for work that does not fall within the normal radiological conditions in regard to isotopic ratios normally encountered.

MERKLING, T.D.

1999-12-29T23:59:59.000Z

245

Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan  

Science Conference Proceedings (OSTI)

This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.

HARRIS, J.P.

2000-03-27T23:59:59.000Z

246

Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan  

Science Conference Proceedings (OSTI)

This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.

HARRIS, J.P.

1999-08-31T23:59:59.000Z

247

Constant Time Sliding Window Filter SLAM as a Basis for Metric Visual Perception  

E-Print Network (OSTI)

on Robotics and Automation, pages 1099­1104, Washington, DC, 2001. [17] G. Sibley. Sliding window filters, pages 652­659, Washington, DC, 2004. [16] C. F. Olson, L. H. Matthies, M. Schoppers, and M. W. MaimoneConstant Time Sliding Window Filter SLAM as a Basis for Metric Visual Perception Gabe Sibley, Larry

Sibley, Gabe

248

Basis functions and parameter optimisation in high-order iterative learning control  

Science Conference Proceedings (OSTI)

In this paper a new parameter-optimal high-order Iterative Learning Control (ILC) algorithms is proposed to extend the work of Owens and Feng [Parameter optimisation in iterative learning control. International Journal of Control 14(11), 1059-1069]. ... Keywords: Basis functions, Iterative learning control, Parameter optimisation

J. HTNen; D. H. Owens; K. Feng

2006-02-01T23:59:59.000Z

249

Evaluation of Authorization Basis Management Systems and Processes at the Pantex Plant  

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

0 0 Evaluation of Authorization Basis Management Systems and Processes at the OVERSIGHT Table of Contents EXECUTIVE SUMMARY ................................................................... 1 1.0 INTRODUCTION ........................................................................... 4 2.0 RESULTS ......................................................................................... 6 Line Management Responsibility for Safety ................................ 6 Clear Roles, Responsibilities, and Authorities ........................... 10 Competence Commensurate with Responsibility ...................... 15 Balanced Priorities ........................................................................ 18 Identification and Flowdown of Requirements.......................... 22 Hazard Analysis and Controls

250

Draft General Conformity Determination  

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

I I Draft General Conformity Determination U.S. Department of the Interior Minerals Management Service MMS Cape Wind Energy Project January 2009 Final EIS Appendix I Draft General Conformity Determination Draft General Conformity Determination Cape Wind Energy Project Prepared by Minerals Management Service Herndon, VA November 2008 i TABLE OF CONTENTS 1.0 INTRODUCTION TO THE PROPOSED ACTION............................................................... 1 2.0 GENERAL CONFORMITY REGULATORY BACKGROUND .......................................... 2 2.1 GENERAL CONFORMITY REQUIREMENTS.................................................................... 2 2.2 GENERAL CONFORMITY APPLICABILITY.....................................................................

251

TECHNICAL BASIS FOR DOE STANDARD 3013 EQUIVALENCY SUPPORTING REDUCED TEMPERATURE STABILIZATION OF OXALATE-DERIVED PLUTONIUM DIOXIDE PRODUCED BY THE HB-LINE FACILITY AT SAVANNAH RIVER SITE  

SciTech Connect

This report documents the technical basis for determining that stabilizing highpurity PuO{sub 2} derived from oxalate precipitation at the SRS HB-Line facility at a minimum of 625 {degree}C for at least four hours in an oxidizing atmosphere is equivalent to stabilizing at a minimum of 950 {degree}C for at least two hours as regards meeting the objectives of stabilization defined by DOE-STD-3013 if the material is handled in a way to prevent excessive absorption of water.

Duffey, J. M.; Livingston, R. R.; Berg, J. M.; Veirs, D. K.

2013-02-06T23:59:59.000Z

252

Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions  

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

Oak Ridge Operations Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions Name: Organization: Directions: This is an open-book evaluation. Complete the questions, and submit your answers (hand-written or electronically) to the Training Center. Someone will check and grade your answers. If you achieve a score of at least 80%, you will receive a completion certificate. Questions: 1. What is safety basis (SB)? 2. How does SB fit with integrated safety management (ISM)? 3. In what primary DOE documents can requirements and guidance for SB be found? 4. What are the "graded approach" factors that DOE takes into account in ensuring that the level of analysis and documentation and the actions used to comply with the requirements are

253

Lawrence Livermore National Laborotory Safety Basis Assessment Final February 11, 2011  

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

Lawrence Livermore National Laboratory Lawrence Livermore National Laboratory Safety Basis Assessment INTRODUCTION This site visit report documents the collective results of the review of Lawrence Livermore National Laboratory (LLNL) safety basis processes and discusses its scope, objective, results and conclusions. Appendix A provides lists of the documents, interviews, and observations and Appendix B includes the plan for the review. This combined assessment was sponsored by the National Nuclear Safety Administration (NNSA) Livermore Site Office (LSO) and conducted jointly by staff from the Office of Health, Safety and Security (HSS) and LSO. The review was conducted in late 2010 and included site visits from November 29 - December 3, 2010 and December 13-17, 2010. Overall, the LLNL programs

254

Report to the Secretary of Energy on Beyond Design Basis Event Pilot  

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

Facilities Facilities Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made. These actions and recommendations were addressed in an August 2011 report to the Secretary of Energy, Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events. Based on recommendations in the August 2011 report, DOE embarked on a project to develop and refine guidance that supports improvements in DOE's processes for analyzing and

255

A Multicellular Basis for the Origination of Blast Crisis in Chronic  

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

Multicellular Basis for the Origination of Blast Crisis in Chronic Multicellular Basis for the Origination of Blast Crisis in Chronic Myeloid Leukemia Philip Hahnfeldt Tufts University School of Medicine Abstract Among radiation-induced cancers, some leukemias, including chronic myeloid leukemia (CML) have especially high excess relative risks. CML, sporadic or radiogenic, is also thought to be comparatively very well understood. Accordingly, CML is considered an important model for assessing radiogenic cancer risk. CML is characterized by a specific chromosome translocation, the BCR-ABL fusion gene, and it has been widely postulated that an advanced stage, CML blast crisis originates mainly via cell-autonomous mechanisms such as secondary mutations or genomic instability. However, there is growing evidence that intercellular interactions can play a critical role

256

A Multicellular Basis for the Origination of Blast Crisis in Chronic Myeloid Leukemia  

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

Multicellular Basis for the Origination of Blast Crisis in Multicellular Basis for the Origination of Blast Crisis in Chronic Myeloid Leukemia Philip Hahnfeldt 1 , Lynn Hlatky 1 , Rainer Sachs 2 1 Center of Cancer Systems Biology, St. Elizabeth's Medical Center, Tufts University School of Medicine, Boston, MA; and 2 Department of Mathematics, University of California, Berkeley, CA Among radiation-induced cancers, some leukemias, including chronic myeloid leukemia (CML) have especially high excess relative risks. CML, sporadic or radiogenic, is also thought to be comparatively very well understood. Accordingly, CML is considered an important model for assessing radiogenic cancer risk. CML is characterized by a specific chromosome translocation, the BCR-ABL fusion gene, and it has been widely postulated that an advanced

257

Lawrence Livermore National Laborotory Safety Basis Assessment Final February 11, 2011  

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

Lawrence Livermore National Laboratory Lawrence Livermore National Laboratory Safety Basis Assessment INTRODUCTION This site visit report documents the collective results of the review of Lawrence Livermore National Laboratory (LLNL) safety basis processes and discusses its scope, objective, results and conclusions. Appendix A provides lists of the documents, interviews, and observations and Appendix B includes the plan for the review. This combined assessment was sponsored by the National Nuclear Safety Administration (NNSA) Livermore Site Office (LSO) and conducted jointly by staff from the Office of Health, Safety and Security (HSS) and LSO. The review was conducted in late 2010 and included site visits from November 29 - December 3, 2010 and December 13-17, 2010. Overall, the LLNL programs

258

Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility  

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

of5 of5 U.S. Department of Energy Subject: Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility - Inspection Criteria, Approach, and Line:~ HS: Rev: Eff. Date: HSS CRAD 45-57 0 January 31,2013 Office of Safety and Emergency Management Evaluations Acting Direc or, Office of Sifety and Emergency Management Evaluations Date: January 31, 2013 Criteria Review and Approach Document LL.v. ~·M Criteria Lead:ife\riew of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility Page 1 of 5 Date: January 31, 2013 1.0 PURPOSE Within the Office of Health, Safety and Security (HSS), the Office of Enforcement and Oversight, Office of Safety and Emergency Management Evaluations (HS-45) mission is to assess the effectiveness of the

259

Biological Basis for Radiation Adaptive Responses that Protect Against Bronchial Epithelial Cell Transformation  

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

Basis for Radiation Adaptive Responses that Protect Against Bronchial Basis for Radiation Adaptive Responses that Protect Against Bronchial Epithelial Cell Transformation Wenshu Chen, Xiuling Xu, Lang Bai, Mabel T. Padilla, Carmen Tellez, Katherine M. Gott, Shuguang Leng, Julie A. Wilder, Steven A. Belinsky, Bobby R. Scott and Yong Lin, Lovelace Respiratory Research Institute, 2425 Ridgecrest Drive SE, Albuquerque, NM 87108 The major hypothesis in this project is that low-dose, low linear-energy-transfer (LET) radiation stimulates an adaptive response that protects cells from neoplastic transformation involving modulation of paracrine factors (e.g., cytokines), cell survival/death signaling pathways, and reprogramming of the epigenome. To test this hypothesis, a validated, sensitive in vitro transformation model and a media transfer

260

Lawrence Livermore Site Office Safety Basis Self-Assessment Final February 11, 2011  

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

Livermore Site Office Livermore Site Office Safety Basis Self-Assessment INTRODUCTION This site visit report documents the collective results of the Office of Health, Safety and Security's (HSS) assessment of National Nuclear Safety Administration (NNSA) Livermore Site Office (LSO) safety basis processes and discusses its scope, objective, results and conclusions. Appendix A provides lists of the documents, interviews, and observations and Appendix B includes the plan for the review. The assessment was sponsored by LSO as a self-assessment and conducted jointly by HSS and LSO staff. It was completed in late 2010 and included site visits from November 29 - December 3, 2010 and December 13-17, 2010. The assessment revealed that LSO has implemented appropriate plans, procedures, and

Note: This page contains sample records for the topic "first-served basis determined" 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

5th International REAC/TS Symposium: The Medical Basis for Radiation  

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

Privacy/Security Statement Privacy/Security Statement 5th International REAC/TS Symposium: The Medical Basis for Radiation Accident Preparedness Skip site navigation and move to main content of page. Home Schedule Speakers Registration Directions and Acommodations Contact 5th International REAC/TS Symposium: The Medical Basis for Radiation Accident Preparedness Sept. 27-29, 2011 Hilton Miami Downtown Miami, Florida United States Introduction This symposium brings together international experts to discuss the advances in the diagnosis and management of radiation emergencies and illnesses. The Oak Ridge Institute for Science and Education (ORISE) designates this live activity for a maximum of 19.25 AMA PRA Category 1 Credit(s)(tm). Physicians should claim only the credit commensurate with the extent of

262

Report to the Secretary of Energy on Beyond Design Basis Event Pilot  

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

Facilities Facilities Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made. These actions and recommendations were addressed in an August 2011 report to the Secretary of Energy, Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events. Based on recommendations in the August 2011 report, DOE embarked on a project to develop and refine guidance that supports improvements in DOE's processes for analyzing and

263

Structural Basis of Pre-existing Immunity to the 2009 H1N1 Pandemic  

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

Structural Basis of Pre-existing Immunity to the 2009 Structural Basis of Pre-existing Immunity to the 2009 H1N1 Pandemic Influenza Virus The emergence of the 2009 H1N1 influenza pandemic, also known as the "swine flu", marks the first human flu pandemic in 40 years and has caused significant human infection and mortality globally (1). The emergence of the 2009 H1N1 flu marks the first time that an influenza pandemic was triggered by a virus carrying the same hemagglutinin (HA) subtype as circulating seasonal strains. In contrast, all prior pandemics were caused by the rise of a novel influenza strain with a different hemagglutinin subtype. And unlike seasonal flu that usually affects the elderly most severely, swine flu has been primarily targeting people under the age of 65, implying some age-related pre-existing immunity (2, 3).

264

Lawrence Livermore Site Office Safety Basis Self-Assessment Final February 11, 2011  

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

Livermore Site Office Livermore Site Office Safety Basis Self-Assessment INTRODUCTION This site visit report documents the collective results of the Office of Health, Safety and Security's (HSS) assessment of National Nuclear Safety Administration (NNSA) Livermore Site Office (LSO) safety basis processes and discusses its scope, objective, results and conclusions. Appendix A provides lists of the documents, interviews, and observations and Appendix B includes the plan for the review. The assessment was sponsored by LSO as a self-assessment and conducted jointly by HSS and LSO staff. It was completed in late 2010 and included site visits from November 29 - December 3, 2010 and December 13-17, 2010. The assessment revealed that LSO has implemented appropriate plans, procedures, and

265

Comparison of CRBR design-basis events with those of foreign LMFBR plants  

Science Conference Proceedings (OSTI)

As part of the Construction Permit (CP) review of the Clinch River Breeder Reactor Plant (CRBR), the Brookhaven National Laboratory was asked to compare the Design Basis Accidents that are considered in CRBR Preliminary Safety Analysis Report with those of the foreign contemporary plants (PHENIX, SUPER-PHENIX, SNR-300, PFR, and MONJU). A brief introductory review of any special or unusual characteristics of these plants is given. This is followed by discussions of the design basis accidents and their acceptance criteria. In spite of some discrepancies due either to semantics or to licensing decisions, there appears to be a considerable degree of unanimity in the selection (definition) of DBAs in all of these plants.

Agrawal, A.K.

1983-04-01T23:59:59.000Z

266

Flammable gas tank safety program: Technical basis for gas analysis and monitoring  

DOE Green Energy (OSTI)

Several Hanford waste tanks have been observed to exhibit periodic releases of significant quantities of flammable gases. Because potential safety issues have been identified with this type of waste behavior, applicable tanks were equipped with instrumentation offering the capability to continuously monitor gases released from them. This document was written to cover three primary areas: (1) describe the current technical basis for requiring flammable gas monitoring, (2) update the technical basis to include knowledge gained from monitoring the tanks over the last three years, (3) provide the criteria for removal of Standard Hydrogen Monitoring System(s) (SHMS) from a waste tank or termination of other flammable gas monitoring activities in the Hanford Tank farms.

Estey, S.D.

1998-04-22T23:59:59.000Z

267

Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions  

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

Oak Ridge Operations Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions Name: Organization: Directions: This is an open-book evaluation. Complete the questions, and submit your answers (hand-written or electronically) to the Training Center. Someone will check and grade your answers. If you achieve a score of at least 80%, you will receive a completion certificate. Questions: 1. What is safety basis (SB)? 2. How does SB fit with integrated safety management (ISM)? 3. In what primary DOE documents can requirements and guidance for SB be found? 4. What are the "graded approach" factors that DOE takes into account in ensuring that the level of analysis and documentation and the actions used to comply with the requirements are

268

Development of Technical Basis for Burnup Credit Regulatory Guidance in the United States  

SciTech Connect

In the United States (U.S.) there has been and continues to be considerable interest in the increased use of burnup credit as part of the safety basis for SNF systems and this interest has motivated numerous technical studies related to the application of burnup credit for maintaining subcriticality. Responding to industry requests and needs, the U.S. Nuclear Regulatory Commission initiated a burnup credit research program, with support from the Oak Ridge National Laboratory, to develop regulatory guidance and the supporting technical basis for allowing and expanding the use of burnup credit in pressurized-water reactor SNF storage and transport applications. The objective of this paper is to summarize the work and significant accomplishments, with references to the technical reports and publications for complete details.

Parks, Cecil V [ORNL; Wagner, John C [ORNL; Mueller, Don [ORNL; Gauld, Ian C [ORNL

2011-01-01T23:59:59.000Z

269

Applications Center: Preventive Maintenance Basis for FLEX EquipmentProject Overview Report  

Science Conference Proceedings (OSTI)

This report describes the status of the EPRI Preventive Maintenance Basis Database (PMBD) and recent modifications that will assist nuclear power plant management in responding to new U.S. federal regulatory requirements known as the Flexible Response (FLEX) program. The FLEX program stems from lessons learned about emergency response to disaster scenarios from the Fukushima Dai-ichi earthquake and related tsunami events in Japan. It requires additional equipment to be stored for long periods to ...

2013-09-30T23:59:59.000Z

270

Technical Basis for Work Place Air Monitoring for the Plutonium Finishing Plan (PFP)  

SciTech Connect

This document establishes the basis for the Plutonium Finishing Plant's (PFP) work place air monitoring program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), Part 835 ''Occupational Radiation Protection''; Hanford Site Radiological Control Manual (HSRCM-1); HNF-PRO-33 1, Work Place Air Monitoring; WHC-SD-CP-SAR-021, Plutonium Finishing Plant Final Safety Analysis Report; and Applicable recognized national standards invoked by DOE Orders and Policies.

JONES, R.A.

1999-10-06T23:59:59.000Z

271

Managing Locational Basis Risk in a Nodal Power Market: A PJM Case Study  

Science Conference Proceedings (OSTI)

The physics of power flows in a congested transmission network can lead to dramatic differences in the value of electric power at different network locations. These cost differences have led a number of market designers to establish systems by which electricity prices vary by location. This report presents a case study demonstrating the effectiveness of an EPRI approach for designing hedges of locational basis risk due to transmission congestion when firm transmission rights (FTRs) are not available.

2001-12-03T23:59:59.000Z

272

A probabilistic risk assessment of the LLNL Plutonium facility`s evaluation basis fire operational accident  

Science Conference Proceedings (OSTI)

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility.

Brumburgh, G.

1994-08-31T23:59:59.000Z

273

Static polarizabilities of hydrogen in the B-spline basis set  

Science Conference Proceedings (OSTI)

The static polarizability of the 1s, 2p, and 3d states of the hydrogen atom has been calculated using the B-splines basis set method, and the portion of the polarizability without poles has been calculated using the B-splines Galerkin method. Excellent agreement with exact values has been obtained. The current algorithm improves the efficiency and accuracy over the finite perturbation method. In addition, closure rules are obtained for the static polarizability of these states.

Bhatti, Mohammad I.; Coleman, Kevin D.; Perger, Warren F. [Department of Physics and Geology, University of Texas-Pan American, Edinburg, Texas 78539-2999 (United States); Physics Department, Michigan Technological University, Houghton, Michigan 49931-1295 (United States)

2003-10-01T23:59:59.000Z

274

Materials Reliability Program (MRP-149, Revision 1) Fatigue Licensing Basis Monitoring Guideline  

Science Conference Proceedings (OSTI)

All nuclear plants are required to operate their mechanical systems within the parameters defined by fatigue design basis requirements, analyses and assumptions. This monitoring guideline is part of the Electric Power Research Institutes (EPRIs) comprehensive and integrated Fatigue Management approach designed to prevent and/or manage cracking of components due to fatigue.BackgroundThis document provides guidance for utility engineers to implement a fatigue ...

2013-12-23T23:59:59.000Z

275

Using Radial Basis Functions to Approximate Battery Differential Capacity and Differential Voltage  

Science Conference Proceedings (OSTI)

As part of the Department of Energys Applied Battery Research Program, lithium-ion cells of various sizes and chemistries are aged with periodic reference performance tests to ascertain degradation rates. The reference tests included a very slow discharge and charge based on a constant current equal to 1/25th of the rated capacity to elucidate the true electrochemical capacity of the cell. A differential analysis of these data helps to identify the individual kinetic and thermodynamic contributions of the anode and cathode. However, differential curves are very noisy, and previous smoothing methods included simple data reduction and moving averages. This paper introduces an alternative method of finding the differential voltage and differential capacity curves based on radial basis functions. The voltage profile is fit with a number of Gaussian curves, and the resulting model is differentiated. This approach also has the added advantage of assessing model uncertainty based on a bootstrap analysis. The radial basis function method was successfully applied to various lithium-ion chemistries tested under the Applied Battery Research Program. The resulting differential capacity and differential voltage curves were generally smoother than the corresponding curves found by previous methods and also showed little variance, indicating a good model fit. These results imply that the radial basis function technique is a more robust tool for assessing differential data.

Jon P. Christophersen; Steven R. Shaw

2010-02-01T23:59:59.000Z

276

Demonstrating Structural Adequacy of Nuclear Power Plant Containment Structures for Beyond Design-Basis Pressure Loadings  

SciTech Connect

ABSTRACT Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment structures, for beyond design-basis internal pressure loadings, is necessary to satisfy Nuclear Regulatory Commission (NRC) requirements and performance goals. This paper discusses methods for demonstrating the structural adequacy of the containment for beyond design-basis pressure loadings. Three distinct evaluations are addressed: (1) estimating the ultimate pressure capacity of the containment structure (10 CFR 50 and US NRC Standard Review Plan, Section 3.8) ; (2) demonstrating the structural adequacy of the containment subjected to pressure loadings associated with combustible gas generation (10 CFR 52 and 10 CFR 50); and (3) demonstrating the containment structural integrity for severe accidents (10 CFR 52 as well as SECY 90-016, SECY 93-087, and related NRC staff requirements memoranda (SRMs)). The paper describes the technical basis for specific aspects of the methods presented. It also presents examples of past issues identified in licensing activities related to these evaluations.

Braverman, J.I.; Morante, R.

2010-07-18T23:59:59.000Z

277

Categorical Exclusion Determinations: Environmental Management...  

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

Environmental Management Categorical Exclusion Determinations: Environmental Management Categorical Exclusion Determinations issued by Environmental Management. DOCUMENTS AVAILABLE...

278

Federal Register Notice for the Waste Determination | Department of Energy  

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

Federal Register Notice for the Waste Determination Federal Register Notice for the Waste Determination Federal Register Notice for the Waste Determination Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) provides that certain waste from reprocessing spent nuclear fuel is not considered high-level waste (HLW) if the Secretary of Energy, in consultation with the Nuclear Regulatory Commission (NRC), determines that the waste meets the statutory criteria set forth in Section 3116(a). Federal Register Notice for the Waste Determination More Documents & Publications EIS-0287: Amended Record of Decision Application to Export Electric Energy OE Docket No. EA-296-B Rainbow Energy Marketing Corp: Federal Register Notice, Volume 77, No. 66 - April 4, 2012 SRS FTF Section 3116 Basis for Determination

279

Secretary Chu Announces Determination of No Adverse Material Impact for  

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

Determination of No Adverse Material Impact Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup Secretary Chu Announces Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup March 2, 2011 - 12:00am Addthis WASHINGTON, D.C. - Secretary of Energy Steven Chu announced today that the Department of Energy has issued a determination and market impact analysis authorizing uranium transfers to fund accelerated cleanup activities at the Portsmouth Site in Piketon, Ohio, through the third quarter of calendar year 2013. The Determination finds that the proposed transfer of uranium will not have an adverse material impact on the domestic uranium industries. The determination authorizes the Department to conduct transfers on a quarterly basis, with no more than 450 metric tons (MTU) of natural uranium

280

Secretary Chu Announces Determination of No Adverse Material Impact for  

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

Determination of No Adverse Material Impact Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup Secretary Chu Announces Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup March 2, 2012 - 4:30pm Addthis WASHINGTON, D.C. - Secretary of Energy Steven Chu announced today that the Department of Energy has issued a determination and market impact analysis authorizing uranium transfers to fund accelerated cleanup activities at the Portsmouth Site in Piketon, Ohio, through the third quarter of calendar year 2013. The Determination finds that the proposed transfer of uranium will not have an adverse material impact on the domestic uranium industries. The determination authorizes the Department to conduct transfers on a quarterly basis, with no more than 450 metric tons (MTU) of natural uranium

Note: This page contains sample records for the topic "first-served basis determined" 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

Research and Education Campus Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

Science Conference Proceedings (OSTI)

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory Research and Education Campus facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

L. Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

282

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

Science Conference Proceedings (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Not Listed

2011-09-01T23:59:59.000Z

283

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

284

Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Central Facilities Area facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facilityspecific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

285

Categorical Exclusion Determination Form  

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

® ® ; ~. ; Program of field Office: Sandia Sile Office Project Title- From Sensing to Enhancing OraiD Processes (l3!dgs. 899, 980, AOQ MRN, and Univ of JIlinois) I oCiltjon- Sandia National Laboratories - New Mexico Proposed Action or project pescription- American Recovery and Reinyestment Acr r Sandia National LaboratoriesINew Mexico (SNLlNM) proposes a project (or basi~ research in human memory and investigating techniques Ihal could be used to improve memory. The project would also establish an eleclroencephalography (EEG) laboratory al Sandia Facility Operations DB 1.1 - Rate increases < innation (not p

286

Accurate Bond Energies of Hydrocarbons from Complete Basis Set Extrapolated Multi-Reference Singles and Doubles Configuration Interaction  

Science Conference Proceedings (OSTI)

Quantum chemistry has become one of the most reliable tools for characterizing the thermochemical underpinnings of reactions, such as bond dissociation energies (BDEs). The accurate prediction of these particular properties (BDEs) are challenging for ab initio methods based on perturbative corrections or coupled cluster expansions of the single-determinant Hartree-Fock wave function: the processes of bond breaking and forming are inherently multi-configurational and require an accurate description of non-dynamical electron correlation. To this end, we present a systematic ab initio approach for computing BDEs that is based on three components: (1) multi-reference single and double excitation configuration interaction (MRSDCI) for the electronic energies; (2) a two-parameter scheme for extrapolating MRSDCI energies to the complete basis set limit; and (3) DFT-B3LYP calculations of minimumenergy structures and vibrational frequencies to account for zero point energy and thermal corrections. We validated our methodology against a set of reliable experimental BDE values of C*C and C*H bonds of hydrocarbons. The goal of chemical accuracy is achieved, on average, without applying any empirical corrections to the MRSDCI electronic energies. We then use this composite scheme to make predictions of BDEs in a large number of hydrocarbon molecules for which there are no experimental data, so as to provide needed thermochemical estimates for fuel molecules.

Oyeyemi, Victor B.; Pavone, Michele; Carter, Emily A.

2011-11-03T23:59:59.000Z

287

Workshop proceedings: Developing the scientific basis for long-term land management of the Idaho National Engineering and Environmental Laboratory  

SciTech Connect

Responses to a survey on the INEEL Comprehensive Facility and Land Use Plan (US DOE 1996a) indicated the need for additional discussion on environmental resources, disturbance, and land use issues on the Idaho National Engineering and Environmental Laboratory (INEEL). As a result, in September 1997, a workshop evaluated the existing scientific basis and determined future data needs for long-term land management on the INEEL. This INEEL Long-Term Land Management Workshop examined existing data on biotic, abiotic, and heritage resources and how these resources have been impacted by disturbance activities of the INEEL. Information gained from this workshop will help guide land and facility use decisions, identify data gaps, and focus future research efforts. This report summarizes background information on the INEEL and its long-term land use planning efforts, presentations and discussions at the workshop, and the existing data available at the INEEL. In this document, recommendations for future INEEL land use planning, research efforts, and future workshops are presented. The authors emphasize these are not policy statements, but comments and suggestions made by scientists and others participating in the workshop. Several appendices covering land use disturbance, legal drivers, land use assumptions and workshop participant comments, workshop participants and contributors, and the workshop agenda are also included.

Sperber, T.D.; Reynolds, T.D. [eds.] [Environmental Science and Research Foundation, Inc., Idaho Falls, ID (United States); Breckenridge, R.P. [ed.] [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States)

1998-03-01T23:59:59.000Z

288

Temperature determination using pyrometry  

DOE Patents (OSTI)

A method for determining the temperature of a surface upon which a coating is grown using optical pyrometry by correcting Kirchhoff's law for errors in the emissivity or reflectance measurements associated with the growth of the coating and subsequent changes in the surface thermal emission and heat transfer characteristics. By a calibration process that can be carried out in situ in the chamber where the coating process occurs, an error calibration parameter can be determined that allows more precise determination of the temperature of the surface using optical pyrometry systems. The calibration process needs only to be carried out when the physical characteristics of the coating chamber change.

Breiland, William G. (Albuquerque, NM); Gurary, Alexander I. (Bridgewater, NJ); Boguslavskiy, Vadim (Princeton, NJ)

2002-01-01T23:59:59.000Z

289

Interim Action Determination  

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

Interim Action Determination Interim Action Determination Processing of Plutonium Materials from the DOE Standard 3013 Surveillance Program in H-Canyon at the Savannah River Site The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS, DOE/EIS-0283-S2). DOE is evaluating alternatives for disposition of non-pit plutonium that is surplus to the national

290

Solids mass flow determination  

DOE Patents (OSTI)

Method and apparatus for determining the mass flow rate of solids mixed with a transport fluid to form a flowing mixture. A temperature differential is established between the solids and fluid. The temperature of the transport fluid prior to mixing, the temperature of the solids prior to mixing, and the equilibrium temperature of the mixture are monitored and correlated in a heat balance with the heat capacities of the solids and fluid to determine the solids mass flow rate.

Macko, Joseph E. (Hempfield Township, Westmoreland County, PA)

1981-01-01T23:59:59.000Z

291

Just in Time DSA-The Hanford Nuclear Safety Basis Strategy  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safety Basis Requirements (the Rule) in January 2001 imposed the requirement that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSA that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: compliance with the Rule; a ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

Olinger, S. J.; Buhl, A. R.

2002-02-26T23:59:59.000Z

292

Basis and implications of the CAP88 age-specific dose coefficients  

Science Conference Proceedings (OSTI)

Recent versions of CAP88 incorporate age-specific dose coefficients based on biokinetic and dosimetric models applied in Federal Guidance Report 13, Cancer Risk Coefficients for Environmental Exposure to Radionuclides (EPA 1999). With a few exceptions the models are those recommended in a series of reports by the International Commission on Radiological Protection (ICRP) on estimation of doses to the public from environmental radionuclides. This paper describes the basis for the ICRP s age-specific biokinetic and dosimetric models and examines differences with age in the derived dose coefficients and in estimates of dose per unit exposure based on those coefficients.

Leggett, Richard Wayne [ORNL; Scofield, Patricia A [ORNL; Eckerman, Keith F [ORNL

2013-01-01T23:59:59.000Z

293

Materials Reliability Program: Preliminary Basis for Potential Reductions in Pipe Fitting Stress Indices (MRP-261)  

Science Conference Proceedings (OSTI)

This report describes the results of Task 1 of a multi-task EPRI program to improve the accuracy and lower the conservatism in the stress indices in NB-3680 of Section III of the ASME Boiler and Pressure Vessel Code. The principal results of Task 1 include a compilation of references relevant to providing a preliminary basis for potential reductions in pipe fitting stress indices. The report also provides a list of future recommendations regarding how fitting characteristics and dimensions can be better ...

2009-09-28T23:59:59.000Z

294

Adaptive local basis set for Kohn-Sham density functional theory in a discontinuous Galerkin framework I: Total energy calculation  

E-Print Network (OSTI)

Kohn-Sham density functional theory is one of the most widely used electronic structure theories. Uniform discretization of the Kohn-Sham Hamiltonian generally results in a large number of basis functions per atom in order to resolve the rapid oscillations of the Kohn-Sham orbitals around the nuclei. Previous attempts to reduce the number of basis functions per atom include the usage of atomic orbitals and similar objects, but the atomic orbitals generally require fine tuning in order to reach the chemical accuracy. We present a novel discretization scheme that adaptively and systematically builds the rapid oscillations of the Kohn-Sham orbitals around the nuclei as well as environmental effects into the basis functions. The resulting basis functions are localized in the real space, and are discontinuous in the global domain. The continuous Kohn-Sham orbitals and the electron density are evaluated from the discontinuous basis functions using the discontinuous Galerkin (DG) framework. Our method is implemented...

Lin, Lin; Ying, Lexing; E, Weinan

2011-01-01T23:59:59.000Z

295

HEU age determination  

SciTech Connect

A new technique has been developed to determine the age of highly enriched uranium (HEU) in solids. Uranium age is defined as the time since the uranium-containing material was last subjected to a process capable of separating uranium from its radioactive-decay daughters. [Most chemical processing, uranium enrichment, volatilization processes, and phase transformations (especially relevant for uranium hexafluoride) can result in separation of the uranium parent material from the decay-product daughters.] Determination of the uranium age, as defined here, may be relevant in verifying arms-control agreements involving uranium-containing nuclear weapons. The HEU age is determined from the ratios of relevant uranium daughter isotopes and their parents, viz {sup 230}Th/{sup 234}U and {sup 231}Pa/{sup 235}U. Uranium isotopes are quantitatively measured by their characteristic gamma rays and their daughters by alpha spectroscopy. In some of the samples, where HEU is enriched more than 99%, the only mode of HEU age determination is by the measurement of {sup 231}Pa since there is negligible quantity of {sup 230}Th due to very low atom concentrations of {sup 234}U in the samples. In this report the methodology and the data for determining the age of two HEU samples are presented.

Moorthy, A.R.; Kato, W.Y.

1997-07-01T23:59:59.000Z

296

Determining age of whales  

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

Determining age of whales Determining age of whales Name: Bruce W Walkey Age: N/A Location: N/A Country: N/A Date: N/A Question: While browsing through the Internet, I came upon a question by two fifth grade students. Their question got me thinking and now I pose it to you. How can you determine the age of whales? Since they are mammals, can the methods that are used on humans be used on whales? What are some tests that can be done on bones or tissues to determine age? Looking forward to your reply. Replies: Although it is difficult to determine the age of whales (unless they are born in captivity and we know their birth date), several methods have been commonly used: 1) (if female) the examination of the ovaries 2) Examination of the ridges on baleen, which are not uniform in size and analogous to tree rings. The problem with this is that baleen wears away over time. 3) Studying layers of ossification in an ear bone is probably the most accurate method of aging, since internal bones don't wear away. The biggest problem with aging methods is that they usually require that you are dissecting the animal, and often, we would like a method of aging for live active animals. The best we can do here is to compare the size and markings of whales of known age to those found in the wild. Great question!

297

CX-008197: Categorical Exclusion Determination | Department of Energy  

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

97: Categorical Exclusion Determination 97: Categorical Exclusion Determination CX-008197: Categorical Exclusion Determination New Mexico TRIBE-JEMEZ PUEBLO CX(s) Applied: A1, A9, B5.1 Date: 04/03/2012 Location(s): New Mexico Offices(s): Energy Efficiency and Renewable Energy Energy Efficiency and Conservation Block Grant. The Jemez Pueblo of New Mexico proposes to 1) conduct energy audits of tribal facilities and member homes which would form the basis for its proposed energy efficiency and renewable energy plan and, if needed, hire a technical consultant to assist with preparation of the plan; and 2) purchase and install energy efficient appliances for Jemez Pueblo tribal members. U.S. Department of Energy NEPA Categorical Exclusion Determination Form More Documents & Publications CX-000662: Categorical Exclusion Determination

298

CX-005528: Categorical Exclusion Determination | Department of Energy  

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

28: Categorical Exclusion Determination 28: Categorical Exclusion Determination CX-005528: Categorical Exclusion Determination Raise the Tank26 High Liquid Level Conductivity Probe Setpoint to 362 Inches CX(s) Applied: B2.2 Date: 01/31/2011 Location(s): Aiken, South Carolina Office(s): Environmental Management, Savannah River Operations Office High Liquid Level Conductivity Probe (HLLCP) setpoint will be documented in the Emergency Response Data (ERD) after implementation of the field work per Technical Safety Requirements (TSR) Administrative Control 5.8.2.44, Tank Fill Limits (SAC). There are no impacts to the Safety Basis as a result of the proposed activity. DOCUMENT(S) AVAILABLE FOR DOWNLOAD CX-005528.pdf More Documents & Publications CX-000563: Categorical Exclusion Determination CX-005535: Categorical Exclusion Determination

299

Self-consistent GW: an all-electron implementation with localized basis functions  

E-Print Network (OSTI)

This paper describes an all-electron implementation of the self-consistent GW (sc-GW) approach -- i.e. based on the solution of the Dyson equation -- in an all-electron numeric atom-centered orbital (NAO) basis set. We cast Hedin's equations into a matrix form that is suitable for numerical calculations by means of i) the resolution of identity technique to handle 4-center integrals; and ii) a basis representation for the imaginary-frequency dependence of dynamical operators. In contrast to perturbative G0W0, sc-GW provides a consistent framework for ground- and excited-state properties and facilitates an unbiased assessment of the GW approximation. For excited-states, we benchmark sc-GW for five molecules relevant for organic photovoltaic applications: thiophene, benzothiazole, 1,2,5-thiadiazole, naphthalene, and tetrathiafulvalene. At self-consistency, the quasi-particle energies are found to be in good agreement with experiment and, on average, more accurate than G0W0 based on Hartree-Fock (HF) or density-...

Caruso, Fabio; Ren, Xinguo; Rubio, Angel; Scheffler, Matthias

2013-01-01T23:59:59.000Z

300

Evaluation of available MHD seed-regeneration processes on the basis of energy considerations  

DOE Green Energy (OSTI)

Of the several processes described in the literature that are capable of separating sulfur from alkali-metal sulfates, seven processes were selected as candidates for regenerating seed material for reuse in open-cycle MHD. After a brief assessment of each process, two were selected for a detailed analysis, namely, a process developed by the Pittsburgh Energy Research Center (PERC) and a modified version of the Tampella process. The processes were compared on the bases of energy requirements and the amount of research work needed to develop a seed-regeneration process for MHD systems. The energy requirements given should be considered as rough values, because factors such as heat losses and component efficiency were not included in the analysis. On the basis of energy consumption, the PERC process has a slight advantage over the Tampella process; on the basis of the present state of development of various components, the Tampella process has a clear advantage. Accordingly, it was recommended that developmental programs be carried out for both the PERC and Tampella processes.

Sheth, A.C.; Johnson, T.R.

1978-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

Infrared and ultraviolet cutoffs in variational calculations with a harmonic oscillator basis  

E-Print Network (OSTI)

I abstract from a recent publication [1] the motivations for, analysis in and conclusions of a study of the ultraviolet and infrared momentum regulators induced by the necessary truncation of the model spaces formed by a variational trial wave function. This trial function is built systematically from a complete set of many-body basis states based upon three-dimensional harmonic oscillator (HO) functions. Each model space is defined by a truncation of the expansion characterized by a counting number (N) and by the intrinsic scale ($\\hbar\\omega$) of the HO basis. Extending both the uv cutoff to infinity and the ir cutoff to zero is prescribed for a converged calculation. In [1] we established practical procedures which utilize these regulators to obtain the extrapolated result from sequences of calculations with model spaces. Finally, I update this subject by mentioning recent work on our extrapolation prescriptions which have appeared since the submission of [1]. The numerical example chosen for this contribution consists of calculations of the ground state energy of the triton with the "bare" and "soft" Idaho N3LO nucleon-nucleon (NN) interaction.

Sidney A Coon

2013-03-26T23:59:59.000Z

302

Development of Probabilistic Design Basis Earthquake (DBE) Parameters for Moderate and High Hazard Facilities at INEEL  

SciTech Connect

Design Basis Earthquake (DBE) horizontal and vertical response spectra are developed for moderate and high hazard facilities or Performance Categories (PC) 3 and 4, respectively, at the Idaho National Engineering and Environmental Laboratory (INEEL). The probabilistic DBE response spectra will replace the deterministic DBE response spectra currently in the U.S. Department of Energy Idaho Operations Office (DOE-ID) Architectural Engineering Standards that govern seismic design criteria for several facility areas at the INEEL. Probabilistic DBE response spectra are recommended to DOE Naval Reactors for use at the Naval Reactor Facility at INEEL. The site-specific Uniform Hazard Spectra (UHS) developed by URS Greiner Woodward Clyde Federal Services are used as the basis for developing the DBE response spectra. In 1999, the UHS for all INEEL facility areas were recomputed using more appropriate attenuation relationships for the Basin and Range province. The revised UHS have lower ground motions than those produced in the 1996 INEEL site-wide probabilistic ground motion study. The DBE response spectra were developed by incorporating smoothed broadened regions of the peak accelerations, velocities, and displacements defined by the site-specific UHS. Portions of the DBE response spectra were adjusted to ensure conservatism for the structural design process.

S. M. Payne; V. W. Gorman; S. A. Jensen; M. E. Nitzel; M. J. Russell; R. P. Smith

2000-03-01T23:59:59.000Z

303

Covariant basis induced by parity for the $(j,0)\\oplus (0,j)$ representation  

E-Print Network (OSTI)

In this work, we build a covariant basis for operators acting on the $(j,0)\\oplus(0,j)$ Lorentz group representations. The construction is based on an analysis of the covariant properties of the parity operator, which for these representations transforms as the completely temporal component of a symmetrical tensor of rank $2j$. The covariant properties of parity involve the Jordan algebra of anti commutators of the Lorentz group generators which unlike the Lie algebra is not universal. We make the construction explicit for $j=1/2,1$ and 3/2, reproducing well-known results for the $j=1/2$ case. We provide an algorithm for the corresponding calculations for arbitrary $j$. This covariant basis provides an inventory of all the possible interaction terms for gauge and non-gauge theories of fields for these representations. In particular, it supplies a single second rank antisymmetric structure, which in the Poincar\\'e projector formalism implies a single Pauli term arising from gauge interactions and a single (free) parameter $g$, the gyromagnetic factor, which characterizes all multipoles of these fields regardless of the spin value.

Selim Gmez-vila; M. Napsuciale

2013-07-17T23:59:59.000Z

304

HEU age determination  

SciTech Connect

A technique has been developed to determine the Highly Enriched Uranium (HEU) Age which is defined as the time since the HEU was produced in an enrichment process. The HEU age is determined from the ratios of relevant uranium parents and their daughters viz {sup 230}Th/{sup 234}U and {sup 231}Pa/{sup 235}U. Uranium isotopes are quantitatively measured by their characteristic gammas and their daughters by alpha spectroscopy. In some of the samples where HEU is enriched more than 99%, the only mode of HEU age determination is by the measurement of {sup 231}Pa since there is negligible quantity of {sup 230}Th due to very low atom concentrations of {sup 234}U in the sample. In this paper we have presented data and methodology of finding the age of two HEU samples.

Moorthy, A.R.; Kato, W.Y.

1995-08-01T23:59:59.000Z

305

Determining Reactor Neutrino Flux  

E-Print Network (OSTI)

Flux is an important source of uncertainties for a reactor neutrino experiment. It is determined from thermal power measurements, reactor core simulation, and knowledge of neutrino spectra of fuel isotopes. Past reactor neutrino experiments have determined the flux to (2-3)% precision. Precision measurements of mixing angle $\\theta_{13}$ by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understanding of the correlation of uncertainties is required for $\\theta_{13}$ experiments. Precise determination of reactor neutrino flux will also improve the sensitivity of the non-proliferation monitoring and future reactor experiments. We will discuss the flux calculation and recent progresses.

Cao, Jun

2011-01-01T23:59:59.000Z

306

Determining Reactor Neutrino Flux  

E-Print Network (OSTI)

Flux is an important source of uncertainties for a reactor neutrino experiment. It is determined from thermal power measurements, reactor core simulation, and knowledge of neutrino spectra of fuel isotopes. Past reactor neutrino experiments have determined the flux to (2-3)% precision. Precision measurements of mixing angle $\\theta_{13}$ by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understanding of the correlation of uncertainties is required for $\\theta_{13}$ experiments. Precise determination of reactor neutrino flux will also improve the sensitivity of the non-proliferation monitoring and future reactor experiments. We will discuss the flux calculation and recent progresses.

Jun Cao

2011-01-12T23:59:59.000Z

307

Categorical Exclusion Determinations: Environmental Management...  

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

Consolidated Business Service Center Categorical Exclusion Determinations: Environmental Management Consolidated Business Service Center Categorical Exclusion Determinations issued...

308

Method and apparatus for determining weldability of thin sheet metal  

DOE Patents (OSTI)

A fixture is provided for testing thin sheet metal specimens to evaluate hot-cracking sensitivity for determining metal weldability on a heat-to-heat basis or through varying welding parameters. A test specimen is stressed in a first direction with a load selectively adjustable over a wide range and then a weldment is passed along over the specimen in a direction transverse to the direction of strain to evaluate the hot-cracking characteristics of the sheet metal which are indicative of the weldability of the metal. The fixture provides evaluations of hot-cracking sensitivity for determining metal weldability in a highly reproducible manner with minimum human error.

Goodwin, Gene M. (Lenoir City, TN); Hudson, Joseph D. (Knoxville, TN)

1988-01-01T23:59:59.000Z

309

Strategic Basis for License Application Planning for a Potential Yucca Mountain Repository  

SciTech Connect

If Yucca Mountain, Nevada is designated as the site for development of a geologic repository for disposal of spent nuclear fuel and high-level radioactive waste, the Department of Energy (DOE) must obtain Nuclear Regulatory Commission (NRC) approval first for repository construction, then for an operating license, and, eventually, for repository closure and decommissioning. The licensing criteria defined in Code of Federal Regulations, Title 10, Part 63 (10 CFR Part 63) establish the basis for these NRC decisions. Submittal of a license application (LA) to the NRC for authorization to construct a repository at the Yucca Mountain site is, at this point, only a potential future action by the DOE. The policy process defined in the Nuclear Waste Policy Act (NWPA), as amended, for recommendation and designation of Yucca Mountain as a repository site makes it difficult to predict whether or when the site might be designated. The DOE may only submit a LA to the NRC if the site designation takes effect. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for development and timely submittal of a LA. This is particularly true given the need for the DOE to develop, load, and certify the operation of its electronic information system to provide access to its relevant records as part of the licensing support network (LSN) in compliance with NRC requirements six months prior to LA submittal. The DOE must also develop a LA, which is a substantially different document from those developed to support a Site Recommendation (SR) decision. The LA must satisfy NRC licensing criteria and content requirements, and address the acceptance criteria defined by the NRC in its forthcoming Yucca Mountain Review Plan (YMRP). The content of the LA must be adequate to facilitate NRC acceptance and docketing for review, and the LA and its supporting documents must provide the documented basis for the NR C findings required for a construction authorization. The LA must also support a licensing proceeding before an Atomic Safety and Licensing Board panel prior to NRC action on any decision to authorize construction. The DOE has established a strategic basis for planning that is intended to provide the framework for development of an integrated plan for activities leading to preparation and submittal of a LA.

Newberry, C. M.; Brocoum, S. J.; Gamble, R. P.; Murray, R. C.; Cline, M.

2002-02-26T23:59:59.000Z

310

Review of Requirements and Capabilities For Analyzing and Responding to Beyond Design Basis Events  

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

to the to the Secretary of Energy Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy August 2011 2011 Safety Bulletin Report TABLE OF CONTENTS Acronyms i Executive Summary ii 1. Introduction 1 2. Report Overview 1 3. Overview of DOE Nuclear Facilities and Operations 2 4. Analysis of Safety Bulletin Submittals 2 5. Review of DOE and Commercial Nuclear Power Industry Requirements and 5 Guidance for BDBEs 6. Results from the Nuclear Safety Workshop 9 7. Summary of Insights and Opportunities for Improvement 10 8. Summary of Recommendations 12 9. Conclusions 14

311

The cohort of the atomic bomb survivors major basis of radiation safety regulations  

E-Print Network (OSTI)

Since 1950 about 87 000 A-bomb survivors from Hiroshima and Nagasaki have been monitored within the framework of the Life Span Study, to quantify radiation-induced late effects. In terms of incidence and mortality, a statistically significant excess was found for leukemia and solid tumors. In another major international effort, neutron and gamma radiation doses were estimated, for those survivors (Dosimetry System DS02). Both studies combined allow the deduction of risk coefficients that serve as a basis for international safety regulations. As an example, current results on all solid tumors combined suggest an excess relative risk of 0.47 per Sievert for an attained age of 70 years, for those who were exposed at an age of 30 years. After exposure to an effective dose of one Sievert the solid tumor mortality would thus be about 50% larger than that expected for a similar cohort not exposed to any ionizing radiation from the bombs.

Rhm, W; Nekolla, E A

2006-01-01T23:59:59.000Z

312

Physics basis for an axicell design for the end plugs of MFTF-B  

SciTech Connect

The primary motivation for conversion of MFTF-B to an axicell configuration lies in its engineering promise as a reactor geometry based on circular high-magnetic-field coils. In comparing this configuration to the previous A-cell geometry, we find a number of differences that might significantly affect the physics performance. The purpose of the present document is to examine those features and to assess their impact on the performance of the axicell, as compared to the A-cell configuration, for MFTF-B. In so doing, we address only those issues thought to be affected by the change in geometry and refer to the original report Physics Basis for MFTF-B, for discussion of those issues thought not to be affected. In Sec. 1, we summarize these physics issues. In Sec. 2, we describe operating scenarios in the new configuration. In the Appendices, we discuss those physics issues that require more detailed treatment.

Baldwin, D.E.; Logan, B.G. (eds.)

1982-04-21T23:59:59.000Z

313

Review and Approval of Nuclear Facility Safety Basis Documents (Documented Safety Analyses and Technical Safety Requirements)  

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

February 1996 February 1996 CHANGE NOTICE NO. 2 Date November 2005 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS DOCUMENTS (DOCUMENTED SAFETY ANALYSES AND TECHNICAL SAFETY REQUIREMENTS) U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, Fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Adminis tration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000.

314

Review of Requirements and Capabilities For Analyzing and Responding to Beyond Design Basis Events  

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

Review of Requirements Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy August 2011 2011 Safety Bulletin Report TABLE OF CONTENTS Acronyms i Executive Summary ii 1. Introduction 1 2. Report Overview 1 3. Overview of DOE Nuclear Facilities and Operations 2 4. Analysis of Safety Bulletin Submittals 2 5. Review of DOE and Commercial Nuclear Power Industry Requirements and 5 Guidance for BDBEs 6. Results from the Nuclear Safety Workshop 9 7. Summary of Insights and Opportunities for Improvement 10 8. Summary of Recommendations 12 9. Conclusions 14 Appendix A - DOE's Nuclear Safety Approach 15

315

Criteria for calculating the efficiency of HEPA filters during and after design basis accidents  

SciTech Connect

We have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

Bergman, W. [Lawrence Livermore National Lab., CA (United States); First, M.W. [Harvard School of Public Health, Boston, MA (United States); Anderson, W.L. [Consultant, LaPlata, MD (United States); Gilbert, H. [Consultant, McLean, VA (United States); Jacox, J.W. [Consultant, Columbus, OH (United States)

1994-12-01T23:59:59.000Z

316

Scientific basis for risk assessment and management of uranium mill tailings  

Science Conference Proceedings (OSTI)

A National Research Council study panel, convened by the Board on Radioactive Waste Management, has examined the scientific basis for risk assessment and management of uranium mill tailings and issued this final report containing a number of recommendations. Chapter 1 provides a brief introduction to the problem. Chapter 2 examines the processes of uranium extraction and the mechanisms by which radionuclides and toxic chemicals contained in the ore can enter the environment. Chapter 3 is devoted to a review of the evidence on health risks associated with radon and its decay products. Chapter 4 provides a consideration of conventional and possible new technical alternatives for tailings management. Chapter 5 explores a number of issues of comparative risk, provides a brief history of uranium mill tailings regulation, and concludes with a discussion of choices that must be made in mill tailing risk management. 211 refs., 30 figs., 27 tabs.

Not Available

1986-01-01T23:59:59.000Z

317

Composition and Technical Basis for K Basin Settler Sludge Simulant for Inspection, Retrieval, and Pump Testing  

SciTech Connect

This report provides the formulation and technical basis for a K Basin Settler Tank Sludge simulant that will be used by the K Basin Closure Project (KBC) to test and develop equipment/approaches for Settler Tank sludge level measurement and retrieval in a mock-up test system of the actual Settler Tanks. The sludge simulant may also be used to demonstrate that the TOYO high pressure positive displacement pump design (reversing valves and hollow balls) is suitable for transfer of Settler Tank sludge from the K West (KW) Basin to the Cold Vacuum Drying Facility (CVDF) (~500 ft). As requested the by the K Basins Sludge Treatment Project (STP) the simulant is comprised of non-radioactive (and non-uranium) constituents.

Schmidt, Andrew J.; Zacher, Alan H.

2007-06-25T23:59:59.000Z

318

Review of the Technical Basis of the Hydrogen Control Limit for Operations in Hanford Tank Farms  

DOE Green Energy (OSTI)

The waste in Hanford tanks generates a mixture of flammable gases and releases it into the tank headspace. The potential hazard resulting from flammable gas generation requires that controls be established to prevent ignition and halt operations if gas concentrations reach levels of concern. In cases where only hydrogen is monitored, a control limit of 6,250 ppm hydrogen has been in use at Hanford for several years. The hydrogen-based control limit is intended to conservatively represent 25% of the lower flammability limit of a gas mixture, accounting for the presence of flammable gases other than hydrogen, with ammonia being the primary concern. This report reviews the technical basis of the current control limit based on observed and projected concentrations of hydrogen and ammonia representing a range of gas release scenarios. The conclusion supports the continued use of the current 6,250 ppm hydrogen control limit

Mahoney, Lenna A. (BATTELLE (PACIFIC NW LAB)); Stewart, Charles W. (BATTELLE (PACIFIC NW LAB))

2002-11-30T23:59:59.000Z

319

Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility  

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

of6 of6 Subject: Review of Safety Basis HS: HSS CRAD 45-59 U.S. Department of Development for the Los Alamos Rev: 0 National Laboratory Transuranic Eff. Date: May 6, 2013 Energy Waste Facility - Criteria and Review Approach Document Office of Safety and ~ Emergency Management Acting Djector, Of~e of Safety and Evaluations Emergency Management Evaluations Date: May 6, 2013 firo,~ Page 1of6 Criteria and Review e;dJatnes 0. Low Approach Document Date: May 6, 2013 1.0 PURPOSE Within the Office of Health, Safety and Security (HSS), the Office of Enforcement and Oversight, Office of Safety and Emergency Management Evaluations (HS-45) mission is to assess the effectiveness of the environment, safety, health, and emergency management systems and practices used by line and

320

Plutonium uranium extraction (PUREX) end state basis for interim operation (BIO) for surveillance and maintenance  

Science Conference Proceedings (OSTI)

This Basis for Interim Operation (BIO) was developed for the PUREX end state condition following completion of the deactivation project. The deactivation project has removed or stabilized the hazardous materials within the facility structure and equipment to reduce the hazards posed by the facility during the surveillance and maintenance (S and M) period, and to reduce the costs associated with the S and M. This document serves as the authorization basis for the PUREX facility, excluding the storage tunnels, railroad cut, and associated tracks, for the deactivated end state condition during the S and M period. The storage tunnels, and associated systems and areas, are addressed in WHC-SD-HS-SAR-001, Rev. 1, PUREX Final Safety Analysis Report. During S and M, the mission of the facility is to maintain the conditions and equipment in a manner that ensures the safety of the workers, environment, and the public. The S and M phase will continue until the final decontamination and decommissioning (D and D) project and activities are begun. Based on the methodology of DOE-STD-1027-92, Hazards Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports, the final facility hazards category is identified as hazards category This considers the remaining material inventories, form and distribution of the material, and the energies present to initiate events of concern. Given the current facility configuration, conditions, and authorized S and M activities, there are no operational events identified resulting in significant hazard to any of the target receptor groups (e.g., workers, public, environment). The only accident scenarios identified with consequences to the onsite co-located workers were based on external natural phenomena, specifically an earthquake. The dose consequences of these events are within the current risk evaluation guidelines and are consistent with the expectations for a hazards category 2 facility.

DODD, E.N.

1999-05-12T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

Categorical Exclusion (CX) Determination  

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

Circle substation expansion Circle substation expansion Description of Proposed Action: Expansion of the Circle substation approximately 4 acres to the south for the purpose of adding additional bays for the Keystone XL pipeline project. Number and Title of Categorical Exclusions Being Applied: 10 CFR 1021.410 Subpart D, Appendix B, B4.11: Construction of electric power substations ... or modification of existing substations and support facilities. Regulatory Requirements for CX Determination: The DOE Guidelines for Compliance with the Regulatory Requirements for the National Environmental Policy Act at 10 CFR 1021.410(b), require the following determinations be made in order for a proposed action to be categorically excluded from National Environmentally Policy Act (NEPA) review:

322

Categorical Exclusion (CX) Determination  

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

Addition of a new substation near Lake Bowdoin, MT. Addition of a new substation near Lake Bowdoin, MT. Description of Proposed Action: Addition of a new substation near Lake Bowdoin on Western's Fort Peck to Havre 161 k V transmission line for the purpose of providing power for a Keystone XL pipeline project pump station. Number and Title of Categorical Exclusions Being Applied: 10 CFR 1021.410 Subpart D, Appendix B, B4.11: Construction of electric power substations ... or modification of existing substations and support facilities. Regulatory Requirements for CX Determination: The DOE Guidelines for Compliance with the Regulatory Requirements for the National Environmental Policy Act at 10 CFR 1021.41 O(b), require the following determinations be made in order for a proposed action to be categorically

323

Categorical Exclusion (CX) Determination  

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

North Oakes tap of the Edgeley to Forman 69 kV line North Oakes tap of the Edgeley to Forman 69 kV line Description of Proposed Action: Central Power Electric Cooperative is proposing to tap into the Western Area Power Administration (Western) Edgeley to Forman 69 kV transmission line with a new substation to meet load growth in the Southeastern North Dakota area. Number and Title of Categorical Exclusions Being Applied: 10 CFR 1021.410 Subpart D, Appendix B, B4.11: Construction of electric power substations ... or modification of existing substations and support facilities. Regulatory Requirements for CX Determination: The DOE Guidelines for Compliance with the Regulatory Requirements for the National Environmental Policy Act at 10 CFR 1021.410(b), require the following determinations be made in order for a proposed action to be categorically

324

NEWTON: Determining Material Degradation  

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

Determining Material Degradation Determining Material Degradation Name: Hamish Status: student Grade: 6-8 Location: CA Country: USA Date: Summer 2013 Question: I am working on a science project about photo-degradation of plastic film. My question is how much degraded a plastic film should be to say that it was 100% photo-degraded? The plastic film I am photo-degrading is turning into dust when I touch it, what level of degradation is that? Replies: Hi Hamish, Thanks for the question. You will need to define what you mean by photo-degraded. 100% photo-degraded could be that the film becomes translucent and lets through only blurry images. Or it could mean that the film turns to dust when you touch it. As long as you clearly state in your science project what you mean by 100% photo-degraded, you will be doing a good job.

325

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

326

Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. U.S. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-11-01T23:59:59.000Z

327

Basis for National and International Low Activity and Very Low Level Waste Disposal Classifications  

Science Conference Proceedings (OSTI)

In order to determine whether the Very Low Level Waste (VLLW) category would be a viable option in the United States, European and U.S. experiences were reviewed in detail.

2012-03-30T23:59:59.000Z

328

The Feasibility of Estimating Ocean Surface Currents on an Operational Basis Using Satellite Feature Tracking Methods  

Science Conference Proceedings (OSTI)

The feasibility of using a relatively new technique, often referred to as satellite feature tracking, for estimating ocean surface currents is described. Sequential satellite imagery is used to determine the displacements of selected ocean ...

L. C. Breaker; D. B. Rao; V. M. Krasnopolsky; X-H. Yan

1994-11-01T23:59:59.000Z

329

CX-008014: Categorical Exclusion Determination | Department of Energy  

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

4: Categorical Exclusion Determination 4: Categorical Exclusion Determination CX-008014: Categorical Exclusion Determination Test Procedures for Measuring Energy Efficiency of Consumer Products and Industrial Equipment CX(s) Applied: A5, A6 Date: 01/05/2012 Location(s): Nationwide Offices(s): Energy Efficiency and Renewable Energy DOE proposes to adopt procedures for consumer products, commercial and industrial equipment that manufacturers of covered equipment must use (1) as the basis for certifying to DOE that their equipment complies with the applicable energy conservation standards adopted under Energy Policy and Conservation Act (ECPA), as amended; and (2) for making representations about the efficiency of those products. Similarly, DOE would use These lest requirements to determine whether the equipment complies with relevant

330

CX-001650: Categorical Exclusion Determination | Department of Energy  

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

650: Categorical Exclusion Determination 650: Categorical Exclusion Determination CX-001650: Categorical Exclusion Determination Safeguards and Security Enhanced Assessment System CX(s) Applied: B2.2 Date: 04/19/2010 Location(s): Richland, Washington Office(s): Environmental Management, Office of River Protection-Richland Office The proposed action will install six wooden utility poles at various locations within and surrounding 200 East Area of the Hanford Site. Each pole will have a 50-foot diameter compacted gravel circle at its base for boom truck access on an as needed basis. DOCUMENT(S) AVAILABLE FOR DOWNLOAD CX-001650.pdf More Documents & Publications Memorandum of Understanding, Responsibilities of Federal Agencies to Protect Migratory Birds CX-009690: Categorical Exclusion Determination

331

CX-009555: Categorical Exclusion Determination | Department of Energy  

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

555: Categorical Exclusion Determination 555: Categorical Exclusion Determination CX-009555: Categorical Exclusion Determination Assisting the Tooling and Machining Industry to Become Energy Efficient CX(s) Applied: A9 Date: 12/10/2012 Location(s): Arizona Offices(s): Golden Field Office The U.S. DOE is proposing to provide federal funding to the Arizona Commerce Authority to conduct an Energy Reduction Challenge Grant competition to identify novel technologies that can be implemented on a pilot project basis to reduce energy consumption within the tooling and machining manufacturing process of aerospace and defense industry suppliers. Funding would be used to make up to 10 research and development pilot project sub-awards over 3 Budget Periods. CX-009555.pdf More Documents & Publications CX-002951: Categorical Exclusion Determination

332

CX-006033: Categorical Exclusion Determination | Department of Energy  

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

033: Categorical Exclusion Determination 033: Categorical Exclusion Determination CX-006033: Categorical Exclusion Determination Monitoring, Maintenance, Environmental and Biological Sampling, and Administrative Actions on Amchitka and Adak Islands, Aleutian Islands, Alaska CX(s) Applied: B1.3, B1.28, B3.1, B3.8 Date: 06/02/2011 Location(s): Amchitka, Alaska Office(s): Legacy Management This determination form provides the results of an evaluation of potential impacts related to various monitoring and maintenance actions on Amchitka Island and to non-routine collection of environmental and biological samples on and offshore of Amchitka and Adak Islands. DOE is committed to the collection of environmental and biological samples to test for radionuclides on a 5-year basis in order to demonstrate that food harvested

333

A Generic Technical Basis for Implementing a Very Low Level Waste Category for Disposal of Low Activity Radioactive Wastes  

Science Conference Proceedings (OSTI)

The International Atomic Energy Agency (IAEA) has recognized Very Low Level Waste (VLLW) as a category that provides both practical and economic benefits. Implementation of VLLW in the international community has been successfully demonstrated in France and Spain, as described in EPRI report 1024844, Basis for National and International Low Activity and Very Low Level Waste (VLLW) Disposal Classifications. This report presents the technical basis for a waste category of Very Low Level ...

2013-12-23T23:59:59.000Z

334

Prediction of solubility of gases in polystyrene by Adaptive Neuro-Fuzzy Inference System and Radial Basis Function Neural Network  

Science Conference Proceedings (OSTI)

Adaptive Neuro-Fuzzy Inference System (ANFIS) and Radial Basis Function Neural Network (RBF NN) have been developed for prediction of solubility of various gases in polystyrene. Solubility of butane, isobutene, carbon dioxide, 1,1,1,2-tetrafluoroethane ... Keywords: ANFIS, ANN, ARD, Adaptive Neuro-Fuzzy Inference System (ANFIS), BP, HCFC-142b, HFC-134a, HFC-l52a, MLP, PS, Polystyrene, RBF NN, Radial Basis Function Neural Network (RBF NN), S-L EOS, Solubility

Aboozar Khajeh; Hamid Modarress

2010-04-01T23:59:59.000Z

335

Decoy state method for measurement device independent quantum key distribution with different intensities in only one basis  

E-Print Network (OSTI)

We show that the three-intensity protocol for measurement device independent quantum key distribution (MDI QKD) can be done with different light intensities in {\\em only one} basis. Given the fact that the exact values yields of single-photon pairs in the $X$ and $Z$ bases must be the same, if we have lower bound of the value in one basis, we can also use this as the lower bound in another basis. Since in the existing set-up for MDI-QKD, the yield of sources in different bases are normally different, therefore our method can improve the key rate drastically if we choose to only use the lower bound of yield of single-photon pairs in the advantageous basis. Moreover, since our proposal here uses fewer intensities of light, the probability of intensity mismatch will be smaller than the existing protocols do. This will further improve the advantage of our method. The advantage of using Z basis or X basis of our method is studied and significant improvement of key rates are numerically demonstrated.

Zong-Wen Yu; Yi-Heng Zhou; Xiang-bin Wang

2013-09-02T23:59:59.000Z

336

HEU age determination  

SciTech Connect

A criteria that a sample of highly enriched uranium (HEU) had come from a weapons stockpile and not newly produced in an enrichment plant is to show that the HEU had been produced a significant time in the past. The time since the HEU has produced in an enrichment plant is defined as the age of the HEU in this paper. The HEU age is determined by measuring quantitatively the daughter products {sup 230}Th and {sup 231}Pa of {sup 234}U and {sup 235}U, respectively, by first chemical separation of the thorium and protactinium and then conducting alpha spectrometry of the daughter products.

Moorthy, A.R.; Kato, W.Y.

1994-12-31T23:59:59.000Z

337

SRS BEDROCK PROBABILISTIC SEISMIC HAZARD ANALYSIS (PSHA) DESIGN BASIS JUSTIFICATION (U)  

SciTech Connect

This represents an assessment of the available Savannah River Site (SRS) hard-rock probabilistic seismic hazard assessments (PSHAs), including PSHAs recently completed, for incorporation in the SRS seismic hazard update. The prior assessment of the SRS seismic design basis (WSRC, 1997) incorporated the results from two PSHAs that were published in 1988 and 1993. Because of the vintage of these studies, an assessment is necessary to establish the value of these PSHAs considering more recently collected data affecting seismic hazards and the availability of more recent PSHAs. This task is consistent with the Department of Energy (DOE) order, DOE O 420.1B and DOE guidance document DOE G 420.1-2. Following DOE guidance, the National Map Hazard was reviewed and incorporated in this assessment. In addition to the National Map hazard, alternative ground motion attenuation models (GMAMs) are used with the National Map source model to produce alternate hazard assessments for the SRS. These hazard assessments are the basis for the updated hard-rock hazard recommendation made in this report. The development and comparison of hazard based on the National Map models and PSHAs completed using alternate GMAMs provides increased confidence in this hazard recommendation. The alternate GMAMs are the EPRI (2004), USGS (2002) and a regional specific model (Silva et al., 2004). Weights of 0.6, 0.3 and 0.1 are recommended for EPRI (2004), USGS (2002) and Silva et al. (2004) respectively. This weighting gives cluster weights of .39, .29, .15, .17 for the 1-corner, 2-corner, hybrid, and Greens-function models, respectively. This assessment is judged to be conservative as compared to WSRC (1997) and incorporates the range of prevailing expert opinion pertinent to the development of seismic hazard at the SRS. The corresponding SRS hard-rock uniform hazard spectra are greater than the design spectra developed in WSRC (1997) that were based on the LLNL (1993) and EPRI (1988) PSHAs. The primary reasons for this difference is the greater activity rate used in contemporary models for the Charleston source zone and proper incorporation of uncertainty and randomness in GMAMs.

(NOEMAIL), R

2005-12-14T23:59:59.000Z

338

Globular Cluster Distance Determinations  

E-Print Network (OSTI)

The present status of the distance scale to Galactic globular clusters is reviewed. Six distance determination techniques which are deemed to be most reliable are discussed in depth. These different techniques are used to calibrate the absolute magnitude of the RR Lyrae stars. The various calibrations fall into three groups. Main sequence fitting using Hipparcos parallaxes, theoretical HB models and the RR Lyrae in the LMC all favor a bright calibration, implying a `long' globular cluster distance scale. White dwarf fitting and the astrometric distances yield a somewhat fainter RR Lyrae calibration, while the statistical parallax solution yields faint RR Lyrae stars implying a `short' distance scale to globular clusters. Various secondary distance indicators discussed all favor the long distance scale. The `long' and `short' distance scales differ by (0.31+/-0.16) mag. Averaging together all of the different distance determinations yields Mv(RR) = (0.23+/-0.04)([Fe/H] + 1.6) + (0.56+/-0.12) mag.

Brian Chaboyer

1998-08-19T23:59:59.000Z

339

Conceptual and computational basis for the quantification of margins and uncertainty.  

Science Conference Proceedings (OSTI)

In 2001, the National Nuclear Security Administration of the U.S. Department of Energy in conjunction with the national security laboratories (i.e, Los Alamos National Laboratory, Lawrence Livermore National Laboratory and Sandia National Laboratories) initiated development of a process designated Quantification of Margins and Uncertainty (QMU) for the use of risk assessment methodologies in the certification of the reliability and safety of the nation's nuclear weapons stockpile. This presentation discusses and illustrates the conceptual and computational basis of QMU in analyses that use computational models to predict the behavior of complex systems. Topics considered include (1) the role of aleatory and epistemic uncertainty in QMU, (2) the representation of uncertainty with probability, (3) the probabilistic representation of uncertainty in QMU analyses involving only epistemic uncertainty, (4) the probabilistic representation of uncertainty in QMU analyses involving aleatory and epistemic uncertainty, (5) procedures for sampling-based uncertainty and sensitivity analysis, (6) the representation of uncertainty with alternatives to probability such as interval analysis, possibility theory and evidence theory, (7) the representation of uncertainty with alternatives to probability in QMU analyses involving only epistemic uncertainty, and (8) the representation of uncertainty with alternatives to probability in QMU analyses involving aleatory and epistemic uncertainty. Concepts and computational procedures are illustrated with both notional examples and examples from reactor safety and radioactive waste disposal.

Helton, Jon Craig (Arizona State University, Tempe, AZ)

2009-06-01T23:59:59.000Z

340

Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant  

Science Conference Proceedings (OSTI)

Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

Hickey, Eva E.; Strom, Daniel J.

2005-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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341

Terracentric Nuclear Fission Reactor: Background, Basis, Feasibility, Structure, Evidence, and Geophysical Implications  

E-Print Network (OSTI)

The background, basis, feasibility, structure, evidence, and geophysical implications of a naturally occurring Terracentric nuclear fission georeactor are reviewed. For a nuclear fission reactor to exist at the center of the Earth, all of the following conditions must be met: (1) There must originally have been a substantial quantity of uranium within Earth's core; (2) There must be a natural mechanism for concentrating the uranium; (3) The isotopic composition of the uranium at the onset of fission must be appropriate to sustain a nuclear fission chain reaction; (4) The reactor must be able to breed a sufficient quantity of fissile nuclides to permit operation over the lifetime of Earth to the present; (5) There must be a natural mechanism for the removal of fission products; (6) There must be a natural mechanism for removing heat from the reactor; (7) There must be a natural mechanism to regulate reactor power level, and; (8) The location of the reactor or must be such as to provide containment and prevent meltdown. Herndon's georeactor alone is shown to meet those conditions. Georeactor existence evidence based upon helium measurements and upon antineutrino measurements is described. Geophysical implications discussed include georeactor origin of the geomagnetic field, geomagnetic reversals from intense solar outbursts and severe Earth trauma, as well as georeactor heat contributions to global dynamics.

J. Marvin Herndon

2013-08-23T23:59:59.000Z

342

Integration by cell algorithm for Slater integrals in a spline basis  

Science Conference Proceedings (OSTI)

An algorithm for evaluating Slater integrals in a B-spline basis is introduced. Based on the piecewise property of the B-splines, the algorithm divides the two-dimensional (r{sub 1}, r{sub 2}) region into a number of rectangular cells according to the chosen grid and implements the two-dimensional integration over each individual cell using Gaussian quadrature. Over the off-diagonal cells, the integrands are separable so that each two-dimensional cell-integral is reduced to a product of two one-dimensional integrals. Furthermore, the scaling invariance of the B-splines in the logarithmic region of the chosen grid is fully exploited such that only some of the cell integrations need to be implemented. The values of given Slater integrals are obtained by assembling the cell integrals. This algorithm significantly improves the efficiency and accuracy of the traditional method that relies on the solution of differential equations and renders the B-spline method more effective when applied to multi-electron atomic systems.

Qiu, Y.; Fischer, C.F.

1999-12-10T23:59:59.000Z

343

The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)  

SciTech Connect

The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration.

NONE

1994-12-01T23:59:59.000Z

344

Multimodal Options for Materials Research to Advance the Basis for Fusion Energy in the ITER Era  

SciTech Connect

Well-coordinated international fusion materials research on multiple fundamental feasibility issues can serve an important role during the next ten years. An overview is given of the current state-of-the-art of major materials systems that are candidates for next-step fusion reactors, including a summary of existing knowledge regarding operating temperature and neutron irradiation fluence limits due to high temperature strength and radiation damage considerations, coolant compatibility information, and current industrial manufacturing capabilities. There are two inter-related overarching objectives of fusion materials research to be performed in the next decade: 1) understanding materials science phenomena in the demanding DT fusion energy environment, and 2) Using this improved understanding to develop and qualify materials to provide the basis for next-step facility construction authorization by funding agencies and public safety licensing authorities. The critical issues and prospects for development of high performance fusion materials are discussed along with recent research results and planned activities of the international materials research community.

Zinkle, Steven J [ORNL; Mslang, Anton [Karlsruhe Institute of Technology, Karlsruhe, Germany; Muroga, Takeo [National Institute for Fusion Science, Toki, Japan; Tanigawa, H. [Japan Atomic Energy Agency (JAEA)

2013-01-01T23:59:59.000Z

345

A chemical basis for the partitioning of radionuclides in incinerator operation  

Science Conference Proceedings (OSTI)

Incineration as a method of treating radioactive or mixed waste is attractive because of volume reduction, but may result in high concentrations of some hazardous components. For safety reasons during operation, and because of the environmental impact of the plant, it is important to know how these materials partition between the furnace slay, the fly ash, and the stack emission. The chemistry of about 50 elements is discussed and through consideration of high temperature thermodynamic equilibria, an attempt is made to provide a basis for predicting how various radionuclides and heavy metals behave in a typical incinerator. The chemistry of the individual elements is first considered and a prediction of the most stable chemical species in the typical incinerator atmosphere is made. The treatment emphasizes volatility and the parameters considered are temperature, acidity, oxygen, sulfur, and halogen content, and the presence of several other key non-radioactive elements. A computer model is used to calculate equilibrium concentrations of many species in several systems at temperatures ranging from 500 to 1600{degrees}K. It is suggested that deliberate addition of various feed chemicals can have a major impact on the fate of many radionuclides and heavy metals. Several problems concerning limitations and application of the data are considered.

Burger, L.L.

1995-01-01T23:59:59.000Z

346

Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis  

Science Conference Proceedings (OSTI)

Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

OHara, J.M.; Higgins, J.C.

2010-01-31T23:59:59.000Z

347

Physics Basis for High-Beta, Low-Aspect-Ratio Stellarator Experiments  

SciTech Connect

High-beta, low-aspect-ratio (compact) stellarators are promising solutions to the problem of developing a magnetic plasma configuration for magnetic fusion power plants that can be sustained in steady-state without disrupting. These concepts combine features of stellarators and advanced tokamaks and have aspect ratios similar to those of tokamaks (2-4). They are based on computed plasma configurations that are shaped in three dimensions to provide desired stability and transport properties. Experiments are planned as part of a program to develop this concept. A beta = 4% quasi-axisymmetric plasma configuration has been evaluated for the National Compact Stellarator Experiment (NCSX). It has a substantial bootstrap current and is shaped to stabilize ballooning, external kink, vertical, and neoclassical tearing modes without feedback or close-fitting conductors. Quasi-omnigeneous plasma configurations stable to ballooning modes at beta = 4% have been evaluated for the Quasi-Omnigeneous Stellarator (QOS) experiment. These equilibria have relatively low bootstrap currents and are insensitive to changes in beta. Coil configurations have been calculated that reconstruct these plasma configurations, preserving their important physics properties. Theory- and experiment-based confinement analyses are used to evaluate the technical capabilities needed to reach target plasma conditions. The physics basis for these complementary experiments is described.

A. Brooks; A.H. Reiman; G.H. Neilson; M.C. Zarnstorff; et al

1999-11-01T23:59:59.000Z

348

Categorical Exclusion Determination Form  

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

ergy ergy Categorical Exclusion Determination Form Proposed Action Title: (0472-1569) G~tomics - Double Sator Switched Reluctance Motor (DSSRM) Technology Progi'am or Field Office: Advanced Research Projects Agency - Energy Location(s) (City/County/State): San Diego, CA Proposed Action Description: General Atomics, in conjunction with the University of Texas-Dallas (UT Dallas), proposes to develop double-stator switched reluctance motor (DSSRM) for electric vehicles (EVs) that will eliminate the use of permanent magnet-based motors that rely on rare earth metals in EVs. General Atomics' application was selected for an initial 18-month period (Phase 1) of funding. The ARPA-E Program Director may decide to negotiate and fund project activities for an additional 18-month period (Phase II) after evaluating the work performed in Phase I. ARPA-E has not obligated

349

Categorical Exclusion (CX) Determination  

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

Letcher to Mitchell 115 kV transmission line to Western's Letcher to Mitchell 115 kV transmission line to Western's Letcher substation. Description of Proposed Action: Interconnection of Northwestern Energy's 115 kV Letcher to Mitchell transmission line at Western's Letcher substation. Northwestern Energy is proposing to build a 14.5 mile transmission line between their Mitchell substation and Western's Letcher substation to shore up reliability of their electrical system in the area. Number and Title of Categorical Exclusions Being Applied: 10 CFR 1021.410 Subpart D, Appendix B, B4.11: Construction of electric power substations ... or modification of existing substations and support facilities. Regulatory Requirements for CX Determination: The DOE Guidelines for Compliance with the Regulatory Requirements for the National Environmental Policy Act at 10 CFR 1021.41 O(b), require the

350

Categorical Exclusion (CX) Determination  

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

Movement of the Shirley Pump substation to a new site away from Movement of the Shirley Pump substation to a new site away from Yellowstone River and replacement of the Shirley Pump substation transformer. Description of Proposed Action: Move the existing Shirley Pump substation approximately 200 meters to the southeast away from its current location and the Yellowstone River as well as replace the aging transformer with a new one. Number and Title of Categorical Exclusions Being Applied: 10 CPR 1021.410 Subpart D, Appendix B, B4.11: Construction of electric power substations ... or modification of existing substations and support facilities. Regulatory Requirements for CX Determination: The DOE Guidelines for Compliance with the Regulatory Requirements for the National Environmental Policy Act at 10 CPR 1021.41 O(b),

351

Categorical Exclusion Determination Form  

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

t t Categorical Exclusion Determination Form Proposed Action Title: (0471-1563) University of South Florida - Development of a Low Cost Thermal Energy Storage System Using Phase Change Materials with Enhanced Radiation Heat Transfer Program or Field Office: Advanced Research Projects Agency - Energy Location(s) (City/County/State): Tampa, FL Proposed Action Description: Funding will support development of low cost, industrially scalable capsules containing high-temperature phase change materials (PCMs) for use in thermal energy storage (TES) systems to enable continuous power supply from concentrated solar thermal and nuclear power plants. No nuclear research and development activities will take place under this project. ARPA-E has undertaken a review of the work to be performed

352

Categorical Exclusion Determination Form  

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

n rgy n rgy Categorical Exclusion Determination Form Proposed Action Title: (0474-1555) University of Colorado - Boulder - Wafer-Level Sub-Module Integrated DCfDC Converter Program or Field Office: Advanced Research Projects Agency - Energy LocationCs) CCity/County/State): Colorado, Maine, Virginia Proposed Action Description: Funding will support development of a planar, wafer-level sub-module integrated converter (SubMIC) device that can be integrated into various types of photovoltaic (PV) modules to enable low-cost maximum power point tracking at high power processing efficiencies. Proposed work consists of indoor laboratory-based research and development (R&D), microfabrication activities, and analytical research, including: (1) simulated modeling and design of SubMIC components and integrated units, (2) development, fabrication, testing, and optimization

353

Categorical Exclusion Determination Form  

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

1537) Utah State University - 1537) Utah State University - Robust Cell-Level Modeling and Control of Large Battery Packs Program or Field Office: Advanced Research Projects Agency - Energy LocationCs) CCity/County/State): Logan, UT; Colorado Springs, CO; Boulder, CO; Golden, CO; Dearborn, MI Proposed Action Description: Funding will support efforts to develop a novel battery pack architecture supported by algorithms to drive analysis, feedback, and operability. Proposed work will consist of: (1) performing a requirements analysis to determine optimal theoretical design for the battery pack; (2) design and theoretical optimization of the necessary algorithms to control and monitor the cells in the pack; (3) creation , testing, and analysis of a proof-of- concept unit; and (4) application of the algorithmic controls to a commercial battery pack to analyze performance.

354

Categorical Exclusion Determination Form  

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

y y Categorical Exclusion Determination Form Proposed Action Title: (0471-1595) Regents of the University of Minnesota - Thermal Fuel: Solar Fuels via Partial Redox Cycles with Heat Recovery Program or Field Office: Advanced Research Projects Agency - Energy LocationCs) CCity/County/State): Minnesota, California, and Colorado. Proposed Action Description: Funding will support development of a dual zone solar thermochemical reactor to produce fuel using ceria-based reactive materials in partial redox cycles and high heat recovery levels through counter-circulation of solid state components. Proposed work consists of indoor laboratory-based research and development, including: (1) designing, fabricating, and characterizing an optimized ceria-based reactive element for use in the reactor to enable maximum fuel productivity and durability; (2) designing and fabricating a

355

Categorical Exclusion Determination Form  

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

of n y of n y Categorical Exclusion Determination Form Proposed Action Title: (0471-1607) University of Florida - Solar Thermochemical Fuel Production via a Novel Low Pressure, Magnetically Stabilized, Non-Volatile Iron Oxide Looping Process Program or Field Office: Advanced Research Projects Agency - Energy LocationCs) CCity/County/State): Gainesville, FL Proposed Action Description: University of Florida proposes to develop a novel solar thermochemical reactor with inputs of water, recycled carbon dioxide (C02), and concentrated solar energy to cost-effectively produce Syngas, a renewable, carbon-neutral fuel. Project activities will include: (1) modeling, design, and fabrication of a high efficiency 1 OkW reactor prototype; (2) test analysis of bench-scale

356

Cat Dish Bacteria Determination  

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

Dish Bacteria Determination Dish Bacteria Determination Name: Ashlyn Status: student Grade: 6-8 Location: FL Country: USA Date: Summer 2011 Question: Is there a simple way to measure bacteria in cat's water dishes without doing something with Agar? To measure bacteria in a water bowl, do I need to use a microscope? I am thinking of using different materials (metal, plastic, and glass) to see which of those has the grows the most bacteria. Replies: Hello Ashlyn, That is a very good idea for a science project. Usually the best way to do a quantitative analysis of bacteria content is to take a measured amount of a liquid, plate it out on some type of agar and do a colony count. This will give a basic indication of bacterial load, but not differentiate the types of bacteria. The most common type of bacteria that causes a pink film to form on water bowls and showers, etc. is Serratia marcescens. It is a fairly harmless organism that reacts with standing water. It may only adhere to the walls of the container and not be 'free floating' in the water. A microscope would not likely help unless you were able to do special stains to help see the bacteria. You might also want to add stoneware or ceramic to your list. Just so you know stoneware or ceramic make the best containers for cats to drink out of. It keeps the water fresher: Maybe less bacteria? You might just have to rely on a visual inspection of the containers to see which has more pink per surface area.

357

Standard test method for determination of bromine and chlorine in UF6 and uranyl nitrate by X-Ray fluorescence (XRF) spectroscopy  

E-Print Network (OSTI)

1.1 This method covers the determination of bromine (Br) and chlorine (Cl) in uranium hexafluoride (UF6) and uranyl nitrate solution. The method as written covers the determination of bromine in UF6 over the concentration range of 0.2 to 8 ?g/g, uranium basis. The chlorine in UF6 can be determined over the range of 4 to 160 ?g/g, uranium basis. Higher concentrations may be covered by appropriate dilutions. The detection limit for Br is 0.2 ?g/g uranium basis and for Cl is 4 ?g/g uranium basis. 1.2 This standard may involve hazardous materials, operations and equipment. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2001-01-01T23:59:59.000Z

358

TECHICAL REPORT A Pilot Project to Establish the Technical Basis and  

E-Print Network (OSTI)

Laboratory 1250 Maryland Ave., Suite 500 Washington, DC 20024 TEL: 202-484-0887 Email: wcdupont of windows, physical testing was the primary means of determining indices of performance, like U (Discrete methods). Both methods mainly try to evaluate total heat flow through the window, which

Massachusetts at Amherst, University of

359

Localized atomic basis set in the projector augmented wave method A. H. Larsen, M. Vanin, J. J. Mortensen, K. S. Thygesen, and K. W. Jacobsen  

E-Print Network (OSTI)

for different basis sets. This error is defined as ELCAO - Egrid = Emol LCAO - atoms Eatoms LCAO - Emol grid

Thygesen, Kristian

360

Comparative analysis of environmental impacts of maize-biogas and photovoltaics on a land use basis  

Science Conference Proceedings (OSTI)

This study aims to stimulate the discussion on how to optimize a sustainable energy mix from an environmental perspective and how to apply existing renewable energy sources in the most efficient way. Ground-mounted photovoltaics (PV) and the maize-biogas-electricity route are compared with regard to their potential to mitigate environmental pressure, assuming that a given agricultural area is available for energy production. Existing life cycle assessment (LCA) studies are taken as a basis to analyse environmental impacts of those technologies in relation to conventional technology for power and heat generation. The life-cycle-wide mitigation potential per area used is calculated for the impact categories non-renewable energy input, green house gas (GHG) emissions, acidification and eutrophication. The environmental performance of each system depends on the scenario that is assumed for end energy use (electricity and heat supply have been contemplated). In all scenarios under consideration, PV turns out to be superior to biogas in almost all studied impact categories. Even when maize is used for electricity production in connection with very efficient heat usage, and reduced PV performance is assumed to account for intermittence, PV can still mitigate about four times the amount of green house gas emissions and non-renewable energy input compared to maize-biogas. Soil erosion, which can be entirely avoided with PV, exceeds soil renewal rates roughly 20-fold on maize fields. Regarding the overall Eco-indicator 99 (H) score under most favourable assumptions for the maize-biogas route, PV has still a more than 100% higher potential to mitigate environmental burden. At present, the key advantages of biogas are its price and its availability without intermittence. In the long run, and with respect to more efficient land use, biogas might preferably be produced from organic waste or manure, whereas PV should be integrated into buildings and infrastructures. (author)

Graebig, Markus; Fenner, Richard [Centre for Sustainable Development, Department of Engineering, University of Cambridge (United Kingdom); Bringezu, Stefan [Wuppertal Institute for Climate, Environment and Energy. P.B. 100480, 42004 Wuppertal (Germany)

2010-07-15T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

Analysis of waste treatment requirements for DOE mixed wastes: Technical basis  

SciTech Connect

The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation`s allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered.

1995-02-01T23:59:59.000Z

362

NNSA?s Computing Strategy, Acquisition Plan, and Basis for Computing Time Allocation  

SciTech Connect

This report is in response to the Omnibus Appropriations Act, 2009 (H.R. 1105; Public Law 111-8) in its funding of the National Nuclear Security Administration's (NNSA) Advanced Simulation and Computing (ASC) Program. This bill called for a report on ASC's plans for computing and platform acquisition strategy in support of stockpile stewardship. Computer simulation is essential to the stewardship of the nation's nuclear stockpile. Annual certification of the country's stockpile systems, Significant Finding Investigations (SFIs), and execution of Life Extension Programs (LEPs) are dependent on simulations employing the advanced ASC tools developed over the past decade plus; indeed, without these tools, certification would not be possible without a return to nuclear testing. ASC is an integrated program involving investments in computer hardware (platforms and computing centers), software environments, integrated design codes and physical models for these codes, and validation methodologies. The significant progress ASC has made in the past derives from its focus on mission and from its strategy of balancing support across the key investment areas necessary for success. All these investment areas must be sustained for ASC to adequately support current stockpile stewardship mission needs and to meet ever more difficult challenges as the weapons continue to age or undergo refurbishment. The appropriations bill called for this report to address three specific issues, which are responded to briefly here but are expanded upon in the subsequent document: (1) Identify how computing capability at each of the labs will specifically contribute to stockpile stewardship goals, and on what basis computing time will be allocated to achieve the goal of a balanced program among the labs. (2) Explain the NNSA's acquisition strategy for capacity and capability of machines at each of the labs and how it will fit within the existing budget constraints. (3) Identify the technical challenges facing the program and a strategy to resolve them.

Nikkel, D J

2009-07-21T23:59:59.000Z

363

NNSA?s Computing Strategy, Acquisition Plan, and Basis for Computing Time Allocation  

SciTech Connect

This report is in response to the Omnibus Appropriations Act, 2009 (H.R. 1105; Public Law 111-8) in its funding of the National Nuclear Security Administration's (NNSA) Advanced Simulation and Computing (ASC) Program. This bill called for a report on ASC's plans for computing and platform acquisition strategy in support of stockpile stewardship. Computer simulation is essential to the stewardship of the nation's nuclear stockpile. Annual certification of the country's stockpile systems, Significant Finding Investigations (SFIs), and execution of Life Extension Programs (LEPs) are dependent on simulations employing the advanced ASC tools developed over the past decade plus; indeed, without these tools, certification would not be possible without a return to nuclear testing. ASC is an integrated program involving investments in computer hardware (platforms and computing centers), software environments, integrated design codes and physical models for these codes, and validation methodologies. The significant progress ASC has made in the past derives from its focus on mission and from its strategy of balancing support across the key investment areas necessary for success. All these investment areas must be sustained for ASC to adequately support current stockpile stewardship mission needs and to meet ever more difficult challenges as the weapons continue to age or undergo refurbishment. The appropriations bill called for this report to address three specific issues, which are responded to briefly here but are expanded upon in the subsequent document: (1) Identify how computing capability at each of the labs will specifically contribute to stockpile stewardship goals, and on what basis computing time will be allocated to achieve the goal of a balanced program among the labs. (2) Explain the NNSA's acquisition strategy for capacity and capability of machines at each of the labs and how it will fit within the existing budget constraints. (3) Identify the technical challenges facing the program and a strategy to resolve them.

Nikkel, D J

2009-07-21T23:59:59.000Z

364

CX-006923: Categorical Exclusion Determination | Department of Energy  

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

23: Categorical Exclusion Determination 23: Categorical Exclusion Determination CX-006923: Categorical Exclusion Determination Design and Install a Modification to the HB-Line Exhaust Fan Dampers CX(s) Applied: B2.5 Date: 10/13/2011 Location(s): Aiken, South Carolina Office(s): Environmental Management As a result of the upgrade of the HB-Line Documented Safety Analysis/Technical Safety Requirements to DOE-STD-3009, several events require protection to prevent a radiological release. The Consolidated Hazards Analysis for the HB-Line Documented Safety Basis Upgrade (U), U-CHA-H-00003, includes 13 specific events. To ensure that the HB-Line events are protected, the HB-Line Room Exhaust (RREX) Fan discharge dampers and inlet vanes need to maintain a flow path to the H-Canyon during the credited events.

365

CX-004163: Categorical Exclusion Determination | Department of Energy  

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

63: Categorical Exclusion Determination 63: Categorical Exclusion Determination CX-004163: Categorical Exclusion Determination Mobile Meteorological Equipment CX(s) Applied: B3.1 Date: 08/02/2010 Location(s): New Mexico Office(s): Sandia Site Office Sandia National Laboratories/New Mexico (SNL/NM) proposes to provide mobile meteorological instrumentation on an as-needed or as-required basis. SNL/NM owns and operates a suite of mobile meteorological instruments including, trailer-mounted meteorological towers, trailer-mounted sound detection and ranging systems (SODAR), and a Digicora System that can be used to tether an instrumented balloon, or send a free balloon into the atmosphere to measure atmospheric-state parameters through the troposphere. DOCUMENT(S) AVAILABLE FOR DOWNLOAD CX-004163.pdf

366

CX-002105: Categorical Exclusion Determination | Department of Energy  

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

05: Categorical Exclusion Determination 05: Categorical Exclusion Determination CX-002105: Categorical Exclusion Determination Washington-Tribal Energy Program-Upper Skagit Indian Tribe CX(s) Applied: A9, A11, B3.1 Date: 04/13/2010 Location(s): Washington Office(s): Energy Efficiency and Renewable Energy 1) Complete feasibility study: Use of technical services to perform a site-specific wind resource assessment at the Bow Hill Reservation Complex, Washington. The assessment will require installation of a temporary 60 meter meteorological tower deployment of a SOnic Detection And Ranging (SODAR) unit between two sites on a seasonal basis and use of technical services to prepare an assessment report on emerging residential wind technology DOCUMENT(S) AVAILABLE FOR DOWNLOAD CX-002105.pdf More Documents & Publications

367

CX-004926: Categorical Exclusion Determination | Department of Energy  

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

926: Categorical Exclusion Determination 926: Categorical Exclusion Determination CX-004926: Categorical Exclusion Determination Radioactive Waste Management Complex ? Analytical Laboratory Operations CX(s) Applied: B3.1 Date: 01/05/2011 Location(s): Idaho Office(s): Nuclear Energy, Idaho Operations Office The Radioactive Waste Management Complex Analytical Laboratory operations will be expanded to provide additional sample analyses on an as needed basis. The operations could include sample analysis of operational samples, samples of an emergency nature or from material spills, as examples. The primary focus of the analytical laboratory operations will continue to provide support to the Waste Isolation Pilot Plant (Carlsbad Field Office) certified transuranic waste analysis capabilities. DOCUMENT(S) AVAILABLE FOR DOWNLOAD

368

CX-009050: Categorical Exclusion Determination | Department of Energy  

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

09050: Categorical Exclusion Determination 09050: Categorical Exclusion Determination CX-009050: Categorical Exclusion Determination Used Nuclear Fuel Dry Storage Phase I Pilot Project CX(s) Applied: B3.6 Date: 08/07/2012 Location(s): South Carolina Offices(s): Savannah River Operations Office The scope of this activity is to establish the technical basis for moving the Used Nuclear Fuel (UNF) currently stored in L-Basin into a commercial style Dry Storage system. This Categorical Exclusion addresses Phase I of a pilot project to move a limited but diverse selection of UNF currently in L-Basin to dry storage. The pilot system would have instrumented UNF containers to monitor the performance and verify storage parameters are suitable for possible future Dry Storage. DOE-SR supports this pilot as part of a potential long term UNF interim storage option for Savannah River

369

CX-006965: Categorical Exclusion Determination | Department of Energy  

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

65: Categorical Exclusion Determination 65: Categorical Exclusion Determination CX-006965: Categorical Exclusion Determination Provide Design to Install a Seismic Switch to Shut Down Both Supply Fans and Both Room Exhaust Fans During a Seismic Event CX(s) Applied: B2.5 Date: 09/16/2011 Location(s): Aiken, South Carolina Office(s): Environmental Management, National Energy Technology Laboratory As a result of the upgrade of the HB-Line Documented Safety Analysis/Technical Safety Requirements to DOE-STD-3009, several events require protection to prevent a radiological release. Consolidated Hazards Analysis Process (CHAP) for the HB-Line Documented Safety Basis Upgrade (U), U-CHA-H-00003, includes two specific events HB-7-001, Earthquake with subsequent fire and post seismic hydrogen explosions in process vessels and

370

CX-003192: Categorical Exclusion Determination | Department of Energy  

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

92: Categorical Exclusion Determination 92: Categorical Exclusion Determination CX-003192: Categorical Exclusion Determination Rush University Advanced Emergency Medical Response Center CX(s) Applied: B3.12 Date: 07/21/2010 Location(s): Chicago, Illinois Office(s): Science, Chicago Office The project consists of building an advanced emergency department based upon the concept of a "Center for Advanced Emergency Response" that allows the Emergency Department to respond to and treat victims of chemical, biological, radiological, nuclear or explosive events as well as functioning as a standard emergency on a day to day basis. The infrastructure involves special heating, ventilation, and air conditioning equipment to provide negative or positive pressure air flow, contaminated waste water runoff containment tanks, redundant utilities, and alternate

371

CX-006637: Categorical Exclusion Determination | Department of Energy  

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

7: Categorical Exclusion Determination 7: Categorical Exclusion Determination CX-006637: Categorical Exclusion Determination Repair Storm Water Drainage Outside the T-Area Cap CX(s) Applied: B1.3 Date: 08/10/2011 Location(s): Aiken, South Carolina Office(s): Savannah River Operations Office The existing drainage channel located to the west side of T-Area closure cap was experiencing heavy erosion. Modification to the channel was required to satisfy flow conditions and minimize the erosion. Installation of a temporary road to access the channel area was required and necessitated the removal of some trees in the floodplain. It is now desired to keep the access road on a permanent basis to accommodate the inspection/maintenance of the cap and drainage system which is required by the Comprehensive Environmental Response, Compensation and Liability Act

372

CX-002022: Categorical Exclusion Determination | Department of Energy  

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

2: Categorical Exclusion Determination 2: Categorical Exclusion Determination CX-002022: Categorical Exclusion Determination Adult Detention Facility Energy Conservation Projects - Domestic Hot Water Heat Pump CX(s) Applied: B5.1 Date: 04/27/2010 Location(s): Lancaster County, Nebraska Office(s): Energy Efficiency and Renewable Energy The energy modeling for the new county detention facility's domestic hot water requirements shows a peak energy consumption of 5.7million British Thermal Units (MMBtu) per hour with an annual usage of 14,241 MMBtu/year (based on 1000 bed occupancy). This energy use is equivalent to 123 % the estimated space heating requirements, which is 11,550 MMBTU/year. The building energy modeling also indicates the overall space conditioning requirements will be cooling load dominated, on an annual basis. With the

373

Cost-Energy Dynamics: An Engineering - Economic Basis for Industrial Energy Conservation Policies  

E-Print Network (OSTI)

This paper develops a theory called cost-energy dynamics that can be used to shape policies for industrial energy conservation. It is built on two hypotheses commonly observed in process engineering; namely, cost varies as positive power function while energy varies as negative power function of the system size and/ or complexity. These two hypotheses, which have roots in thermodynamics, give rise to a technological parameter (denoted c) that can be determined for each unit process. Cost-energy dynamics ranks energy conservation potentials of industrial processes by the technology parameter c, aggregates energy consumption by unit processes, considers energy embodied in the investment, considers the trade-offs between cost and energy, and distinguishes bases for decision making in the public and private sectors. Five unit processes are used to represent the U.S. manufacturing industry. The aggregated technology parameter for industry is determined to be about 3.5. This value and the data on existing energy consumption allow the determination of energy conservation potentials, extra capital investment requirements, and the possible energy picture by the year 2000. Several public policy tools are evaluated for their effectiveness in stimulating energy conservation.

Phung, D. L.; van Gool, W.

1980-01-01T23:59:59.000Z

374

Approach to developing a ground-motion design basis for facilities important to safety at Yucca Mountain  

SciTech Connect

The Department of Energy has proposed a methodology for developing a ground-motion design basis for prospective facilities at Yucca Mountain that are important to safety. The methodology utilizes a quasi-deterministic construct that is designed to provide a conservative, robust, and reproducible estimate of ground motion that has a one-in-ten chance of occurring during the preclosure period. This estimate is intended to define a ground-motion level for which the seismic design would ensure minimal disruption to operations; engineering analyses to ensure safe performance in the unlikely event that the design basis is exceeded are a part of the proposed methodology. 8 refs.

King, J.L.

1990-04-01T23:59:59.000Z

375

Determinations | Building Energy Codes Program  

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

Regulations Regulations Site Map Printable Version Development Adoption Compliance Regulations Determinations Federal Buildings Manufactured Housing Resource Center Determinations Commercial Determinations Residential Determinations Final Determination on ASHRAE Standard 90.1-2010 On October 19, 2011, DOE issued a final determination that ASHRAE Standard 90.1-2010 would achieve greater energy efficiency in buildings subject to the standard than if they were built to ASHRAE Standard 90.1-2007. View the complete final determination notice that appeared in the Federal Register on October 19, 2011. View the complete preliminary determination notice that appeared in the Federal Register on July 20, 2011. State Certification This final determination is being published before the two year deadline

376

Plasma temperature determination from the total intensity of a self-reversed spectral line  

SciTech Connect

A method is introduced for determining the temperature of a high-pressure gas discharge from the total intensity of a self-reversed spectral line, if the plasma is in local thermodynamic equilibrium. The structural characteristics of the plasma are determined from observable parameters of the line on the basis of a simplified model for the light source. An application is given with the self-reversed mercury lines 5461, 4358, and 4047 A emitted from a high-pressure mercury discharge.

Karabourniotis, D.; Karras, C.; Drakakis, M.; Damelincourt, J.J.

1982-11-01T23:59:59.000Z

377

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND  

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

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. 2011 Secretarial Fee Adequacy Determination.PDF More Documents & Publications Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee

378

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND  

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

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. 2011 Secretarial Fee Adequacy Determination.PDF More Documents & Publications Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee

379

Drain Tank Information for Developing Design Basis of the Preliminary Design  

Science Conference Proceedings (OSTI)

Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of coolant accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)]; Neutral Beam Injector (NBI) components; and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004-design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by US ITER and AREVA Federal Services, the US ITER A and E Company. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design basis accident: a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassette lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout and dimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

Ferrada, Juan J [ORNL

2012-02-01T23:59:59.000Z

380

Drain Tank Information for Developing Design Basis of the Preliminary Design  

Science Conference Proceedings (OSTI)

Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of cooling accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)], Neutral Beam Injector (NBI) components, and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004 design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by U.S. ITER. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design-basis accident:1 a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassettes lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout anddimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

Ferrada, Juan J [ORNL

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

RECORD OF CATEGORICAL EXCLUSION DETERMINATION Project ID No. PR 10069318  

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

318 318 Title: WH Air Conditioning/Heating Repairs, 2010-2013 Description: Subcontractor shall provide all labor, materials, tools, equipment, transportation and supervision required to tear down, inspect, and perform minor repairs to the air conditioning and heating units at WH on a "will call or as needed basis" during the period from 2010 to 2013. Regulatory Requirements: NEPA Implementing Procedures (10 CFR 1021) 10 CFR 1021.410 (Application of Categorical Exclusions) (a) The actions listed in Appendices A and B of Subpart D are classes of actions that DOE has determined do not individually or cumulatively have a significant effect on the human environment (categorical exclusions).

382

Independent Oversight Review of Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades, November 2011  

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

Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades November 2011 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope and Approach .............................................................................................................................. 2

383

An outdoor time scenes simulation scheme based on support vector regression with radial basis function on DCT domain  

Science Conference Proceedings (OSTI)

In this paper, a novel strategy for forecasting outdoor scenes is introduced. This new approach combines the support vector regression in neural network computation and the discrete cosine transform (DCT). In 1995, Vapnik introduced a neural-network ... Keywords: Discrete cosine transform, Neural network, Radial basis function (RBF), Scene, Support vector regression

Chen-Chung Liu; Kai-Wen Chuang

2009-09-01T23:59:59.000Z

384

Multilayer perceptrons and radial basis function neural network methods for the solution of differential equations: A survey  

Science Conference Proceedings (OSTI)

Since neural networks have universal approximation capabilities, therefore it is possible to postulate them as solutions for given differential equations that define unsupervised errors. In this paper, we present a wide survey and classification of different ... Keywords: Backpropagation algorithm, Differential equations, Multilayer perceptron, Neural network, Radial basis functions

Manoj Kumar; Neha Yadav

2011-11-01T23:59:59.000Z

385

Least Squares Fitting of Low-Level Gamma-ray Spectra with B-Spline Basis Functions  

E-Print Network (OSTI)

In this paper, new methods for smoothing gamma-ray spectra measured by NaI detector are derived. Least squares fitting method with B-spline basis functions is used to reduce the influence of statistical fluctuations. The derived procedures are simple and automatic. The results show that this method is better than traditional method with a more complete reduction of staistical fluctuation.

Zhu, M H; You, Z; Xu, A A

2007-01-01T23:59:59.000Z

386

Information Retrieval Information retrieval is a dynamic area of research, which forms the basis for many of today's  

E-Print Network (OSTI)

Information Retrieval Information retrieval is a dynamic area of research, which forms the basis contains a selection of the papers accepted for the annually organized Dutch-Belgian Information Retrieval of information retrieval and related disciplines, can exchange information and present new research developments

Hiemstra, Djoerd

387

356 BOOK REVIEWS thorough development of the theoretical basis of the icr technique. Chapters 1 and 2  

E-Print Network (OSTI)

356 BOOK REVIEWS thorough development of the theoretical basis of the icr technique. Chapters 1. It is not until the third chapter that the book seems to hit its full stride. Also, for the price of $22.75, one a typed manuscript. The book would be useful for those unfamiliar or slightly familiar with ion cyclotron

Pines, Alexander

388

High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2  

Science Conference Proceedings (OSTI)

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

1995-06-01T23:59:59.000Z

389

Combining the radial basis function eulerian and Lagrangian schemes with geostatistics for modeling of radionuclide migration through the geosphere  

Science Conference Proceedings (OSTI)

To assess the long-term safety of a radioactive waste disposal system, mathematical models are used to describe groundwater flow, chemistry, and potential radionuclide migration through geological formations. A number of processes need to be considered, ... Keywords: Eulerian method, Geostatistics, Lagrangian method, Radial basis function, Radionuclide migration

L. Vrankar; G. Turk; F. Runovc

2004-11-01T23:59:59.000Z

390

Analytical Thresholds: Determination of Minimum ...  

Science Conference Proceedings (OSTI)

... Different color channels behave differently if possible, determine ATs for each color ATs derived from methods based ...

2010-11-12T23:59:59.000Z

391

Determining the neutrino mass hierarchy  

Science Conference Proceedings (OSTI)

In this proceedings I review the physics that future experiments will use to determine the neutrino mass hierarchy.

Parke, Stephen J.; /Fermilab

2006-07-01T23:59:59.000Z

392

CX-004720: Categorical Exclusion Determination | Department of...  

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

would receive training in a mentored research program. This work would involve the molecular aspects of infectious diseases, and focus on understanding the genetic basis of...

393

Alternative methods to determine headwater benefits  

DOE Green Energy (OSTI)

In 1992, the Federal Energy Regulatory Commission (FERC) began using a Flow Duration Analysis (FDA) methodology to assess headwater benefits in river basins where use of the Headwater Benefits Energy Gains (HWBEG) model may not result in significant improvements in modeling accuracy. The purpose of this study is to validate the accuracy and appropriateness of the FDA method for determining energy gains in less complex basins. This report presents the results of Oak Ridge National Laboratory`s (ORNL`s) validation of the FDA method. The validation is based on a comparison of energy gains using the FDA method with energy gains calculated using the MWBEG model. Comparisons of energy gains are made on a daily and monthly basis for a complex river basin (the Alabama River Basin) and a basin that is considered relatively simple hydrologically (the Stanislaus River Basin). In addition to validating the FDA method, ORNL was asked to suggest refinements and improvements to the FDA method. Refinements and improvements to the FDA method were carried out using the James River Basin as a test case.

Bao, Y.S.; Perlack, R.D.; Sale, M.J.

1997-11-10T23:59:59.000Z

394

Errors associated with particulate matter measurements on rural sources: appropriate basis for regulating cotton gins  

E-Print Network (OSTI)

Agricultural operations across the United States are encountering difficulties complying with current air pollution regulations for particulate matter (PM). PM is currently regulated in terms of particle diameters less than or equal to a nominal 10 ?m (PM10); however, current legislation is underway to regulate PM with diameters less than or equal to a nominal 2.5 ?m (PM2.5). The goals of this research were to determine the biases and uncertainties associated with current PM10 and PM2.5 sampling methods and to determine the extent to which these errors may impact the determination of cotton gin emission factors. Ideally, PM samplers would produce an accurate measure of the pollutant indicator; for instance, a PM10 sampler would produce an accurate measure of PM less than or equal to 10 ?m. However, samplers are not perfect and errors are introduced because of the established tolerances associated with sampler performance characteristics and the interaction of particle size and sampler performance characteristics. Results of this research indicated that a source emitting PM characterized by a mass median diameter (MMD) of 20 ?m and a geometric standard deviation (GSD) of 1.5 could be forced to comply with a 3.2 and 14 times more stringent regulation of PM10 and PM2.5, respectively, than a source emitting PM characterized by a MMD of 10 ?m and a GSD of 1.5. These estimates are based on both sources emitting the same concentrations of true PM or concentrations corresponding to the particle diameters less than the size of interest. Various methods were used to estimate the true PM10 and PM2.5 emission factors associated with cotton gin exhausts and the extent to which the sampler errors impacted the PM regulation. Results from this research indicated that current cotton gin emission factors could be over-estimated by about 40%. This over-estimation is a consequence of the relatively large PM associated with cotton gin exhausts. These PM sampling errors are contributing to the misappropriation of source emissions in State Implementation Plans, essentially forcing Air Pollution Regulatory Agencies to require additional controls on sources that may be incorrectly classified has high emitters.

Buser, Michael Dean

2003-05-01T23:59:59.000Z

395

ANALYSIS OF THE PHENOMENON OF CREEP ON THE BASIS OF STATIC TESTS FOR TENSION  

SciTech Connect

Using a machine for static testing, a study was made of the influence of the method and rate of loading on the course of the creep curve. A metallic specimen was subjected first to static tests for tension up to a certain value of the load, and then to a test for creep at a constant load. The speed of tension of the specimen in the initial phase preceding the creep of the metal, as well as the value of the constant load which determines the start of the creep phenomenon, were varied. The duration of the initial phase fluctuates from 16 minutes to nine days, and the tests for creep proper averaged two days each. The values of the elongations and loads obtained in this manner and recorded as functions of the time were used to calculate the stress, the hardening, and the speed of deformation for all creep tests.

Wantuchowski, J.

1958-01-01T23:59:59.000Z

396

CX-008810: Categorical Exclusion Determination | Department of...  

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

0: Categorical Exclusion Determination CX-008810: Categorical Exclusion Determination CX-008810.pdf More Documents & Publications CX-002336: Categorical Exclusion Determination...

397

Previous Determinations | Building Energy Codes Program  

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

Previous Determinations Commercial Determinations Residential Determinations ANSIASHRAEIESNA Standard 90.1-2007 On July 20, 2011, DOE issued a final determination that...

398

Inferential determination of various properties of a gas mixture  

DOE Patents (OSTI)

Methods for inferentially determining various properties of a gas mixture, when the speed of sound in the gas is known at an arbitrary temperature and pressure. The method can be applied to natural gas mixtures, where the known parameters are the sound speed, temperature, pressure, and concentrations of any dilute components of the gas. The method uses a set of reference gases and their calculated density and speed of sound values to estimate the density of the subject gas. Additional calculations can be made to estimate the molecular weight of the subject gas, which can then be used as the basis for heating value calculations. The method may also be applied to inferentially determine density and molecular weight for gas mixtures other than natural gases.

Morrow, Thomas B. (San Antonio, TX); Behring, II, Kendricks A. (Torrance, CA)

2007-03-27T23:59:59.000Z

399

Draft Function Allocation Framework and Preliminary Technical Basis for Advanced SMR Concepts of Operations  

Science Conference Proceedings (OSTI)

This report presents preliminary research results from the investigation in to the development of new models and guidance for concepts of operations (ConOps) in advanced small modular reactor (aSMR) designs. In support of this objective, three important research areas were included: operating principles of multi-modular plants, functional allocation models and strategies that would affect the development of new, non-traditional concept of operations, and the requiremetns for human performance, based upon work domain analysis and current regulatory requirements. As part of the approach for this report, we outline potential functions, including the theoretical and operational foundations for the development of a new functional allocation model and the identification of specific regulatory requirements that will influence the development of future concept of operations. The report also highlights changes in research strategy prompted by confirmationof the importance of applying the work domain analysis methodology to a reference aSMR design. It is described how this methodology will enrich the findings from this phase of the project in the subsequent phases and help in identification of metrics and focused studies for the determination of human performance criteria that can be used to support the design process.

Jacques Hugo; John Forester; David Gertman; Jeffrey Joe; Heather Medema; Julius Persensky; April Whaley

2013-04-01T23:59:59.000Z

400

Carbazole-containing polyphenylquinolines as a basis for optoelectronic materials with white luminescence  

Science Conference Proceedings (OSTI)

The photophysical properties of poly-2,2 Prime -(1-dodecyl carbazole-4,7-yl)-6,6 Prime -(oxy)-bis-(4-phenylquinoline) in a solution, as a film, and in a poly(methyl methacrylate) or poly-N-vinylcarbazole host matrix have been studied. Considerable positive solvatochromism in the photoluminescence spectra, compared with solvatochromism in the absorption spectra, indicates that the dipole moment of the donor-acceptor complex increases in the excited state. Calculations show that the dipole moments of the complex in the ground and excited states differ by more than an order of magnitude. Upon transition to films, photoluminescence is observed in the entire visible spectral range (white luminescence). The intensity of the white luminescence grows by an order of magnitude when the polymer is dispersed in a poly(methyl methacrylate) matrix. The integrated photosensitivity and parameters of the photogeneration process (quantum yield of carrier photogeneration, quantum yield of free carrier formation, and thermalization radii) have been determined.

Svetlichnyi, V. M., E-mail: valsvet@hq.macro.ru [Russian Academy of Sciences, Institute of Macromolecular Compounds (Russian Federation); Aleksandrova, E. L. [Russian Academy of Sciences, Ioffe Physical-Technical Institute (Russian Federation); Nekrasova, T. N.; Smyslov, R. Yu.; Miagkova, L. A.; Matyushina, N. V. [Russian Academy of Sciences, Institute of Macromolecular Compounds (Russian Federation)

2012-04-15T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

Technical basis for radiological release of Grand Junction Office Building 2. Volume 1, dose assessment  

SciTech Connect

Building 2 on the US Department of Energy (DOE) Grand Junction Office (GJO) site is part of the GJO Remedial Action Program (GJORAP). During evaluation of Building 2 for determination of radiological release disposition, some inaccessible surface contamination measurements were detected to be greater than the generic surface contamination guidelines of DOE Order 5400.5 (which are functionally equivalent to US Nuclear Regulatory Commission [NRC] Regulatory Guide 1.86). Although the building is nominal in size, it houses the site telecommunications system, that is critical to continued GJO operations, and demolition is estimated at $1.9 million. Because unrestricted release under generic surface contamination guidelines is cost-prohibitive, supplemental standards consistent with DOE Order 5400.5 are being pursued. This report describes measurements and dose analysis modeling efforts to evaluate the radiation dose to members of the public who might occupy or demolish Building 2, a 2,480 square-foot (ft) building constructed in 1944. The north portion of the building was used as a shower facility for Manhattan Project uranium-processing mill workers and the south portion was a warehouse. Many originally exposed surfaces are no longer accessible for contamination surveys because expensive telecommunications equipment have been installed on the floors and mounted on panels covering the walls. These inaccessible surfaces are contaminated above generic contamination limits.

Morris, R.; Warga, J.; Thorne, D.

1997-07-01T23:59:59.000Z

402

The Structural Basis of [beta]-Peptide-Specific Cleavage by the Serine Protease Cyanophycinase  

Science Conference Proceedings (OSTI)

Cyanophycin, or poly-L-Asp-multi-L-Arg, is a non-ribosomally synthesized peptidic polymer that is used for nitrogen storage by cyanobacteria and other select eubacteria. Upon synthesis, it self-associates to form insoluble granules, the degradation of which is uniquely catalyzed by a carboxy-terminal-specific protease, cyanophycinase. We have determined the structure of cyanophycinase from the freshwater cyanobacterium Synechocystis sp. PCC6803 at 1.5-{angstrom} resolution, showing that the structure is dimeric, with individual protomers resembling aspartyl dipeptidase. Kinetic characterization of the enzyme demonstrates that the enzyme displays Michaelis-Menten kinetics with a k{sub cat} of 16.5 s{sup -1} and a k{sub cat}/K{sub M} of 7.5 x 10{sup -6} M{sup -1} s{sup -1}. Site-directed mutagenesis experiments confirm that cyanophycinase is a serine protease and that Gln101, Asp172, Gln173, Arg178, Arg180 and Arg183, which form a conserved pocket adjacent to the catalytic Ser132, are functionally critical residues. Modeling indicates that cyanophycinase binds the {beta}-Asp-Arg dipeptide residue immediately N-terminal to the scissile bond in an extended conformation in this pocket, primarily recognizing this penultimate {beta}-Asp-Arg residue of the polymeric chain. Because binding and catalysis depend on substrate features unique to {beta}-linked aspartyl peptides, cyanophycinase is able to act within the cytosol without non-specific cleavage events disrupting essential cellular processes.

Law, Adrienne M.; Lai, Sandy W.S.; Tavares, John; Kimber, Matthew S.; (Guelph)

2010-10-01T23:59:59.000Z

403

Massachusetts | Department of Energy  

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

and organizations who install high-efficiency, low-particulate matter wood pellet boilers or furnaces. Grants are awarded on a first-come, first -served basis, and may be...

404

MEMORANDUM FOR DISTRIBUTION - Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events  

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

September 16, 2011 September 16, 2011 MEMORANDUM FOR DISTRIBUTION FROM: SUBJECT: DANIEL B. PONEMA Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events Following the March 2011 accident at the Fukushima Daiichi nuclear power plant, the Department of Energy (DOE) took several actions to review the safety of its nuclear facilities. These actions focused on learning how DOE can better prepare to manage potential beyond design basis events. A summary of these actions and the resulting insights, and recommended opportunities and actions to improve nuclear safety at DOE> are included in the attached report. I have directed the Office of Health, Safety and Security (HSS) to work with DOE's Nuclear Safety and Security Coordinating Council, and the Program and Field Offices of

405

Analytical transformed harmonic oscillator basis for three-body nuclei of astrophysical interest: Application to 6He  

E-Print Network (OSTI)

Recently, a square-integrable discrete basis, obtained performing a simple analytical local scale transformation to the harmonic oscillator basis, has been proposed and successfully applied to study the properties of two-body systems. Here, the method is generalized to study three-body systems. To test the goodness of the formalism and establish its applicability and limitations, the capture reaction rate for the nucleosynthesis of the Borromean nucleus 6He (4He + n + n) is addressed. Results are compared with previous publications and with calculations based on actual three-body continuum wave functions, which can be generated for this simple case. The obtained results encourage the application to other Borromean nuclei of astrophysical interest such as 9Be and 12C, for which actual three-body continuum calculations are very involved.

J. Casal; M. Rodrguez-Gallardo; J. M. Arias

2013-07-24T23:59:59.000Z

406

MEMORANDUM FOR DISTRIBUTION - Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events  

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

September 16, 2011 September 16, 2011 MEMORANDUM FOR DISTRIBUTION FROM: SUBJECT: DANIEL B. PONEMA Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events Following the March 2011 accident at the Fukushima Daiichi nuclear power plant, the Department of Energy (DOE) took several actions to review the safety of its nuclear facilities. These actions focused on learning how DOE can better prepare to manage potential beyond design basis events. A summary of these actions and the resulting insights, and recommended opportunities and actions to improve nuclear safety at DOE> are included in the attached report. I have directed the Office of Health, Safety and Security (HSS) to work with DOE's Nuclear Safety and Security Coordinating Council, and the Program and Field Offices of

407

DOE Hydrogen and Fuel Cells Program Record 5038: Hydrogen Cost Competitive on a Cents per Mile Basis - 2006  

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

8 Date: May 22, 2006 8 Date: May 22, 2006 Title: Hydrogen Cost Competitive on a Cents per Mile Basis - 2006 Originator: Patrick Davis & Steve Chalk Approved by: JoAnn Milliken Approval Date: May 22, 2006 Item : Lower the cost of hydrogen from natural gas to be competitive on a cents per mile basis with conventional gasoline vehicles. Supporting Information: The results of a 2003 economic analysis were used to estimate the cost of hydrogen produced from distributed natural gas reforming at $5 per gallon of gasoline equivalent (gge) (See U.S. DOE Record 5030: Hydrogen Baseline Cost of $5 per gge in 2003; available at http://www.hydrogen.energy.gov/program_records). Since the original analysis, DOE-sponsored R&D has resulted in significant cost reductions,

408

Relation of exact Gaussian basis methods to the dephasing representation: Theory and application to time-resolved electronic spectra  

E-Print Network (OSTI)

We recently showed that the Dephasing Representation (DR) provides an efficient tool for computing ultrafast electronic spectra and that further acceleration is possible with cellularization [M. \\v{S}ulc and J. Van\\'i\\v{c}ek, Mol. Phys. 110, 945 (2012)]. Here we focus on increasing the accuracy of this approximation by first implementing an exact Gaussian basis method, which benefits from the accuracy of quantum dynamics and efficiency of classical dynamics. Starting from this exact method, the DR is derived together with ten other methods for computing time-resolved spectra with intermediate accuracy and efficiency. These methods include the Gaussian DR, an exact generalization of the DR, in which trajectories are replaced by communicating frozen Gaussian basis functions evolving classically with an average Hamiltonian. The newly obtained methods are tested numerically on time correlation functions and time-resolved stimulated emission spectra in the harmonic potential, pyrazine S0/S1 model, and quartic osci...

ulc, Miroslav; Martnez, Todd J; Van?ek, Ji?

2013-01-01T23:59:59.000Z

409

Categorical Exclusion Determinations: Pennsylvania | Department...  

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

Categorical Exclusion Determination Solid-Fueled Pressurized Chemical Looping with Flue-Gas Turbine Combined Cycle for Improved Plant Efficiency and Capture CX(s) Applied: A9...

410

Exchange rate determination in Indonesia.  

E-Print Network (OSTI)

??This thesis examines the options for adopting normative and prescriptive models of exchange rate determination suitable for developed and developing countries. It also develops a (more)

Rusydi, Mohammad

2006-01-01T23:59:59.000Z

411

Categorical Exclusion Determinations: Tennessee | Department...  

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

Golden Field Office May 14, 2012 CX-008803: Categorical Exclusion Determination Milling Machine Replacement Projects CX(s) Applied: B1.31 Date: 05142012 Location(s):...

412

Categorical Exclusion Determinations: Washington | Department...  

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

CX-009223: Categorical Exclusion Determination CH2MHill Plateau Remediation Company - Asbestos Removal Actions CX(s) Applied: B1.16 Date: 08032012 Location(s): Washington...

413

Categorical Exclusion Determinations: Washington | Department...  

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

August 30, 2012 CX-009317: Categorical Exclusion Determination Enhancement of SOFC Cathode Electrochemical Performance Using Multi-Phase Interfaces CX(s) Applied: B3.6...

414

Generally Contracted Valence-Core/Valence Basis Sets for Use with Relativistic Effective Core Potentials and Spin-Orbit Coupling Operators  

SciTech Connect

A procedure for structuring generally contracted valence-core/valence basis sets of Gaussian-type functions for use with relativistic effective core potentials (gcv-c/v-RECP basis sets) is presented. Large valence basis sets are enhanced using a compact basis set derived for outer core electrons in the presence of small-core RECPs. When core electrons are represented by relativistic effective core potentials (RECPs), and appropriate levels of theory, these basis sets are shown to provide accurate representations of atomic and molecular valence and outer-core electrons. Core/valence polarization and correlation effects can be calculated using these basis sets through standard methods for treating electron correlation. Calculations of energies and spectra for Ru, Os, Ir, In and Cs are reported. Spectroscopic constants for RuO2+, OsO2+, Cs2 and InH are calculated and compared with experiment.

Ermler, Walter V.; Tilson, Jeffrey L.

2012-12-15T23:59:59.000Z

415

Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development, August 2013  

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

Savannah River Site Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development May 2011 August 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope and Methodology ......................................................................................................................... 2 4.0 Results .................................................................................................................................................... 3

416

Technical Basis for Averaging C-14 Filters, Interim Report: Carbon-14 Source Term Analysis for Encapsulated Filter Waste Forms  

Science Conference Proceedings (OSTI)

The number of power plants implementing submicron-size cartridge filters has increased with the incentive of radiation dose reduction. However, utilities are experiencing difficulty disposing of these filters due to significant increases in (14)C concentrations. This study provides an important technical basis for concentration averaging of encapsulated filters with the grouting of filter waste. The concentration averaging with grouting will save costs in disposal of Greater than Class C filters and will...

2000-11-07T23:59:59.000Z

417

A Hybrid approach to molecular continuum processes combiningGaussian basis functions and the discrete variable representation  

SciTech Connect

Gaussian basis functions, routinely employed in molecular electronic structure calculations, can be combined with numerical grid-based functions in a discrete variable representation to provide an efficient method for computing molecular continuum wave functions. This approach, combined with exterior complex scaling, obviates the need for slowly convergent single-center expansions, and allows one to study a variety of electron-molecule collision problems. The method is illustrated by computation of various bound and continuum properties of H2+.

Rescigno, Thomas N.; Horner, Daniel A.; Yip, Frank L.; McCurdy,C. William

2005-08-29T23:59:59.000Z

418

Critical Equipment Maintenance Using EPRI Preventive Maintenance Basis Database (PMBD) Recommendations for a Combustion Turbine Plan t  

Science Conference Proceedings (OSTI)

This technical update report covers specific component preventive maintenance strategies that were developed in cooperation with East Kentucky Power Cooperatives J.K. Smith plant personnel and EPRIs Generation Sector Fossil O&M group personnel. The EPRI Preventive Maintenance Basis Database (PMBD) 2.0 software tool was used to define preventive maintenance defense strategies for specific plant components. Many of the plant components were located in the balance-of-plant (BOP) areas at the station. The ma...

2009-11-06T23:59:59.000Z

419

A Brief Review of the Basis for, and the Procedures Currently Utilized in, Gross Gamma-Ray Log Calibration (October 1976)  

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

A Brief Review of the Basis for, and the Procedures Currently Utilized in, Gross Gamma-Ray Log Calibration (October 1976)

420

Long-Baseline Neutrino Experiment (LBNE)Water Cherenkov Detector Basis of Estimate Forms and Backup Documentation LBNE Far Site Internal Review (December 6-9, 2011)  

Science Conference Proceedings (OSTI)

Basis of Estimate (BOE) forms and backup documentation developed for the Water Cherenkov Detector (WCD) option for the far detector of the Long Baseline Neutrino Experiment (LBNE)

Stewart J.; Diwan, M.; Dolph, J.; Novakova, P.; Sharma, R.; Stewart, J.; Viren, B.; Russo, T.; Kaducak, M.; Mantsch, P.; Paulos, B.; Feyzi, F.; Sullivan, G.; Bionta, R.; Fowler, J.; Warner, D.; Bahowick, S.; Van Berg, R.; Kearns, E.; Hazen, E.; Sinnis, G.; Sanchez, M.

2011-12-09T23:59:59.000Z

Note: This page contains sample records for the topic "first-served basis determined" 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

DOE G 435.1-1 Appendix A, Technical Basis and Considerations for DOE M 435.1-1 (Appendix A)  

Directives, Delegations, and Requirements

This appendix establishes the technical basis of the order revision process and of each of the requirements included in the revised radioactive waste ...

1999-07-09T23:59:59.000Z

422

Structural basis of RNA recognition and activation by innate immune receptor RIG-I  

Science Conference Proceedings (OSTI)

Retinoic-acid-inducible gene-I (RIG-I; also known as DDX58) is a cytoplasmic pathogen recognition receptor that recognizes pathogen-associated molecular pattern (PAMP) motifs to differentiate between viral and cellular RNAs. RIG-I is activated by blunt-ended double-stranded (ds)RNA with or without a 5'-triphosphate (ppp), by single-stranded RNA marked by a 5'-ppp and by polyuridine sequences. Upon binding to such PAMP motifs, RIG-I initiates a signalling cascade that induces innate immune defences and inflammatory cytokines to establish an antiviral state. The RIG-I pathway is highly regulated and aberrant signalling leads to apoptosis, altered cell differentiation, inflammation, autoimmune diseases and cancer. The helicase and repressor domains (RD) of RIG-I recognize dsRNA and 5'-ppp RNA to activate the two amino-terminal caspase recruitment domains (CARDs) for signalling. Here, to understand the synergy between the helicase and the RD for RNA binding, and the contribution of ATP hydrolysis to RIG-I activation, we determined the structure of human RIG-I helicase-RD in complex with dsRNA and an ATP analogue. The helicase-RD organizes into a ring around dsRNA, capping one end, while contacting both strands using previously uncharacterized motifs to recognize dsRNA. Small-angle X-ray scattering, limited proteolysis and differential scanning fluorimetry indicate that RIG-I is in an extended and flexible conformation that compacts upon binding RNA. These results provide a detailed view of the role of helicase in dsRNA recognition, the synergy between the RD and the helicase for RNA binding and the organization of full-length RIG-I bound to dsRNA, and provide evidence of a conformational change upon RNA binding. The RIG-I helicase-RD structure is consistent with dsRNA translocation without unwinding and cooperative binding to RNA. The structure yields unprecedented insight into innate immunity and has a broader impact on other areas of biology, including RNA interference and DNA repair, which utilize homologous helicase domains within DICER and FANCM.

Jiang, Fuguo; Ramanathan, Anand; Miller, Matthew T.; Tang, Guo-Qing; Gale, Jr., Michael; Patel, Smita S.; Marcotrigiano, Joseph (Rutgers); (RWJ-Med); (UW-MED)

2012-05-29T23:59:59.000Z

423

Automatic Black-Box Model Order Reduction using Radial Basis Functions  

SciTech Connect

Finite elements methods have long made use of model order reduction (MOR), particularly in the context of fast freqeucny sweeps. In this paper, we discuss a black-box MOR technique, applicable to a many solution methods and not restricted only to spectral responses. We also discuss automated methods for generating a reduced order model that meets a given error tolerance. Numerical examples demonstrate the effectiveness and wide applicability of the method. With the advent of improved computing hardware and numerous fast solution techniques, the field of computational electromagnetics are progressed rapidly in terms of the size and complexity of problems that can be solved. Numerous applications, however, require the solution of a problem for many different configurations, including optimization, parameter exploration, and uncertainly quantification, where the parameters that may be changed include frequency, material properties, geometric dimensions, etc. In such cases, thousands of solutions may be needed, so solve times of even a few minutes can be burdensome. Model order reduction (MOR) may alleviate this difficulty by creating a small model that can be evaluated quickly. Many MOR techniques have been applied to electromagnetic problems over the past few decades, particularly in the context of fast frequency sweeps. Recent works have extended these methods to allow more than one parameter and to allow the parameters to represent material and geometric properties. There are still limitations with these methods, however. First, they almost always assume that the finite element method is used to solve the problem, so that the system matrix is a known function of the parameters. Second, although some authors have presented adaptive methods (e.g., [2]), the order of the model is often determined before the MOR process begins, with little insight about what order is actually needed to reach the desired accuracy. Finally, it not clear how to efficiently extend most methods to the multiparameter case. This paper address the above shortcomings be developing a method that uses a block-box approach to the solution method, is adaptive, and is easily extensible to many parameters.

Stephanson, M B; Lee, J F; White, D A

2011-07-15T23:59:59.000Z

424

Cell, Vol. 103, 11431154, December 22, 2000, Copyright 2000 by Cell Press The Structural Basis for the Action of the  

E-Print Network (OSTI)

This situation has now changed with the determina-Salt Lake City, Utah 84132 tion of complete atomic structures to determine the location of antibioticsWe have used the recently determined atomic struc- in difference

Ramakrishnan, Venki

425

Categorical Exclusion Determinations: Intelligence and Counterintellig...  

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

Intelligence and Counterintelligence Categorical Exclusion Determinations: Intelligence and Counterintelligence Categorical Exclusion Determinations issued by Intelligence and...

426

DOE Completes Annual Determination of the Adequacy of the Nuclear Waste  

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

Completes Annual Determination of the Adequacy of the Nuclear Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee DOE Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee November 2, 2010 - 7:41pm Addthis As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. Addthis Related Articles GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions

427

An approach to estimating radiological risk of offsite release from a design basis earthquake for the Process Experimental Pilot Plant (PREPP)  

SciTech Connect

In compliance with Department of Energy (DOE) Order 6430.1A, a seismic analysis was performed on DOE's Process Experimental Pilot Plant (PREPP), a facility for processing low-level and transuranic (TRU) waste. Because no hazard curves were available for the Idaho National Engineering Laboratory (INEL), DOE guidelines were used to estimate the frequency for the specified design-basis earthquake (DBE). A dynamic structural analysis of the building was performed, using the DBE parameters, followed by a probabilistic risk assessment (PRA). For the PRA, a functional organization of the facility equipment was effected so that top events for a representative event tree model could be determined. Building response spectra (calculated from the structural analysis), in conjunction with generic fragility data, were used to generate fragility curves for the PREPP equipment. Using these curves, failure probabilities for each top event were calculated. These probabilities were integrated into the event tree model, and accident sequences and respective probabilities were calculated through quantification. By combining the sequences failure probabilities with a transport analysis of the estimated airborne source term from a DBE, onsite and offsite consequences were calculated. The results of the comprehensive analysis substantiated the ability of the PREPP facility to withstand a DBE with negligible consequence (i.e., estimated release was within personnel and environmental dose guidelines). 57 refs., 19 figs., 20 tabs.

Lucero, V.; Meale, B.M.; Reny, D.A.; Brown, A.N.

1990-09-01T23:59:59.000Z

428

Novel Technique of Sizing the Stand-Alone Photovoltaic Systems Using the Radial Basis Function Neural Networks: Application in Isolated Sites  

E-Print Network (OSTI)

The objective of this work is to investigate the Radial Basis Function Neural Networks (RBFN) to identifying and modeling the optimal sizing couples of stand-alone photovoltaic (PV) system using a minimum of input data, These optimal couples allow to the users of stand-alone PV systems to determine the number of solar panel modules and storage batteries necessary to satisfy a given consumption. The advantage of this model is to estimate of the sizing PV system in any site in Algeria particularly in isolated sites, where the global solar radiation data is not always available. A RBFN has been trained by using 200 known sizing couples data corresponding to 200 locations. In this way, it was trained to accept and even handle a number of unusual case, known sizing couples were subsequently used to investigate the accuracy of prediction the training of the RBFN model was performed with adequate accuracy. Subsequently, the unknown validation sizing couples set produced very set accurate predictions with the correlation coefficient between the actual and the RBFN model identified data of 98% was obtained. This result indicates that the proposed method can be successfully used for estimating of optimal sizing couples of PV systems for any locations in Algeria, but the methodology can be generalized using different locations in the world.

Mellit, A.; Benghanme, M.; Arab, A. H.; Guessoum, A.

2004-01-01T23:59:59.000Z

429

The geologic basis for appraising undiscovered hydrocarbon resources in the National Petroleum Reserve of Alaska by the play-appraisal method. [Glossary included  

SciTech Connect

The Naval Petroleum Reserves Production Act of 1976 provided for a Government study to determine the best general procedure for the development, production, transportation, and distribution of the hydrocarbon resources in the National Petroleum Reserve in Alaska (NPRA). An essential and distinguishing feature of this study was the development of a resource-appraisal method that would furnish the estimates of undiscovered oil and gas resources in a form compatible with the sophisticated computer model demanded by the economic and policy-analysis portion of the study. This appraisal represents the first use of the newly developed play method and is the latest in a series of hydrocarbon-resource appraisals of the NPRA. As the most recent of the series, it is based on a larger number of data. In the NPRA, the play method was first used by the USGS in November 1979. At intervals averaging 6 months, as new information was gained from the ongoing drilling program, the original assessment was reviewed and updated. The chapter was prepared to document the petroleum geology for each assessed play and thus serve as a basis for further assessments. In addition, it provides information about the assessment personnel, the data base, and analogous formations; for each play, it includes a petroleum geology summary, an outline map, a completed assessment form, and resource estimates. A glossary of terms used in the assessment may be found at the end of this chapter.

Bird, K.J.

1989-01-01T23:59:59.000Z

430

Method of determining glass durability  

DOE Patents (OSTI)

A process is described for determining one or more leachate concentrations of one or more components of a glass composition in an aqueous solution of the glass composition by identifying the components of the glass composition, including associated oxides, determining a preliminary glass dissolution estimator, {Delta}G{sub p}, based upon the free energies of hydration for the component reactant species, determining an accelerated glass dissolution function, {Delta}G{sub a}, based upon the free energy associated with weak acid dissociation, {Delta}G{sub a}{sup WA}, and accelerated matrix dissolution at high pH, {Delta}G{sub a}{sup SB} associated with solution strong base formation, and determining a final hydration free energy, {Delta}G{sub f}. This final hydration free energy is then used to determine leachate concentrations for elements of interest using a regression analysis and the formula log{sub 10}(N C{sub i}(g/L))=a{sub i} + b{sub i}{Delta}G{sub f}. The present invention also includes a method to determine whether a particular glass to be produced will be homogeneous or phase separated. The present invention is also directed to methods of monitoring and controlling processes for making glass using these determinations to modify the feedstock materials until a desired glass durability and homogeneity is obtained. 4 figs.

Jantzen, C.M.; Pickett, J.B.; Brown, K.G.; Edwards, T.B.

1998-12-08T23:59:59.000Z

431

Boundary determinations for trivariate solids  

Science Conference Proceedings (OSTI)

The trivariate tensor-product B-spline solid is a direct extension of the B-spline patch and has been shown to be useful in the creation and visualization of free-form geometric solids. Visualizing these solid objects requires the determination of the boundary surface of the solid, which is a combination of parametric and implicit surfaces. This paper presents a method that determines the implicit boundary surface by examination of the Jacobian determinant of the defining B-spline function. Using an approximation to this determinant, the domain space is adaptively subdivided until a mesh can be determined such that the boundary surface is close to linear in the cells of the mesh. A variation of the marching cubes algorithm is then used to draw the surface. Interval approximation techniques are used to approximate the Jacobian determinant and to approximate the Jacobian determinant gradient for use in the adaptive subdivision methods. This technique can be used to create free-form solid objects, useful in geometric modeling applications.

Duchaineau, M; Joy, K I

1999-05-14T23:59:59.000Z

432

Method of determining glass durability  

DOE Patents (OSTI)

A process for determining one or more leachate concentrations of one or more components of a glass composition in an aqueous solution of the glass composition by identifying the components of the glass composition, including associated oxides, determining a preliminary glass dissolution estimator, .DELTA.G.sub.p, based upon the free energies of hydration for the component reactant species, determining an accelerated glass dissolution function, .DELTA.G.sub.a, based upon the free energy associated with weak acid dissociation, .DELTA.G.sub.a.sup.WA, and accelerated matrix dissolution at high pH, .DELTA.G.sub.a.sup.SB associated with solution strong base formation, and determining a final hydration free energy, .DELTA.G.sub.f. This final hydration free energy is then used to determine leachate concentrations for elements of interest using a regression analysis and the formula log.sub.10 (N C.sub.i (g/L))=a.sub.i +b.sub.i .DELTA.G.sub.f. The present invention also includes a method to determine whether a particular glass to be produced will be homogeneous or phase separated. The present invention is also directed to methods of monitoring and controlling processes for making glass using these determinations to modify the feedstock materials until a desired glass durability and homogeneity is obtained.

Jantzen, Carol Maryanne (Aiken, SC); Pickett, John Butler (Aiken, SC); Brown, Kevin George (Augusta, GA); Edwards, Thomas Barry (Aiken, SC)

1998-01-01T23:59:59.000Z

433

Categorical Exclusion Determinations: Minnesota | Department...  

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

2012 CX-008997: Categorical Exclusion Determination Next Generation Solar Collectors for CSP CX(s) Applied: B3.6, B5.17 Date: 08142012 Location(s): Minnesota Offices(s): Golden...

434

Categorical Exclusion Determinations: Nationwide | Department...  

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

16, 2011 CX-008025: Categorical Exclusion Determination Traffic Signals and Street Lighting CX(s) Applied: B1.32, B5.1 Date: 11162011 Location(s): Nationwide Offices(s):...

435

Categorical Exclusion Determinations: Nationwide | Department...  

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

Office September 21, 2010 CX-007105: Categorical Exclusion Determination United States China Clean Energy Research Center for Clean Vehicles CX(s) Applied: A1, A9, B1.2, B3.6,...

436

Categorical Exclusion Determinations: Environmental Management...  

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

Office February 12, 2010 CX-000893: Categorical Exclusion Determination Benchtop Distillation and Recovery of Volatile Solvents CX(s) Applied: B3.6 Date: 02122010 Location(s):...

437

Gender determination of avian embryo  

DOE Patents (OSTI)

Disclosed is a method for gender determination of avian embryos. During the embryo incubation process, the outer hard shells of eggs are drilled and samples of allantoic fluid are removed. The allantoic fluids are directly introduced into an ion mobility spectrometer (IMS) for analysis. The resulting spectra contain the relevant marker peaks in the positive or negative mode which correlate with unique mobilities which are sex-specific. This way, the gender of the embryo can be determined.

Daum, Keith A. (Idaho Falls, ID); Atkinson, David A. (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

438

Program for documenting the criticality safety basis for operations in a research and development facility consistent with new regulatory requirements  

SciTech Connect

A program was developed and implemented at LLNL to provide more detailed, documented Criticality Safety Evaluations of operations in an R&D facility. The new Criticality Safety evaluations were consistent with regulatory requirements of the then new DOE Order 5480.24, Nuclear Criticality Safety. The evaluations provide a criticality safety basis for each operation in the facility in support of the facility Safety Analysis Report. This implementation program provided a transition from one method of conducting and documenting Criticality Safety Evaluations to a new method consistent with new regulatory requirements. The program also allowed continued safe operation of the facility while the new implementation level Criticality Safety Evaluations were developed.

Pearson, J.S.; Evarts, R.B.; Huang, S.T.; Goebel, G.

1997-04-24T23:59:59.000Z

439

Basis to demonstrate compliance with the National Emission Standards for Hazardous Air Pollutants for the Stand-off Experiments Range  

SciTech Connect

The purpose of this report is to provide the basis and the documentation to demonstrate general compliance with the National Emission Standard for Hazardous Air Pollutants (NESHAPS) 40 CFR 61 Subpart H, National Emission Standards for Emissions of Radionuclides Other Than Radon from Department of Energy Facilities, (the Standard) for outdoor linear accelerator operations at the Idaho National Laboratory (INL) Stand-off Experiments Range (SOX). The intent of this report is to inform and gain acceptance of this methodology from the governmental bodies regulating the INL.

Michael Sandvig

2011-01-01T23:59:59.000Z

440

Materials Reliability Program: Technical Basis for Preemptive Weld Overlays for Alloy 82/182 Butt Welds in PWRs (MRP-169)  

Science Conference Proceedings (OSTI)

Dissimilar metal Alloy 82/182 bimetallic pipe-to-nozzle butt welds (DMWs) have experienced cracking in recent years due to primary water stress corrosion cracking (PWSCC). Although weld overlays have been used primarily as a repair for flawed piping, they also can be applied at locations that have not yet exhibited any cracking but are considered susceptible to PWSCC. An overlay used in this manner is termed a preemptive weld overlay (PWOL). This report provides the technical basis for PWOL overlays for ...

2005-10-25T23:59:59.000Z

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


441

CX-007754: Categorical Exclusion Determination | Department of...  

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

8 groundwater wells to monitor contaminant concentrations. On a quarterly basis, gas and produced water samples are collected from operating gas wells within a one-mile radius of...

442

Determination of a Z-R Relationship for Snowfall Using a Radar and High Sensitivity Snow Gauges  

Science Conference Proceedings (OSTI)

A best-fit power-law relationship (Z = 427 R1.09) between 1-minute integrated averages of snowfall rate (R) and radar reflectivity factor (Z) was determined on the basis of observations made by using high sensitivity snow gauges (accuracy 0.03 mm ...

Yasushi Fujiyoshi; Tatsuo Endoh; Tomomi Yamada; Kazuhisa Tsuboki; Yoshihiro Tachibana; Gorow Wakahama

1990-02-01T23:59:59.000Z

443

Secretarial Determination Pursuant to the USEC Privatization...  

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

Secretarial Determination Pursuant to the USEC Privatization Act Secretarial Determination Pursuant to the USEC Privatization Act Secretary Steven Chu determined that such sales or...

444

Revision D to 2006 AOP Renewal Statement of Basis For Hanford Site Air Operating Permit No. 00-05-006  

E-Print Network (OSTI)

The Statement of Basis (Statement) is issued by the permitting agencies as a separate supporting reference document to the Hanford Air Operating Permit (AOP). The Statement sets forth the legal and factual basis for the AOP conditions, and is not intended for enforcement purposes. The Statement includes references to the applicable statutory or regulatory provisions, technical supporting information on specific emission units, and clarifications of specific requirements. [Washington Administrative Code (WAC) 173-401-700(8)] In 1990, U.S. Congress amended the federal Clean Air Act (CAA). One change was to create air operating permits for industrial sources of air pollution (codified in Title 5 of the CAA). Prior to the creation of these permits, facility managers, regulators and the public had to look through many separate requirements to find those that applied to a certain facility. An air operating permit brings all applicable requirements into one place and requires the manager of the source to certify that it complies with all the applicable requirements. Further, the burden of proof for compliance changed from the regulating agencies to the sources. In 1991, the Washington State Legislature updated the Washington Clean Air Act [Chapter 70.94 of the Revised Code of Washington (RCW)] to make it consistent with the new federal program. In 1993, Ecology developed Washingtons operating permits regulation to comply with federal

unknown authors

2008-01-01T23:59:59.000Z

445

Determining solar abundances using helioseismology  

E-Print Network (OSTI)

The recent downward revision of solar photospheric abundances of Oxygen and other heavy elements has resulted in serious discrepancies between solar models and solar structure as determined through helioseismology. In this work we investigate the possibility of determining the solar heavy-element abundance without reference to spectroscopy by using helioseismic data. Using the dimensionless sound-speed derivative in the solar convection zone, we find that the heavy element abundance, Z, of 0.0172 +/- 0.002, which is closer to the older, higher value of the abundances.

H. M. Antia; Sarbani Basu

2006-02-28T23:59:59.000Z

446

MEANS FOR DETERMINING CENTRIFUGE ALIGNMENT  

DOE Patents (OSTI)

An apparatus is presented for remotely determining the alignment of a centrifuge. The centrifage shaft is provided with a shoulder, upon which two followers ride, one for detecting radial movements, and one upon the shoulder face for determining the axial motion. The followers are attached to separate liquid filled bellows, and a tube connects each bellows to its respective indicating gage at a remote location. Vibrations produced by misalignment of the centrifuge shaft are transmitted to the bellows, and tbence through the tubing to the indicator gage. This apparatus is particularly useful for operation in a hot cell where the materials handled are dangerous to the operating personnel.

Smith, W.Q.

1958-08-26T23:59:59.000Z

447

CX-001298: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-001298: Categorical Exclusion Determination Full-Scale Mercury Control Demonstrations: Information Collection Request Sampling with Mercury Control...

448

CX-006848: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-006848: Categorical Exclusion Determination State Energy Program American Recovery and Reinvestment Act - Deployment of Innovative Energy...

449

CX-003206: Categorical Exclusion Determination | Department of...  

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

Categorical Exclusion Determination CX-003206: Categorical Exclusion Determination BioenergyBionanotechnology Projects Louisiana Technical University, Ruston (Louisiana) CX(s)...

450

CX-000690: Categorical Exclusion Determination | Department of...  

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

0: Categorical Exclusion Determination CX-000690: Categorical Exclusion Determination Pennsylvania - Economic Development Authority Sustainable Business Recovery: Solar Farm at...

451

CX-006496: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-006496: Categorical Exclusion Determination Midwest Regional Carbon Sequestration Partnership Phase 3: Michigan 3-Dimensional Seismic Data Collection...

452

CX-000425: Categorical Exclusion Determination | Department of...  

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

Determination CX-000425: Categorical Exclusion Determination Geoscience Perspectives in Carbon Sequestration: Educational Training and Research through Classroom, Field, and...

453

EA-1835: Environmental Assessment Determination | Department...  

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

Assessment Determination EA-1835: Environmental Assessment Determination Midwest Regional Carbon Sequestration Partnership (MRCSP) Phase II Michigan Basin Project in Chester...

454

CX-008439: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-008439: Categorical Exclusion Determination Modeling Carbon Dioxide Sequestration in Saline Aquifer and Depleted Oil Reservoir (Task 17 -...

455

CX-002613: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-002613: Categorical Exclusion Determination Modeling Carbon Dioxide Sequestration in Saline Aquifer and Depleted Oil Reservoir to Evaluate...

456

CX-000424: Categorical Exclusion Determination | Department of...  

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

Determination CX-000424: Categorical Exclusion Determination Geoscience Perspectives in Carbon Sequestration: Educational Training and Research through Classroom, Field, and...

457

CX-002609: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-002609: Categorical Exclusion Determination Modeling Carbon Dioxide Sequestration in Saline Aquifer and Depleted Oil Reservoir to Evaluate...

458

CX-008441: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-008441: Categorical Exclusion Determination Modeling Carbon Dioxide Sequestration in Saline Aquifer and Depleted Oil Reservoir (Task 17 -...

459

CX-002612: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-002612: Categorical Exclusion Determination Modeling Carbon Dioxide Sequestration in Saline Aquifer and Depleted Oil Reservoir to Evaluate...

460

CX-008440: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-008440: Categorical Exclusion Determination Modeling Carbon Dioxide Sequestration in Saline Aquifer and Depleted Oil Reservoir (Task 17 -...

Note: This page contains sample records for the topic "first-served basis determined" 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

CX-008794: Categorical Exclusion Determination | Department of...  

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

Categorical Exclusion Determination CX-008794: Categorical Exclusion Determination Transformer Replacement and Foundation Work at Flaming Gorge Substation Daggett County, Utah...

462

CX-003056: Categorical Exclusion Determination | Department of...  

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

Determination CX-003056: Categorical Exclusion Determination Synchrophasor Based Tracking Three Phase State Estimator and Its Applications (Summary Categorical Exclusion)...

463

CX-008811: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-008811: Categorical Exclusion Determination Utility Energy Service Contract Closed Loop Centrifugal Chiller at the Central Chilled Water...

464

CX-000294: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-000294: Categorical Exclusion Determination A Novel Biogas Desulphurization Sorbent Technology for Molten Carbonate Fuel Cell- Based Combined...

465

CX-000293: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination CX-000293: Categorical Exclusion Determination A Novel Biogas Desulphurization Sorbent Technology for Molten Carbonate Fuel Cell - Based Combined...

466

Categorical Exclusion Determinations: Brookhaven Site Office...  

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

Brookhaven Site Office Categorical Exclusion Determinations: Brookhaven Site Office Categorical Exclusion Determinations issued by Brookhaven Site Office. DOCUMENTS AVAILABLE FOR...

467

CX-008314: Categorical Exclusion Determination | Department of...  

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

Categorical Exclusion Determination CX-008314: Categorical Exclusion Determination Next Generation Environmentally-Friendly Driving Feedback Systems Research and Development...

468

Categorical Exclusion Determinations: Office of Electricity Delivery...  

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

Electricity Delivery and Energy Reliability Categorical Exclusion Determinations: Office of Electricity Delivery and Energy Reliability Categorical Exclusion Determinations issued...

469

CX-006453: Categorical Exclusion Determination | Department of...  

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

Categorical Exclusion Determination CX-006453: Categorical Exclusion Determination Geothermal Incentive Program - Matunaliec Residence geothermal (Deercliff Road) CX(s) Applied:...